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{{#Wiki_filter:o g[en aic ,"h ,
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UNITE D 'i T ATES 3             g             NUCLEAR REGULATORY COMMISSION
UNITE D 'i T ATES 3
%            :j                     WASHINGTON, D. C. 20555
g NUCLEAR REGULATORY COMMISSION
%            c
:j WASHINGTON, D. C. 20555 c
            /
/
t.lah 3 7 rM LER MONTHLY REPORT The enclosed computer listing, as identified on the attached sheet, provides information concerning Licensee Event Reports (LERs) entered into the data base during the month of March.
t.lah 3 7 rM LER MONTHLY REPORT The enclosed computer listing, as identified on the attached sheet, provides information concerning Licensee Event Reports (LERs) entered into the data base during the month of March.
If you desire additional information or special searches, please feel free to contact me on 301/492 4834.
If you desire additional information or special searches, please feel free to contact me on 301/492 4834.
Sincerely,
Sincerely,
                                                            .      /
/
                                                                  . o   c Eugen a L. Boyle Data Management Unit Office for Analysis and Evaluation of Operational Data
o c
Eugen a L. Boyle Data Management Unit Office for Analysis and Evaluation of Operational Data


==Enclosure:==
==Enclosure:==
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MAR 26, 1981                                                                                                                     LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 1 PROCESSED DURING MARCH, 1931 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                                       DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 1 PROCESSED DURING MARCH, 1931 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                             REPORT DATE/                                       EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                                                           CONTROL NO. REPORT TYPE                                         CAUSE DESCRIPTION ARKANSAS-1                                                                                                           05000313       011381 DURING REFUELING SHUTDOWN, WHILE INSTALLING A SIX INCH CONDUIT PENETRATI FIRE PROTECTION SYS + CONT                                                                                     81-003/03L-0     020981 NG THE FLOOR OF THE COMPRESSOR ROOM (FIRE ZONE 76-W) BETWEEN THE NORTH W COMPONENT CODE NOT APPLICABLE                                                                                     036078         30-DAY ALL AND COMPRESSOR C2B, THE PENETRATION FIRE BARRIER WAS REMOVED AND A C SUBCOMPONENT NOT APPLICABLE                                                                                                         ONTINUOUS FIRE WATCH WAS NOT ESTABLISHED AS REQUIRED BY TECH. SPEC. 3.21 PERSONNEL ERROR                                                                                                                             .2. THERE HAVE BEEN NO SIMILAR OCCURRENCES ON UNIT 1. REPORTABLE PER T MAINTENANCE
EVENT DATE/
* REPAIR PERSONNEL                                                                                                       ECH. SPEC. 6.12.3.2.B.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
ITEM NOT APPLICABLE A FIRE WATCH WAS ESTABLISHED UPON DISCOVERY AND MAINTAINED UNTIL THE FIR E BARRIER WAS INSTALLED. OCCURRENCE CAUSED BY INADEQUATE INSTRUCTIONS T 0 CONTRACTOR PERSONNEL.             THE CONTRACTOR HAS BEEN INSTRUCTED TO MAINTAIN A FIREWATCH WHENEVER PENETRATIONS ARE OPENED AND TO SEAL PENETRATIONS AS QUICKLY AS POSSIBLE. CONTRACTAR PROCEDURES HAVE BEEN MODIFIED.
REPORT DATE/
ARKANSAS-2                                                                                                           05000368       070380 DURING MODE 1 OPERATION, WHILE MAKING A ROUTINE CHECK OF THE PLANT RADIA AREA MONITORING SYSTEMS                                                                                         80-047/03X-1     020681 TION MONITORING SYSTEM (RMS), THE CONTAINMENT ATMOSPHERE RADIATION MONIT INSTRUMENTATION + CONTROLS                                                                                         032093         OTHER   OR, 2RITS-8271, WAS FOUND TO BE IHOPERABLE. THE CONTAINMENT SUMP LEVEL TRANSMITTER                                                                                                                           AND CONTAINMENT BUILDING AREA MONITORS REMAINED OPERABLE. NO SIMILAR OC DESIGN / FABRICATION ERROR                                                                                                               CURRENCES. OTHER RMS OCCURRENCES WERE LER'S 50-368/79-057, 79-067, 80-0 CONSTRUCTION / INSTALLATION                                                                                                           43 AND 80-046.     REPORTABLE PER T.S. 6.9.1.9.B.
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-1 05000313 011381 DURING REFUELING SHUTDOWN, WHILE INSTALLING A SIX INCH CONDUIT PENETRATI FIRE PROTECTION SYS + CONT 81-003/03L-0 020981 NG THE FLOOR OF THE COMPRESSOR ROOM (FIRE ZONE 76-W) BETWEEN THE NORTH W COMPONENT CODE NOT APPLICABLE 036078 30-DAY ALL AND COMPRESSOR C2B, THE PENETRATION FIRE BARRIER WAS REMOVED AND A C SUBCOMPONENT NOT APPLICABLE ONTINUOUS FIRE WATCH WAS NOT ESTABLISHED AS REQUIRED BY TECH. SPEC. 3.21 PERSONNEL ERROR
.2.
THERE HAVE BEEN NO SIMILAR OCCURRENCES ON UNIT 1.
REPORTABLE PER T MAINTENANCE
* REPAIR PERSONNEL ECH. SPEC. 6.12.3.2.B.
ITEM NOT APPLICABLE A FIRE WATCH WAS ESTABLISHED UPON DISCOVERY AND MAINTAINED UNTIL THE FIR E BARRIER WAS INSTALLED. OCCURRENCE CAUSED BY INADEQUATE INSTRUCTIONS T 0 CONTRACTOR PERSONNEL.
THE CONTRACTOR HAS BEEN INSTRUCTED TO MAINTAIN A FIREWATCH WHENEVER PENETRATIONS ARE OPENED AND TO SEAL PENETRATIONS AS QUICKLY AS POSSIBLE. CONTRACTAR PROCEDURES HAVE BEEN MODIFIED.
ARKANSAS-2 05000368 070380 DURING MODE 1 OPERATION, WHILE MAKING A ROUTINE CHECK OF THE PLANT RADIA AREA MONITORING SYSTEMS 80-047/03X-1 020681 TION MONITORING SYSTEM (RMS), THE CONTAINMENT ATMOSPHERE RADIATION MONIT INSTRUMENTATION + CONTROLS 032093 OTHER OR, 2RITS-8271, WAS FOUND TO BE IHOPERABLE. THE CONTAINMENT SUMP LEVEL TRANSMITTER AND CONTAINMENT BUILDING AREA MONITORS REMAINED OPERABLE. NO SIMILAR OC DESIGN / FABRICATION ERROR CURRENCES. OTHER RMS OCCURRENCES WERE LER'S 50-368/79-057, 79-067, 80-0 CONSTRUCTION / INSTALLATION 43 AND 80-046.
REPORTABLE PER T.S. 6.9.1.9.B.
WESTINGHOUSE ELECTRIC CORP.
WESTINGHOUSE ELECTRIC CORP.
MONITOR'S VACUUM PUMP THERMAL DVERLOAD TRIPPED DUE TO HIGH AMBIENT TEMPE RATURE IN NORTH PIPING PENETRATION ROOM (MONITOR LOCATION). OVERLOAD RE SET 2 MONITOR DECLARED OPERABLE. PIPE INSULATION, PACKING LEAK HEAT LOA DS 2 POOR COOLING AIR FLOW WERE CAUSES. VENTILATION SYSTEM AIR DUCTS WE RE RELOCATED.
MONITOR'S VACUUM PUMP THERMAL DVERLOAD TRIPPED DUE TO HIGH AMBIENT TEMPE RATURE IN NORTH PIPING PENETRATION ROOM (MONITOR LOCATION). OVERLOAD RE SET 2 MONITOR DECLARED OPERABLE. PIPE INSULATION, PACKING LEAK HEAT LOA DS 2 POOR COOLING AIR FLOW WERE CAUSES. VENTILATION SYSTEM AIR DUCTS WE RE RELOCATED.
ARKANSAS-2                                                                                                           05000363       072780 IN MODE I, CORE OPERATING LIMITS SUPERVISORY SYSTEM WAS DECLARED IN0PERA OTHR INST SYS NOT REQD FR SFTY                                                                                 80-059/03X-1     011981 BLE ON TWO OCCASIONS. ON 7/27/80 COLSS PLANT COMPUTER PROGRAM INDICATED INSTRUMENTATION + CONTROLS                                                                                         032202       OTHER   A POWER MARGIN OF -80?. RATHER THAN EXPECTED 0% AT RATED POWER. ON 12/31 COMPUTATION MODULE                                                       '
ARKANSAS-2 05000363 072780 IN MODE I, CORE OPERATING LIMITS SUPERVISORY SYSTEM WAS DECLARED IN0PERA OTHR INST SYS NOT REQD FR SFTY 80-059/03X-1 011981 BLE ON TWO OCCASIONS. ON 7/27/80 COLSS PLANT COMPUTER PROGRAM INDICATED INSTRUMENTATION + CONTROLS 032202 OTHER A POWER MARGIN OF -80?. RATHER THAN EXPECTED 0% AT RATED POWER.
                                                                                                                                                                    /80 COLSS PROGRAM OUTPUT DATA WOULD NOT UPDATE. ACTION INITIATED TO RED COMPONENT FAILURE                                                                                                                         UCE POWER TO BRING CPC INDICATED LPD & DNBR VALUES WITHIN LIMITS OF TECH ELECTRONIC                                                                                                                           NICAL SPECIFICATION 3.2.4 4 FIG 3.2-3. SIMILAR TO LER 50-368/80-032.
ON 12/31 COMPUTATION MODULE
/80 COLSS PROGRAM OUTPUT DATA WOULD NOT UPDATE. ACTION INITIATED TO RED COMPONENT FAILURE UCE POWER TO BRING CPC INDICATED LPD & DNBR VALUES WITHIN LIMITS OF TECH ELECTRONIC NICAL SPECIFICATION 3.2.4 4 FIG 3.2-3.
SIMILAR TO LER 50-368/80-032.
SYSTEMS ENGINEER. LABS., INC.
SYSTEMS ENGINEER. LABS., INC.
ON 7/27/80 INTEGRATED DETECTOR FLUX ARRAY (TPHI) BECAME ALTERED, AFFECTI NG COLSS CORE POWER DISTRIBUTION CALCULATORS. ON 12/31/80, A DISC INPUT
ON 7/27/80 INTEGRATED DETECTOR FLUX ARRAY (TPHI) BECAME ALTERED, AFFECTI NG COLSS CORE POWER DISTRIBUTION CALCULATORS. ON 12/31/80, A DISC INPUT
                                                                                                                                                                    /0UTPUT FAILURE OCCURRED ON FIXED HEAD DISK SOFTWARE. DIAGNOSTICS DID H t
/0UTPUT FAILURE OCCURRED ON FIXED HEAD DISK SOFTWARE. DIAGNOSTICS DID H t
"                                                                                                                                                                  OT REVEAL CAUSE.       INTERMITTENT HARDWARE FAILURE SUSPECTED. FAILURES COR RECTED BY RELOADING APPROPRIATE SOFTWARE.
OT REVEAL CAUSE.
ARKANSAS-2                                                                                                             05000368       112980 HIGH PRESSURE SAFETY INJECTION VALVE 2CV-5056 FAILED TO CLOSE-ON 11/29/8 EMERG CORE COOLING SYS + CONT                                                                                   80-087/03X-1     012081   O WHILE PERFORMING ROUTINE LEVEL ADJUSTMENTS OF SAFETY INJECTION TANK 2T CIRCUIT CLOSERS / INTERRUPTERS                                                                                     033375       OTHER   -2C IN MODE 1 8 ON 12/21/80 WHILE PERFORMING SURVEILLANCE STROKE TEST M0 CIRCUIT BREAKER                                                                                                                       DE 2.     HPSI VALVE WAS PLACED IN OPEN POSITION, BUT CONSIDERED INOPERABLE COMPONENT FAILURE                                                                                                                             AS VALVE REQUIRED TO BE THROTTLED TO MEET TECH. SPEC. 4.5.2.H.         LOOP 1 ELECTRICAL                                                                                                                           HPSI SYSTEM. REMAINED OPERABLE.
INTERMITTENT HARDWARE FAILURE SUSPECTED. FAILURES COR RECTED BY RELOADING APPROPRIATE SOFTWARE.
ITEM NOT APPLICABLE INVESTIGATION REVEALED A BLOWN CONTROL POWER FUSE.             CAUSE OF FUSE FAILUR E WAS NOT IDENTIFIED. . NO ABNORMALITIES WERE IDENTIFIED DURING CHECKOUT.
ARKANSAS-2 05000368 112980 HIGH PRESSURE SAFETY INJECTION VALVE 2CV-5056 FAILED TO CLOSE-ON 11/29/8 EMERG CORE COOLING SYS + CONT 80-087/03X-1 012081 O WHILE PERFORMING ROUTINE LEVEL ADJUSTMENTS OF SAFETY INJECTION TANK 2T CIRCUIT CLOSERS / INTERRUPTERS 033375 OTHER
-2C IN MODE 1 8 ON 12/21/80 WHILE PERFORMING SURVEILLANCE STROKE TEST M0 CIRCUIT BREAKER DE 2.
HPSI VALVE WAS PLACED IN OPEN POSITION, BUT CONSIDERED INOPERABLE COMPONENT FAILURE AS VALVE REQUIRED TO BE THROTTLED TO MEET TECH. SPEC. 4.5.2.H.
LOOP 1 ELECTRICAL HPSI SYSTEM. REMAINED OPERABLE.
ITEM NOT APPLICABLE INVESTIGATION REVEALED A BLOWN CONTROL POWER FUSE.
CAUSE OF FUSE FAILUR E WAS NOT IDENTIFIED.. NO ABNORMALITIES WERE IDENTIFIED DURING CHECKOUT.
FUSE WAS REPLACED, VALVE WAS STROKE TESTED AND DECLARED OPERABLE. CAU SE OF THE FUSE FAILURE WILL BE INVESTIGATED FURTHER.
FUSE WAS REPLACED, VALVE WAS STROKE TESTED AND DECLARED OPERABLE. CAU SE OF THE FUSE FAILURE WILL BE INVESTIGATED FURTHER.
  = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - .                ___        __                    _
=


MAR 26, 1981                                                             LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 2 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /         DOCKET NO./                 EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 2 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                             REPORT DATE/                               EVENT DEstRIPTION/
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO.                 REPORT TYPE                               CAUSE DESCRIPTION ARKANSAS-2                                         05000368               010281     DURING MODE 1 OPERATION, A LEAK WAS IDENTIFIED AT A VENT LINE bcLD ON CH CHEM, VOL CDNT + LIQ POISH SYS               81-0G1/03L-0                 012781     ARGING PUMP SUCTION STABILIZER, 2M115C.
EVENT DATE/
PIPES, FITTINGS                                                                                                                THE LEAK WAS IS7 LATED RENDERING 036017       30-DAY       CHARGING PUMP, 2P36C, INOPERABLE. THE REDUNDANT CHARGING PUMPS AND THE LESS THAN 4 INCHES                                                                   THREE HIGH PRESSURE INJECTION PUMPS REMAINED AVAILABLE FOR BORATION PAT COMPONENT FAILURE                                                                   HS. N3 SIMILAR OCCURRENCES; HOWEVER. THIS OCCURRENCE IS RELATED TO LER METALLURGICAL                                                                     50-368/80-090. REPORTABLE PER TECHNICAL SPECIFICATION 6.9.t.9.D.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
OTHER THE SUBJECT WELD WAS MADE DURING PIPF SPDDL PIECE REPLACEMENT DUE YO A C HARGING PUNP SUCTICH HEADER LEAK (SEE LER 50-368/80-4401. THE PINH9LE L EAK WAS CAUSED bY f. DISSOLYING SLAG INCLUSION. THE MELD WAS REPAIRED AN D THE CHARGING PUMP, 2P36C, DECLARED OPERABLE.
REPORT DATE/
ARKANSAS 2                                         05000368               010681     DURING A REVIEN OF BLOCK WALLS, PURSUANT TO I.E. BULLETIN 80-11, IT WAS AIR COND. HEAT COOL, VENT SYSTEM             81-002/03L-0                 020281     IDENTIFIED THAT A POSTULATED FAILURE DF MASONRY WALL, 24-B-217/218 NOUL OTHER COMPONENTS                                             036018       30-DAY     D RESULT IN LOSS OF CABLES 2BS3L1 AND 2BS3L2, WHICH FEED CONTAINMENT C00 SUBCOMPONENT NOT APPLICABLE                                                       LING FANS 2VSF-1A/B. BOTH CONTAINMENT SPRAY LOOFS WOULD REMAIM GPERABL DESIGN / FABRICATION ERROR                                                           E. AS WILL THE REDUNDANT CONTAINMENT COOLING UNIT GR9GP. NO SIMILAR OCC DESIGN                                                                           URRENCES. REPORTABLE PER TECHNICAL SPECIFICATION 6 < *.1.9'.B.
EVENT DEstRIPTION/
IT EM NOT APPLICABLE DESIGN CRITERIA SPECIFIED IN I.E. BULIETIN 80-11 NAS MORE RESTRICTIVE TH AN THAT USED IN THE DRIGINAL DESIGN. WHEN MASONRY WALL WAS RE-AHALYZED UNDER THE NEW CRITERIA. TFE POSSIBLE WALL FAILURE WAS IDENTIFIED. THE W ALL MAS BRACED IN ACCDRDAHCE WITH THE NEW DESIGN CRITERIA WITHIN THE TIM E REQUIREMENT OF ACTION STATEMENT D. OF TECH. SPEC. 3.6.2.3.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
.QRKANSAS-2                                         05000368               011381     DURING MODE 1 OPERATION, THE PLANT COMPUTER FAILED AND WOULD NOT RESTART O'HR INST SYS NOT REQD FR SFTY               81-003/03L-0                 020381     ,
REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 010281 DURING MODE 1 OPERATION, A LEAK WAS IDENTIFIED AT A VENT LINE bcLD ON CH CHEM, VOL CDNT + LIQ POISH SYS 81-0G1/03L-0 012781 ARGING PUMP SUCTION STABILIZER, 2M115C.
RENDERING THE CORE OPERATING LIMITS SUPERVISORY SYSTEM (COLSS) IN0PERA Ib3YRUMENTATION + CONTROLS                                 036079       30-DAY     BLE. ACTION WAS TAKEN TO REDUCE POWER TO BRING THE CORE PROTECTION CALC ODMPUTATION MODULE                                                               ULATOR (CPC) INDICATED LPD A DNBR VALUES WITHIH THE LIMITS OF TECH. SPEC CtMPONENT FAILURE                                                                   . 3.2.4 AND TECH. SPEC. FIGURE 3.2-3. SIMILAR TO LER'S 50-368/80-082, 8 INSTRUMENT                                                                       0-041, AND 80-032. REPORTABLE PER TECH. SPEC. 6.9.1.9.B.
THE LEAK WAS IS7 LATED RENDERING PIPES, FITTINGS 036017 30-DAY CHARGING PUMP, 2P36C, INOPERABLE. THE REDUNDANT CHARGING PUMPS AND THE LESS THAN 4 INCHES THREE HIGH PRESSURE INJECTION PUMPS REMAINED AVAILABLE FOR BORATION PAT COMPONENT FAILURE HS.
N3 SIMILAR OCCURRENCES; HOWEVER. THIS OCCURRENCE IS RELATED TO LER METALLURGICAL 50-368/80-090.
REPORTABLE PER TECHNICAL SPECIFICATION 6.9.t.9.D.
OTHER THE SUBJECT WELD WAS MADE DURING PIPF SPDDL PIECE REPLACEMENT DUE YO A C HARGING PUNP SUCTICH HEADER LEAK (SEE LER 50-368/80-4401.
THE PINH9LE L EAK WAS CAUSED bY f. DISSOLYING SLAG INCLUSION. THE MELD WAS REPAIRED AN D THE CHARGING PUMP, 2P36C, DECLARED OPERABLE.
ARKANSAS 2 05000368 010681 DURING A REVIEN OF BLOCK WALLS, PURSUANT TO I.E. BULLETIN 80-11, IT WAS AIR COND. HEAT COOL, VENT SYSTEM 81-002/03L-0 020281 IDENTIFIED THAT A POSTULATED FAILURE DF MASONRY WALL, 24-B-217/218 NOUL OTHER COMPONENTS 036018 30-DAY D RESULT IN LOSS OF CABLES 2BS3L1 AND 2BS3L2, WHICH FEED CONTAINMENT C00 SUBCOMPONENT NOT APPLICABLE LING FANS 2VSF-1A/B.
BOTH CONTAINMENT SPRAY LOOFS WOULD REMAIM GPERABL DESIGN / FABRICATION ERROR E. AS WILL THE REDUNDANT CONTAINMENT COOLING UNIT GR9GP.
NO SIMILAR OCC DESIGN URRENCES. REPORTABLE PER TECHNICAL SPECIFICATION 6 < *.1.9'.B.
IT EM NOT APPLICABLE DESIGN CRITERIA SPECIFIED IN I.E. BULIETIN 80-11 NAS MORE RESTRICTIVE TH AN THAT USED IN THE DRIGINAL DESIGN. WHEN MASONRY WALL WAS RE-AHALYZED UNDER THE NEW CRITERIA. TFE POSSIBLE WALL FAILURE WAS IDENTIFIED. THE W ALL MAS BRACED IN ACCDRDAHCE WITH THE NEW DESIGN CRITERIA WITHIN THE TIM E REQUIREMENT OF ACTION STATEMENT D.
OF TECH. SPEC. 3.6.2.3.
.QRKANSAS-2 05000368 011381 DURING MODE 1 OPERATION, THE PLANT COMPUTER FAILED AND WOULD NOT RESTART O'HR INST SYS NOT REQD FR SFTY 81-003/03L-0 020381 RENDERING THE CORE OPERATING LIMITS SUPERVISORY SYSTEM (COLSS) IN0PERA Ib3YRUMENTATION + CONTROLS 036079 30-DAY BLE.
ACTION WAS TAKEN TO REDUCE POWER TO BRING THE CORE PROTECTION CALC ODMPUTATION MODULE ULATOR (CPC) INDICATED LPD A DNBR VALUES WITHIH THE LIMITS OF TECH. SPEC CtMPONENT FAILURE
. 3.2.4 AND TECH. SPEC. FIGURE 3.2-3.
SIMILAR TO LER'S 50-368/80-082, 8 INSTRUMENT 0-041, AND 80-032.
REPORTABLE PER TECH. SPEC.
6.9.1.9.B.
SYSTEMS ENGINEER. LABS., INC.
SYSTEMS ENGINEER. LABS., INC.
THE COMPUTER HAD A PARITY ERROR CAUSED BY A CAPACITOR IN THE FLOATING PO INT POWER SUPPLY, GENERATING NOISE DUF TO A SHORT. THE CAPACITOR WAS RE PLACED, POWER SUPPLY ADJUSTED FOR PROPER OPERATION, AND COMPUTER DIAGNOS TICS SUCCESSFULLY RUN WITH NO ERRORS DETECTED. COLSS WAS RETURNED TO OP ERABLE STATUS AND NORMAL POWER OPERATION WAS CONTINUED.                         r BEAVER VALLEY-1                                     05000334             060879     IN JUNE, 1979. TWO POWER CABLES ORIGINATJMG AT THE 1B LOW HEAD SAFETY IN EMERG CCRE COOLING SYS + COMT               79-016/03X-2.               012881     JECTION PUMP HEADER ISOLATION VALVE AND THE FUMP SUCTION VALVE WERE FOUN ELECTRICAL CONDUCTORS                                       026480       OTHER     D INCORRECTLY ROUTED THROUGH TWO HON-COLOR-CDDED CABLE TRAYS,     AS A RESU SUBCOMPONENT NOT APPL'ICABLE                                                     LT OF THESE FINDINGS, A CABLE SAMPLING PROGRAM WAS INITIATED WHERE AN AD PERSONNEL ERROR                                                                     DITIONAL 26 CABLES WFRE INSPECTED. NO ROUTING VIOLATIONS WERE DISCOVERE CONSTRUCTION PERSONNEL                                                           D. DURING THE 1980 REFUELING OUTAGE. 10 ADDITIOP^L CABLE ROUTING PROBLE OTHER                                                                               MS WERE FOUND DURING DESIGN WORK CHANGES.
THE COMPUTER HAD A PARITY ERROR CAUSED BY A CAPACITOR IN THE FLOATING PO INT POWER SUPPLY, GENERATING NOISE DUF TO A SHORT.
ORIGINAL TWO CABLES WERE REROUTED IN 1979. 10 CABLE ROUTING PROBLEMS DI SCOVERED IN 1980 HAVE BEEN REROUTED A VERIFIED AS CORRECT UNDER DESIGN C HANGE PACKAGE (DCP3 253. BECAUSE OF THESE DEFICIENCIES. STATION HAS INI TIATED DCP 393 WHICH CALLS FOR A SECOND CABLE VERIFICATION PROGRAM. ONS ITE ENGINEERING GROUP IS CURRENTLY SETTING UP THIS PROGRAM.
THE CAPACITOR WAS RE PLACED, POWER SUPPLY ADJUSTED FOR PROPER OPERATION, AND COMPUTER DIAGNOS TICS SUCCESSFULLY RUN WITH NO ERRORS DETECTED. COLSS WAS RETURNED TO OP ERABLE STATUS AND NORMAL POWER OPERATION WAS CONTINUED.
r BEAVER VALLEY-1 05000334 060879 IN JUNE, 1979. TWO POWER CABLES ORIGINATJMG AT THE 1B LOW HEAD SAFETY IN EMERG CCRE COOLING SYS + COMT 79-016/03X-2.
012881 JECTION PUMP HEADER ISOLATION VALVE AND THE FUMP SUCTION VALVE WERE FOUN ELECTRICAL CONDUCTORS 026480 OTHER D INCORRECTLY ROUTED THROUGH TWO HON-COLOR-CDDED CABLE TRAYS, AS A RESU SUBCOMPONENT NOT APPL'ICABLE LT OF THESE FINDINGS, A CABLE SAMPLING PROGRAM WAS INITIATED WHERE AN AD PERSONNEL ERROR DITIONAL 26 CABLES WFRE INSPECTED. NO ROUTING VIOLATIONS WERE DISCOVERE CONSTRUCTION PERSONNEL D.
DURING THE 1980 REFUELING OUTAGE. 10 ADDITIOP^L CABLE ROUTING PROBLE OTHER MS WERE FOUND DURING DESIGN WORK CHANGES.
ORIGINAL TWO CABLES WERE REROUTED IN 1979.
10 CABLE ROUTING PROBLEMS DI SCOVERED IN 1980 HAVE BEEN REROUTED A VERIFIED AS CORRECT UNDER DESIGN C HANGE PACKAGE (DCP3 253.
BECAUSE OF THESE DEFICIENCIES. STATION HAS INI TIATED DCP 393 WHICH CALLS FOR A SECOND CABLE VERIFICATION PROGRAM. ONS ITE ENGINEERING GROUP IS CURRENTLY SETTING UP THIS PROGRAM.


MAR 26, 1981                                                                 LER MONTHLY REPORT SORTED BY FACILITY                                                                                     PAGE 3 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                   DOCKET NO./         EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 3 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / (ER NO./                               REPORT DATE/                                                                                           EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                       CONTROL NO.         REPORT TYPE                                                                                             CAUSE DESCRIPTION SEAVER VALLEY-1                                           05000334           092080         THE MOTOR-DRIVEN FIRE PUMP WAS RETURNED FROM WESTINGHOUSE AFTER BEING RE FIRE PROTECTION SYS + CONT                             80-069/01X-2         013081         BUILT FOR THE THIRD TIME. DURING THE PERFORMANCE OF A SURVEILLANCE TEST MOTORS                                                   032599             OTHER               ON 1/25/81, MOTOR BEARING PROBLEMS WERE AGAIN OBSERVED. TWO TEMPORARY SUBCOMPONENT NOT APPLICABLE                                                               FIRE PUMPS REMAIN AVAILABLE ALONG WITH THE INSTALLED ENGINE-DRIVEN FIRE COMPONENT FAILURE                                                                           PUMP.                                                                                                             I OTHER OTHER THE CAUSE FOR THIS FAILURE IS BEING INVESTIGATED FURTHER. THE MOTOR HAS BEEN SENT OFF-SITE TO BE REBUILT AGAIN AND THE PUMP WILL BE REMOVED FOR FURTHER INVESTIGATION.
EVENT DATE/
BEAVER VALLEY-1                                           05000334           111780         AT 1403 HOURS, THE STATION OPERATING SUPERVISOR (505) WAS NOTIFIED OF A EMERG CORE COOLING SYS + CONT                         80-394/99X-0         021381         STEAM LINE LOW PRES 5URE BISTABLE IBS-MS-4853 INTERMITTENTLY TRIPPING 8 R INSTRUMENTATION + CONTROLS                               033745             DTHER         ESETTING. WHEN SOS ACCOMPANIED OPERATOR TO THE PPOCESS-RACKS TO TRIP BI INDICATOR                                                                                 STABLE. THEY OPERATED THE WRONG CHANNEL [BS-MS-4843, IN VIOLATION OF TEC PERSONNEL ERROR                                                                             H. SPECS. 3.5.2 8 3.5.3. ECCS SYSTEMS. THE PUBLIC HEALTH & SAFETY WERE                                           i LICENSED & SENIOR OPERATORS                                                               NOT JEOPARDIZED SINCE ALL ACTIONS OCCURRED IN THE MOST CONSERVATIVE MANN                                         i OTHER                                                                                       ER.           SAFETY INJECTIONS TO DATE: 15 OPERATIONAL AND 2 PRE-OPERATIONAL.
COMPONENT SUBCODE/CAUSE CODE / (ER NO./
THIS INCIDENT OCCURRED BECAUSE THE SOS DID NOT LOOK AT THE STATUS PANtl HIMSELF, BUT TOCK THE WORD OF ANOTHER PERSON INVOLVED IN PLANT OPERATION S. THE REQUIPED READING INCIDENT REPORT DISTRIBUTION IS BEING USED TO I NDICATE THE NEED TO RECHECK IMPORTANT EVOLUTIONS SUCH AS TRIPPING BISTAB LES.
REPORT DATE/
BEAVER VALLEY-1                                           05000335           120680         CCRING PERFORhANCE OF MAINTENANCE SURVEILLANCE PROCEDURE MSP 46.03B, FOR CNTHMNT COMBUS GAS CONTROL -SYS                       80-108/03X-1         021881             CALIBRATION OF HYDROGEN ANALYZER H2-HY-100B, A FAILED FUNCTION CIRCUIT INSTRUMENTATION + CONTROLS                               033490             OTHER         CARD WAS FOUND.                                 THE ANALYZER WAS DECLARED INOPERABLE AT 1025 HOURS PER OTHER                                                                                     TECHNICAL SPECIFI' CATION 3.6.4.1. THE HEALTH AND SAFETY OF THE PUBLIC WA' COMPONENT FAILURE                                                                           S NOT JEOPARDIZED SINCE THE 9EDUNDANT ANALYZER WAS AVAILABLE FOR SERVICE ELECTRONIC                                                                               ,          IF NEEDED, AND THE ANALYZER WAS REPAIRED AND RETURNED TO SERVICE WITHI BENDIX CORP., THE                                                                           N A SHORT PERIOD OF TIME.
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SEAVER VALLEY-1 05000334 092080 THE MOTOR-DRIVEN FIRE PUMP WAS RETURNED FROM WESTINGHOUSE AFTER BEING RE FIRE PROTECTION SYS + CONT 80-069/01X-2 013081 BUILT FOR THE THIRD TIME.
DURING THE PERFORMANCE OF A SURVEILLANCE TEST MOTORS 032599 OTHER ON 1/25/81, MOTOR BEARING PROBLEMS WERE AGAIN OBSERVED. TWO TEMPORARY SUBCOMPONENT NOT APPLICABLE FIRE PUMPS REMAIN AVAILABLE ALONG WITH THE INSTALLED ENGINE-DRIVEN FIRE COMPONENT FAILURE PUMP.
I OTHER OTHER THE CAUSE FOR THIS FAILURE IS BEING INVESTIGATED FURTHER. THE MOTOR HAS BEEN SENT OFF-SITE TO BE REBUILT AGAIN AND THE PUMP WILL BE REMOVED FOR FURTHER INVESTIGATION.
BEAVER VALLEY-1 05000334 111780 AT 1403 HOURS, THE STATION OPERATING SUPERVISOR (505) WAS NOTIFIED OF A EMERG CORE COOLING SYS + CONT 80-394/99X-0 021381 STEAM LINE LOW PRES 5URE BISTABLE IBS-MS-4853 INTERMITTENTLY TRIPPING 8 R INSTRUMENTATION + CONTROLS 033745 DTHER ESETTING. WHEN SOS ACCOMPANIED OPERATOR TO THE PPOCESS-RACKS TO TRIP BI INDICATOR STABLE. THEY OPERATED THE WRONG CHANNEL [BS-MS-4843, IN VIOLATION OF TEC PERSONNEL ERROR H.
SPECS. 3.5.2 8 3.5.3. ECCS SYSTEMS.
THE PUBLIC HEALTH & SAFETY WERE i
LICENSED & SENIOR OPERATORS NOT JEOPARDIZED SINCE ALL ACTIONS OCCURRED IN THE MOST CONSERVATIVE MANN i
OTHER ER.
SAFETY INJECTIONS TO DATE: 15 OPERATIONAL AND 2 PRE-OPERATIONAL.
THIS INCIDENT OCCURRED BECAUSE THE SOS DID NOT LOOK AT THE STATUS PANtl HIMSELF, BUT TOCK THE WORD OF ANOTHER PERSON INVOLVED IN PLANT OPERATION S.
THE REQUIPED READING INCIDENT REPORT DISTRIBUTION IS BEING USED TO I NDICATE THE NEED TO RECHECK IMPORTANT EVOLUTIONS SUCH AS TRIPPING BISTAB LES.
BEAVER VALLEY-1 05000335 120680 CCRING PERFORhANCE OF MAINTENANCE SURVEILLANCE PROCEDURE MSP 46.03B, FOR CNTHMNT COMBUS GAS CONTROL -SYS 80-108/03X-1 021881 CALIBRATION OF HYDROGEN ANALYZER H2-HY-100B, A FAILED FUNCTION CIRCUIT INSTRUMENTATION + CONTROLS 033490 OTHER CARD WAS FOUND.
THE ANALYZER WAS DECLARED INOPERABLE AT 1025 HOURS PER OTHER TECHNICAL SPECIFI' CATION 3.6.4.1.
THE HEALTH AND SAFETY OF THE PUBLIC WA' COMPONENT FAILURE S NOT JEOPARDIZED SINCE THE 9EDUNDANT ANALYZER WAS AVAILABLE FOR SERVICE ELECTRONIC IF NEEDED, AND THE ANALYZER WAS REPAIRED AND RETURNED TO SERVICE WITHI BENDIX CORP., THE N A SHORT PERIOD OF TIME.
THE FAILURE WAS AN ELECTRONIC CIRCUIT CARD FAILURE. THE FUNCTION CARD W AS REPLACED WITH A NEW ONE FROM STOCK AND THEN MSP 46.03B WAS SUCCESSFUL LY COMPLETED. THE ANALYZER WAS RETURNED TO SERVICE AT 1524 HOURS.
THE FAILURE WAS AN ELECTRONIC CIRCUIT CARD FAILURE. THE FUNCTION CARD W AS REPLACED WITH A NEW ONE FROM STOCK AND THEN MSP 46.03B WAS SUCCESSFUL LY COMPLETED. THE ANALYZER WAS RETURNED TO SERVICE AT 1524 HOURS.
BEAVER VALLEY-1                                           05000334           123080         ON 12/30/80, WHILE PERFORMING THE SURVEILLANCE TEST ON THE CHLORINE DETE CONT ROOM HABITBLTY SYS + CONT                         30-115/03L-0         012681         CTION SYSTEM, IT WAS DISCOVERED THAT THE 101A, 101B AND 101C DETECTORS' INSTRUMENTATION + CONTROLS                               033738             30-DAY         ELECTROLYTE WAS NOT DRIPPING. PRIOR TO INCREASING REACTOR COOLANT SYSTE SENSOR / DETECTOR / ELEMENT                                                               M TEMPERATURE TO ABOVE 200F, THE DETECTORS WERE DECLARED OUT OF SERVICE DESIGN / FABRICATION ERROR                                                                 AND THE 101A DETECTOR WAS TRIPPCD. OPERATION CONTINUED IN ACCORDANCE WI
BEAVER VALLEY-1 05000334 123080 ON 12/30/80, WHILE PERFORMING THE SURVEILLANCE TEST ON THE CHLORINE DETE CONT ROOM HABITBLTY SYS + CONT 30-115/03L-0 012681 CTION SYSTEM, IT WAS DISCOVERED THAT THE 101A, 101B AND 101C DETECTORS' INSTRUMENTATION + CONTROLS 033738 30-DAY ELECTROLYTE WAS NOT DRIPPING. PRIOR TO INCREASING REACTOR COOLANT SYSTE SENSOR / DETECTOR / ELEMENT M TEMPERATURE TO ABOVE 200F, THE DETECTORS WERE DECLARED OUT OF SERVICE DESIGN / FABRICATION ERROR AND THE 101A DETECTOR WAS TRIPPCD. OPERATION CONTINUED IN ACCORDANCE WI
[   MANUFACTURING                                                                             TH TECHNICAL SPECIFICATION 3.3.3.7. THIS WAS THE TENTH FAILURE OF THIS l WALLACE & TIERNAN, INC.                                                                     TYPE AT BVPS.
[
THE WICKS AND GLASS ORIFICES WERE CLOGGED. THE WICKS WERE REPLACED AND THE ORIFICES CLEANED. ENGINEERING HAS BEEN REQUESTED TO EVALUATE THIS S YSTEM DUE TO THE REPEATED FAILURES.
MANUFACTURING TH TECHNICAL SPECIFICATION 3.3.3.7.
THIS WAS THE TENTH FAILURE OF THIS l
WALLACE & TIERNAN, INC.
TYPE AT BVPS.
THE WICKS AND GLASS ORIFICES WERE CLOGGED. THE WICKS WERE REPLACED AND THE ORIFICES CLEANED.
ENGINEERING HAS BEEN REQUESTED TO EVALUATE THIS S YSTEM DUE TO THE REPEATED FAILURES.
{
{
l l
l l


MAR 26, 1981                                                         LER MONTHLY REPORT SCRTED BY FACILITY                                         PAGE 4 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPO..ENT/                     DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 4 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPO..ENT/
COMPONENT SUBCODE/CAUSE CODE / LER NO./                           REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                         CONTROL NO. REPORT TYPE                                 CAUSE DESCPIPTION DEAVER VALLEY-1                                           05000334     010281 REACTOR CONTAIMMENT SYSTEMS                                                      AT 0630 HOURS WHILE IN HOT STANDBY. THE CLMTAINMENT DUTER AIRLOCK DOOR F 81-003/03L-0 020281       AILED ITS SEAL LEAKAGE SURVEILLANCE TEST. THE AIRLOCK WAS DECLARED IHOP PENETRATIONS.PRIMRY CONTAINMNT                           036042     30-DAY     ERABLE IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.6.1.3. THE HEALTH A PERSONNEL ACCESS DESIGN / FABRICATION ERROR                                                      ND SAFETY OF THE PUBLIC WERE NOT JEOPARDIZED SINCE LEAKAGE THROUGH THE A DESIGN                                                                         IRLOCK WAS PREVENTED BY THE INNER DOOR WHICH RC"AINED SEALED.
EVENT DATE/
OTHER PREPARATIONS WERE BEING MADE TO RETURN THE PLANT TO PCWER FOLLOWING AN U NPLANNED OUTAGE TO REPAIR THE PRESSURIZER SAFETY VALVES.     AT 2230 HOURS, WHILE STILL IN. HOT STANDBY. THE AIRLOCK WAS RETURNED TO SERVICE AFTER C LEANING, GREASING AND REALIGNING THE SEALS.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
. BEAVER VALLEY-1                                           05000334     010681     DURING THE PERFORMANCE OF A SURVEILLANCE TEST ON THE CONTROL ROOM EMERGE CONT ROOM HABITBLTY SYS + COHT                         81-004/03L-0   020481     NCY SUPPLY FANS. THE AIR FiOW CALCULATIONS INDICATED FLOW RATES OF 464 A VALVES                                                   036043     30-DAY     ND 473 CFM. TECHNICAL SPECIFICATION 4.7.7.1 REQUIRES A SYSTEM FLOW RATE PROPORTIONING LOUVER                                                             OF 400 CFM +/- 10% DURING SYSTEM OPERATION. THE HEALTH AND SAFETY OF T DESIGN / FABRICATION ERROR                                                       HE GENERAL PUBLIC AND SITE PERSONNEL WERE NOT JEOPARDIZED.
REPORT DATE/
DESIGN OTHER AFTER AN ADJUSTMENT WAS MADE TO THE SUPPLY FANS INLET DAMPER. THE FLOW R ATE WAS VERIFIED TO BE WITHIN ACCEPlABLE LIMITS.     THE SURVEILLANCE TEST WAS COMPLETED SATISFACTORILY AT 1400 HOURS ON JANUARY 6, 1981.
EVENT DESCRIPTION /
BEAVER VALLEY-1                                           05000334     010681     ON 1/6/81 THE DUQUESHE LIGHT COMPANY ENGINEERING DEPARTMENT REPORTED TH MAIN STEAM SYSTEMS + CCHTROLS                         81-001/01T-0   012081     AT 32" SHP-1. 2. 3-601-Q2 SUPPORTS H-162. H-164 AMD H-166 HAD MOT BEEN M HANGERS. SUPPORTS. SHOCK SUPPRSS                         036179     2-WEEK     ODIFIED AS ORIGINALLY REPORTED IN THE 8/14/80 IE BULLETIN 79-14 LETTER.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
SUPPORTS                                                                         THIS IS A VIOLATION OF TECHNICAL SPECIFICATION 6.9.1.8.I. ANALYSIS OF DESIGN / FABRICATION ERROR                                                       STRUCTURES. THE CONSEQUENCES OF SUPPORT FAILURE DUE TO PIPE WHIP IS POS DESIGN OTHER                                                                            TULATED TO BE FAILURE OF THE MAIN STEAM VALVE HOUSE WALL. RESULTING IN F AILURE OF THE OTHER TWO STEAM LINES.DUE TO FALLING DEBRIS.
REPORT TYPE CAUSE DESCPIPTION DEAVER VALLEY-1 05000334 010281 AT 0630 HOURS WHILE IN HOT STANDBY. THE CLMTAINMENT DUTER AIRLOCK DOOR F REACTOR CONTAIMMENT SYSTEMS 81-003/03L-0 020281 AILED ITS SEAL LEAKAGE SURVEILLANCE TEST.
CAUSE OF PROBLEM IS THAT ILLEGIBLE CRAWINGS WERE TRANSf11TTED TO CONSTRUC TION DEPARTMENT FOR USE. MHEN DRAWINGS WERE SENT BACK FOR BETTER COFIES
THE AIRLOCK WAS DECLARED IHOP PENETRATIONS.PRIMRY CONTAINMNT 036042 30-DAY ERABLE IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.6.1.3.
                                                                                    . THE DRAWING PERTAINING TO SUPPORTS H-162, H-164 A H-166 WAS LOST. WOR K ON H- 162. 164 & 166 WAS C0f1PLETED ON 1/7/81 & A LETTER FROM QUALITY AS BEAVER VALLEY-1                                                                  SURANCE DEPT. WAS RECEIVED. VERIFYING THAT ALL OTHER ITEMS ARE COMPLETED-05000334     010781     ON 1/7/81 WHILE PERFORMING ThE SURVEILLANCE TEST ON THE CHLORINE DETECT CONT ROOM HABITBLTY SYS + CONT                         81-005/03L-0   012681     ION SYSTEM. IT WAS DISCOVERED THAT THE 101A AND 101B DETECTORS' ELECTROL 1NSTRUMENTATION & CONTROLS                               036044     30-DAY     YTE WAS NOT DRIPPING. THESE DETECTORS WERE DECLARED OUT OF SERVICE AND SENSOR / DETECTOR / ELEMENT                                                     THE 101A DETECTOR WAS TRIPPED. OPERATION CONTINUED IN ACCORDANCE WITH T DESIGN / FABRICATION ERROR                                                       ECHNICAL SPECIFICATI0H 3.3.3.7. THIS WAS THE ELEVENTH FAILURE OF THIS T MANUFACTURING                                                                   YPE AT BVPS.
THE HEALTH A PERSONNEL ACCESS ND SAFETY OF THE PUBLIC WERE NOT JEOPARDIZED SINCE LEAKAGE THROUGH THE A DESIGN / FABRICATION ERROR IRLOCK WAS PREVENTED BY THE INNER DOOR WHICH RC"AINED SEALED.
DESIGN OTHER PREPARATIONS WERE BEING MADE TO RETURN THE PLANT TO PCWER FOLLOWING AN U NPLANNED OUTAGE TO REPAIR THE PRESSURIZER SAFETY VALVES.
AT 2230 HOURS, WHILE STILL IN. HOT STANDBY. THE AIRLOCK WAS RETURNED TO SERVICE AFTER C LEANING, GREASING AND REALIGNING THE SEALS.
BEAVER VALLEY-1 05000334 010681 DURING THE PERFORMANCE OF A SURVEILLANCE TEST ON THE CONTROL ROOM EMERGE CONT ROOM HABITBLTY SYS + COHT 81-004/03L-0 020481 NCY SUPPLY FANS. THE AIR FiOW CALCULATIONS INDICATED FLOW RATES OF 464 A VALVES 036043 30-DAY ND 473 CFM.
TECHNICAL SPECIFICATION 4.7.7.1 REQUIRES A SYSTEM FLOW RATE PROPORTIONING LOUVER OF 400 CFM +/- 10% DURING SYSTEM OPERATION. THE HEALTH AND SAFETY OF T DESIGN / FABRICATION ERROR HE GENERAL PUBLIC AND SITE PERSONNEL WERE NOT JEOPARDIZED.
DESIGN OTHER AFTER AN ADJUSTMENT WAS MADE TO THE SUPPLY FANS INLET DAMPER. THE FLOW R ATE WAS VERIFIED TO BE WITHIN ACCEPlABLE LIMITS.
THE SURVEILLANCE TEST WAS COMPLETED SATISFACTORILY AT 1400 HOURS ON JANUARY 6, 1981.
BEAVER VALLEY-1 05000334 010681 ON 1/6/81 THE DUQUESHE LIGHT COMPANY ENGINEERING DEPARTMENT REPORTED TH MAIN STEAM SYSTEMS + CCHTROLS 81-001/01T-0 012081 AT 32" SHP-1. 2. 3-601-Q2 SUPPORTS H-162. H-164 AMD H-166 HAD MOT BEEN M HANGERS. SUPPORTS. SHOCK SUPPRSS 036179 2-WEEK ODIFIED AS ORIGINALLY REPORTED IN THE 8/14/80 IE BULLETIN 79-14 LETTER.
SUPPORTS THIS IS A VIOLATION OF TECHNICAL SPECIFICATION 6.9.1.8.I.
ANALYSIS OF DESIGN / FABRICATION ERROR STRUCTURES. THE CONSEQUENCES OF SUPPORT FAILURE DUE TO PIPE WHIP IS POS DESIGN TULATED TO BE FAILURE OF THE MAIN STEAM VALVE HOUSE WALL. RESULTING IN F OTHER AILURE OF THE OTHER TWO STEAM LINES.DUE TO FALLING DEBRIS.
CAUSE OF PROBLEM IS THAT ILLEGIBLE CRAWINGS WERE TRANSf11TTED TO CONSTRUC TION DEPARTMENT FOR USE.
MHEN DRAWINGS WERE SENT BACK FOR BETTER COFIES THE DRAWING PERTAINING TO SUPPORTS H-162, H-164 A H-166 WAS LOST.
WOR K ON H-162. 164 & 166 WAS C0f1PLETED ON 1/7/81 & A LETTER FROM QUALITY AS SURANCE DEPT. WAS RECEIVED. VERIFYING THAT ALL OTHER ITEMS ARE COMPLETED-BEAVER VALLEY-1 05000334 010781 ON 1/7/81 WHILE PERFORMING ThE SURVEILLANCE TEST ON THE CHLORINE DETECT CONT ROOM HABITBLTY SYS + CONT 81-005/03L-0 012681 ION SYSTEM. IT WAS DISCOVERED THAT THE 101A AND 101B DETECTORS' ELECTROL 1NSTRUMENTATION & CONTROLS 036044 30-DAY YTE WAS NOT DRIPPING. THESE DETECTORS WERE DECLARED OUT OF SERVICE AND SENSOR / DETECTOR / ELEMENT THE 101A DETECTOR WAS TRIPPED. OPERATION CONTINUED IN ACCORDANCE WITH T DESIGN / FABRICATION ERROR ECHNICAL SPECIFICATI0H 3.3.3.7.
THIS WAS THE ELEVENTH FAILURE OF THIS T MANUFACTURING YPE AT BVPS.
WALLACE & TIERNAN, INC.
WALLACE & TIERNAN, INC.
THE WICKS WERE REPLACED AND THE URIFICES CLEANED. EUGINEERING HAS BEEN REQUESTED TO EVALUATE THIS SYSTEM DUE TO THE REPEATED FAILURES.
THE WICKS WERE REPLACED AND THE URIFICES CLEANED.
EUGINEERING HAS BEEN REQUESTED TO EVALUATE THIS SYSTEM DUE TO THE REPEATED FAILURES.


MAR 26, 1981                                                             LER MONTHLY REPORT SORTED BY FACILITY                                                                                       PAGE 5 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                   DOCKET NO./       EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 5 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                             REPORT DATE/                                                                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                       CONTROL NO.       REPORT TYPE                                                                                 CAUSE DESCRIPTION BEAVER VALLEY-1                                         05000334             010781                                           WITH THE REACTOR SHUTDOWN. AN OPERATOR WAS PERFORMING A MANIPULATION OF COOLANT RECIRC SYS + CONTROLS                         81-002/01T-0           012131                                           THE SEAL LEAK-OFF VALVES AT 1105 HOURS WHEN THE SEAL FLOW DROFPED BELCW PUMPS                                                     036080             2-WEEK                                             THE MINIMUM ON THE 1C REACTOR COOLANT PUMP. THE ONLY RCP RUNNING. THE P CENTRIFUGAL                                                                                                                   UMP WAS MANUALLY TRIPPED, AS REQUIRED. HOWEVER. TECH. SPEC. 3.4.1.1 REQU DESIGN / FABRICATION ERROP                                                                                                       IRES AT LEAST ONE PUMP RUNNING. PUMP WAS RESTARTED WITHIN 20 MIN. THERE DESIGN                                                                                                                         WAS A MINIMUM OF DECAY HEAT IN CORE 8 SUBC00 LED CONDITIONS WERE MAINTAIN DTHER                                                                                                                           ED.       HEALTH & SAFETY OF THE PUBLIC 8 SITE PERSONNEL WAS NOT JEOPADIZED.
EVENT DATE/
THE CAUSE OF THE UNSTABLE SEAL FLOW OCCURRED DURING THE VALVING ATTEMPT TO TRANSFER THE RCP SEAL LEAK-OFF FLOW PATH. THE VALVING INVOLVED IS SE NSITIVE ENDUGH TO CAUSE THIS INSTABILITY. THE PLANT ENGINEERING GROUP I S INVESTIGATING A PROPOSED WESTINGHOUSE SOLUTION TO THIS PROBLEM.               ,
COMPONENT SUBCODE/CAUSE CODE / LER NO./
i BEAVER VALLEY-1                                           05000334             010881                                           WITH A REACTOR START-UP IN PROGRESS, A CURVEILLANCE TEST WAS BEING PERF0 EMERG CORE COOLING SYS + CONT                         81-0 06 / 0 3L-0       020681                                           RMED ON THE LOW HEAD SAFETY INJECTION PUMPS WHEN THE WATER IN THE COMMON ELECTRICAL CONDUCTORS                                     036045             30-DAY                                                 RECIRCULATION LINE ON THE REFUELING WATER STORAGE TANK WAS FOUND FROZEN SUBCOMPONENT NOT APPLICABLE                                                                                                     . IN ACCORDANCE WIin T.S. 3.5.3, BOTH PUMPS WERE DECLARED INOPERABLE AT DEFECTIVE PROCEDURES                                                                                                                   1850 HOURS. THE EFFRGENCY CORE COOLING FLOW PATH WAS UNAFFECTED BY THI NOT APPLICABLE                                                                                                                 S BLOCKAGE AND THE HIGH HEAD SAFETY INJECTION PUMPS WERE AVAILABLE. THE OTHER                                                                                                                                 HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE i?OT JEOPARDIZED.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BEAVER VALLEY-1 05000334 010781 WITH THE REACTOR SHUTDOWN. AN OPERATOR WAS PERFORMING A MANIPULATION OF COOLANT RECIRC SYS + CONTROLS 81-002/01T-0 012131 THE SEAL LEAK-OFF VALVES AT 1105 HOURS WHEN THE SEAL FLOW DROFPED BELCW PUMPS 036080 2-WEEK THE MINIMUM ON THE 1C REACTOR COOLANT PUMP. THE ONLY RCP RUNNING. THE P CENTRIFUGAL UMP WAS MANUALLY TRIPPED, AS REQUIRED. HOWEVER. TECH. SPEC. 3.4.1.1 REQU DESIGN / FABRICATION ERROP IRES AT LEAST ONE PUMP RUNNING. PUMP WAS RESTARTED WITHIN 20 MIN. THERE DESIGN WAS A MINIMUM OF DECAY HEAT IN CORE 8 SUBC00 LED CONDITIONS WERE MAINTAIN DTHER ED.
HEALTH & SAFETY OF THE PUBLIC 8 SITE PERSONNEL WAS NOT JEOPADIZED.
THE CAUSE OF THE UNSTABLE SEAL FLOW OCCURRED DURING THE VALVING ATTEMPT TO TRANSFER THE RCP SEAL LEAK-OFF FLOW PATH.
THE VALVING INVOLVED IS SE NSITIVE ENDUGH TO CAUSE THIS INSTABILITY. THE PLANT ENGINEERING GROUP I S INVESTIGATING A PROPOSED WESTINGHOUSE SOLUTION TO THIS PROBLEM.
i BEAVER VALLEY-1 05000334 010881 WITH A REACTOR START-UP IN PROGRESS, A CURVEILLANCE TEST WAS BEING PERF0 EMERG CORE COOLING SYS + CONT 81-0 06 / 0 3L-0 020681 RMED ON THE LOW HEAD SAFETY INJECTION PUMPS WHEN THE WATER IN THE COMMON ELECTRICAL CONDUCTORS 036045 30-DAY RECIRCULATION LINE ON THE REFUELING WATER STORAGE TANK WAS FOUND FROZEN SUBCOMPONENT NOT APPLICABLE
. IN ACCORDANCE WIin T.S.
3.5.3, BOTH PUMPS WERE DECLARED INOPERABLE AT DEFECTIVE PROCEDURES 1850 HOURS.
THE EFFRGENCY CORE COOLING FLOW PATH WAS UNAFFECTED BY THI NOT APPLICABLE S BLOCKAGE AND THE HIGH HEAD SAFETY INJECTION PUMPS WERE AVAILABLE. THE OTHER HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE i?OT JEOPARDIZED.
THE HEAT TRACE CIRCUIT (HERMOSTAT FOR THE FROZEN LINE WAS FOUND IN THE O FF POSITION. THE THERM 05 TATS WERE SET IMMEDIATELY AND THE LINE THAWED.
THE HEAT TRACE CIRCUIT (HERMOSTAT FOR THE FROZEN LINE WAS FOUND IN THE O FF POSITION. THE THERM 05 TATS WERE SET IMMEDIATELY AND THE LINE THAWED.
AT 1048 HOURS ON 1/9/81, THE PUMPS WERE DECLARED OPERABLE. AN INVESTIG ATIOC OF OTHER SAFETY-RELATED HEAT TRACING WAS INITIATED AND THEIR OPERA BILITY VERIFIED.
AT 1048 HOURS ON 1/9/81, THE PUMPS WERE DECLARED OPERABLE. AN INVESTIG ATIOC OF OTHER SAFETY-RELATED HEAT TRACING WAS INITIATED AND THEIR OPERA BILITY VERIFIED.
BEAVER VALLEY-1                                           05000334             011281                                           AT 1130 HOURS WITH THE PLANT AT 50 PERCENT POWER. A LOW PRESSURE ALARM W EMERG CORE COOLING SYS + CONT                         81-0C8/03L-0             021181                                           AS RECEIVED ON THE 1C SAFETY INJECTION ACCUMULATOR ISI-TK-1C). PLANT OP VALVES                                                   036081             30-DAY                                             ERATION CONTINUED AS PER TECH. SPEC. 3.5.1. THE HEALTH AND SAFETY OF TH GLOBE                                                                                                                           E PUBLIC WERE NOT JEOPARDIZED SINCE ONLY TWO ACCUMULATORS ARE REQUIRED F COMPONENT FAILURE                                                                                                               OR ADEQUATE CORE COOLING IN THE EVENT OF A LOSS OF COOLANT ACCIDENT. TH MECHANICAL                                                                                                                     E REMAINING TWO ACCUMULATORS WERE CAPABLE OF FULFILLING THIS FUNCTION.
BEAVER VALLEY-1 05000334 011281 AT 1130 HOURS WITH THE PLANT AT 50 PERCENT POWER. A LOW PRESSURE ALARM W EMERG CORE COOLING SYS + CONT 81-0C8/03L-0 021181 AS RECEIVED ON THE 1C SAFETY INJECTION ACCUMULATOR ISI-TK-1C).
PLANT OP VALVES 036081 30-DAY ERATION CONTINUED AS PER TECH. SPEC.
3.5.1.
THE HEALTH AND SAFETY OF TH GLOBE E PUBLIC WERE NOT JEOPARDIZED SINCE ONLY TWO ACCUMULATORS ARE REQUIRED F COMPONENT FAILURE OR ADEQUATE CORE COOLING IN THE EVENT OF A LOSS OF COOLANT ACCIDENT. TH MECHANICAL E REMAINING TWO ACCUMULATORS WERE CAPABLE OF FULFILLING THIS FUNCTION.
VELAN VALVE CORP.
VELAN VALVE CORP.
THE PRESSURE IN ISI-TK-1C) WAS RESTORED ABOVE THE TECH. SPEC. LIMIT OF 6 05 PSIG AT 1203 HOURS. THE SUSPECTED CAUSE FOR THE LOW PRESSURE IS A LE AKING DRAIN VALVE. AN INVESTIGATION TO FIND THE LEAKIhG VALVE OR VALVES WILL BE MADE DURING THE NEXT GUTAGE AND THEY WILL BE REPAIRED OR REPLAC ED AS REQUIRED.
THE PRESSURE IN ISI-TK-1C) WAS RESTORED ABOVE THE TECH. SPEC. LIMIT OF 6 05 PSIG AT 1203 HOURS.
BEAVER VALLEY-1                                           05000334             011481                                           ON 1/14/81 AT 95 PERCENT POWER, WHILE PEPFORMING THE SURVEILLANCE TEST CONT ROOM HABITBLTY SYS + CONT                       81-007/03L-0             012681                                           ON THE CHLORINE DETECTION SYSTEM, IT WAS DISCOVERED THAT THE 101A AND to INSTRUMENTATION + CONTROLS                               036046               30-DAY                                             1B DETECTORS' ELECTROLYTE WAS NOT DRIPPING. THESE DETECTORS WERE DECLAR SENSOR / DETECTOR / ELEMENT                                                                                                     ED OUT OF SERVICE AND THE 101B DETECTOR WAS TRIPPED. OPERATION CONTINUE DESIGN / FABRICATION ERROR                                                                                                       D IN ACCORDANCE WITH TECHNICAL SPECIFICATIGN 3.3.3.7. THIS WAS THE TWEL MANUFACTURING                                                                                                                   FTH FAILURE OF THIS TYPE AT BVPS.
THE SUSPECTED CAUSE FOR THE LOW PRESSURE IS A LE AKING DRAIN VALVE.
AN INVESTIGATION TO FIND THE LEAKIhG VALVE OR VALVES WILL BE MADE DURING THE NEXT GUTAGE AND THEY WILL BE REPAIRED OR REPLAC ED AS REQUIRED.
BEAVER VALLEY-1 05000334 011481 ON 1/14/81 AT 95 PERCENT POWER, WHILE PEPFORMING THE SURVEILLANCE TEST CONT ROOM HABITBLTY SYS + CONT 81-007/03L-0 012681 ON THE CHLORINE DETECTION SYSTEM, IT WAS DISCOVERED THAT THE 101A AND to INSTRUMENTATION + CONTROLS 036046 30-DAY 1B DETECTORS' ELECTROLYTE WAS NOT DRIPPING. THESE DETECTORS WERE DECLAR SENSOR / DETECTOR / ELEMENT ED OUT OF SERVICE AND THE 101B DETECTOR WAS TRIPPED. OPERATION CONTINUE DESIGN / FABRICATION ERROR D IN ACCORDANCE WITH TECHNICAL SPECIFICATIGN 3.3.3.7.
THIS WAS THE TWEL MANUFACTURING FTH FAILURE OF THIS TYPE AT BVPS.
WALLACE 8 TIERNAN. INC.
WALLACE 8 TIERNAN. INC.
THE WICKS WERE REPLACED AND THE ORIFICES CLEANED. ENGINEERING HAS BEEN REQUESTED TO EVALUATE THIS SYSTEM DUE TO THE REPEATED FAILURES.
THE WICKS WERE REPLACED AND THE ORIFICES CLEANED. ENGINEERING HAS BEEN REQUESTED TO EVALUATE THIS SYSTEM DUE TO THE REPEATED FAILURES.


i i
i i
i MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 6 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS F ACIL ITY/SYST E. /COMPON ENT/   DCCKET NO./   EVENT DATE/
i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 6 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS F ACIL ITY/SYST E. /COMPON ENT/
i        COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                                   EVENT DESCRIPTION /
DCCKET NO./
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION BEAVER VALLEY-1                           05000334     011781     OH 1/17/81 A SURVEILLANCE TEST MAS PERFORMED TO VERIFY THE OPERABILITY EMERG CORE COOLING SYS + CONT         81-009/03L-C   021381     0F VARIOUS CONTAINMENT ISOLATICN VALVES. [MOV-SI-864B) WAS STROKED SHUT VALVES                                   036082     30-DAY     BUT THEN FAILED TO RE-OPEN, ISOLATING ONE OF THE TWO LOW HEAD SAFETY IN OTHER                                                         JECTION TRAINS FOR A PERIOD OF 11 MINUTES. PLANT OPERATION CONTINUED AS OTHER                                                           PER TECH. SPEC. 3.S.2. THE DEGRADATION TO PLANT AND PUBLIC SAFETY WAS NOT APPLICJBLE                                                 MINIMAL SINCE ONE LOW HEAD TRAIN REMAINED OPERATIONAL AND WAS CAPABLE OF OTHER                                                             PROVIDING EMERGENCY COOLING IF REQUIRED.
EVENT DATE/
AFTER DISPATCHING AN OPERATOR TO THE VALVE, IT WAS MANUALLY OPENED SEVER AL TURNS OF THE HANDWHEEL AND THEN FULLY RE-OPENED ELECTRICALLY IN 11 MI NUTES TIME. THE INITIAL FAILURE TO RE-OPEN WAS CAUSED BY THE VALVE'S OP EN TORQUE CUTOUT SWITCH BEING OUT OF ADJUSTMENT. THE SWITCH WAS ADJUSTE D AND THE VALVE RETURNED TO SERVICE AT 1015 HOURS ON t/18/81 GEAVER VALLEY-1                           05000334     012181     ON 1/21/81 REACTOR COOLANT SYSTEM LOOP t LOW FLOW ANNUNCIATOR BEGAN INT               ,
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REACTOR TRIP SYSTEMS                 81-010/03L-0 022081       ERMITTENTLY FLASHING IN ALARM. AT 1239 HOURS. FLOW CHANNEL 414 WAS REMD INSTRUMENTATION + CONTROLS               036225     30-DAY     VED FROM SERVICE AND ITS ASSOCIATED BISTABLE TRIPPED WHEN IT WAS FOUND R TRANSMITTER                                                   EADING THE LOWEST OF THE THREE LOOP 1 FLOW CHANNELS. POWER OPERATION CO COMPONENT FAILURE                                               NTINUED AS PER TECHNICAL SPECIFICATION 3.3.1.1.         THE PUBLIC HEALTH AND S INSTRUMENT                                                   AFETY WERE NOT JEOPARDIZED %INCE THE CHANNEL FAILURE WAS IN THE CONSERVA WESTINGHOUSE ELECTRIC CORP.                                     TIVE DIRECTION.
REPORT DATE/
DURING THE INITIAL INVESTIGATION, A LOW VOLTAGE INPUT TO THE TRANSMITTER WAS DISCOVERED. AFTER MAKING AN ADJUSTMENT. THE CHANNEL WAS RETURNED T 0 SERVICE ON 1/23/81.     CONTINUING PROBLEMS WITH THIS CHANNEL HAVE DEVELO PED AND ARE NOW UNDER INVESTIGATION. THEY HAVE BEEN ATTRIBUTED TO EITHE R TRANSMITTER DRIFT OR A SMALL LEAK THROUGH TRANSMITTER BYPASS VALVE.
EVENT DESCRIPTION /
BEAVER VALLEY-1                           05000334     012181     WHILE PERFORMING A SURVEILLANCE TEST ON THE CONTROL ROOM CHLORINE DETECT CONT ROOM HABITBLTY SYS + CONT       81-011/03L-0   022081     ION SYSTEM AT 1840 HOURS, IT WAS DISCOVERED THAT THE 101A AND 101B DETEC INSTRUMENTATION + CONTROLS               036226     30-DAY     TOR'S ELECTROLYTE WAS NOT DRIPPING AND THE 10lc DETECTOR HAD A SLOW DRIP             '
i CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
SENSOR / DETECTOR / ELEMENT                                     RATE. THE DETECTORS WERE DECLARED INOPERABLE AND THE OPERATION OF THE DESIGN / FABRICATION ERROR                                     SYSTEM CONTINUED IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.3.3.7. TH MANUFACTURING                                                 IS IS THE THIRTEENTH REPORTED EVENT INVOLVING THE CHLORINE DETECTORS.
REPORT TYPE CAUSE DESCRIPTION BEAVER VALLEY-1 05000334 011781 OH 1/17/81 A SURVEILLANCE TEST MAS PERFORMED TO VERIFY THE OPERABILITY EMERG CORE COOLING SYS + CONT 81-009/03L-C 021381 0F VARIOUS CONTAINMENT ISOLATICN VALVES.
[MOV-SI-864B) WAS STROKED SHUT VALVES 036082 30-DAY BUT THEN FAILED TO RE-OPEN, ISOLATING ONE OF THE TWO LOW HEAD SAFETY IN OTHER JECTION TRAINS FOR A PERIOD OF 11 MINUTES. PLANT OPERATION CONTINUED AS OTHER PER TECH. SPEC.
3.S.2.
THE DEGRADATION TO PLANT AND PUBLIC SAFETY WAS NOT APPLICJBLE MINIMAL SINCE ONE LOW HEAD TRAIN REMAINED OPERATIONAL AND WAS CAPABLE OF OTHER PROVIDING EMERGENCY COOLING IF REQUIRED.
AFTER DISPATCHING AN OPERATOR TO THE VALVE, IT WAS MANUALLY OPENED SEVER AL TURNS OF THE HANDWHEEL AND THEN FULLY RE-OPENED ELECTRICALLY IN 11 MI NUTES TIME.
THE INITIAL FAILURE TO RE-OPEN WAS CAUSED BY THE VALVE'S OP EN TORQUE CUTOUT SWITCH BEING OUT OF ADJUSTMENT. THE SWITCH WAS ADJUSTE D AND THE VALVE RETURNED TO SERVICE AT 1015 HOURS ON t/18/81 GEAVER VALLEY-1 05000334 012181 ON 1/21/81 REACTOR COOLANT SYSTEM LOOP t LOW FLOW ANNUNCIATOR BEGAN INT
,t REACTOR TRIP SYSTEMS 81-010/03L-0 022081 ERMITTENTLY FLASHING IN ALARM.
AT 1239 HOURS. FLOW CHANNEL 414 WAS REMD INSTRUMENTATION + CONTROLS 036225 30-DAY VED FROM SERVICE AND ITS ASSOCIATED BISTABLE TRIPPED WHEN IT WAS FOUND R TRANSMITTER EADING THE LOWEST OF THE THREE LOOP 1 FLOW CHANNELS. POWER OPERATION CO COMPONENT FAILURE NTINUED AS PER TECHNICAL SPECIFICATION 3.3.1.1.
THE PUBLIC HEALTH AND S INSTRUMENT AFETY WERE NOT JEOPARDIZED %INCE THE CHANNEL FAILURE WAS IN THE CONSERVA WESTINGHOUSE ELECTRIC CORP.
TIVE DIRECTION.
DURING THE INITIAL INVESTIGATION, A LOW VOLTAGE INPUT TO THE TRANSMITTER WAS DISCOVERED. AFTER MAKING AN ADJUSTMENT. THE CHANNEL WAS RETURNED T 0 SERVICE ON 1/23/81.
CONTINUING PROBLEMS WITH THIS CHANNEL HAVE DEVELO PED AND ARE NOW UNDER INVESTIGATION. THEY HAVE BEEN ATTRIBUTED TO EITHE R TRANSMITTER DRIFT OR A SMALL LEAK THROUGH TRANSMITTER BYPASS VALVE.
BEAVER VALLEY-1 05000334 012181 WHILE PERFORMING A SURVEILLANCE TEST ON THE CONTROL ROOM CHLORINE DETECT CONT ROOM HABITBLTY SYS + CONT 81-011/03L-0 022081 ION SYSTEM AT 1840 HOURS, IT WAS DISCOVERED THAT THE 101A AND 101B DETEC INSTRUMENTATION + CONTROLS 036226 30-DAY TOR'S ELECTROLYTE WAS NOT DRIPPING AND THE 10lc DETECTOR HAD A SLOW DRIP SENSOR / DETECTOR / ELEMENT RATE.
THE DETECTORS WERE DECLARED INOPERABLE AND THE OPERATION OF THE DESIGN / FABRICATION ERROR SYSTEM CONTINUED IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.3.3.7.
TH MANUFACTURING IS IS THE THIRTEENTH REPORTED EVENT INVOLVING THE CHLORINE DETECTORS.
WALLICE & TIERNAN, INC.
WALLICE & TIERNAN, INC.
AT 1914 HOURS. THE if:C DETECTOR WAS ADJUSTED AND DECLARED OPERABLE. TH E 101A AND 101B DEfEL. ORS WERE REPAIRED AND DECLARED OPERABLE ON 1/29/81
AT 1914 HOURS. THE if:C DETECTOR WAS ADJUSTED AND DECLARED OPERABLE. TH E 101A AND 101B DEfEL. ORS WERE REPAIRED AND DECLARED OPERABLE ON 1/29/81
                                                                      . THE CAUSE OF THE REPEATED FAILURES OF THE DETECTOPS TO FUNCTION PROPE RLY HAS NOT BEEN SATISFACTORILY IDENTIFIED. THE PROBLEM IS BEING INVEST IGATED TO DETERMINE THE CORRECTIVE ACTIONS.
. THE CAUSE OF THE REPEATED FAILURES OF THE DETECTOPS TO FUNCTION PROPE RLY HAS NOT BEEN SATISFACTORILY IDENTIFIED. THE PROBLEM IS BEING INVEST IGATED TO DETERMINE THE CORRECTIVE ACTIONS.
QEAVER VALLEY-1                           05000334     012181     AT 1535 HOURS ON t/21/81. THE 1A MAIN FILTER BANK WAS DECLARED INOPERABL CNTNMNT AIR PURI + CLEANUP SYS       81-013/03L-0   022081     E AS A RESULT OF A ROUTINE LAB ANALYSIS DONE ON THE BANK'S CHARCOAL BED.
QEAVER VALLEY-1 05000334 012181 AT 1535 HOURS ON t/21/81. THE 1A MAIN FILTER BANK WAS DECLARED INOPERABL CNTNMNT AIR PURI + CLEANUP SYS 81-013/03L-0 022081 E AS A RESULT OF A ROUTINE LAB ANALYSIS DONE ON THE BANK'S CHARCOAL BED.
FILTERS                                   036227     30-DAY       THE ANALYSIS-SHOWED THAT THE METHYL IODIDE REMOVAL EFFICIENCY FOR THE B SUBCOMPONENT NOT APPLICABLE                                   ED HAD FALLEN BELOW 90 PERCENT. POWER OPERATION CONTINUED IN ACCORDANCE COMPONENT FAILURE                                                 WITH TECHNICAL SPECIFICATION 3.7.8.1. THE EFFECT TO THE HEALTH AND SAF-NATURAL END OF LIFE                                           ETY OF THE PUBLIC WAS MINIMAL SINCE THE BED EFFICIENCY AT THE TIME OF DI BARNEBEY-CHENEY                                                 SCOVERY HAD ONLY DROPPED TO 86.6 PERCENT.
FILTERS 036227 30-DAY THE ANALYSIS-SHOWED THAT THE METHYL IODIDE REMOVAL EFFICIENCY FOR THE B SUBCOMPONENT NOT APPLICABLE ED HAD FALLEN BELOW 90 PERCENT. POWER OPERATION CONTINUED IN ACCORDANCE COMPONENT FAILURE WITH TECHNICAL SPECIFICATION 3.7.8.1.
THE-CHARCOAL BED HAD REACHED THE END OF ITS HORMAL LIFE EXPECTANCY. THE FILTER BANK WAS RE-PACKED WITH NEW CHARCOAL AND RETURNED TO SERVICE ON 1/26/81. A DESIGN CHANGE HAS BEEN INITIATED TO INSTALL AN ADDITIONAL 30 CHARCOAL CELLS PER BANK. THIS WILL GREATLY EXTEND THE CHARCOAL SERVICE LIFE BY REDUCING THE AIR VELOCITY THROUGH EACH INDIVIDUAL CELL.
THE EFFECT TO THE HEALTH AND SAF-NATURAL END OF LIFE ETY OF THE PUBLIC WAS MINIMAL SINCE THE BED EFFICIENCY AT THE TIME OF DI BARNEBEY-CHENEY SCOVERY HAD ONLY DROPPED TO 86.6 PERCENT.
__          _                              .-            .        ___ __        .          _                          . . ~
THE-CHARCOAL BED HAD REACHED THE END OF ITS HORMAL LIFE EXPECTANCY. THE FILTER BANK WAS RE-PACKED WITH NEW CHARCOAL AND RETURNED TO SERVICE ON 1/26/81.
A DESIGN CHANGE HAS BEEN INITIATED TO INSTALL AN ADDITIONAL 30 CHARCOAL CELLS PER BANK.
THIS WILL GREATLY EXTEND THE CHARCOAL SERVICE LIFE BY REDUCING THE AIR VELOCITY THROUGH EACH INDIVIDUAL CELL.
. ~


MAR 26, 1981                                     LER MONTHLY REPORT SORTED BY FACILITY                                                                               'PAGE 7 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILTTY/ SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY
COMPONENT SUSCODE/CAUSE CODE / LER NO./     REPORT DATE/                                                                       EVENT DESCRIPTION /
'PAGE 7 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILTTY/ SYSTEM / COMPONENT /
CAUSE SUBCODE/ MANUFACTURER   CONTROL NO. REPORT TYPE                                                                       CAUSE DESCRIPTION DIG ROCK POINT                       05000155     020180                 FOLLOWING OBSERVATION OF MINOR TEMPERATURE 2 PRESSURE CHANGES IN REACTOR' COOL SYS FCR REAC AUX + CONT       80-004/01X-1   021781                   COOLING WATER AUXILIARY SYSTEMS. INVESTIGATION BY OPERATIONS PERSONNEL PENETRATIONS,PRIMRY CONTAINMNT       030127     OTHER                 GN 1/31/80 REVEALED A BROKEN AIR TUBING LINE TO CONTROL VALVE CV4029. T INSTRUMENT LINE                                                       HE LINE WAS TEMPORARILY REPAIRED AT 0110 HRS ON 1/31/80. FOLLOWING REVI OTPER                                                                     EW BY TECHNICAL PERSONNEL ON 2/1/30. THE LINE. WHICH REPRESENIS A CONTAI NLT APPLICABLE                                                         NMENT BOUNDARY. WAS REPAIRED 4 TESTED ON 2/1/30. NO HAZARD TO PUBLIC OCC ITEM NOT APPLICABLE                                                     URRED.                             NOT REPETITIVE. REPORTABILITY BASED ON TECH. SPEC. 6.9.2.A.(3).
DOCKET NO./
CONTRACTOR WORKERS MAY HAVE UNKNOWINGLY BROKEN THE TUBING WHILE DOING M0 DIFICATION WORK IN THE AREA ABOUT'2200 HRS ON 1/30/80. OTHER CONTAINMEN T PENETRATION TUBING IN THE AREA WAS INSPECTED 8 A TEMPORARY CAUTION SIG N WAS POSITIONED NEARBY. DURING A REFUELING OUTAGE. THE CONTROL AIR TUB                               i ING PENETRATIONS FOR THREE VALVES WERE ELIMINATED BY A MODIFICATION.
EVENT DATE/
BIG ROCK POINT                       0500015S     091980                 DURING ROUTINE ANNUAL LEAK RATE AND OPERABILITY CHECKS (PER TECH SPEC 3.
COMPONENT SUSCODE/CAUSE CODE / LER NO./
CNTNMNT ISOLATION SYS + CONT       80-030/03X-1   021781                 7 (B)) 0F CONTAINMENT ISOLATION VALVE CV027 IN THE REACTOR AND FUEL PIT UALVES                               032697     OTHER                 DRAIN LINE, MINOR THROUGH SEAT LEAKAGE IN EXCESS OF TECH SPEC LIMITS WAS GLOBE                                                                     OBSERVED. THE BACK-UP VALVE CV4117 IN SERIES WAS FOUND TO BE ACCEPTABL OTHER                                                                   E AND WAS TAGGED AND DISABLED IN THE CLOSED CONDITION UNTIL REPAIRS COUL NOT APPLICABLE                                                         D BE MADE DURING A PLANT SHUTDCWN. NO HAZARD TO THE PUBLIC OCCURRED. R QLACK-SIVALS-BRYSON                                                     EPORTABILITY BASED ON TECHNICAL SPECIFICATION 6.9.2.B(2).
REPORT DATE/
INVESTIGATION DURING A REFUELING OUTAGE REVEALED THAT THE SPRING THAT PR                               i 0VIDES THE SEATING FORCE WAS NOT PROPERLY TENSIONED. THIS APPEARS TO BE'                               !
EVENT DESCRIPTION /
THE PRIME CAUSE FOR EVENT R0-79-23 ALSO. THE EXACT CAUSE OF THE SPRING DEFECT IS NOT KNOWN.                             THE VALVE OPERATOR WAS ADJUSTED AND THE SEAT WAS REPLACED FER THE COMMITMENT IN R0-79-23.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
BIG ROCK POINT                       05000155     123080                 ROUTINE CALIBRATION OF THE CONTAINMENT BUILDINC LEVEL TRANSMITTER INDICA' EMERG CORE COOLING SYS + CONT     80-049/03L-0   012881                 TED AN OUTPUT CORRESPONDING TO 587 1/2' LEVEL WHEN THE ACTUAL LEVEL SHOU INSTRUMENTATION + CONTROLS           033693     30-DAY                 LD HAVE BEEN 590'. THE 590' LEVEL IS AN OPERATOR ACTION POINT FOR TERMI TRANSMITTER                                                             NATION OF INJECTION WATER TO PROTECT CORE SPRAY SYSTEM VALVE CONTROLS AN OTHER                                                                   D THUS THE ERROR IS NOT CONSERVATIVE. A SECOND LEVEL SYSTEM PROVIDES PA NOT APPLICABLE                                                         RTIAL REDUNDANCY. THE TRANSMITTER WAS RECALIBRATED ON 12/30/80. REPORT
REPORT TYPE CAUSE DESCRIPTION DIG ROCK POINT 05000155 020180 FOLLOWING OBSERVATION OF MINOR TEMPERATURE 2 PRESSURE CHANGES IN REACTOR' COOL SYS FCR REAC AUX + CONT 80-004/01X-1 021781 COOLING WATER AUXILIARY SYSTEMS. INVESTIGATION BY OPERATIONS PERSONNEL PENETRATIONS,PRIMRY CONTAINMNT 030127 OTHER GN 1/31/80 REVEALED A BROKEN AIR TUBING LINE TO CONTROL VALVE CV4029.
'BARTON INSTRU CO., DIV 0F ITT                                           ABILITY BASED ON T/S 6.9.2.B(1). NO HAZARD TO THE PUBLIC OCCURRED.
T INSTRUMENT LINE HE LINE WAS TEMPORARILY REPAIRED AT 0110 HRS ON 1/31/80.
FOLLOWING REVI OTPER EW BY TECHNICAL PERSONNEL ON 2/1/30. THE LINE. WHICH REPRESENIS A CONTAI NLT APPLICABLE NMENT BOUNDARY. WAS REPAIRED 4 TESTED ON 2/1/30. NO HAZARD TO PUBLIC OCC ITEM NOT APPLICABLE URRED.
NOT REPETITIVE. REPORTABILITY BASED ON TECH. SPEC. 6.9.2.A.(3).
CONTRACTOR WORKERS MAY HAVE UNKNOWINGLY BROKEN THE TUBING WHILE DOING M0 DIFICATION WORK IN THE AREA ABOUT'2200 HRS ON 1/30/80.
OTHER CONTAINMEN T PENETRATION TUBING IN THE AREA WAS INSPECTED 8 A TEMPORARY CAUTION SIG N WAS POSITIONED NEARBY.
DURING A REFUELING OUTAGE. THE CONTROL AIR TUB i
ING PENETRATIONS FOR THREE VALVES WERE ELIMINATED BY A MODIFICATION.
BIG ROCK POINT 0500015S 091980 DURING ROUTINE ANNUAL LEAK RATE AND OPERABILITY CHECKS (PER TECH SPEC 3.
CNTNMNT ISOLATION SYS + CONT 80-030/03X-1 021781 7 (B)) 0F CONTAINMENT ISOLATION VALVE CV027 IN THE REACTOR AND FUEL PIT UALVES 032697 OTHER DRAIN LINE, MINOR THROUGH SEAT LEAKAGE IN EXCESS OF TECH SPEC LIMITS WAS GLOBE OBSERVED. THE BACK-UP VALVE CV4117 IN SERIES WAS FOUND TO BE ACCEPTABL OTHER E AND WAS TAGGED AND DISABLED IN THE CLOSED CONDITION UNTIL REPAIRS COUL NOT APPLICABLE D BE MADE DURING A PLANT SHUTDCWN. NO HAZARD TO THE PUBLIC OCCURRED. R QLACK-SIVALS-BRYSON EPORTABILITY BASED ON TECHNICAL SPECIFICATION 6.9.2.B(2).
INVESTIGATION DURING A REFUELING OUTAGE REVEALED THAT THE SPRING THAT PR i
0VIDES THE SEATING FORCE WAS NOT PROPERLY TENSIONED. THIS APPEARS TO BE' THE PRIME CAUSE FOR EVENT R0-79-23 ALSO.
THE EXACT CAUSE OF THE SPRING DEFECT IS NOT KNOWN.
THE VALVE OPERATOR WAS ADJUSTED AND THE SEAT WAS REPLACED FER THE COMMITMENT IN R0-79-23.
BIG ROCK POINT 05000155 123080 ROUTINE CALIBRATION OF THE CONTAINMENT BUILDINC LEVEL TRANSMITTER INDICA' EMERG CORE COOLING SYS + CONT 80-049/03L-0 012881 TED AN OUTPUT CORRESPONDING TO 587 1/2' LEVEL WHEN THE ACTUAL LEVEL SHOU INSTRUMENTATION + CONTROLS 033693 30-DAY LD HAVE BEEN 590'.
THE 590' LEVEL IS AN OPERATOR ACTION POINT FOR TERMI TRANSMITTER NATION OF INJECTION WATER TO PROTECT CORE SPRAY SYSTEM VALVE CONTROLS AN OTHER D THUS THE ERROR IS NOT CONSERVATIVE. A SECOND LEVEL SYSTEM PROVIDES PA NOT APPLICABLE RTIAL REDUNDANCY. THE TRANSMITTER WAS RECALIBRATED ON 12/30/80. REPORT
'BARTON INSTRU CO., DIV 0F ITT ABILITY BASED ON T/S 6.9.2.B(1). NO HAZARD TO THE PUBLIC OCCURRED.
AN EXACT CAUSE OF THE DEFICIENCY IN THE BARTON MODEL 386 TRANSMITTER WAS NOT DETERMINED. NO ABNORMAL DRIFT HAS BEEN NOTED PREVIOUSLY. THE INST RUMENT ACCURACY HAS BEEN CHECKED ON TWO OCCASIONS SUBSEQUENT TO 12/30/80 AND WAS FOUND ACCEP1ABLE. THE UNIT WILL BE TESTED AGAIN PRIOR TO OR DU RING THE NEXT REFUELING OUTAGE.
AN EXACT CAUSE OF THE DEFICIENCY IN THE BARTON MODEL 386 TRANSMITTER WAS NOT DETERMINED. NO ABNORMAL DRIFT HAS BEEN NOTED PREVIOUSLY. THE INST RUMENT ACCURACY HAS BEEN CHECKED ON TWO OCCASIONS SUBSEQUENT TO 12/30/80 AND WAS FOUND ACCEP1ABLE. THE UNIT WILL BE TESTED AGAIN PRIOR TO OR DU RING THE NEXT REFUELING OUTAGE.
BROWNS FERRY-1                       05000259     100680                 DURING NORMAL OPERATION, AN OPERATOR DISCOVERED LOSS OF VALVE POSITION I-REAC CORE ISOL COOL SYS + CONT     80-075/03X-1   012981                 NDICATION FOR RCIC STEAM SUPPLY VALVE FCV-71-3. THE VALVE WOULD HAVE CL OTHER COMPONENTS                     032897     OTHER                 OSED FROM AN AUTO CLOSE SIGNAL 1.UT THE OPERATOR WOULD NOT HAVE BEEN AWAR SUBCOMPONENT NOT APPLICABLE                                             E OF THE POSITION. REFERENCE TECHNICAL SPECIFICATION 3.7.D.1 1 2 AND 3.
BROWNS FERRY-1 05000259 100680 DURING NORMAL OPERATION, AN OPERATOR DISCOVERED LOSS OF VALVE POSITION I-REAC CORE ISOL COOL SYS + CONT 80-075/03X-1 012981 NDICATION FOR RCIC STEAM SUPPLY VALVE FCV-71-3.
COMPONENT FAILURE                                                       5.F.2.                             HPCI WAS AVAILABLE. iHERE WERE NO SIGNIFICANT RESULTING EVENTS.
THE VALVE WOULD HAVE CL OTHER COMPONENTS 032897 OTHER OSED FROM AN AUTO CLOSE SIGNAL 1.UT THE OPERATOR WOULD NOT HAVE BEEN AWAR SUBCOMPONENT NOT APPLICABLE E OF THE POSITION. REFERENCE TECHNICAL SPECIFICATION 3.7.D.1 1 2 AND 3.
CORROSION                                                                   THERE WAS NO DANGER To HEALTH OR SAFETY OF PUBLIC. NO PREVIOUS DCCURR GENERAL ELECTRIC CO.                                                     ENCES.
COMPONENT FAILURE 5.F.2.
CAUSE WAS CORROSION ON GE.                               '2 POINT. 600V. 30 AMP. MODEL 6422482612 TERM INAL BLOCK. INSIDE JUNCT. BOX 1681. CORRODED TERT 1. MERE BYPASSED TEMP BY REMOVING 8 SPLICING TOGETHEP ASSOC WIRING. IERM BLOCK WILL BE REPLACED DURING NEXT EXTENDED OUTAGE. UNIT 2 & 3 JUNCT BOXES HAVE BEEN INSPECTED 4 WERE FOUND TO BE WELL-SEALED 8 TERM BLOCKS FREE OF CORROSION.
HPCI WAS AVAILABLE. iHERE WERE NO SIGNIFICANT RESULTING EVENTS.
CORROSION THERE WAS NO DANGER To HEALTH OR SAFETY OF PUBLIC. NO PREVIOUS DCCURR GENERAL ELECTRIC CO.
ENCES.
CAUSE WAS CORROSION ON GE.
'2 POINT. 600V. 30 AMP. MODEL 6422482612 TERM INAL BLOCK. INSIDE JUNCT. BOX 1681. CORRODED TERT 1. MERE BYPASSED TEMP BY REMOVING 8 SPLICING TOGETHEP ASSOC WIRING. IERM BLOCK WILL BE REPLACED DURING NEXT EXTENDED OUTAGE. UNIT 2 & 3 JUNCT BOXES HAVE BEEN INSPECTED 4 WERE FOUND TO BE WELL-SEALED 8 TERM BLOCKS FREE OF CORROSION.


l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 8 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./     EVENT DATE/
l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 8 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION BROWNS FERRY-1                               05000259         121780   DURING NORMAL OPERATION, WHILE PERFORMING SI 4.7.H. DRYWELL HYDROGEN MON ENGNRD SAFETY FEATR INSTR SYS       80-091/03X-1     021381     ITOR, 1-HC2)M-76-39. WOULD NOT CALIBRATE PROPERLY TO CALIBRATION GAS (TE INSTRUMENTATION + CONTROLS             033550         OTHER     CH. SPEC. 3.7.H-3). REDUNDANT 1-H(2)M-76-37 WAS OPERABLE. THERE WAS NO SENSOR / DETECTOR / ELEMENT COMPONENT FAILURE                                                  EFFECT ON THE PUBLIC HEALTH OR SAFETY. PREVIOUS EVENTS: 296/80-37 AND 260/80-36.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-1 05000259 121780 DURING NORMAL OPERATION, WHILE PERFORMING SI 4.7.H.
DRYWELL HYDROGEN MON ENGNRD SAFETY FEATR INSTR SYS 80-091/03X-1 021381 ITOR, 1-HC2)M-76-39. WOULD NOT CALIBRATE PROPERLY TO CALIBRATION GAS (TE INSTRUMENTATION + CONTROLS 033550 OTHER CH. SPEC. 3.7.H-3).
REDUNDANT 1-H(2)M-76-37 WAS OPERABLE. THERE WAS NO SENSOR / DETECTOR / ELEMENT EFFECT ON THE PUBLIC HEALTH OR SAFETY. PREVIOUS EVENTS: 296/80-37 AND COMPONENT FAILURE 260/80-36.
INSTRUMENT GENERAL ELECTRIC CD.
INSTRUMENT GENERAL ELECTRIC CD.
THE GE MODEL 47E226428G2 SENSOR FAILED. ALTERNATE SENSOR 1-HC2)E-76-39A WAS CONNECTED TO THE HYDROGEN MONITOR AND SI 4.7.H COMFLETED SATISFACTO RILY. THIS SYSTEM WILL BE REPLACED WITH A HAYES-REPUBLIC SYSTEM AT THE NEXT REFUELING OUTAGE.
THE GE MODEL 47E226428G2 SENSOR FAILED. ALTERNATE SENSOR 1-HC2)E-76-39A WAS CONNECTED TO THE HYDROGEN MONITOR AND SI 4.7.H COMFLETED SATISFACTO RILY.
BROWNS FERRY-1                                 05000259       010581   DURING NORMAL OPERATION, WHILE PERFORMIFG SI 4.2.B-24. CORE SPRAY SPARGE ENGNRD SAFETY FEATR INSTR SYS       81-001/03L-0     012881   R TO RPV D/P SWITCH t-PDIS-75-28 WAS FOUND SET AT 1.4 PSID.
THIS SYSTEM WILL BE REPLACED WITH A HAYES-REPUBLIC SYSTEM AT THE NEXT REFUELING OUTAGE.
INSTRUMENTATION + CONTROLS             036019         30-DAY                                                                         TECHNICAL 5 SWITCH                                                        PECIFICATION 3.2.B LIMIT IS 2 +/- 0.4 PSID. REDUNDANT SWITCH 1-PDIS                                                                                     56 WAS OPERABLE.       THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF THE PUB COMPONENT FAILURE                                               LIC. PREVIOUS EVENT:     259/80-87.
BROWNS FERRY-1 05000259 010581 DURING NORMAL OPERATION, WHILE PERFORMIFG SI 4.2.B-24. CORE SPRAY SPARGE ENGNRD SAFETY FEATR INSTR SYS 81-001/03L-0 012881 R TO RPV D/P SWITCH t-PDIS-75-28 WAS FOUND SET AT 1.4 PSID.
INSTRUMENT DARTON INSTRU CO., DIV 0F ITT THE BARTON MODEL 288 SETPOINT HAD DRIFTED. THE SWITCH WAS RECALIBRATED AND FUNCTIONALLY TESTED FOR REPEATABILITY. THE SWITCH WAS REPLACED WITH A NEW SWITCH ON JANUARY 15, 1981       NO FURTHER ACTION IS PLANNED.
TECHNICAL 5 INSTRUMENTATION + CONTROLS 036019 30-DAY PECIFICATION 3.2.B LIMIT IS 2 +/- 0.4 PSID.
BROWNS FERRY-1                                 05000259       011481   DURING NORMAL OPERATION, A SMOKE DETECTOR IN RELAY ROOM ALARMED AND WOUL FIRE PROTECTION SYS + CONT           81-002/03L-0     020581   D NOT CLEAR.
REDUNDANT SWITCH 1-PDIS SWITCH 56 WAS OPERABLE.
INSTRUMENTATION + CONTROLS              036170                                      THE ALARM WOULD HAVE MASKED SIGNALS FROM DETECTORS REQUIRE 30-DAY   D TO BE OPERATIONAL BY TECHNICAL SPECIFICATION 3.11.C.1           THERE WERE NO SENSOR / DETECTOR / ELEMENT                                   SIGNIFICANT RESULTING EVENTS. THERE WERE NO EFFECTS ON PUBLIC HEALTH OR COMPONENT FAILURE                                                   SAFETY.
THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF THE PUB COMPONENT FAILURE LIC.
NATURAL END OF LIFE                                                        THERE ARE NO REDUNDANT SYSTEMS. PREVIOUS OCCURRENCE:       BFRO-50 KIODE, WALTER & CO
PREVIOUS EVENT:
                                                                                    -259/80-41.
259/80-87.
INCREASED DETECTOR SENSITIVITY DUE TO NORMAL, NATURAL AGING CAUSED THE E VENT. DETECTOR WAS REPLACED AND SUCCESSFULLY TESTED PER SI 4.11.C.1 AND
INSTRUMENT DARTON INSTRU CO., DIV 0F ITT THE BARTON MODEL 288 SETPOINT HAD DRIFTED. THE SWITCH WAS RECALIBRATED AND FUNCTIONALLY TESTED FOR REPEATABILITY. THE SWITCH WAS REPLACED WITH A NEW SWITCH ON JANUARY 15, 1981 NO FURTHER ACTION IS PLANNED.
: 5. KIDDE IONIZATION DETECTOR, MODEL FT-200. NO RECURRENCE CONTROL PEQ UIRED.
BROWNS FERRY-1 05000259 011481 DURING NORMAL OPERATION, A SMOKE DETECTOR IN RELAY ROOM ALARMED AND WOUL FIRE PROTECTION SYS + CONT 81-002/03L-0 020581 D NOT CLEAR.
BROWNS FERRY-1                                 05000259       012481   DURING NORMAL OPERATION, THE PLANT RECEIVED NOTIFICATION FROM TVA'S DIVI REACTIVITY CONTROL SYSTEMS           81-003/01T-0     020481 COMPONENT CODE NOT APPLICABLE            036083                  SION OF ENGINEERING DESIGN THAT THE ONE-INCH VENT LINE ON UNIT 1 SCRAM D 2-WEEK   ISCHARGE VOLUME WAS NOT SEISMICALLY QUALIFIED BASED ON ANALYSIS RESULTIN SUBCOMPONENT NOT APPLICABLE                                   G FROM NRC IE BULLETIN 79-14 INSPECTION DATA. REFERENCE FSAR CHAPTER 12 DESIGN / FABRICATION ERROR                                       . NO SIGNIFICANT RESULTING EVENTS. NO DANGER TO HEALTH OR SAFETY OF TH CONSTRUCTION / INSTALLATION                                   E PUBLIC. NO PREVIOUS OCCURRENCES.
THE ALARM WOULD HAVE MASKED SIGNALS FROM DETECTORS REQUIRE INSTRUMENTATION + CONTROLS 036170 30-DAY D TO BE OPERATIONAL BY TECHNICAL SPECIFICATION 3.11.C.1 THERE WERE NO SENSOR / DETECTOR / ELEMENT SIGNIFICANT RESULTING EVENTS.
ITEM NOT APPLICABLE THE AS-CONSTRUCTED PIPING CONFIGURATION DID NOT CONFORM TO DESIGN REQUIR EMENTS. SEISMIC RESTRAINTS WERE INSTALLED ON THE ONE INCH VENT LINE. T HIS PUT THE SYSTEM IN A " MINIMUM POTENTIAL FOR PRESSURE BOUNDARY FAILURE
THERE WERE NO EFFECTS ON PUBLIC HEALTH OR COMPONENT FAILURE SAFETY.
                                                                                    " CATEGORY.
THERE ARE NO REDUNDANT SYSTEMS. PREVIOUS OCCURRENCE:
BFRO-50 NATURAL END OF LIFE
-259/80-41.
KIODE, WALTER & CO INCREASED DETECTOR SENSITIVITY DUE TO NORMAL, NATURAL AGING CAUSED THE E VENT.
DETECTOR WAS REPLACED AND SUCCESSFULLY TESTED PER SI 4.11.C.1 AND 5.
KIDDE IONIZATION DETECTOR, MODEL FT-200.
NO RECURRENCE CONTROL PEQ UIRED.
BROWNS FERRY-1 05000259 012481 DURING NORMAL OPERATION, THE PLANT RECEIVED NOTIFICATION FROM TVA'S DIVI REACTIVITY CONTROL SYSTEMS 81-003/01T-0 020481 SION OF ENGINEERING DESIGN THAT THE ONE-INCH VENT LINE ON UNIT 1 SCRAM D COMPONENT CODE NOT APPLICABLE 036083 2-WEEK ISCHARGE VOLUME WAS NOT SEISMICALLY QUALIFIED BASED ON ANALYSIS RESULTIN SUBCOMPONENT NOT APPLICABLE G FROM NRC IE BULLETIN 79-14 INSPECTION DATA.
REFERENCE FSAR CHAPTER 12 DESIGN / FABRICATION ERROR
. NO SIGNIFICANT RESULTING EVENTS.
NO DANGER TO HEALTH OR SAFETY OF TH CONSTRUCTION / INSTALLATION E PUBLIC. NO PREVIOUS OCCURRENCES.
ITEM NOT APPLICABLE THE AS-CONSTRUCTED PIPING CONFIGURATION DID NOT CONFORM TO DESIGN REQUIR EMENTS.
SEISMIC RESTRAINTS WERE INSTALLED ON THE ONE INCH VENT LINE.
T HIS PUT THE SYSTEM IN A " MINIMUM POTENTIAL FOR PRESSURE BOUNDARY FAILURE
" CATEGORY.


MAR 26. 1981                                                                               LER MONTHLY REPORT SORTED BY FACILITY                                                                   PAGE 9 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                   DOCKET NO./         EVENT DATE/
MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 9 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                               REPORT DATE/                                           EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                       CONTROL NO.         REPORT TYPE                                             CAUSE DESCRIPTION BROWNS FERRY-1                                                             05000259         012581           DURING NORMAL OPERATION AN OPERATOR OBSERVED THAT SBGT TRAIN "C" RELATIV SYS REQRD FOR SAFE SHUTDOWN                                             81-004/03L-0       020981           E HUMIDITY HEATERS DID NOT FUNCTION PROPERLY 3 SBGT TRAIN "C" DECLARED-IN INSTRUMENTATION + CONTROLS                                                   036180         30-DAY           OPERABLE AT 1400. (TECH SPEC 3.7.B.1) THIS SYSTEM IS COMMON TO UNIT 1.-
EVENT DATE/
SWITCH                                                                                                         2. AND 3. THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
COMPONENT FAILURE                                                                                             SBGT TRAINS "A" AND "B" WERE OPERABLE. PREVIOUS EVEHTS: NONE..
REPORT DATE/
INSTRUMENT DUST SUPPRESSION SYSTEMS A DWYER PHOT 0 HELIC PRESSURE SWITCH / GAGE CIRCUIT HH AND AN ITE IMPERIAL R                     j ELAY CONTACT BLOCK MALFUNCTIONED. SI 4.7.C WAS PERFORMED M!THIH 2 HOURS AND THE MALFUNCTIONING COMPONENTS WERE REPAIRED. SBGT TPAEH "C" WAS RE TURNED TO SERVICE AT 0645 ON JANUARY 26, 1981.                     NO RECURRENCE CONTROL AC TION IS PLANNED.                                                                                   l BROWNS FERRY-1                                                             05000259         012981           DURING POWER INCREASES. THE TECHNICAL SPECIFICATION LIMIl 0F 13.33'KW/FT REACTOR CORE                                                             81-0 0 7/ 0 3L-0   021381             FOR LINEAR HEAT GENERATION RATE WAS EXCEEDED IN ONE N3DE. (T.S. 3.5.J)
EVENT DESCRIPTION /
FUEL ELEMENTS                                                               036182         30-DAY           . THE NODE REACHED 13.77 KW/FT. PREVIOUS EVENTS: 50-259/80-53. 50-259 SUBCOMPONENT NOT APPLICABLE                                                                                 /80-56. AND 50-259/80-78. THERE WAS NO EFFECT ON THE PUBLIC HEALTH OR S PERSONNEL ERROR                                                                                               AFETY AND HO RESULTIUG SIGNIFICANT CHAIN OF EVENTS.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
LICENSED 3 SENIOR OPERATORS ITEM NOT APPLICABLE UNANTICTVAYED RAPID POWER DENSITY INCREASE DUE TO A XENON TkANSIENT WHIC H RESULTED FROM INCREASED CORE POWER FOLLOWING A LOAD DECREASE. LOAD WA S DECREASED 25 MWE. LARGER MARGIN TO LIMITS WILL BE MAINTAINED DURING X ENON TRANSIENTS.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-1 05000259 012581 DURING NORMAL OPERATION AN OPERATOR OBSERVED THAT SBGT TRAIN "C" RELATIV SYS REQRD FOR SAFE SHUTDOWN 81-004/03L-0 020981 E HUMIDITY HEATERS DID NOT FUNCTION PROPERLY 3 SBGT TRAIN "C" DECLARED-IN INSTRUMENTATION + CONTROLS 036180 30-DAY OPERABLE AT 1400.
BROWNS FERRY-1                                                             05000259         013181           DURING STEADY STATE OPERATION, PH OF THE RESERVOIR NEAR THE PL ANT WAS F0 CHEM. VOL CONT + LIQ POISH SYS                                           81-005/04L-0       020981           UND TO BE IN EXCESS OF THE ALLOWABLE DISCHARGE LIMIT OF 9.e PH.                         MONITOR COMPONENT CODE NOT APPLICABLE                                               036181         30-DAY           ING WAS IN PROGRESS TO SUPPORT THE ROUTINE RELEASE OF SPEFt DEMINERALIZE SUBCOMPONENT NOT APPLICABLE                                                                                 D REGENERANTS. TECHNICAL SPECIFICATION: ETS 2 2.1..THERE MAS NO DANGER OTHER                                                                                                           TO THE PUBLIC. NO PREVIOUS OCCURRENCES.
(TECH SPEC 3.7.B.1)
NOT APPLICABLE ITEM NOT APPLICABLE THE CAUSE OF THE EXCESS PH VALUE IS UNKNOWN.                     HOWEVER. IT APPEARS TO BE CAUSED BY AN UPSTREAM SOURCE.         THE DISCHARGE OF SPENT REGE5ERANTS WAS ST OPPED. A TEMPORARY PROGRAM WAS ESTABLISHED TO MONITOR THE RESERVOIR PH.
THIS SYSTEM IS COMMON TO UNIT 1.-
SWITCH 2.
AND 3.
THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC.
COMPONENT FAILURE SBGT TRAINS "A" AND "B" WERE OPERABLE. PREVIOUS EVEHTS: NONE..
INSTRUMENT DUST SUPPRESSION SYSTEMS A DWYER PHOT 0 HELIC PRESSURE SWITCH / GAGE CIRCUIT HH AND AN ITE IMPERIAL R j
ELAY CONTACT BLOCK MALFUNCTIONED. SI 4.7.C WAS PERFORMED M!THIH 2 HOURS AND THE MALFUNCTIONING COMPONENTS WERE REPAIRED. SBGT TPAEH "C" WAS RE TURNED TO SERVICE AT 0645 ON JANUARY 26, 1981.
NO RECURRENCE CONTROL AC TION IS PLANNED.
l BROWNS FERRY-1 05000259 012981 DURING POWER INCREASES. THE TECHNICAL SPECIFICATION LIMIl 0F 13.33'KW/FT REACTOR CORE 81-0 0 7/ 0 3L-0 021381 FOR LINEAR HEAT GENERATION RATE WAS EXCEEDED IN ONE N3DE.
(T.S. 3.5.J)
FUEL ELEMENTS 036182 30-DAY
. THE NODE REACHED 13.77 KW/FT.
PREVIOUS EVENTS:
50-259/80-53. 50-259 SUBCOMPONENT NOT APPLICABLE
/80-56. AND 50-259/80-78.
THERE WAS NO EFFECT ON THE PUBLIC HEALTH OR S PERSONNEL ERROR AFETY AND HO RESULTIUG SIGNIFICANT CHAIN OF EVENTS.
LICENSED 3 SENIOR OPERATORS ITEM NOT APPLICABLE UNANTICTVAYED RAPID POWER DENSITY INCREASE DUE TO A XENON TkANSIENT WHIC H RESULTED FROM INCREASED CORE POWER FOLLOWING A LOAD DECREASE. LOAD WA S DECREASED 25 MWE.
LARGER MARGIN TO LIMITS WILL BE MAINTAINED DURING X ENON TRANSIENTS.
BROWNS FERRY-1 05000259 013181 DURING STEADY STATE OPERATION, PH OF THE RESERVOIR NEAR THE PL ANT WAS F0 CHEM. VOL CONT + LIQ POISH SYS 81-005/04L-0 020981 UND TO BE IN EXCESS OF THE ALLOWABLE DISCHARGE LIMIT OF 9.e PH.
MONITOR COMPONENT CODE NOT APPLICABLE 036181 30-DAY ING WAS IN PROGRESS TO SUPPORT THE ROUTINE RELEASE OF SPEFt DEMINERALIZE SUBCOMPONENT NOT APPLICABLE D REGENERANTS. TECHNICAL SPECIFICATION: ETS 2 2.1..THERE MAS NO DANGER OTHER TO THE PUBLIC. NO PREVIOUS OCCURRENCES.
NOT APPLICABLE ITEM NOT APPLICABLE THE CAUSE OF THE EXCESS PH VALUE IS UNKNOWN.
HOWEVER. IT APPEARS TO BE CAUSED BY AN UPSTREAM SOURCE.
THE DISCHARGE OF SPENT REGE5ERANTS WAS ST OPPED. A TEMPORARY PROGRAM WAS ESTABLISHED TO MONITOR THE RESERVOIR PH.
HD RECURRENCE CONTROL REQUIRED.
HD RECURRENCE CONTROL REQUIRED.
    -B20WNS FERRY-2                                                             05000260         011980           DURING NORMAL OPERATION. CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY REACTOR CORE                                                             81-005/03L-0       020681             EXCEEDED LIMIT BY 0.002 FOR ONE NODE IN CORE. DISCOVERY WAS MADE BY-RE COMPONENT CODE NOT APPLICABLE                                               036085         30-DAY           VIEW OF N00N COMPUTER EDIT AT APPROXIMATELY 1430. NO REDUNDANT SYSTEM.
-B20WNS FERRY-2 05000260 011980 DURING NORMAL OPERATION. CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY REACTOR CORE 81-005/03L-0 020681 EXCEEDED LIMIT BY 0.002 FOR ONE NODE IN CORE.
SUBCOMPONENT NOT APPLICABLE                                                                                   POWER WAS REDUCED APPROXIMATELY 10 MWE.                   THERE WAS NO DANGER TO THE HEA OTHER                                                                                                         LTH OR SAFETY OF THE PUBLIC. NO PREVIOUS OCCURRENCES.
DISCOVERY WAS MADE BY-RE COMPONENT CODE NOT APPLICABLE 036085 30-DAY VIEW OF N00N COMPUTER EDIT AT APPROXIMATELY 1430.
NOT APPLICABLE ITEM NOT APPLICABLE CAUSE OF EVENT WAS OPERATION CLOSE TO A LIMIT IN CONJUNCTION WITH MINOR (NORMAL) PERTURBATION IN MONITORED PARAMETERS SUCH AS RECIRC. FLOW. POW ER WAS SLIGHTLY REDUCED SHORTLY AFTER DISCOVERY TO PREVENT SHORT TERM RE CURRENCE. A PROPOSED TECHNICAL SPECIFICATION REVISION IS BEING PREPARED TO REMOVE POWER SPIKING PENALTY ON 8 X 8 FUEL.
NO REDUNDANT SYSTEM.
SUBCOMPONENT NOT APPLICABLE POWER WAS REDUCED APPROXIMATELY 10 MWE.
THERE WAS NO DANGER TO THE HEA OTHER LTH OR SAFETY OF THE PUBLIC.
NO PREVIOUS OCCURRENCES.
NOT APPLICABLE ITEM NOT APPLICABLE CAUSE OF EVENT WAS OPERATION CLOSE TO A LIMIT IN CONJUNCTION WITH MINOR (NORMAL) PERTURBATION IN MONITORED PARAMETERS SUCH AS RECIRC. FLOW.
POW ER WAS SLIGHTLY REDUCED SHORTLY AFTER DISCOVERY TO PREVENT SHORT TERM RE CURRENCE.
A PROPOSED TECHNICAL SPECIFICATION REVISION IS BEING PREPARED TO REMOVE POWER SPIKING PENALTY ON 8 X 8 FUEL.


s MAR 26. 1981                                                                                   LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE'to PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/                         DOCKET NO./             EVENT DATE/
s MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE'to PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
i                             CCMPONENT SUBCODE/CAUSE CODE / LER NO./                                       REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                           CONTROL NO.           REPORT TYPE                                   CAUSE DESCRIPTION QROWNS FERRY-2                                                                     05000260   091630     WITH THE UNIT IN COLD SHUTDOWN AND REFUELING. DRYWELL CONTROL AIR VALVE CNTNMNT ISOLATION SYS + CONT                                       80-039/03L-1           022081     2-FCV-32-62 COULD NOT BE CLOSED BY OPERATING ITS HANDSWITCH IN THE CONTR VALVE OPERATORS                                                                 032704     30-DAY     OL ROOM. 2-FCV-32-63 UAS OPERABLE. THERE WAS NO EFFECT ON THE HEALTH 0 GTHER                                                                                         R SAFETY OF THE PUBLIC. THESE VALVES SHOULD BE INCLUDED IN TECH. SPEC.
EVENT DATE/
COMPONENT FAILURE                                                                                     3.7.D.2 BUT ARE NOT.
i CCMPONENT SUBCODE/CAUSE CODE / LER NO./
MECHANICAL                                                                                                            THIS FAILURE 15. THEREFORE. VIOLATION OF INTENT OF TECHNICAL SPECIFICATIONS.
REPORT DATE/
ITEM HOT APPLICABLE IT APPEARS THE CONTROL AIR SOLENCID WAS STICKING. THIS COULD NOT BE SUB             '
EVENT DESCRIPTION /
ST ANTI ATED BEC AUSE THE PROBLEM COULD NOT BE REPRODUCED. THE VALVE HAS C YCL ED FROM CONTROL ROOM AND LOCAL HAND SWITCHES. NO FURTHER PROBLEMS WE RE FOUND. CHANGES TO INCLUDE THESE VALVES IN TECHNICAL %PECIFICATION HA VE BEEN INITIATED.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
BROWNS FERRY-2                                                                     05000260   112180     DURING HEATUP AFTER A REFUELING OUTAGE WHILE PERFORMING SI 4.2.B-1. REAC REACTOR TRIP SYSTEMS                                               80-051/03X-1           012988     TOR WATER LEVEL SWITCH 2-LIS-3-58C 5 WITCH 4 (LPCI INITIATION) UAS FOUND INSTRUMENTATION + CONTROLS                                                     0335t4     OTHER     NOT TO OPERATE AT THE PROPFR SETPOINT. (TECHNICAL SPECIFICATION 3.2.B).
REPORT TYPE CAUSE DESCRIPTION QROWNS FERRY-2 05000260 091630 WITH THE UNIT IN COLD SHUTDOWN AND REFUELING. DRYWELL CONTROL AIR VALVE CNTNMNT ISOLATION SYS + CONT 80-039/03L-1 022081 2-FCV-32-62 COULD NOT BE CLOSED BY OPERATING ITS HANDSWITCH IN THE CONTR VALVE OPERATORS 032704 30-DAY OL ROOM.
OTHER                                                                                           REDUNDANT SUITCHES WERE OPERABLE.
2-FCV-32-63 UAS OPERABLE. THERE WAS NO EFFECT ON THE HEALTH 0 GTHER R SAFETY OF THE PUBLIC.
COMPONENT FAILURE THERE WAS NO EFFECT ON THE HEALTH OR MECHANICAL                                                                                      SAFETY OF THE PUBLIC. PREVIOUS EVENTS: 260/80-5. 260/80-1
THESE VALVES SHOULD BE INCLUDED IN TECH. SPEC.
* 259/74-37 YARWAY CORP.
COMPONENT FAILURE 3.7.D.2 BUT ARE NOT.
THE YARWAY CATALOG NUMBER 4418C HAD DIRTY SWITCH CONTACTS. THE CONTACTS WERE CLEANED AND FUNCTIONALLY CHECKED SEVERAL TIMES AT THE PROPER SETP0 INT. THESE SWITCHES WILL BE REPLACED WITH AN ANALOG TRIP SYSTEM BY DCR               '
THIS FAILURE 15. THEREFORE. VIOLATION OF INTENT OF MECHANICAL TECHNICAL SPECIFICATIONS.
1398.
ITEM HOT APPLICABLE IT APPEARS THE CONTROL AIR SOLENCID WAS STICKING. THIS COULD NOT BE SUB ST ANTI ATED BEC AUSE THE PROBLEM COULD NOT BE REPRODUCED. THE VALVE HAS C YCL ED FROM CONTROL ROOM AND LOCAL HAND SWITCHES. NO FURTHER PROBLEMS WE RE FOUND.
QROWNS FERRY-2                                                                     05000260   123080     DURING HORMAL OPERATION. 1HE UNIT OPERATOR OBSERVED FR-77-16 DOWNSCALE W SAFETY RELATED DISPLAY INSTR                                       80-059/03L-0           012681     HILE THE DRYMELL EQUIPMENT DRAIN SUMP PUMP WAS OPERATING. FLOW SYSTEM D' INSTRUMENTATION + CONTROLS                                                     033694     30-DAY     ECLARED INOPERABLE AT 0001 (TECHNICAL SPECIFICATION 3.6.C.2). THERE ARE TRANSMITTER                                                                                     NO REDUNDANT SYSTEMS. THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF T COMPONENT FAILURE                                                                                     HE PUBLIC. PREVIOUS EVENTS: 296/80-19.
CHANGES TO INCLUDE THESE VALVES IN TECHNICAL %PECIFICATION HA VE BEEN INITIATED.
BROWNS FERRY-2 05000260 112180 DURING HEATUP AFTER A REFUELING OUTAGE WHILE PERFORMING SI 4.2.B-1. REAC REACTOR TRIP SYSTEMS 80-051/03X-1 012988 TOR WATER LEVEL SWITCH 2-LIS-3-58C 5 WITCH 4 (LPCI INITIATION) UAS FOUND INSTRUMENTATION + CONTROLS 0335t4 OTHER NOT TO OPERATE AT THE PROPFR SETPOINT. (TECHNICAL SPECIFICATION 3.2.B).
OTHER REDUNDANT SUITCHES WERE OPERABLE.
THERE WAS NO EFFECT ON THE HEALTH OR COMPONENT FAILURE SAFETY OF THE PUBLIC. PREVIOUS EVENTS: 260/80-5. 260/80-1
* 259/74-37 MECHANICAL YARWAY CORP.
THE YARWAY CATALOG NUMBER 4418C HAD DIRTY SWITCH CONTACTS. THE CONTACTS WERE CLEANED AND FUNCTIONALLY CHECKED SEVERAL TIMES AT THE PROPER SETP0 INT.
THESE SWITCHES WILL BE REPLACED WITH AN ANALOG TRIP SYSTEM BY DCR 1398.
QROWNS FERRY-2 05000260 123080 DURING HORMAL OPERATION. 1HE UNIT OPERATOR OBSERVED FR-77-16 DOWNSCALE W SAFETY RELATED DISPLAY INSTR 80-059/03L-0 012681 HILE THE DRYMELL EQUIPMENT DRAIN SUMP PUMP WAS OPERATING. FLOW SYSTEM D' INSTRUMENTATION + CONTROLS 033694 30-DAY ECLARED INOPERABLE AT 0001 (TECHNICAL SPECIFICATION 3.6.C.2).
THERE ARE TRANSMITTER NO REDUNDANT SYSTEMS.
THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF T COMPONENT FAILURE HE PUBLIC. PREVIOUS EVENTS:
296/80-19.
INSTRUMENT GENERAL ELECTRIC CD.
INSTRUMENT GENERAL ELECTRIC CD.
A MODEL 555 GE TRANSMITTER FT77-16 ZERO ADJUSTMENT HAD SHIFTED. THE TRA NSMITTER WAS RECALIBRATED. FUNCTIONALLY TESTED AND RETURNED TO SERVICE A T 1030 ON 12/30/80. HD RECURRENCE CONTROL ACTION IS REQUIRED.
A MODEL 555 GE TRANSMITTER FT77-16 ZERO ADJUSTMENT HAD SHIFTED. THE TRA NSMITTER WAS RECALIBRATED. FUNCTIONALLY TESTED AND RETURNED TO SERVICE A T 1030 ON 12/30/80. HD RECURRENCE CONTROL ACTION IS REQUIRED.
BROWNS FERRY-2                                                                     05000260   010281     DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A-8. SCRAM DISCHARGE INS ENGNRD SAFETY FEATR INSTR SYS                                     81-002/03L-0           012981     TRUMENT VOLUME ROD-BLOCK LEVEL SUITCH (25 OAL) 2-LS-85-45E WAS FOUND SET INSTRUMENTATION + CONTROLS                                                     036020     30-DAY       AT 27 GALLONS. IN ADDITION, 2-LS-85-45F (3 CAL) ALARM SWITCH REMAINS I             e SWITCH                                                                                       NOPERABLE AS REPORTED ON 260/80-58. THERE ARE NO REDUNDANT SYSTEMS. TH               '
BROWNS FERRY-2 05000260 010281 DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A-8.
COMPONENT FAILURE                                                                                     ERE WAS NO.EFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC. PREVIOUS EVENT INSTRUMENT                                                                                   5:   260/80-52. 260/80-58. AND 260/81-01     THIS ITEM REPORTED UNDER NRCB ROBERTSHAW CONTROLS CO.                                                                                 80-t4.
SCRAM DISCHARGE INS ENGNRD SAFETY FEATR INSTR SYS 81-002/03L-0 012981 TRUMENT VOLUME ROD-BLOCK LEVEL SUITCH (25 OAL) 2-LS-85-45E WAS FOUND SET INSTRUMENTATION + CONTROLS 036020 30-DAY AT 27 GALLONS.
IN ADDITION, 2-LS-85-45F (3 CAL) ALARM SWITCH REMAINS I e
SWITCH NOPERABLE AS REPORTED ON 260/80-58.
THERE ARE NO REDUNDANT SYSTEMS.
TH COMPONENT FAILURE ERE WAS NO.EFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC. PREVIOUS EVENT INSTRUMENT 5:
260/80-52. 260/80-58. AND 260/81-01 THIS ITEM REPORTED UNDER NRCB ROBERTSHAW CONTROLS CO.
80-t4.
THE ROBERT SHAM MODEL SL-305-EI-X SETPOINT HAD DRIFTED. THE SWITCH WAS RECALIBRATED. FUNCTIONALLY TESTED AND RETURNED TO SERVICE. THIS SWITCH WILL BE REPLACED AS PART OF CRD IMPROVEMENT DCR 2203.
THE ROBERT SHAM MODEL SL-305-EI-X SETPOINT HAD DRIFTED. THE SWITCH WAS RECALIBRATED. FUNCTIONALLY TESTED AND RETURNED TO SERVICE. THIS SWITCH WILL BE REPLACED AS PART OF CRD IMPROVEMENT DCR 2203.
      ,_ . ._                                          -,_ _      _ . - - _ .- -_                                    .a    .      .. _ _ _ .      __          i,               . _ . . _ _  ,_a,,.~._
i,
,_a,,.~._
.a


MAR 26, 1981                                                                                                                                           LER MONTHLY REPO*T SORTED BY FACILITY                                                                                                                                     PAGE 11 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                                                                     DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPO*T SORTED BY FACILITY PAGE 11 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
l     COMPONENT SUBCODE/CAUSE CODE / LER HO./                                                                                                           REPORT DATE/                                       EVEdT DESCRIPTION /
DOCKET NO./
l     CAUSE SUBCODE/ MANUFACTURER                                                                                                         CONTROL NO. REPORT TYPE                                         CAUSE DESCRIPTION BROWNS FERRY-2                                                                                                                             05000260     011281     DURING NORMAL OPERATION, WHILE PERFORMING SI 4.2.B-21, CORE SPRAY PUMP D ENGNRD SAFETY FEATR INSTR SYS                                                                                                           81-003/03L-0   020481     ISCHARGE PRESSURE SWITCH 2-PS-75-16, WHICH DEFERS ADS ACTUATION, WAS FOU INSTRUMENTATION + CONTROLS                                                                                                                 036084     30-DAY     ND 2.8% OUT OF TECH. SPEC. 3.2.B LIMITS. REDUNDANT SWITCHES 2-PS-75-7, SWITCH                                                                                                                                                           -35 AND -44 WERE OPERABLE. THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OTHER                                                                                                                                                             OF THE PUBLIC. PREVIOUS EVENTS: 260/80-55, 259/80-46, 259/78-3, 259/73.
EVENT DATE/
NOT APPLICABLE                                                                                                                                                   -37.
l COMPONENT SUBCODE/CAUSE CODE / LER HO./
MERCOID CORP MERCOID MODEL DA-7004-804 HAD DRIFTED OUT OF TOLERANCE. THE SWITCH WAS INSPECTED, RECALIBRATED AND SI 4.2.B-21 SUCCESSFULLY COMPLETED. THE SWI TCH WAS REPLACED WITH A NEW SWITCH ON JANUARY 21e 1981.                                                                                                   NO FURTHER ACTI ON IS PLANNED.
REPORT DATE/
BROWNS FERRY-2                                                                                                                             05000260     011981     DURING NORMAL OPERATION WHILE PERFORMING SI-4.1.A-7, REACTOR WATER LEVEL REACTOR TRIP SYSTEMS                                                                                                                     81-004/01T-0   012881     SWITCHES LIS-3-203A SWITCH 1               LIS-3-A, B, C, AND D SWITCHES 2 WERE FOUN INSTRUMENTATION + CONTROLS                                                                                                                 036021     2-WEEK     D OUTSIDE TECHNICAL SPEC 1FICATION 3.1.A AND 3.E.B LIMITS BY 2.3%; 0.6%;
EVEdT DESCRIPTION /
SWITCH       .
l CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
2.1%, AND 3.6% RESPECTIVELY. REDUNDANT SUITCHES LIS-3-203 B, C, AND D S COMPONENT FAILURE                                                                                                                                                 WITCHES UERE OPERATING WITHIN LIMITS. THERE WAS NO EFFECT ON THE HEALTH INSTRUMENT                                                                                                                                                       OR SAFE 7Y OF THE PUBLIC. PREVIOUS EVENTS: 260/80-29.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-2 05000260 011281 DURING NORMAL OPERATION, WHILE PERFORMING SI 4.2.B-21, CORE SPRAY PUMP D ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 020481 ISCHARGE PRESSURE SWITCH 2-PS-75-16, WHICH DEFERS ADS ACTUATION, WAS FOU INSTRUMENTATION + CONTROLS 036084 30-DAY ND 2.8% OUT OF TECH. SPEC. 3.2.B LIMITS. REDUNDANT SWITCHES 2-PS-75-7, SWITCH
BARTON INSTRU CO., DIV 0F ITT THE BARTON MODEL 288 SWITCHES DRIFTED DUE TO AIR IMPACT DRILLING NEXT TO THE PANEL ON WHICH THEY WERE. MOUNTED. THIS DRILLING WAS NECESSARY TO I NSTALL PANEL STANCHION GUARDS. EACH SWITCH WAS INSPECTED, RECALIBRATED, FUNCTIONALLY TESTED AND RETURNED TO SERVICE. NO RECURRENCE CONTROL CAN.
-35 AND -44 WERE OPERABLE.
THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OTHER OF THE PUBLIC. PREVIOUS EVENTS:
260/80-55, 259/80-46, 259/78-3, 259/73.
NOT APPLICABLE
-37.
MERCOID CORP MERCOID MODEL DA-7004-804 HAD DRIFTED OUT OF TOLERANCE. THE SWITCH WAS INSPECTED, RECALIBRATED AND SI 4.2.B-21 SUCCESSFULLY COMPLETED. THE SWI TCH WAS REPLACED WITH A NEW SWITCH ON JANUARY 21e 1981.
NO FURTHER ACTI ON IS PLANNED.
BROWNS FERRY-2 05000260 011981 DURING NORMAL OPERATION WHILE PERFORMING SI-4.1.A-7, REACTOR WATER LEVEL REACTOR TRIP SYSTEMS 81-004/01T-0 012881 SWITCHES LIS-3-203A SWITCH 1 LIS-3-A, B, C, AND D SWITCHES 2 WERE FOUN INSTRUMENTATION + CONTROLS 036021 2-WEEK D OUTSIDE TECHNICAL SPEC 1FICATION 3.1.A AND 3.E.B LIMITS BY 2.3%; 0.6%;
SWITCH 2.1%, AND 3.6% RESPECTIVELY. REDUNDANT SUITCHES LIS-3-203 B, C, AND D S COMPONENT FAILURE WITCHES UERE OPERATING WITHIN LIMITS.
THERE WAS NO EFFECT ON THE HEALTH INSTRUMENT OR SAFE 7Y OF THE PUBLIC. PREVIOUS EVENTS:
260/80-29.
BARTON INSTRU CO., DIV 0F ITT THE BARTON MODEL 288 SWITCHES DRIFTED DUE TO AIR IMPACT DRILLING NEXT TO THE PANEL ON WHICH THEY WERE. MOUNTED. THIS DRILLING WAS NECESSARY TO I NSTALL PANEL STANCHION GUARDS.
EACH SWITCH WAS INSPECTED, RECALIBRATED, FUNCTIONALLY TESTED AND RETURNED TO SERVICE. NO RECURRENCE CONTROL CAN.
BE IDENTIFIED AT THIS-TIME.
BE IDENTIFIED AT THIS-TIME.
BROWNS FERRY-2                                                                                                                             05000260     012181     DURING NORMAL OPERATION, CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY REACTOR CORE                                                                                                                             31-006/03L-0   920681     LIMIT WAS EXCEEDED FOLLOWING A 10 MUE INCREASE VIA RECIRCULATION FLOU.
BROWNS FERRY-2 05000260 012181 DURING NORMAL OPERATION, CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY REACTOR CORE 31-006/03L-0 920681 LIMIT WAS EXCEEDED FOLLOWING A 10 MUE INCREASE VIA RECIRCULATION FLOU.
COMPONENT CODE NOT APPLICABLE                                                                                                               036086     >0-DAY     PROBLEM WAS NOT IMMEDIATELY DISCOVERED EECAUSE THE PROCESS COMPUTER WAS SUBCOMPONENT NOT APPLICABLE                                                                                                                                       INOPERABLE FOR APPROXIMATELY 10 HOURS. POWER WAS REDUCED.                                                                                                   THERE WAS H OTHER                                                                                                                                                             0 DANGER TO HEALTH OR SAFETY OF PUBLIC. PREVIOUS OCCURRENCE:                                                                                                     BFRO-50-2
COMPONENT CODE NOT APPLICABLE 036086
:  NOT APPLICABLE                                                                                                                                                   60/81-005. REFERENCE TECH. SPEC. 3.5.J.
>0-DAY PROBLEM WAS NOT IMMEDIATELY DISCOVERED EECAUSE THE PROCESS COMPUTER WAS SUBCOMPONENT NOT APPLICABLE INOPERABLE FOR APPROXIMATELY 10 HOURS.
l ITEM NOT APPLICABLE EVENT CAUSED BY POWER INCREASE IN CONJUNCTION WITH INOPERABLE PROCESS CD MPUTER. POWER IMMEDIATELY REDUCED UPON DISCOVERY AND A NOTE POSTED IN C R TO REMIND OPERATOR HOT TO INCREASE POWER.                             THERE WAS A CONTROL ROD PAT TERN ADJUSTMENT MADE JANUARY 23, 1981 FOR RECURRENCE CONTROL.
POWER WAS REDUCED.
BROWNS FERRY-3                                                                                                                             05000296     040280   WITH UNIT AT 100 PERCENT STEADY STATE POWER, THE 3B DIESEL GENERATOR GOV AC ONSITE POWER SYS + CONTROLS                                                                                                           80-008/03X-1   012681     ERNOR ACTUATOR WOULD NOT RESPOND PROPERLY DURING OPERABLILITY SURVEILLAN-MECHANICAL FUNCTION UNITS                                                                                                                   030885     OTHER     CE INSTRUCTION 4.9.A.1,             SUPPLEMENT A. REDUNDANT SYSTEMS WERE OPERABLE.
THERE WAS H OTHER 0 DANGER TO HEALTH OR SAFETY OF PUBLIC. PREVIOUS OCCURRENCE:
SUBCOMPONENT NOT APPLICABLE                                                                                                                                       THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC, AND NO SIGNI OTHER-                                                                                                                                                             FICANT RESULTING CHAIN OF FVENTS. PREVIOUS SIMILAR OCCURRENCE REPORTED NOT APPLICABLE                                                                                                                                                   ON LER BFRO-050-259/76-23.
BFRO-50-2 NOT APPLICABLE 60/81-005.
REFERENCE TECH. SPEC. 3.5.J.
l ITEM NOT APPLICABLE EVENT CAUSED BY POWER INCREASE IN CONJUNCTION WITH INOPERABLE PROCESS CD MPUTER.
POWER IMMEDIATELY REDUCED UPON DISCOVERY AND A NOTE POSTED IN C R TO REMIND OPERATOR HOT TO INCREASE POWER.
THERE WAS A CONTROL ROD PAT TERN ADJUSTMENT MADE JANUARY 23, 1981 FOR RECURRENCE CONTROL.
BROWNS FERRY-3 05000296 040280 WITH UNIT AT 100 PERCENT STEADY STATE POWER, THE 3B DIESEL GENERATOR GOV AC ONSITE POWER SYS + CONTROLS 80-008/03X-1 012681 ERNOR ACTUATOR WOULD NOT RESPOND PROPERLY DURING OPERABLILITY SURVEILLAN-MECHANICAL FUNCTION UNITS 030885 OTHER CE INSTRUCTION 4.9.A.1, SUPPLEMENT A.
REDUNDANT SYSTEMS WERE OPERABLE.
SUBCOMPONENT NOT APPLICABLE THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC, AND NO SIGNI OTHER-FICANT RESULTING CHAIN OF FVENTS. PREVIOUS SIMILAR OCCURRENCE REPORTED NOT APPLICABLE ON LER BFRO-050-259/76-23.
WOODWARD GOVERNOR CO.
WOODWARD GOVERNOR CO.
UNKNOWN; SUSPECTED OIL CONTAMINATION. THE SUMP WAS FLUSHED AND REFILLED WITH NEW OIL, AND SURVEILLANCE INSTRUCTION 4.9.A.I SUPPLEMENT A WAS SUC CESSFULLY RUN. WOODUARD GOVERNOR. TYPE EGB, MODEL 10-C.                                                                                                     OIL WILL BE SA MPLED AND CHANGED ANNUALLY.
UNKNOWN; SUSPECTED OIL CONTAMINATION. THE SUMP WAS FLUSHED AND REFILLED WITH NEW OIL, AND SURVEILLANCE INSTRUCTION 4.9.A.I SUPPLEMENT A WAS SUC CESSFULLY RUN.
                      - _    _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ = _-~                                                                 _ - . .      -        -- -                                                            ..
WOODUARD GOVERNOR. TYPE EGB, MODEL 10-C.
OIL WILL BE SA MPLED AND CHANGED ANNUALLY.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ = _-~


l MAR 26, 1981                                                                     LER MONTHLY REPORT SORTED BY FACILITY                                                   PAGE 12 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS 1
l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 12 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS 1
FACILITY /SYSTEP/ COMPONENT /                             DOCKET NO./   EVENT DATE/
FACILITY /SYSTEP/ COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                 REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                               CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION BROWNS FERRY-3                                                       05000296     051280     UPON COMPLETION OF THE FLOW TEST ON 3B RHR PUMP SEAL HEAT EXCHANGER. IT RESIDUAL HEAT REMOV SYS + CONT                                   80-015/03X-1   012688     WAS DETERMINED THAT THE COOLING WATER FLOW WAS INADEQUATE PER T.S. 3.5.B COMPONENT CODE NOT APPLICABLE                                       033739     OTHER         1(2) AND 3.5.B.5. REDUNDANT SYSTEMS WERE OPERABLE PER TECH. SPEC.               THE SUBCOMPONENT NOT APPLICABLE                                                             RE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. NO RESULTING SIG l        OTHER                                                                                       HIFICANT CHAIN OF EVENTS, AND NO PREVIOUS SIMILAR OCCURRENCES.
EVENT DATE/
I NOT APPLICABLE ITEM NOT APPLICABLE APPARENT RESTRICTION IN THE COOLING WATER PIPING UPSTREAM AND/OR DOWNSTR EAM FROM THE HEAT EXCHANGER. THE HEAT EXCHANGER WAS REMOVED. THE C00LIN C WATER LINES FLUSHED, AND THE UNIT PERFORMED NORMALLY. A SYSTEM FLUSHI NG EVALUATION IS BEING PERFORMED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
BROWHS FERRY-3                                                       05000290     051380     UPON COMPLETION OF THE FLOW TEST ON 3D DIESEL GENERATOR HEAT EXCHANGER.
REPORT DATE/
EMERG GENERATOR SYS + CONTROLS                                 80-016/03X-1   011981     IT WAS DETERMINED THAT THE COOLING WATER FLCW WAS INADEQUATE PER TECHNIC ENGINES. INTERNAL COMBUSTION                                       033695     OTHER       Al SPECIFICATION 3.9.B.2. REDUNDANT SYSTEMS 3A. 3B. AND 3C DIESEL GENER SUBCOMPONENT NOT APPLICABLE                                                             ATORS WERE OPERABLE. THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE OTHER                                                                                         PUBLIC. NO RESULTING SIGNIFICANT CHAIN OF EVENTS. PREVIOUS SIMILAR OCC NOT APPLICABLE                                                                         URRENCES ON BFR0 50-296/80-15.
EVENT DESCRIPTION /
ITEM NOT APPLICABLE APPARENT RESTRICTION IN THE COOLING WATER PIPING UPSTREAM AND/OR DOWNSTR                           I EAM FROM THE HEAT EXCHANGER. THE HEAT EXCHANGER WAS REMOVED. THE C00LIN                       ;
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
G WATER LINES FLUSHED. AND UNIT PERFORMED NORMALLY. A SYSTEM FLUSHING E                           !
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 051280 UPON COMPLETION OF THE FLOW TEST ON 3B RHR PUMP SEAL HEAT EXCHANGER. IT RESIDUAL HEAT REMOV SYS + CONT 80-015/03X-1 012688 WAS DETERMINED THAT THE COOLING WATER FLOW WAS INADEQUATE PER T.S.
VALUATION IS BEING PERFORMED.                            .
3.5.B COMPONENT CODE NOT APPLICABLE 033739 OTHER 1(2) AND 3.5.B.5.
BROWNS FERRY-3                                                       05000296     071480     DURING NORMAL OPERATION WHILE PERFORMING SI 4.5.B.1.D. 3D RHR PUMP MOTOR RESIDUAL HEAT REMOV SYS + CONT                                   80-027/03X-1   012981         TRIPPED ON INSTANTANEOUS OVERCURRENT ON "A" PHASE WHEN STARTED. REFERE COMPONENT CODE NOT APPLICABLE                                     032025     OTHER       NCE TECHNICAL SPECIFICATION 3.5.B.3. REMAINING RHR PUMPS. CSS AND DIESE SUSCOMPONENT NOT APPLICABLE                                                             L GENERATORS OPERABLE. THERE WAS NO DANGER TO HEALTH CR SAFETY OF PUBLI OTHER                                                                                     C. NO PREVIOUS OCCURRENCES.
REDUNDANT SYSTEMS WERE OPERABLE PER TECH. SPEC.
THE SUBCOMPONENT NOT APPLICABLE RE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. NO RESULTING SIG OTHER HIFICANT CHAIN OF EVENTS, AND NO PREVIOUS SIMILAR OCCURRENCES.
l I
NOT APPLICABLE ITEM NOT APPLICABLE APPARENT RESTRICTION IN THE COOLING WATER PIPING UPSTREAM AND/OR DOWNSTR EAM FROM THE HEAT EXCHANGER. THE HEAT EXCHANGER WAS REMOVED. THE C00LIN C WATER LINES FLUSHED, AND THE UNIT PERFORMED NORMALLY. A SYSTEM FLUSHI NG EVALUATION IS BEING PERFORMED.
BROWHS FERRY-3 05000290 051380 UPON COMPLETION OF THE FLOW TEST ON 3D DIESEL GENERATOR HEAT EXCHANGER.
EMERG GENERATOR SYS + CONTROLS 80-016/03X-1 011981 IT WAS DETERMINED THAT THE COOLING WATER FLCW WAS INADEQUATE PER TECHNIC ENGINES. INTERNAL COMBUSTION 033695 OTHER Al SPECIFICATION 3.9.B.2.
REDUNDANT SYSTEMS 3A. 3B. AND 3C DIESEL GENER SUBCOMPONENT NOT APPLICABLE ATORS WERE OPERABLE.
THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE OTHER PUBLIC. NO RESULTING SIGNIFICANT CHAIN OF EVENTS.
PREVIOUS SIMILAR OCC NOT APPLICABLE URRENCES ON BFR0 50-296/80-15.
ITEM NOT APPLICABLE APPARENT RESTRICTION IN THE COOLING WATER PIPING UPSTREAM AND/OR DOWNSTR I
EAM FROM THE HEAT EXCHANGER.
THE HEAT EXCHANGER WAS REMOVED. THE C00LIN G WATER LINES FLUSHED. AND UNIT PERFORMED NORMALLY. A SYSTEM FLUSHING E VALUATION IS BEING PERFORMED.
BROWNS FERRY-3 05000296 071480 DURING NORMAL OPERATION WHILE PERFORMING SI 4.5.B.1.D.
3D RHR PUMP MOTOR RESIDUAL HEAT REMOV SYS + CONT 80-027/03X-1 012981 TRIPPED ON INSTANTANEOUS OVERCURRENT ON "A" PHASE WHEN STARTED. REFERE COMPONENT CODE NOT APPLICABLE 032025 OTHER NCE TECHNICAL SPECIFICATION 3.5.B.3.
REMAINING RHR PUMPS. CSS AND DIESE SUSCOMPONENT NOT APPLICABLE L GENERATORS OPERABLE. THERE WAS NO DANGER TO HEALTH CR SAFETY OF PUBLI OTHER C.
NO PREVIOUS OCCURRENCES.
NOT APPLICABLE ITEM NOT APPLICABLE RHR PUMP MOTOR TRIPPED ON INSTANTANEOUS OVERCURRENT. MOTOR WAS MEGGERED
NOT APPLICABLE ITEM NOT APPLICABLE RHR PUMP MOTOR TRIPPED ON INSTANTANEOUS OVERCURRENT. MOTOR WAS MEGGERED
                                                                                                      . HI POTTED AND BRIDGED. RELAY SETTING CHECKED IN TOLERANCE. TRACES OF STARTING CURRENT SHOW DC OFFSET CAUSED BY SATURATION OF CT TO BE HIGHER THAN ANTICIPATED. INCREASING CURRENT MONITORED BY RELAY. SETTINGS FOR RHR RELAYS ASSOCIATED WITH THIS LER HAVE BEEN REVISED.
. HI POTTED AND BRIDGED. RELAY SETTING CHECKED IN TOLERANCE. TRACES OF STARTING CURRENT SHOW DC OFFSET CAUSED BY SATURATION OF CT TO BE HIGHER THAN ANTICIPATED. INCREASING CURRENT MONITORED BY RELAY.
BROWNS FERRY-3                                                       05000296     080980     DURING THE PERFORMANCE OF MRI 303 IT WAS DISCOVERED THAT THE EECW FLOW W RESIDUAL HEAT REMOV SYS + CONT                                 80-031/03L-1   012781     AS BELOW THE MINIMUM ALLOWED FLOW ON 3B RHR PUMP SEAL HEAT EXCHANGER. T HEAT EXCHANGERS                                                     032363     30-DAY     HERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPE OTHER                                                                                   CIFICATION 3.5.B. PREVIOUS SIMILAR OCCURRENCES WERE REPORTED ON LER/R0 OTHER                                                                                     NUMBERS BFRO-50-296/80-015 AND BFRO-50-296/80-006.
SETTINGS FOR RHR RELAYS ASSOCIATED WITH THIS LER HAVE BEEN REVISED.
NOT APPLICABLE ITEM NOT APPLICABLE IT WAS DISCOVERED THAT MUD AND SHELLS WERE RESTRICTING THE FLOW IN THE E ECW PIPING INLET TO THE RHR PUMP SEAL HEAT EXCHANGER.               THE PIPING WAS DI SASSEMBLED AND CLEANED. PERIODIC TESTING WILL CONTROL RECURRENCE.
BROWNS FERRY-3 05000296 080980 DURING THE PERFORMANCE OF MRI 303 IT WAS DISCOVERED THAT THE EECW FLOW W RESIDUAL HEAT REMOV SYS + CONT 80-031/03L-1 012781 AS BELOW THE MINIMUM ALLOWED FLOW ON 3B RHR PUMP SEAL HEAT EXCHANGER. T HEAT EXCHANGERS 032363 30-DAY HERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SPE OTHER CIFICATION 3.5.B.
PREVIOUS SIMILAR OCCURRENCES WERE REPORTED ON LER/R0 OTHER NUMBERS BFRO-50-296/80-015 AND BFRO-50-296/80-006.
NOT APPLICABLE ITEM NOT APPLICABLE IT WAS DISCOVERED THAT MUD AND SHELLS WERE RESTRICTING THE FLOW IN THE E ECW PIPING INLET TO THE RHR PUMP SEAL HEAT EXCHANGER.
THE PIPING WAS DI SASSEMBLED AND CLEANED. PERIODIC TESTING WILL CONTROL RECURRENCE.


MAR 26, 1981                                                                                                                     LER MONTHLY REPORT SORTED BY FACILITY                                                                                                                                             PAGE 13 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                             DOCKET NO./                                   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 13 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                                     REPORT DATE/                                                                                                             EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                                   CONTROL NO.                                   REPORT TYPE                                                                                                             CAUSE DESCRIPTION l
EVENT DATE/
BROWNS FERRY-3                                                                                         05000296                   081380                                                                   DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A.14, PRESSURE SWITCHES REACTOR TRIP SYSTEMS                                                                   80-030/03X-1                             011981                                                                   PS-1-81A AND PS-1-91A, TURBINE FIRST STAGE PRESSURE, SETPOINTS HAD DRIFT i  INSTRUMENTATION + CONTROLS                                                                                 032261             DTHER                                                                   ED ABOVE TECH. SPEC. LIMITS.                     (REF. T.S. TABLE 3.1.A). SETPOINTS WERE F l   SWITCH                                                                                                                                                                                                 CUND TO BE 7 PSIG 8 2 PSI, RESPECTIVELY, ABOVE T.S.                                   LIMIT OF 154 PSI. RE COMPONENT FAILURE                                                                                                                                                                                         DUNDANT SWITCHES PS-1-81B 8 PS-1-91B WERE OPERABLE. THERE WAS NO EFFECT INSTRUMENT                                                                                                                                                                                             ON PUBLIC HEALTH / SAFETY. PREVIOUS EVENTS:                               259/80-58, 259/79-08, 259/78-             1 BARKSDALE COMPANY                                                                                                                                                                                         16, 260/80-22, 260/79-16, 296/80-22, 296/79-12, 8 296/79-07.                                                       j PRESSURE EUITCHES, MODEL B2T-A12SS, SETPOINTS HAD DRIFTED. THE SWITCHES                                             l UERE INSPECTED, RECALIBRATED AND FUNCTIONALLY TESTED FOR REPEATABILITY.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION l
BROWNS FERRY-3 05000296 081380 DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A.14, PRESSURE SWITCHES REACTOR TRIP SYSTEMS 80-030/03X-1 011981 PS-1-81A AND PS-1-91A, TURBINE FIRST STAGE PRESSURE, SETPOINTS HAD DRIFT INSTRUMENTATION + CONTROLS 032261 DTHER ED ABOVE TECH. SPEC. LIMITS.
(REF. T.S.
TABLE 3.1.A).
SETPOINTS WERE F i
l SWITCH CUND TO BE 7 PSIG 8 2 PSI, RESPECTIVELY, ABOVE T.S.
LIMIT OF 154 PSI. RE COMPONENT FAILURE DUNDANT SWITCHES PS-1-81B 8 PS-1-91B WERE OPERABLE. THERE WAS NO EFFECT INSTRUMENT ON PUBLIC HEALTH / SAFETY. PREVIOUS EVENTS:
259/80-58, 259/79-08, 259/78-1 BARKSDALE COMPANY 16, 260/80-22, 260/79-16, 296/80-22, 296/79-12, 8 296/79-07.
j PRESSURE EUITCHES, MODEL B2T-A12SS, SETPOINTS HAD DRIFTED. THE SWITCHES l
UERE INSPECTED, RECALIBRATED AND FUNCTIONALLY TESTED FOR REPEATABILITY.
OTHER UNITS WILL BE CHECKED BY THE NORMAL SI SCHEDULE. THESE SWITCHES WILL BE REPLACED BY AN ANALOG SYSTEM.
OTHER UNITS WILL BE CHECKED BY THE NORMAL SI SCHEDULE. THESE SWITCHES WILL BE REPLACED BY AN ANALOG SYSTEM.
BROWNS FERRY-3                                                                                         05000296 . 090780                                                                                   WITH UNIT AT 63.6 PERCENT STEADY STATE POWER, MAIN STEAM ISOLATION VALVE.
BROWNS FERRY-3 05000296. 090780 WITH UNIT AT 63.6 PERCENT STEADY STATE POWER, MAIN STEAM ISOLATION VALVE.
MAIN STEAM ISOL SYS + CONTROLS                                                         80-038/03X-1                             012781                                                                     3-FCV-1-26 CLOSED TOO FAST UHILE RUNNING SURVEILLANCE INSTRUCTION 4.7.D VALVE OPERATORS                                                                                             032657             OTHER                                                                   .1.B.2. THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. THE PNEUMATIC / DIAPHRAGM / CYLINDER                                                                                                                                                                         VALVE WAS C" 0 SED AND POWER WAS REDUCED FOR 144 HOURS AS A RESULT.                                         "A",
MAIN STEAM ISOL SYS + CONTROLS 80-038/03X-1 012781 3-FCV-1-26 CLOSED TOO FAST UHILE RUNNING SURVEILLANCE INSTRUCTION 4.7.D VALVE OPERATORS 032657 OTHER
COMPONENT FAILURE                                                                                                                                                                                           "C" AND "D" MAIN STEAM LINES WERE OPERAELE. SEE TECHNICAL SPECIFICATI0                                           l OTHER                                                                                                                                                                                                   H 3.7.D.1. PREVIOUS SINILAR OCCURRENCES WERE REPORTED ON LER BFRO-50-29 ATWOOD 8 MORRILL CO.,       INC.                                                                                                                                                                         6/78-014.
.1.B.2.
THE DIL LEVEL IN THE HYDRAULIC CYLINDER WAS LOW. NO LEAKAGE WAS FOUND.
THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. THE PNEUMATIC / DIAPHRAGM / CYLINDER VALVE WAS C" 0 SED AND POWER WAS REDUCED FOR 144 HOURS AS A RESULT.
ONE GALLON OF OIL WAS ADDED AND THE FLOW CONTROL VALVE ADJUSTED TO OBTAI N CORRECT SPEED SETTING.                   NO FUTURE CORRECTIVE ACTION IS NEEDED DUE TO L OW OCCURRENCE RATE.                   ATWOOD AND MORRILL, 26 INCH C.S.,                 WYE PATTERN, 1250 LB.
"A",
BROWNS FERRY-3                                                                                       05000296                   091580                                                                   WITH UNIT AT 99 PERCENT STEADY STATE POWER, SURVEILLANCE INSTRUCTION 4.9 EMERG GENERATOR SYS + CONTROLS                                                       80-036/03X-1                               012081                                                                   .A.1.A. WAS BEING RUN FOLLOWING A SPECIAL ELECTRICAL NAINTENANCE INSTRUC MECHANICAL FUNCTION UNITS                                                                                   032543               OTHER                                                                   TION 18 TEST WHEN DIESEL GENERATOR 3A WOULD NOT TRIP TO IDLE SPEED FROM SUBCOMPONENT NOT APPLICABLE                                                                                                                                                                             A LOADED CONDITION. DIESEL GENERATORS 3B, 3C, AND 3D WERE OPERABLE.                                             TH COMPONENT FAILURE                                                                                                                                                                                         ERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC, NO SIGNIFICANT-MECHANICAL                                                                                                                                                                                             RESULTING CHAIN OF EVENTS, AND THERE HAVE BEEN NO PREVIOUS SIMILAR OCCUR WOODWARD GOVERNOR CO.                                                                                                                                                                                     RENCES. SEE TECHNICAL SPECIFICATION 3.9.B.2.
COMPONENT FAILURE "C"
THE PIN ON THE PINION GEAR TO THE INTERMEDIATE SHAFT GEAR USED FOR SPEED-ADJUSTING ON THE WOODWARD GOVERNOR WAS SHEARED. THE GOVERNOR WAS REPLAC ED WITH A REBUILT ONE OF THE SAME TYPE. WOODWARD TYPE EGB10-C.                                             RECURRE HCE COHTROL NOT REQUIRED BECAUSE FAILURE IS RANDOM IN NATURE.
AND "D" MAIN STEAM LINES WERE OPERAELE. SEE TECHNICAL SPECIFICATI0 l
BROWNS FERRY-3                                                                                       05000296                   121080                                                                   DURING REFUELING, WHILE PERFORMING SI 4.8.B.4.3,                                 A BAD ELECTRONIC CARD W AIRBORNE RADIDACT MONITOR SYS                                                         80-055/03L-0                               010881                                                                   AS IDENTIFIED AND CAM 3-RM-90-250 WAS DECLARED INOPERABLE AT 1710 HOURS INSTRUMENTATION + CONTROLS                                                                                 033746               30-DAY                                                                   (TECH. SPEC. 3.8.B.6 8 TECH. SPEC. 3.8.B.8). CHEMICAL LABORATORY SAMPLI-OTHER                                                                                                                                                                                                   NG PROGRAM WAS INITIATED.                   THERE WAS NO EFFECT ON THE HEALTH GR SAFETY 0 COMPONENT FAILURE                                                                                                                                                                                         F THE PUBLIC. THERE ARE NO REDUNDANT SYSTEMS. PREVIUUS EVENTS: NONE.
OTHER H 3.7.D.1.
PREVIOUS SINILAR OCCURRENCES WERE REPORTED ON LER BFRO-50-29 ATWOOD 8 MORRILL CO.,
INC.
6/78-014.
THE DIL LEVEL IN THE HYDRAULIC CYLINDER WAS LOW.
NO LEAKAGE WAS FOUND.
ONE GALLON OF OIL WAS ADDED AND THE FLOW CONTROL VALVE ADJUSTED TO OBTAI N CORRECT SPEED SETTING.
NO FUTURE CORRECTIVE ACTION IS NEEDED DUE TO L OW OCCURRENCE RATE.
ATWOOD AND MORRILL, 26 INCH C.S.,
WYE PATTERN, 1250 LB.
BROWNS FERRY-3 05000296 091580 WITH UNIT AT 99 PERCENT STEADY STATE POWER, SURVEILLANCE INSTRUCTION 4.9 EMERG GENERATOR SYS + CONTROLS 80-036/03X-1 012081
.A.1.A. WAS BEING RUN FOLLOWING A SPECIAL ELECTRICAL NAINTENANCE INSTRUC MECHANICAL FUNCTION UNITS 032543 OTHER TION 18 TEST WHEN DIESEL GENERATOR 3A WOULD NOT TRIP TO IDLE SPEED FROM SUBCOMPONENT NOT APPLICABLE A LOADED CONDITION. DIESEL GENERATORS 3B, 3C, AND 3D WERE OPERABLE.
TH COMPONENT FAILURE ERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC, NO SIGNIFICANT-MECHANICAL RESULTING CHAIN OF EVENTS, AND THERE HAVE BEEN NO PREVIOUS SIMILAR OCCUR WOODWARD GOVERNOR CO.
RENCES.
SEE TECHNICAL SPECIFICATION 3.9.B.2.
THE PIN ON THE PINION GEAR TO THE INTERMEDIATE SHAFT GEAR USED FOR SPEED-ADJUSTING ON THE WOODWARD GOVERNOR WAS SHEARED. THE GOVERNOR WAS REPLAC ED WITH A REBUILT ONE OF THE SAME TYPE.
WOODWARD TYPE EGB10-C.
RECURRE HCE COHTROL NOT REQUIRED BECAUSE FAILURE IS RANDOM IN NATURE.
BROWNS FERRY-3 05000296 121080 DURING REFUELING, WHILE PERFORMING SI 4.8.B.4.3, A BAD ELECTRONIC CARD W AIRBORNE RADIDACT MONITOR SYS 80-055/03L-0 010881 AS IDENTIFIED AND CAM 3-RM-90-250 WAS DECLARED INOPERABLE AT 1710 HOURS INSTRUMENTATION + CONTROLS 033746 30-DAY (TECH. SPEC. 3.8.B.6 8 TECH. SPEC. 3.8.B.8).
CHEMICAL LABORATORY SAMPLI-OTHER NG PROGRAM WAS INITIATED.
THERE WAS NO EFFECT ON THE HEALTH GR SAFETY 0 COMPONENT FAILURE F THE PUBLIC.
THERE ARE NO REDUNDANT SYSTEMS. PREVIUUS EVENTS:
NONE.
ELECTRONIC NUCLEAR MEASUREMENTS CORP.
ELECTRONIC NUCLEAR MEASUREMENTS CORP.
THE WINDOW CARD IN NMC CAM MODEL AO-331F(BF) MALFUNCTIONED. THE ITEM WA S REPAIRED, CAM FUNCTIONALLY TESTED AND RETURNED TO SERVICE. NO RECURRE NCE CONTROL ACTION IS PLANNED, DUE TG LOW FAILURE HISTORY.
THE WINDOW CARD IN NMC CAM MODEL AO-331F(BF) MALFUNCTIONED. THE ITEM WA S REPAIRED, CAM FUNCTIONALLY TESTED AND RETURNED TO SERVICE. NO RECURRE NCE CONTROL ACTION IS PLANNED, DUE TG LOW FAILURE HISTORY.
                                  - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ - _ _ _ _ _ _ - - _ -                                                                                       _.  ._      .                          . - -          - - _ .          ._--    _ . _ _ - _
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ - _ _ _ _ _ _ - - _ -


MAR 26, 1981                                                           LER MONTHLY REPORT SORTED BY FACILITY                                                       PAGE 14 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /       DOCKET NO./                 EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 14 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                           REPORT DATE/                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER           CONTROL NO.               REPORT TYPE                                   CAUSE DESCRIPTION BROWNS FERRY-3                               05000296                   123080     DURING REFUELING OPERATIONS, WHILE PERFORMING SI 4.4.A.2 IT WAS FOUND TH EMERG CORE COOLING SYS + CONT             80-061/03L-0                 012681     AT 3B SLC PUMP DISCHARGE RELIEF VALVE WOULD HOT RELIEVE AT 1425 +/- 75 P VALVES                                         033697                   30-DAY     SIG. REFERENCE TECHNICAL SPECIFICATION 4.4.A.2. 3A PUMP WAS DEMONSTRATE OTHER                                                                             D OPERABLE. THERE WERE NO SIGNIFICANT RESULTING EVENTS. THERE WAS NO D COMPONENT FAILURE                                                                 ANGER TO HEALTH OR SAFETY- OF PUBLIC. PREVIOUS EVENT BFRO-50-259/79-002.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 123080 DURING REFUELING OPERATIONS, WHILE PERFORMING SI 4.4.A.2 IT WAS FOUND TH EMERG CORE COOLING SYS + CONT 80-061/03L-0 012681 AT 3B SLC PUMP DISCHARGE RELIEF VALVE WOULD HOT RELIEVE AT 1425 +/- 75 P VALVES 033697 30-DAY SIG. REFERENCE TECHNICAL SPECIFICATION 4.4.A.2.
3A PUMP WAS DEMONSTRATE OTHER D OPERABLE. THERE WERE NO SIGNIFICANT RESULTING EVENTS.
THERE WAS NO D COMPONENT FAILURE ANGER TO HEALTH OR SAFETY-OF PUBLIC. PREVIOUS EVENT BFRO-50-259/79-002.
MECHANICAL CROSBY VALVE 3 GAGE CO.
MECHANICAL CROSBY VALVE 3 GAGE CO.
SUSPECT VALVE DISC GALLED OR BINDING WITH VALVE GUIDE.               VALVE WAS REPLAC ED AND VERIFIED OPERABLE. THE DAMAGED VALVE, CROSBY, SIZE 1 X 2. TYPE J MWK, 1600 PSI RELIEF VALVE, WILL BE SENT TO MANUFACTURER FOR REBUILD AND TESTING. NO RECURRENCE CONTROL REQUIRED.
SUSPECT VALVE DISC GALLED OR BINDING WITH VALVE GUIDE.
BROWNS FERRY-3                               0500J296                   123180     DURING REFUELING OPERATIONS, IT WAS FOUND THAT MAIN STEAM ISOLATION VALV MAIN STEAM SYSTEMS + CONTROLS             80-059/03L-0 012781                     ES 1-14,   1-15. 1-26, 1-27, 1-37, 1-38, 1-51 CAUSED TOTAL "AS FOUND" PRIM VALVES                                         033664                   30-DAY     ARY CONTAINMENT LEAK RATE TO EXCEED 60 PERCENT LA LEAK RATE OF 655.9 SCF GLOBE                                                                             H. LEAK RATE UAS 3941.1027 SCFH. MAIN STEAM ISOLATION VALVE LEA % AGE CO COMPONENT FAILURE                                                                 NTRIBUTED 97 PERCENT OF LEAKAGE. NO SIGNIFICANT RESULTING EVENTS. NO D CORROSION                                                                         ANGER TO HEALTH OR SAFETY OF PUBLIC. REFERENCE TECH. SPEC. 3.7.A. PREV ATWOOD 8 MORRILL CO., INC.                                                         IOUS EVENT BFRO-50-260/80-049.                                                                        .
VALVE WAS REPLAC ED AND VERIFIED OPERABLE. THE DAMAGED VALVE, CROSBY, SIZE 1 X 2. TYPE J MWK, 1600 PSI RELIEF VALVE, WILL BE SENT TO MANUFACTURER FOR REBUILD AND TESTING. NO RECURRENCE CONTROL REQUIRED.
CAUSE OF EVENT WAS DETERIORATION OF VALVE SEATING SURFACES DURING POWER DPERATION DUE TO STEAM EROSION. ATWOOD MORRILL, 26 IN. GLOBE, MODEL 208 51H, RATING 125D PSIG AT 575 DEG. F.       EFFECT MAINTENANCE AND RETEST UNTI' L PRIMARY CONTAINMENT LEAK RATE IS ACCEPTABLE. RECURRENCE CONTROL INVES TIGATION CONTINUING.
BROWNS FERRY-3 0500J296 123180 DURING REFUELING OPERATIONS, IT WAS FOUND THAT MAIN STEAM ISOLATION VALV MAIN STEAM SYSTEMS + CONTROLS 80-059/03L-0 012781 ES 1-14, 1-15.
GROWHS FERRY-3                               05000296                   123180     DURING REFUELING OPERATIONS WHILE PERFORMING MAINTENANCE INSTRUCTION FOR REACTIVITY CONTROL SYSTEMS                 80-060/03L-C                 012781     SCRAM ACCUMULATOR LEVEL SWITCHES, IT WAS FOUND THAT SEVENTEEN LEVEL SWI INSTRUMENTATION + CONTROLS                     033696                   30-DAY     TCHES WOULD NOT OPERATE DUE TO DIRTY FLOATS AND ONE OTHER SWITCH NEEDED SWITCH                                                                           TO BE REPLACED.  
1-26, 1-27, 1-37, 1-38, 1-51 CAUSED TOTAL "AS FOUND" PRIM VALVES 033664 30-DAY ARY CONTAINMENT LEAK RATE TO EXCEED 60 PERCENT LA LEAK RATE OF 655.9 SCF GLOBE H.
LEAK RATE UAS 3941.1027 SCFH.
MAIN STEAM ISOLATION VALVE LEA % AGE CO COMPONENT FAILURE NTRIBUTED 97 PERCENT OF LEAKAGE. NO SIGNIFICANT RESULTING EVENTS. NO D CORROSION ANGER TO HEALTH OR SAFETY OF PUBLIC. REFERENCE TECH. SPEC.
3.7.A.
PREV ATWOOD 8 MORRILL CO., INC.
IOUS EVENT BFRO-50-260/80-049.
CAUSE OF EVENT WAS DETERIORATION OF VALVE SEATING SURFACES DURING POWER l
DPERATION DUE TO STEAM EROSION. ATWOOD MORRILL, 26 IN. GLOBE, MODEL 208 51H, RATING 125D PSIG AT 575 DEG. F.
EFFECT MAINTENANCE AND RETEST UNTI' L PRIMARY CONTAINMENT LEAK RATE IS ACCEPTABLE. RECURRENCE CONTROL INVES TIGATION CONTINUING.
GROWHS FERRY-3 05000296 123180 DURING REFUELING OPERATIONS WHILE PERFORMING MAINTENANCE INSTRUCTION FOR REACTIVITY CONTROL SYSTEMS 80-060/03L-C 012781 SCRAM ACCUMULATOR LEVEL SWITCHES, IT WAS FOUND THAT SEVENTEEN LEVEL SWI INSTRUMENTATION + CONTROLS 033696 30-DAY TCHES WOULD NOT OPERATE DUE TO DIRTY FLOATS AND ONE OTHER SWITCH NEEDED SWITCH TO BE REPLACED.  


==REFERENCE:==
==REFERENCE:==
TECHNICAL SPECIFICATION 4.3.A.2.D.                             THERE W COMPONENT FAILURE                                                                 AS NO DANGER TO HEALTH OR SAFETY OF PUBLIC. NO REDUNDANT SYSTEM. PREVI INSTRUMENT                                                                       OUS OCCURRENCE:   BFRO-50-260/80-43.
TECHNICAL SPECIFICATION 4.3.A.2.D.
THERE W COMPONENT FAILURE AS NO DANGER TO HEALTH OR SAFETY OF PUBLIC. NO REDUNDANT SYSTEM. PREVI INSTRUMENT OUS OCCURRENCE:
BFRO-50-260/80-43.
GEMS, INC.
GEMS, INC.
SOME GUMMY SUBSTANCE WAS OBSERVED ON SOME SWITCHES BETWEEN FLOAT BOTTCM AND TOP OF SPOOL BOTTOM WHICH MIGHT HAVE CAUSED A FLOAT TO STICK. THESE SWITCHES WERE CLEANE'D AND TESTED. ONE WAS REPLACED. GEtts INC., TYPE L' IQUID LEVEL, SIZE T1AX. RESIST. LOAD 10.0 VA DWG. 117C1434 F001                           EFFORTS TO IDENTIFY AND REMOVE SUBSTANCE FROM SYSTEM ARE IN PROGRESS.
SOME GUMMY SUBSTANCE WAS OBSERVED ON SOME SWITCHES BETWEEN FLOAT BOTTCM AND TOP OF SPOOL BOTTOM WHICH MIGHT HAVE CAUSED A FLOAT TO STICK. THESE SWITCHES WERE CLEANE'D AND TESTED.
BROWNS FERRY-3                               05000296                   010681     DURING REFUELING OPERATIONS BOTH SMOKE DETECTORS IN A REACTOR BUILDING F FIRE PROTECTION SYS + CONT                 81- 0 01/ 0 3 L- 0 012881               IXED SPRAY ZONE WERE INOPERABLE. CHLY ONE DETECTOR IS ALLOWED TO BE IHO COMPONENT CODE NOT APPLICABLE                 036022                   30-DAY     PERABLE BY TECHNICAL SPECIFICATION 3.11.C.1. THERE WERE NO SIGNIFICANT SUBCOMPONENT NOT APPLICABLE                                                       RESULTING EVENTS. NO EFFECT ON PUBLIC HEALTH OR SAFETY. NO PREVIOUS EV OTHER                                                                             ENTS.
ONE WAS REPLACED. GEtts INC., TYPE L' IQUID LEVEL, SIZE T1AX. RESIST. LOAD 10.0 VA DWG. 117C1434 F001 EFFORTS TO IDENTIFY AND REMOVE SUBSTANCE FROM SYSTEM ARE IN PROGRESS.
NOT APPLICABLE ITEM NOT APPLICABLE A SCREW CAME LOOSE FROM A TERMINAL BLOCK AND THIS INTERRUPTED POWER TO B OTH SMOKE DETECTORS IN A FIXED SPRAY ZONE. ACTUAL CAUSE OF SCREW COMING LOOSE IS UNKNOUN. REPLACED SCREW IN BLOCK AND CHECKED OTHER TERMINAL B LOCKS IN PANEL; NO OTHER LOOSE SCREWS FOUND.         FURTHER RECURRENCE CONTROL NOT PLANNED.
BROWNS FERRY-3 05000296 010681 DURING REFUELING OPERATIONS BOTH SMOKE DETECTORS IN A REACTOR BUILDING F FIRE PROTECTION SYS + CONT 81- 0 01/ 0 3 L- 0 012881 IXED SPRAY ZONE WERE INOPERABLE. CHLY ONE DETECTOR IS ALLOWED TO BE IHO COMPONENT CODE NOT APPLICABLE 036022 30-DAY PERABLE BY TECHNICAL SPECIFICATION 3.11.C.1.
n         ,_            y   -        -iv -
THERE WERE NO SIGNIFICANT SUBCOMPONENT NOT APPLICABLE RESULTING EVENTS.
                                                                                                                                                                        - - - = ~ - - r-_g_m---, ~ ____,,_-__,.__m., _
NO EFFECT ON PUBLIC HEALTH OR SAFETY. NO PREVIOUS EV OTHER ENTS.
NOT APPLICABLE ITEM NOT APPLICABLE A SCREW CAME LOOSE FROM A TERMINAL BLOCK AND THIS INTERRUPTED POWER TO B OTH SMOKE DETECTORS IN A FIXED SPRAY ZONE.
ACTUAL CAUSE OF SCREW COMING LOOSE IS UNKNOUN. REPLACED SCREW IN BLOCK AND CHECKED OTHER TERMINAL B LOCKS IN PANEL; NO OTHER LOOSE SCREWS FOUND.
FURTHER RECURRENCE CONTROL NOT PLANNED.
n y
-iv
- - - = ~ - -
r-_g_m---,
~
____,,_-__,.__m.,


MAR 26, 1981                                                                                                                                             LER MONTHLY REPORT SORTED BY FACILITY                                                                                                                                                   PAGE 15 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM. COMPONENT /                           DOCKET NO./                                                                                 EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 15 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM. COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                                                             REPORT DATE/                                                                                                                             EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                             CONTROL NO.                                                                                 REPORT TYPE                                                                                                                             CAUSE DESCRIPTION BROWNS FERRY-3                                                                                           05000296                                       011081               DURING REFUELING OPERATIONS, DIESEL GENERATOR 3A AND BREAKER 1836 TRIPPE EMERG GENERATOR SYS + CONTROLS                                     81-004/03L-0                                                                         020381               D FROM DIESEL GENERATOR OVERSPEED DURING DIESEL GENERATOR EMERGENCY LOAD INSTRUMENTATION - CONTROLS                                                                                                 036087                       30-DAY                   ACCEPTANCE TEST.                         THERE WERE NO SIGNIFICANT RESULTING EVENTS. THERE WA CONTROLLER                                                                                                                                                                   S NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC.                                                                                                   NO PREVIOUS EVENTS.
EVENT DATE/
COMPONENT FAILURE                                                                                                                                                                 REFERENCE TECHNICAL SPECIFICATION 3.9.C.1.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 011081 DURING REFUELING OPERATIONS, DIESEL GENERATOR 3A AND BREAKER 1836 TRIPPE EMERG GENERATOR SYS + CONTROLS 81-004/03L-0 020381 D FROM DIESEL GENERATOR OVERSPEED DURING DIESEL GENERATOR EMERGENCY LOAD INSTRUMENTATION - CONTROLS 036087 30-DAY ACCEPTANCE TEST.
THERE WERE NO SIGNIFICANT RESULTING EVENTS. THERE WA CONTROLLER S NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC.
NO PREVIOUS EVENTS.
COMPONENT FAILURE REFERENCE TECHNICAL SPECIFICATION 3.9.C.1.
OTHER ELECTRO - MOTIVE DIV. OF G. M.
OTHER ELECTRO - MOTIVE DIV. OF G. M.
VS RELAY ON SPEED SENSING PANEL 2 ENERGIZED AT LESS THAN 870 RPM AND RES ULTED IN DIESEL GENERATOR TRIP. POTENTI0 METERS FOR VS RELAYS ON SSP 1 AN D SSP 2 WERE CALIBRATED AND VERIFIED OPERABLE. SI 4.9.A.1.D WILL BE REVI SED TO VERIFY OPERABILITY OF VS RELAYS. EMD PART NO. 8409614.
VS RELAY ON SPEED SENSING PANEL 2 ENERGIZED AT LESS THAN 870 RPM AND RES ULTED IN DIESEL GENERATOR TRIP.
BRUNSWICK-1                                                                                               05000325                                       110580               DURING NORMAL OPERATION, WHILE VERIFYING CONTROL ROD POSITIONS, CONTROL SAFETY RELATED DISPLAY INSTR                                       80-087/03L-0                                                                         120180               ROD 50-27 HAD NO " FULL OU1" INDICATION ON THE ROD STATUS DISPLAY AND CON INSTRUMENTATION + CONTROLS                                                                                                 033698                       30-DAY               TROL ROD 38-23 LACKED POSITIDH INDICATION ON THE ROD STATUS DISPLAY AND SWITCH                                                                                                                                                                       ON THE COMPUTER PRINTOUT MHILE AT POSITION "02". SIMILAR EVENTS INVOLVI COMPONENT FAILURE                                                                                                                                                             NG CONTROL ROD POSITION INDICATIONS WERE REPORTED IN LER'S 1-80-25, 1-80 ELECTRICAL                                                                                                                                                                   -62, AND 1-80-78.                           THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY                                                                         OF THE GENERAL ELECTRIC CO.                                                                                                                                                               PUCLIC. TECHNICAL SPECIFICATIONS 3.1.3.7, 6.9.1.9B.
POTENTI0 METERS FOR VS RELAYS ON SSP 1 AN D SSP 2 WERE CALIBRATED AND VERIFIED OPERABLE. SI 4.9.A.1.D WILL BE REVI SED TO VERIFY OPERABILITY OF VS RELAYS. EMD PART NO. 8409614.
BRUNSWICK-1 05000325 110580 DURING NORMAL OPERATION, WHILE VERIFYING CONTROL ROD POSITIONS, CONTROL SAFETY RELATED DISPLAY INSTR 80-087/03L-0 120180 ROD 50-27 HAD NO " FULL OU1" INDICATION ON THE ROD STATUS DISPLAY AND CON INSTRUMENTATION + CONTROLS 033698 30-DAY TROL ROD 38-23 LACKED POSITIDH INDICATION ON THE ROD STATUS DISPLAY AND SWITCH ON THE COMPUTER PRINTOUT MHILE AT POSITION "02".
SIMILAR EVENTS INVOLVI COMPONENT FAILURE NG CONTROL ROD POSITION INDICATIONS WERE REPORTED IN LER'S 1-80-25, 1-80 ELECTRICAL
-62, AND 1-80-78.
THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE GENERAL ELECTRIC CO.
PUCLIC.
TECHNICAL SPECIFICATIONS 3.1.3.7, 6.9.1.9B.
THE INDICATION PROBLEMS EXPERIENCED WITH THESE TWO RODS ARE BELIEVED TO HAVE RESULTED FROM DEFECTIVE ROD POSITION INDICATION REED SWITCHES. CDR RECTIVE MAINTENANCE FOR THESE RODS WILL BE COMPLETED DURING THE NEXT GUT AGE OF SUFFICIEllT LENGTH THAT ALLOWS ACCESS TO THE PRIMARY CONTAINMENT.
THE INDICATION PROBLEMS EXPERIENCED WITH THESE TWO RODS ARE BELIEVED TO HAVE RESULTED FROM DEFECTIVE ROD POSITION INDICATION REED SWITCHES. CDR RECTIVE MAINTENANCE FOR THESE RODS WILL BE COMPLETED DURING THE NEXT GUT AGE OF SUFFICIEllT LENGTH THAT ALLOWS ACCESS TO THE PRIMARY CONTAINMENT.
BRUNSWICK-1                                                                                               05000325                                       121180               DURING NORMAL SURVEILLANCE ROD BLOCK MONITOR "B" WAS OBSERVED INDICATING REACTGR TRIP SYSTEFS                                               80-091/03L-0                                                                         010881                   DOWNSCALE. THE MONITOR WAS THEN DECLARED INOPERABLE AS REQUIRED BY TEC INSTRUMENTATION + CONTROLS                                                                                                 033665                       30-DAY               HNICAL SPECIFICATIONS. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY 0 OTHER                                                                                                                                                                         F THE PUBLIC.                           TECHNICAL SPECIFICATIONS 3.1.4.3,                                                                     6.9.1.9B.
BRUNSWICK-1 05000325 121180 DURING NORMAL SURVEILLANCE ROD BLOCK MONITOR "B" WAS OBSERVED INDICATING REACTGR TRIP SYSTEFS 80-091/03L-0 010881 DOWNSCALE. THE MONITOR WAS THEN DECLARED INOPERABLE AS REQUIRED BY TEC INSTRUMENTATION + CONTROLS 033665 30-DAY HNICAL SPECIFICATIONS. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY 0 OTHER F THE PUBLIC.
TECHNICAL SPECIFICATIONS 3.1.4.3, 6.9.1.9B.
COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.
MONITOR INDICATED DOWNSCALE DUE TO A FAILED POWER SUPPLY CAUSED BY A DEF ECTIVE POWER SUPPLY REGULATOR & ZENER DIODE IN POWER SUPPLY REGULATOR CI RCUIT. REGULATOR & DIODE WERE REPLACED & MONITOR RETURNED TO NORMAL OPE R.           THIS IS FIRST EVENT INVOLVING A FAILURE OF THESE COMPONENTS & IS CON SIDERED AN ISOLATED EVENT WITH NO FURTHER CORRECTIVt ACTION REQUIRED.
MONITOR INDICATED DOWNSCALE DUE TO A FAILED POWER SUPPLY CAUSED BY A DEF ECTIVE POWER SUPPLY REGULATOR & ZENER DIODE IN POWER SUPPLY REGULATOR CI RCUIT.
BRUNSWICK-1                                                                                               05000325                                       122880               MHILE PERFORMING A NORMAL SHUTDOWN FROM POWER OPERATION, THE ROD WORTH M REACTIVITY CONVROL SYSTEMS                                       80-093/03L-0                                                                           012181               INIMIZER (RWM) INITIATED AN INSERT / WITHDRAWAL ROD BLOCK AT ROD GROUP 56.
REGULATOR & DIODE WERE REPLACED & MONITOR RETURNED TO NORMAL OPE R.
THIS IS FIRST EVENT INVOLVING A FAILURE OF THESE COMPONENTS & IS CON SIDERED AN ISOLATED EVENT WITH NO FURTHER CORRECTIVt ACTION REQUIRED.
BRUNSWICK-1 05000325 122880 MHILE PERFORMING A NORMAL SHUTDOWN FROM POWER OPERATION, THE ROD WORTH M REACTIVITY CONVROL SYSTEMS 80-093/03L-0 012181 INIMIZER (RWM) INITIATED AN INSERT / WITHDRAWAL ROD BLOCK AT ROD GROUP 56.
INSTRUMENTATION
INSTRUMENTATION
* CONTROLS                                                                                                 033699                       30-DAY                   A COMPUTER VERIFICATION SHOUED ALL RODS WERE IN THE CORRECT POSITIONS.
* CONTROLS 033699 30-DAY A COMPUTER VERIFICATION SHOUED ALL RODS WERE IN THE CORRECT POSITIONS.
COMPUTATION MGDULE                                                                                                                                                               THE RWM MAS THEN BYPASSED AND A SECOND OPERATOR WAS UTILIZED TO VERIFY DESIGN / FABRICATION ERROR                                                                                                                                                     COMPLIANCE WITH 1HE PRESCRIBED ROD PATTERN AND THE RW:1 WAS DECLARED INOP DESIGN                                                                                                                                                                       ERABLE AS REQUIRED BY TECHNICAL SPECIFICATIONS 3.1.4.1,                                                                                                   6.9.1.9B.
COMPUTATION MGDULE THE RWM MAS THEN BYPASSED AND A SECOND OPERATOR WAS UTILIZED TO VERIFY DESIGN / FABRICATION ERROR COMPLIANCE WITH 1HE PRESCRIBED ROD PATTERN AND THE RW:1 WAS DECLARED INOP DESIGN ERABLE AS REQUIRED BY TECHNICAL SPECIFICATIONS 3.1.4.1, 6.9.1.9B.
GENERAL ELECTRIC CD.
GENERAL ELECTRIC CD.
SEVERAL COMPUTER RWM SOFTWEAR PROBLEMS WERE DISCOVERED WHICH ARE BELIEVE D TO HAVE CAUSED THIS EVENT.. THESE PROBLEMS WERE CORRECTED AND THE RMM SYSTEM WAS PETURNED TO NORMAL OPERATION. THE UNIT NO. 2 RUM SOFTWEAR WA S ALSO CHANGED TO THE SAME CONFIGURATION AS THAT ON UNIT NO. I IN ORDER TO AVOID ANY SIMILAR EVENTS WITH THE RWM SYSTEM IN THE FUTURE.
SEVERAL COMPUTER RWM SOFTWEAR PROBLEMS WERE DISCOVERED WHICH ARE BELIEVE D TO HAVE CAUSED THIS EVENT..
THESE PROBLEMS WERE CORRECTED AND THE RMM SYSTEM WAS PETURNED TO NORMAL OPERATION. THE UNIT NO. 2 RUM SOFTWEAR WA S ALSO CHANGED TO THE SAME CONFIGURATION AS THAT ON UNIT NO. I IN ORDER TO AVOID ANY SIMILAR EVENTS WITH THE RWM SYSTEM IN THE FUTURE.


4 MAR 26, 1981                                               LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 16 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./       EVENT DATE/
4 MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 16 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./           REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.       REPORT TYPE                                 CAUSE DESCRIPTION i
EVENT DATE/
BRUNSWICK-1                               05000325           010181 DURING NORMAL SURVEILLANCE IT WAS DISCOVERED THAT THE SECONDARY CONTAINM REACTOR CONTAINMENT SYSTEMS         81-005/03L-0           012781 ENT 20' ELEVATION INNER AIR LOCK DOOR HAD A MISSING SECTION OF GASKET SE PENETRATIONS,PRIMRY CONTAINMNT           036024           30-DAY ALING MATERIAL MAKING THE DOOR INOPERABLE. THIS EVENT DID NOT AFFECT TH     '
COMPONENT SUBCODE/CAUSE CODE / LER NO./
PERSONNEL ACCESS                                                 E HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.6.5.1, 6.9 COMPONENT FAILURE                                                   .1.9B.
REPORT DATE/
NATURAL END OF LIFE                                                                                                                           '
EVENT DESCRIPTION /
OTHER HIGH PERSONNEL TRAFFIC THROUGH THE DOOR CAUSED AN APPROXIMATE 6" SECTION i                                                                         0F THE GASKET TO BECOME EXCESSIVELY WORN AND DETACHED FROM THE DOOR STR UCTURE. THE MISSING GASKET SECTION WAS REPLACED AND THE GASKETS ON THE DOORS OF BOTH UNITS WERE INSPECTED TO ENSURE PROPER SEALING. A PROCEDUR E IS PRESENTLY BEING DEVELOPED TO INSPECT THESE DOORS ON A REGULAR BASIS BRUNSWICK-1                               05000325           010181 WHILE PERFORMING A CALIBRATION CHECK ON THE CONTAINMENT ATMOSPHERIC MONI CNTHMNT COMBUS GAS CONTROL SYS       81-006/03L-0           012781 TOR, 1-CAC-ATH-1259-2. IT WAS DETERMINED THAT THIS INSTRUMENT WAS-0UT OF INSTRUMENTATION + CONTROLS               036025           30-DAY   CALIBRATION. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUB     ,
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
COMPUTATION MODULE
REPORT TYPE CAUSE DESCRIPTION i
* LIC. TECHNICAL SPECIFICATION 3.3.5.3, 6.9.1.9B.
BRUNSWICK-1 05000325 010181 DURING NORMAL SURVEILLANCE IT WAS DISCOVERED THAT THE SECONDARY CONTAINM REACTOR CONTAINMENT SYSTEMS 81-005/03L-0 012781 ENT 20' ELEVATION INNER AIR LOCK DOOR HAD A MISSING SECTION OF GASKET SE PENETRATIONS,PRIMRY CONTAINMNT 036024 30-DAY ALING MATERIAL MAKING THE DOOR INOPERABLE. THIS EVENT DID NOT AFFECT TH PERSONNEL ACCESS E HEALTH OR SAFETY OF THE PUBLIC.
COMPONENT FAILURE INSTRUMENT
TECHNICAL SPECIFICATIONS 3.6.5.1, 6.9 COMPONENT FAILURE
-  BECKMAN INSTRUMENTS, INC.
.1.9B.
1                                                                       THE INSTRUMENT WAS OUT OF CALIBRATION DUE TO INSTRUMENT DRIFT. THE MONI
NATURAL END OF LIFE OTHER HIGH PERSONNEL TRAFFIC THROUGH THE DOOR CAUSED AN APPROXIMATE 6" SECTION i
'                                                                      TOR WAS RECALIBRATED AND RETURNED TO SERVICE. DUE TO A HISTORY OF PROBL EMS INVOLVING THESE MONITORS, THEY WILL BE REPLACED WITH 0THERS OF A MOR E RELIABLE DESIGN DURING A FUTURE SCHEDULED OUTAGE.
0F THE GASKET TO BECOME EXCESSIVELY WORN AND DETACHED FROM THE DOOR STR UCTURE.
B2UNSWICK-1                               05000325           010381 DURING A NORMAL REACTOR SlARTUP, CONTROL ROD 26-35 HAD "Ft"it IH" POSITIO ENGNRD SAFETY FEATR INSTR SYS       81-003/03L-0           012081 N INDICATION LIGHTS LIT REGARDLESS OF THE ACTUAL ROD POSITION. FOLLOWING
THE MISSING GASKET SECTION WAS REPLACED AND THE GASKETS ON THE DOORS OF BOTH UNITS WERE INSPECTED TO ENSURE PROPER SEALING. A PROCEDUR E IS PRESENTLY BEING DEVELOPED TO INSPECT THESE DOORS ON A REGULAR BASIS BRUNSWICK-1 05000325 010181 WHILE PERFORMING A CALIBRATION CHECK ON THE CONTAINMENT ATMOSPHERIC MONI CNTHMNT COMBUS GAS CONTROL SYS 81-006/03L-0 012781 TOR, 1-CAC-ATH-1259-2. IT WAS DETERMINED THAT THIS INSTRUMENT WAS-0UT OF INSTRUMENTATION + CONTROLS 036025 30-DAY CALIBRATION. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUB COMPUTATION MODULE LIC.
  ' INSTRUMENTATION + CONTROLS               036023           30-DAY   THE REACTOR STARTUP WHILE MOVING CONTROL RODS DURING LOAD CHANGES, ON J SENSOR / DETECTOR / ELEMENT                                       ANUARY 13, 1981, ROD 18-51 DID NOT HAVE POSITION INDICATION AT POSITION COMPONENT FAILURE                                                   "48," AND ON JANUARY 14,   1981 ROD 38-31 DID NOT HAVE POSITION INDICATIO NATURAL END OF LIFE                                               N AT POSITION "05" WHILE ROD 22-15 DID NOT HAVE " FULL IN" POSITION INDIC GENERAL ELECTRIC CD.                                               ATION AT POSITION "00." TECHNICAL SPECIFICATION 3.1.3.7, 6.9.1.9B.
TECHNICAL SPECIFICATION 3.3.5.3, 6.9.1.9B.
LOGIC CHIP G-33 0F THE ROD 26-35 BUFFER CARD FAILED.     THE BUFFER CARD WA S REPLACED AND NORMAL INDICATION FOR ROD 26-35 WAS RESTORED. RODS 18-51
COMPONENT FAILURE INSTRUMENT BECKMAN INSTRUMENTS, INC.
                                                                        ,  38-31, AND 22-15 ARE BELIEVED TO HAVE DEFECTIVE REED SWITCHES LOCATED IN THE PIP PROBE. THESE SWITCHES'WILL BE REPAIRED DURING THE NEXT DUTAG E OF SUFFICIENT LENGTH TO ALLOW WORK IN THE DRYWELL.
1 THE INSTRUMENT WAS OUT OF CALIBRATION DUE TO INSTRUMENT DRIFT.
BRUNSWICT-1                               05000325           010681 WHILE PERFORMING PRIMARY CONTAINMENT LEAK RATE TESTING OF PERSONNEL AIRL REACTOR CONTAINMENT SYSTEMS         81 - 0 0 8.'0 3 L - 0 020381   OCK INTERIOR AND EXTERIOR DOORS, PT 2.6.5P, IT WAS DISCOVERED THAT DRYWE PENETRATIONS.PRIMRY CONTAINMNT           036183           30-DAY LL EXTERIOR AIRLOCK DOOR LEAKAGE RATE EXCEEDED THE SPECIFIED < 5 SCFH.
THE MONI TOR WAS RECALIBRATED AND RETURNED TO SERVICE. DUE TO A HISTORY OF PROBL EMS INVOLVING THESE MONITORS, THEY WILL BE REPLACED WITH 0THERS OF A MOR E RELIABLE DESIGN DURING A FUTURE SCHEDULED OUTAGE.
PERSONNEL ACCESS                                                   THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECH. SPE OTHER                                                               CS. 3.6.1.3,   6.9.1.9B.
B2UNSWICK-1 05000325 010381 DURING A NORMAL REACTOR SlARTUP, CONTROL ROD 26-35 HAD "Ft"it IH" POSITIO ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 012081 N INDICATION LIGHTS LIT REGARDLESS OF THE ACTUAL ROD POSITION. FOLLOWING
NOT APPLICABLE i   OTHER A TUBING FITTING BECAME LODGED IN THE DOOR SEALING AREA WHICH DENTED IT AND CUT THE DOOR GASKET. THE FITTING UAS REMOVED. THE DENTED SEALING AR EA RESURFACED AND A NEW DOOR GASKET WAS INSTALLED. THE PT WAS THEN SATI SFACTORILY PERFORMED WITH AN EXTERIOR DOOR LEAKAGE RATE OF 4.5 SCFH. TH IS IS CONSIDERED AN ISCLATED EVENT WITH NO FURTHER ACTION REQUIRED.
' INSTRUMENTATION + CONTROLS 036023 30-DAY THE REACTOR STARTUP WHILE MOVING CONTROL RODS DURING LOAD CHANGES, ON J SENSOR / DETECTOR / ELEMENT ANUARY 13, 1981, ROD 18-51 DID NOT HAVE POSITION INDICATION AT POSITION COMPONENT FAILURE "48," AND ON JANUARY 14, 1981 ROD 38-31 DID NOT HAVE POSITION INDICATIO NATURAL END OF LIFE N AT POSITION "05" WHILE ROD 22-15 DID NOT HAVE " FULL IN" POSITION INDIC GENERAL ELECTRIC CD.
I
ATION AT POSITION "00."
                                                                                                                        , . __          ~   .
TECHNICAL SPECIFICATION 3.1.3.7, 6.9.1.9B.
LOGIC CHIP G-33 0F THE ROD 26-35 BUFFER CARD FAILED.
THE BUFFER CARD WA S REPLACED AND NORMAL INDICATION FOR ROD 26-35 WAS RESTORED. RODS 18-51 38-31, AND 22-15 ARE BELIEVED TO HAVE DEFECTIVE REED SWITCHES LOCATED IN THE PIP PROBE.
THESE SWITCHES'WILL BE REPAIRED DURING THE NEXT DUTAG E OF SUFFICIENT LENGTH TO ALLOW WORK IN THE DRYWELL.
BRUNSWICT-1 05000325 010681 WHILE PERFORMING PRIMARY CONTAINMENT LEAK RATE TESTING OF PERSONNEL AIRL REACTOR CONTAINMENT SYSTEMS 81 - 0 0 8.'0 3 L - 0 020381 OCK INTERIOR AND EXTERIOR DOORS, PT 2.6.5P, IT WAS DISCOVERED THAT DRYWE PENETRATIONS.PRIMRY CONTAINMNT 036183 30-DAY LL EXTERIOR AIRLOCK DOOR LEAKAGE RATE EXCEEDED THE SPECIFIED < 5 SCFH.
PERSONNEL ACCESS THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECH. SPE OTHER CS.
3.6.1.3, 6.9.1.9B.
NOT APPLICABLE i
OTHER A TUBING FITTING BECAME LODGED IN THE DOOR SEALING AREA WHICH DENTED IT AND CUT THE DOOR GASKET.
THE FITTING UAS REMOVED. THE DENTED SEALING AR EA RESURFACED AND A NEW DOOR GASKET WAS INSTALLED. THE PT WAS THEN SATI SFACTORILY PERFORMED WITH AN EXTERIOR DOOR LEAKAGE RATE OF 4.5 SCFH.
TH IS IS CONSIDERED AN ISCLATED EVENT WITH NO FURTHER ACTION REQUIRED.
I i
~


MAR 26, 1981                                                                                 LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 17 -
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 17 -
PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                   DOCKET NO./         EVENT DATE/
PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                 REPORT DATE/                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                       CONTROL NO.         REPORT TYPE                                   CAUSE DESCRIPTION BRUNSWICK-1                                                                     05000325     011281     DURING THE PERFORMANCE OF CONTAINMENT ATMOSPHERE CONTROL (CAC). DRYWELL CNTNMHf COMBUS GAS CONTROL SYS                                             81-023/03L-0     021181     HYDROGEN AND OXYGEN CHANNEL CALIBRATION,     P.T. 55.4PC, CAC MONITOR. 1-CAC INSTRUMENTATION + CONTROLS                                                     036089     30-DAY     -ATH-1259. INDICATED UPSCALE REGARDLESS OF THE SAMPLE POINT SELECTED. T SENSOR / DETECTOR / ELEMENT                                                                           HIS MONITOR HAS A HISTORY OF SIMILAR EVENTS INVOLVING UPSCALE INDICATION COMPONENT FAlltfRE                                                                                       . THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNI ELECTRICAL                                                                                             CAL SPECIFICATION 3.3.5.3, 6.9.1.9B BECKMAN INSTRUMENTS, INC.
EVENT DATE/
A FAILED MP51eun MAGNETIC ANALYZER SAMPLE CELL OCCURRED DUE TO EXCESSIVE MOISTURE EUILD-UP IN THE MONITOR SAMPLE LINES. THE SAMPLE LINES WERE B LOWN DOWN TO REM 9VE THE MOISTURE AND THE MAGNETIC ANALYZER WAS REPLACED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-1 05000325 011281 DURING THE PERFORMANCE OF CONTAINMENT ATMOSPHERE CONTROL (CAC). DRYWELL CNTNMHf COMBUS GAS CONTROL SYS 81-023/03L-0 021181 HYDROGEN AND OXYGEN CHANNEL CALIBRATION, P.T. 55.4PC, CAC MONITOR. 1-CAC INSTRUMENTATION + CONTROLS 036089 30-DAY
-ATH-1259. INDICATED UPSCALE REGARDLESS OF THE SAMPLE POINT SELECTED. T SENSOR / DETECTOR / ELEMENT HIS MONITOR HAS A HISTORY OF SIMILAR EVENTS INVOLVING UPSCALE INDICATION COMPONENT FAlltfRE
. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNI ELECTRICAL CAL SPECIFICATION 3.3.5.3, 6.9.1.9B BECKMAN INSTRUMENTS, INC.
A FAILED MP51eun MAGNETIC ANALYZER SAMPLE CELL OCCURRED DUE TO EXCESSIVE MOISTURE EUILD-UP IN THE MONITOR SAMPLE LINES.
THE SAMPLE LINES WERE B LOWN DOWN TO REM 9VE THE MOISTURE AND THE MAGNETIC ANALYZER WAS REPLACED.
THE MONITOR WAS THEN CALIBRATED AND RETURNED TO SATISFACTORY OPERATION.
THE MONITOR WAS THEN CALIBRATED AND RETURNED TO SATISFACTORY OPERATION.
BRUNSWICK-1                                                                     05000325     011481     DURING THE PERFORMAPCE OF MAIN STEAM LINE ISOLATION. VALVE CLOSURE FUNCTI MAIN SiEAM ISOL SYS + CONTROLS                                           81-002/03L-0       021281     DNAL TEST, P.T. 1.3.1P, RPS LOGIC RELAYS, C71-K3D & K3E, DID NOT DE-ENGE INSTRUMENTATION + CONTROLS                                                       036047     30-DAY     RGIZE AS REQUIRED WHEN MSIV-1-B21-F028B WAS CLOSED. "A" RPS CHANNEL WAS SWITCH                                                                                                 THEN PLACED IN THE " TRIPPED" POSITION AS REQUIRED BY TECHNICAL SPECIFICA OTHER                                                                                                   TIONS. THIS EVENT OCCURRED AGAIN ON FEBRUARY 12, 1981, AND A SIMILAR PA NOT APPLICABLE                                                                                         ST EVENT WAS REPORTED IN LER 1-80-75. THIS EVENT DID HOT AFFECT-THE HEA NAMCO CONTROLS                                                                                           LTH OR SAFETY OF THE PUBLIC. TECHNI \L SPECIFICATIONS 3.3.1, 6.9.1.9B.
BRUNSWICK-1 05000325 011481 DURING THE PERFORMAPCE OF MAIN STEAM LINE ISOLATION. VALVE CLOSURE FUNCTI MAIN SiEAM ISOL SYS + CONTROLS 81-002/03L-0 021281 DNAL TEST, P.T.
A STICKING VALVE POSITION LIMIT SUI'       ACTUATOR ART 1 CAM, OF LIMIT SUITCH MODEL NO. EA740-80100, PREVENTED LC .. RELAYS FROM DE-ENERGIZING. ACTUA TOR ARM & ARM CAM UERE MECH EXERCISED 3 LUB TO ENSURE FREE MOVEMENT AFTE R 1-14-81 EVENT. AFTER EVENT ON 2-12-81, LIMIT SUITCH UAS REPLACED & INS TR RETURNED TO NORMAL OPER. NO HISTORY OF FAILURE WITH SIMILAR' SWITCHES.
1.3.1P, RPS LOGIC RELAYS, C71-K3D & K3E, DID NOT DE-ENGE INSTRUMENTATION + CONTROLS 036047 30-DAY RGIZE AS REQUIRED WHEN MSIV-1-B21-F028B WAS CLOSED. "A" RPS CHANNEL WAS SWITCH THEN PLACED IN THE " TRIPPED" POSITION AS REQUIRED BY TECHNICAL SPECIFICA OTHER TIONS.
BRUNSWICK-1                                                                     05000325     011581     DURING THE PERFORMANCE OF THE RCIC SYSTEM COMPONENT OPERABILITY TEST, P.
THIS EVENT OCCURRED AGAIN ON FEBRUARY 12, 1981, AND A SIMILAR PA NOT APPLICABLE ST EVENT WAS REPORTED IN LER 1-80-75.
REAC CORE ISOL COOL SYS + CONT                                           81-009/03L-0       020581     T. 10.2, THE SYSTEM OIL COOLER INLET ISOLATION VALVE, 1-E51-F046, WOULD INSTRUMENTATION + CONTROLS                                                       036088     30-DAY     NOT OPEN FROM THE RTGB THEREBY MAKING THE RCIC SYSTEM INOPERABLE. THIS SWITCH                                                                                                 EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPEC OTHER                                                                                                   IFICATIONS 3.7.4, 6.9.1.9B.
THIS EVENT DID HOT AFFECT-THE HEA NAMCO CONTROLS LTH OR SAFETY OF THE PUBLIC.
TECHNI \\L SPECIFICATIONS 3.3.1, 6.9.1.9B.
A STICKING VALVE POSITION LIMIT SUI' ACTUATOR ART 1 CAM, OF LIMIT SUITCH MODEL NO. EA740-80100, PREVENTED LC.. RELAYS FROM DE-ENERGIZING. ACTUA TOR ARM & ARM CAM UERE MECH EXERCISED 3 LUB TO ENSURE FREE MOVEMENT AFTE R 1-14-81 EVENT. AFTER EVENT ON 2-12-81, LIMIT SUITCH UAS REPLACED & INS TR RETURNED TO NORMAL OPER. NO HISTORY OF FAILURE WITH SIMILAR' SWITCHES.
BRUNSWICK-1 05000325 011581 DURING THE PERFORMANCE OF THE RCIC SYSTEM COMPONENT OPERABILITY TEST, P.
REAC CORE ISOL COOL SYS + CONT 81-009/03L-0 020581 T.
10.2, THE SYSTEM OIL COOLER INLET ISOLATION VALVE, 1-E51-F046, WOULD INSTRUMENTATION + CONTROLS 036088 30-DAY NOT OPEN FROM THE RTGB THEREBY MAKING THE RCIC SYSTEM INOPERABLE. THIS SWITCH EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SPEC OTHER IFICATIONS 3.7.4, 6.9.1.9B.
NOT APPLICABLE OTHER THE VALVE MOTOR CONTROL CENTER LOCAL-NORMAL KEY LOCK SWITCH WAS NOT FULL Y TURNED TO THE " NORMAL" POSITION WHICH PREVENTED AN OPEN SIGNAL TO THE VALVE FROM THE RTGB CONTROL SWITCH. KEY LOCK SWITCH WAS POSITIONED TO "N ORMAL" 1 VALVE OPERATED SATISFACTORILY. A CHECK OF THE OTHER MOTOR CONT ROL CENTER KEY LOCK SWITCHES ON BOTH UNITS DID NOT REVEAL ANY PROBLEM.
NOT APPLICABLE OTHER THE VALVE MOTOR CONTROL CENTER LOCAL-NORMAL KEY LOCK SWITCH WAS NOT FULL Y TURNED TO THE " NORMAL" POSITION WHICH PREVENTED AN OPEN SIGNAL TO THE VALVE FROM THE RTGB CONTROL SWITCH. KEY LOCK SWITCH WAS POSITIONED TO "N ORMAL" 1 VALVE OPERATED SATISFACTORILY. A CHECK OF THE OTHER MOTOR CONT ROL CENTER KEY LOCK SWITCHES ON BOTH UNITS DID NOT REVEAL ANY PROBLEM.
BRUNSWICK-1                                                                     05000325     012081     UPON AN AUTO INITIATION FOLLOUING A REACTOR SCRAM. THE RCIC TURBINE FAIL REAC CORE ISOL COOL SYS + CONT                                           81-010/03L-0       021881     ED TO ACCELERATE TO GREATER THAN ITS DESIGNED IDLE SPEED, f1AKING THE RCI CIRCUIT CLOSERS / INTERRUPTERS                                                   036228     30-DAY     C SYSTEM INOPERABLE. THE HPCI SYSTEM UAS THEN UTILIZED TO RESTORE AND M SWITCH (OTHER THAN SENSOR)                                                                             AINTAIN REACTOR LEVEL IMMEDIATELY FOLLOUING THE SCRAM. THIS EVENT DID N COMPONENT FAILURE                                                                                       OT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS ELECTRICAL                                                                                             3.7.4, 6.9.1.9B.
BRUNSWICK-1 05000325 012081 UPON AN AUTO INITIATION FOLLOUING A REACTOR SCRAM. THE RCIC TURBINE FAIL REAC CORE ISOL COOL SYS + CONT 81-010/03L-0 021881 ED TO ACCELERATE TO GREATER THAN ITS DESIGNED IDLE SPEED, f1AKING THE RCI CIRCUIT CLOSERS / INTERRUPTERS 036228 30-DAY C SYSTEM INOPERABLE. THE HPCI SYSTEM UAS THEN UTILIZED TO RESTORE AND M SWITCH (OTHER THAN SENSOR)
AINTAIN REACTOR LEVEL IMMEDIATELY FOLLOUING THE SCRAM.
THIS EVENT DID N COMPONENT FAILURE OT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SPECIFICATIONS ELECTRICAL 3.7.4, 6.9.1.9B.
LIMITORQUE CORP.
LIMITORQUE CORP.
DIRTY HIGH RESISTIVE CONTACTS IN TURBINE STEAM INLET SUPPLY VALVE, 1-E51
DIRTY HIGH RESISTIVE CONTACTS IN TURBINE STEAM INLET SUPPLY VALVE, 1-E51
                                                                                                                -F045, POSITION LIMIT SWITCH PREVENTED TURBINE RAMP GENERATOR FROM ACCEL ERATING TURBINE BEYOND ITS DESIGNED IDLE SPEED DUE TO HIGHER THAN NORMAL VOLTAGE DROP ACROSS THESE CONTACTS. CONTACTS WERE CLEANED 1 RCIC TURBIN E WAS SUCCESSFULLY OPERATED. OTHER CONTACTS CHECKED ON BOTH UNIT #1 & 2.
-F045, POSITION LIMIT SWITCH PREVENTED TURBINE RAMP GENERATOR FROM ACCEL ERATING TURBINE BEYOND ITS DESIGNED IDLE SPEED DUE TO HIGHER THAN NORMAL VOLTAGE DROP ACROSS THESE CONTACTS. CONTACTS WERE CLEANED 1 RCIC TURBIN E WAS SUCCESSFULLY OPERATED. OTHER CONTACTS CHECKED ON BOTH UNIT #1 & 2.


LER MONTHL.Y REPORT SORTED BY FACILITY                                                     PAGE 18 MAR 26, 1981 PROCESSED DURING MARCU, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /           DOCKET NO./               EVENT DATE/
MAR 26, 1981 LER MONTHL.Y REPORT SORTED BY FACILITY PAGE 18 PROCESSED DURING MARCU, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
CCMPONENT SUBCODE/CAUSE CODE / LER NO./                               REPORT DATE/                                       EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER               CONTROL NO.               REPORT TYPE                                         CAUSE DESCRIPTION BRUNSWICK-1                                         05000325                 012181             DURING ROUTINE SHUTDOWN OPERATIONS IT WAS DISCOVERED THAT REACTOR RECIRC PROCESS SAMPLING SYSTEMS                       81-011/03L-0               021881             ULATION SAMPLE INBOARD ISOLATION VALVE, 1-B32-F019. MODEL NO. T36D-1B, H VALVES                                             036229                 30-DAY             AD SEAT LEAKAGE OF APPROXIMATELY .25 GPM. THE RECIRCULATION SAMFLE CUTB OARD ISOLATICH VALVE, 1-B32-F020, WAS THEN CLOSED AND DEACTIVATED AS REQ GLOBE OTHER                                                                                          UIRED BY TECHNICil SPECIFICATIONS. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.1.3, 6.9.1.9B.
EVENT DATE/
NOT APPLICABLE UELAN VALVE CORP.
CCMPONENT SUBCODE/CAUSE CODE / LER NO./
THE CAUSE OF THE VALVE SEAT LEAKAGE IS PRESENTLY UNKNOWN. THIS VALVE WI LL BE INSPECTED AND REPAIRED DURING THE NEXT PLANNED OUTAGE OF SUFFICIEN T LENGTH AS TO ALLOW PERSONNEL ACCESS TO THE PRIMARY CONTAINMENT.
REPORT DATE/
BRUNSWICK-2                                         05000324                 101980             DURING THE PERFORMANCE OF CONTAINMENT ATMOSPHERE MONITORING SYSTEM COMPO 80-080/03X-1               012081             NENT TEST PT 24.2, THE REACTOR INSTRUMENT PENETRATION (RIP) ISCLATION VA CNTHMNT ISOLATION SYS + CONT                                                                  LVE X76-B, WOULD NOT REOPEN WHICH MADE THE CONTAINMENT ATMOSPHERIC CONTR CIRCUIT CLOSERS / INTERRUPTERS                      032999                OTHER SWITCH (OTHER THAN SENSOR)
EVENT DESCRIPTION /
DL (CAC) MONITORS 1259, 1260, AND 1261 INOPERABLE DUE TO LOSS OF SAMPLE i   COMPONENT FAILURE                                                                             FLOW THROUGH THE PENETRATION. THIS EVENT DID NOT AFFECT THE HEALTH OR S l     HATURAL END OF LIFE                                                                         AFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.6.3, 6.9.1.9B.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
OTHER                                                                                         ACTUATION SWITCH, MANUFACTURED BY MASTER SPECIALTIES. WAS F0ttND TO HAVE ITS BAKE-LITE NIPPLE BROKEN OFF, WHICH PREVENTED THE SWITCH ACTUATION PL TH UNGER FROM RESE1 TING THE SWITCH CONTACTS AFTER THE VALVE RAS CLOSED.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-1 05000325 012181 DURING ROUTINE SHUTDOWN OPERATIONS IT WAS DISCOVERED THAT REACTOR RECIRC PROCESS SAMPLING SYSTEMS 81-011/03L-0 021881 ULATION SAMPLE INBOARD ISOLATION VALVE, 1-B32-F019. MODEL NO. T36D-1B, H VALVES 036229 30-DAY AD SEAT LEAKAGE OF APPROXIMATELY.25 GPM.
E ENTIRE SWITCH MODULE WAS REPL ACED AND THE VALVE WAS SUCcESSFULLY CYCLE D. THIS IS CONSIDERED AN ISOLATED EVENT WITH NO FURTHER ACTION REQ.
THE RECIRCULATION SAMFLE CUTB GLOBE OARD ISOLATICH VALVE, 1-B32-F020, WAS THEN CLOSED AND DEACTIVATED AS REQ UIRED BY TECHNICil SPECIFICATIONS. THIS EVENT DID NOT AFFECT THE HEALTH OTHER NOT APPLICABLE OR SAFETY OF THE PUBLIC.
DRUNSWICK-2                                         05000324                 122580             DURING THE PERFORMANCE OF A CALIBRATION CHECK ON PRIMARY CONTAIFhENT ATM CNTHMNT COMBUS GAS CONTROL SYS                 80-119/03L-0               012181             OSPHERIC MONITOR, 2-CAC-AT-1263, MODEL NO. 7C6A-1A3AX, IT WAS DISCOVERED T
TECHNICAL SPECIFICATIONS 3.1.3, 6.9.1.9B.
INSTRUMENTATION + CONTRDLS                         033703                 30-DAY               THAT THE MONI!OR HYDROGEN ANALYZER TRANSMITTER HAD NO OUTPUT SIGNAL.
UELAN VALVE CORP.
HIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.           TECHNICAL SWITCH                                                                                       SPECIFICATIONS 3.3.5.3, 6.9.1.9B.
THE CAUSE OF THE VALVE SEAT LEAKAGE IS PRESENTLY UNKNOWN.
COMPONENT FAILURE ELECTRICAL DECKMAN INSTRUMENTS, INC.
THIS VALVE WI LL BE INSPECTED AND REPAIRED DURING THE NEXT PLANNED OUTAGE OF SUFFICIEN T LENGTH AS TO ALLOW PERSONNEL ACCESS TO THE PRIMARY CONTAINMENT.
BRUNSWICK-2 05000324 101980 DURING THE PERFORMANCE OF CONTAINMENT ATMOSPHERE MONITORING SYSTEM COMPO CNTHMNT ISOLATION SYS + CONT 80-080/03X-1 012081 NENT TEST PT 24.2, THE REACTOR INSTRUMENT PENETRATION (RIP) ISCLATION VA CIRCUIT CLOSERS / INTERRUPTERS 032999 OTHER LVE X76-B, WOULD NOT REOPEN WHICH MADE THE CONTAINMENT ATMOSPHERIC CONTR SWITCH (OTHER THAN SENSOR)
DL (CAC) MONITORS 1259, 1260, AND 1261 INOPERABLE DUE TO LOSS OF SAMPLE i
COMPONENT FAILURE FLOW THROUGH THE PENETRATION. THIS EVENT DID NOT AFFECT THE HEALTH OR S l
HATURAL END OF LIFE AFETY OF THE PUBLIC.
TECHNICAL SPECIFICATIONS 3.6.3, 6.9.1.9B.
OTHER ACTUATION SWITCH, MANUFACTURED BY MASTER SPECIALTIES. WAS F0ttND TO HAVE ITS BAKE-LITE NIPPLE BROKEN OFF, WHICH PREVENTED THE SWITCH ACTUATION PL UNGER FROM RESE1 TING THE SWITCH CONTACTS AFTER THE VALVE RAS CLOSED.
TH E ENTIRE SWITCH MODULE WAS REPL ACED AND THE VALVE WAS SUCcESSFULLY CYCLE D.
THIS IS CONSIDERED AN ISOLATED EVENT WITH NO FURTHER ACTION REQ.
DRUNSWICK-2 05000324 122580 DURING THE PERFORMANCE OF A CALIBRATION CHECK ON PRIMARY CONTAIFhENT ATM CNTHMNT COMBUS GAS CONTROL SYS 80-119/03L-0 012181 OSPHERIC MONITOR, 2-CAC-AT-1263, MODEL NO. 7C6A-1A3AX, IT WAS DISCOVERED INSTRUMENTATION + CONTRDLS 033703 30-DAY THAT THE MONI!OR HYDROGEN ANALYZER TRANSMITTER HAD NO OUTPUT SIGNAL.
T HIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SWITCH COMPONENT FAILURE SPECIFICATIONS 3.3.5.3, 6.9.1.9B.
ELECTRICAL DECKMAN INSTRUMENTS, INC.
THE MONITOR LOCAL / REMOTE SWITCH, LOCATED IN THE CONTROL ROOM HAD DIRTY C OHTACTS WHICH BLOCKED SIGNAL OUTPUT FROM HYDROGEN ANALYZER 8 PREVENTED I TS CALIBRATION. SWITCH CONTACTS WERE CLEANED 1 MONITOR WAS SUCCESSFULLY CALIBRATIDH CHECKED. AS THERE IS NO HISTORY OF PROBLEMS WITH THESE SWIT CHES THIS IS CONSIDERED AN ISCL EVENT WITH NO FURTHER ACTION REQUIRED.
THE MONITOR LOCAL / REMOTE SWITCH, LOCATED IN THE CONTROL ROOM HAD DIRTY C OHTACTS WHICH BLOCKED SIGNAL OUTPUT FROM HYDROGEN ANALYZER 8 PREVENTED I TS CALIBRATION. SWITCH CONTACTS WERE CLEANED 1 MONITOR WAS SUCCESSFULLY CALIBRATIDH CHECKED. AS THERE IS NO HISTORY OF PROBLEMS WITH THESE SWIT CHES THIS IS CONSIDERED AN ISCL EVENT WITH NO FURTHER ACTION REQUIRED.
05000324                 122780             DURING THE PERFORMANCE OF RHR SERVICE WATER SYSTEM COMPONENT TEST, PT 8.
BRUNSWICK-2 05000324 122780 DURING THE PERFORMANCE OF RHR SERVICE WATER SYSTEM COMPONENT TEST, PT 8.
BRUNSWICK-2                                                                                    2.4, A VIBRATION OF 3.2 MILS WAS RECORDED FOR 2C RHR SW PUMP WHICH EXCEE RESIDUAL HEAT REMOV SYS + CONT                80-197/03L-0                012381 PUMPS                                               033701                 30-DAY             DED THE SPECIFIED REQUIRED ACTION RANGE OF > 1.5 MILS. THE PUMP WAS THE CENTRIFUGAL                                                                                  REFDRE DEOJRED INOPERABLE AS REQUIRED BY TECHNICAL SPECIFICATIONS. THI DESIGN / FABRICATION ERROR                                                                     S EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SP DESIGN ECIFICATIONS 3.7.1.1, 6.9.1.93.
RESIDUAL HEAT REMOV SYS + CONT 80-197/03L-0 012381 2.4, A VIBRATION OF 3.2 MILS WAS RECORDED FOR 2C RHR SW PUMP WHICH EXCEE PUMPS 033701 30-DAY DED THE SPECIFIED REQUIRED ACTION RANGE OF > 1.5 MILS.
THE PUMP WAS THE REFDRE DEOJRED INOPERABLE AS REQUIRED BY TECHNICAL SPECIFICATIONS. THI CENTRIFUGAL DESIGN / FABRICATION ERROR S EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SP DESIGN ECIFICATIONS 3.7.1.1, 6.9.1.93.
INGERSOLL-RAND CD THE PUMP DIFFUSER ANTI-ROTATING PIN DISLODGED FROM THE PUMP CASING ANG B ECAME EMBEDDED BETWEEN THE DIFFUSER VANE AND PUMP IMPELLER CAUSING A RUB BING CONDITION BETWEEN THE IMPELLER AND THE PIN WHEN THE PUMP WAS IN OPE RATION. PIN WAS REPLACED 2 PUMP RETURNED TO NORMAL OPERABILITY. THIS I S CONSIDERED AN ISOLATED EVENT WITH NO FURTHER CORRECTIVE ACTION REQ.
INGERSOLL-RAND CD THE PUMP DIFFUSER ANTI-ROTATING PIN DISLODGED FROM THE PUMP CASING ANG B ECAME EMBEDDED BETWEEN THE DIFFUSER VANE AND PUMP IMPELLER CAUSING A RUB BING CONDITION BETWEEN THE IMPELLER AND THE PIN WHEN THE PUMP WAS IN OPE RATION. PIN WAS REPLACED 2 PUMP RETURNED TO NORMAL OPERABILITY. THIS I S CONSIDERED AN ISOLATED EVENT WITH NO FURTHER CORRECTIVE ACTION REQ.


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                       PAGE 19 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 19 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/MAMUFACTURER     CONTROL NO. REPORT TYPE                               CAUSE DESCRIPTION BRUNSWICK-2                             05000324     122980     FOLLOWING A REACTOR SCRAM, REACTOR LEVEL INSTRUMENT, 2-B21-LI-R604A, DID OTHR INST SYS REQD FOR SAFETY       80-121/03L-0   012781     NOT TRACK PROPERLY TO DECREASING REACTOR LEVEL. ALL OTHER LEVEL INDICA INSTRUMENTATION + CONTROLS             033704     30-DAY     TIONS RESPONDED PROPERLY TO CHANGES IN REACTOR LEVEL. THIS EVENT DID NO TRANSMITTER                                                 T AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3 DESIGN / FABRICATION ERROR                                     .3.5.3, 6.9.1.93.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/MAMUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 122980 FOLLOWING A REACTOR SCRAM, REACTOR LEVEL INSTRUMENT, 2-B21-LI-R604A, DID OTHR INST SYS REQD FOR SAFETY 80-121/03L-0 012781 NOT TRACK PROPERLY TO DECREASING REACTOR LEVEL.
ALL OTHER LEVEL INDICA INSTRUMENTATION + CONTROLS 033704 30-DAY TIONS RESPONDED PROPERLY TO CHANGES IN REACTOR LEVEL.
THIS EVENT DID NO TRANSMITTER T AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SPECIFICATIONS 3 DESIGN / FABRICATION ERROR
.3.5.3, 6.9.1.93.
DESIGN YARWAY CORP.
DESIGN YARWAY CORP.
THE GAIN SETTING ON THE INSTRUMENT LEVEL TRANSMITTER, 2-B21-LT-N026A, DR IFTED OUT OF CALIBRATICN. THE TRANSMITTER WAS THEN RECALIBRATED AND RET URNED TO NORMAL OPERATION. A CHECK OF THE OTHER SIMILAR LEVEL TRANSMITT ERS ON BOTH UNITS DIo NOT REVEAL ANY PROBLEMS. THESE TYPE TRAHSM WILL BE REPLACED WITH MORE RELIABLE INSTRUMENTATION DURING A FUTURE OUTAGE.
THE GAIN SETTING ON THE INSTRUMENT LEVEL TRANSMITTER, 2-B21-LT-N026A, DR IFTED OUT OF CALIBRATICN. THE TRANSMITTER WAS THEN RECALIBRATED AND RET URNED TO NORMAL OPERATION.
BRUNSWICK-2                             05000324     123180     DURING THE PERFORMANCE OF ADS HIGH DRYWELL PRESSURE CHANNEL CALIBRATION ENGNRD SAFETY FEATR INSTR SYS       80-116/03L-0   012351     AND FUNCTIONAL TEST, PT 11.1.4PC, 2-E11-PS-N010A, MODEL NO. D28-M18SS. A INSTRUMENTATION + CONTROLS             033700     30-DAY     CTUATED AT 2.1 PSIG WHILE THE REPORTABLE LIMIT IS > 2.0 PSIG. ALL OTHER SWITCH                                                         PRESSURE SWITCHES ACTUATED WITHIN SPECIFICATIONS. THIS EVENT DID NOT A OTHER                                                         FFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 4.3.
A CHECK OF THE OTHER SIMILAR LEVEL TRANSMITT ERS ON BOTH UNITS DIo NOT REVEAL ANY PROBLEMS. THESE TYPE TRAHSM WILL BE REPLACED WITH MORE RELIABLE INSTRUMENTATION DURING A FUTURE OUTAGE.
NOT APPLICABLE                                               3.1, 6.9.1.9B.
BRUNSWICK-2 05000324 123180 DURING THE PERFORMANCE OF ADS HIGH DRYWELL PRESSURE CHANNEL CALIBRATION ENGNRD SAFETY FEATR INSTR SYS 80-116/03L-0 012351 AND FUNCTIONAL TEST, PT 11.1.4PC, 2-E11-PS-N010A, MODEL NO. D28-M18SS. A INSTRUMENTATION + CONTROLS 033700 30-DAY CTUATED AT 2.1 PSIG WHILE THE REPORTABLE LIMIT IS > 2.0 PSIG.
BARKSDALE COMPANY THE PRESSURE SWITCH WAS OUT OF CALIBRATION DUE TO INSTRUMENT DRIFT. IT WAS RECALIBRATED ACCORDING TO THE PT AND RETURNED TO SATISFACTORY OPERAT ION. THIS INSTRUMENT HAS A HISTORY OF RELIABLE OPERATION; HOWEVER, PERF CRMANCE OF OTHER SIMILAR INSTRUMENTS WILL BE REVIEWED IN ACCCRDANCE WITH THE?R PT SCHEDULE TO ENSURE THERE ARE NO FAILURE TRENDS.
ALL OTHER SWITCH PRESSURE SWITCHES ACTUATED WITHIN SPECIFICATIONS. THIS EVENT DID NOT A OTHER FFECT THE HEALTH OR SAFETY OF THE PUBLIC.
BRUNSWICK-2                             05000324     123180   DURING UNIT LOAD CHANGES WHILE MOVING CONTROL RODS, NO. 38-11 POSITION I REACTIVITY CONTROL SYSTEMS         80-118/03L-0   012281     HDICATION SHOWED A SUPERIMPOSED "3" DVER THE "8" DIGIT WHEN AT POSITION INSTRUMENTATION + CONTROLS             033702     30-DAY     "48". ALL OTHER CONTROL ROD POSITIDH INDICATIONS WERE NORMAL. THIS EVE SWITCH                                                     NT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFI COMPONENT FAILURE                                             CATIONS 3.1.3.F,   6.9.1.98.
TECHNICAL SPECIFICATIONS 4.3.
NOT APPLICABLE 3.1, 6.9.1.9B.
BARKSDALE COMPANY THE PRESSURE SWITCH WAS OUT OF CALIBRATION DUE TO INSTRUMENT DRIFT.
IT WAS RECALIBRATED ACCORDING TO THE PT AND RETURNED TO SATISFACTORY OPERAT ION.
THIS INSTRUMENT HAS A HISTORY OF RELIABLE OPERATION; HOWEVER, PERF CRMANCE OF OTHER SIMILAR INSTRUMENTS WILL BE REVIEWED IN ACCCRDANCE WITH THE?R PT SCHEDULE TO ENSURE THERE ARE NO FAILURE TRENDS.
BRUNSWICK-2 05000324 123180 DURING UNIT LOAD CHANGES WHILE MOVING CONTROL RODS, NO. 38-11 POSITION I REACTIVITY CONTROL SYSTEMS 80-118/03L-0 012281 HDICATION SHOWED A SUPERIMPOSED "3" DVER THE "8" DIGIT WHEN AT POSITION INSTRUMENTATION + CONTROLS 033702 30-DAY "48".
ALL OTHER CONTROL ROD POSITIDH INDICATIONS WERE NORMAL.
THIS EVE SWITCH NT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
TECHNICAL SPECIFI COMPONENT FAILURE CATIONS 3.1.3.F, 6.9.1.98.
ELECTRICAL GENERAL ELECTRIC CO.
ELECTRICAL GENERAL ELECTRIC CO.
A REED SWITCH PROBLEM IN THE ROD PIP PROBE IS SUSPECTED AS THE CAUSE OF THIS EVENT. THIS PROBLEM WILL BE CORRECTED DURING THE NEXT GUTAGE OF SU FFICIENT LENGTH THAT ALLOWS ACCESS TO THE DRYWELL.
A REED SWITCH PROBLEM IN THE ROD PIP PROBE IS SUSPECTED AS THE CAUSE OF THIS EVENT.
BRUNSWICK-2                             05000324     010481     DURING THE P RFORMANCE OF THE DRYWELL 10 SUPPRESSION CHAMBER VACUUM BREA REACTOR CONTAINMENT SYSTEMS         81-002/03L-0   013081     KERS' FUNCTIONAL TEST, PT 2.3.1,   VACUUM BREAKER X-18A HAD DUAL OPEN-CLOS VALVES                                 036090     30-DAY     E POSITION INDICATION WHILE IN THE CPEN POSITION. ALL OTHER VACUUM BREA CHECK                                                       KER POSITION INDICATIONS WERE NORMAL. THIS EVENT DID NOT AFFECT THE HEA LTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.6.4.1,     6.9.1.9B OTHER NOT APPLICABLE GENERAL PRECISION INC.
THIS PROBLEM WILL BE CORRECTED DURING THE NEXT GUTAGE OF SU FFICIENT LENGTH THAT ALLOWS ACCESS TO THE DRYWELL.
THIS EVENT IS BELIEVED TO HAVE BEEN CAUSED BY A PROBLEM WITH THE VACUUM BREAKER POSITION LIMIT SWITCHES. THE PROBLEM WILL BE FULLY INVESTIGATED AND RESOLVED DURING THE NEXT OUTAGE OF SUFFICIENT LENGTH THAT ALLCMS FE RSONNEL ACCESS TO THE DRYWELL.
BRUNSWICK-2 05000324 010481 DURING THE P RFORMANCE OF THE DRYWELL 10 SUPPRESSION CHAMBER VACUUM BREA REACTOR CONTAINMENT SYSTEMS 81-002/03L-0 013081 KERS' FUNCTIONAL TEST, PT 2.3.1, VACUUM BREAKER X-18A HAD DUAL OPEN-CLOS VALVES 036090 30-DAY E POSITION INDICATION WHILE IN THE CPEN POSITION.
ALL OTHER VACUUM BREA CHECK KER POSITION INDICATIONS WERE NORMAL.
THIS EVENT DID NOT AFFECT THE HEA OTHER LTH OR SAFETY OF THE PUBLIC.
TECHNICAL SPECIFICATIONS 3.6.4.1, 6.9.1.9B NOT APPLICABLE GENERAL PRECISION INC.
THIS EVENT IS BELIEVED TO HAVE BEEN CAUSED BY A PROBLEM WITH THE VACUUM BREAKER POSITION LIMIT SWITCHES.
THE PROBLEM WILL BE FULLY INVESTIGATED AND RESOLVED DURING THE NEXT OUTAGE OF SUFFICIENT LENGTH THAT ALLCMS FE RSONNEL ACCESS TO THE DRYWELL.


MAR 26. 1981                                         LER MONTHLY REPORT SORTED BY FACILITY                                       PAGE 20 I
MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 20 I
PROCESSED DURING MARCH. 1981 FOR POWER REACTORS                                                   '
PROCESSED DURING MARCH. 1981 FOR POWER REACTORS 3
3 FACILITY / SYSTEM /CCMPONENT/ DOCKET NO./       EVENT DATE/                                                                                 -
FACILITY / SYSTEM /CCMPONENT/
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                               EVENT DESCRIPTION /                             I CAUSE SUBCODE/ MANUFACTURER   CONTROL NO.       REPORT TYPE                                 CAUSE DESCRIPTION BRUNSWICK-2                         05000324         011081     DURING A NORMAL REACTOR STARTUP, IRM "A" DID NOT RESPOND TO CHANGES IN I REACTOR TRIP SYSTEMS             81-004/03L-0       020581     TS INPUT SIGNAL UHILE IRM "C" INDICATED DOWNSCALE WHEN ON RANGE 7. ON J INSTRUMENTATION + CONTROLS           036091         30-DAY     ANUARY 11. 1981 IRM *E" INDICATED DOWNSCALE WHILE FRM "C" WAS STILL IMO-POWER SUPPLY                                                   PERABLE FROM THE PREVIOUS DAY. THESE EVENTS DID NOT AFFECT THE HEALTH 0 COMPONENT FAILURE                                               R SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.3.1 6.9.1.9B NATURAL END OF LIFE GENERAL ELECTRIC CD.
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
I CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 011081 DURING A NORMAL REACTOR STARTUP, IRM "A" DID NOT RESPOND TO CHANGES IN I REACTOR TRIP SYSTEMS 81-004/03L-0 020581 TS INPUT SIGNAL UHILE IRM "C" INDICATED DOWNSCALE WHEN ON RANGE 7.
ON J INSTRUMENTATION + CONTROLS 036091 30-DAY ANUARY 11. 1981 IRM *E" INDICATED DOWNSCALE WHILE FRM "C" WAS STILL IMO-POWER SUPPLY PERABLE FROM THE PREVIOUS DAY.
THESE EVENTS DID NOT AFFECT THE HEALTH 0 COMPONENT FAILURE R SAFETY OF THE PUBLIC.
TECHNICAL SPECIFICATIONS 3.3.1 6.9.1.9B NATURAL END OF LIFE GENERAL ELECTRIC CD.
IRM "A" HAD 2 FAILED CAPACITORS IN ITS HIGH VOLTAGE POWER SUPPLY. IRM "C
IRM "A" HAD 2 FAILED CAPACITORS IN ITS HIGH VOLTAGE POWER SUPPLY. IRM "C
                                                                  " HAD A FAILED HIGH FREQUENCY CHANNEL TRANSISTOR, AND IRM "E" HAD AN OPE
" HAD A FAILED HIGH FREQUENCY CHANNEL TRANSISTOR, AND IRM "E" HAD AN OPE N SIGNAL AT THE MONITOR PEE
* N SIGNAL AT THE MONITOR PEE
* AMP CONNECTOR.
* AMP CONNECTOR. THE FAILED COMPONENTS IN IRN
THE FAILED COMPONENTS IN IRN
                                                                  'S A AND C WERE REPLACCD F40 THE CONNECTOR OF IRM "E" WAS REPAIRED WHICH       i RETURNED ALL THREE IRM't TG NORMAL OPERATION.
'S A AND C WERE REPLACCD F40 THE CONNECTOR OF IRM "E" WAS REPAIRED WHICH i
BRUNSWICK-2                         05000324         011381     DURING NORMAL SURVEILLANr&- IT MAS DISCOVERED THAT THE SECONDARY CONTAIN REACTOR CONTAINMENT SYSTEMS     81-005/03L-0       021181     MENT 20' ELEVATION OUTER air LOCK PERSONNEL DOOR WAS NOT SEALING CUE To       '
RETURNED ALL THREE IRM't TG NORMAL OPERATION.
PENETRATIONS.PRIMRY CONTAINMNT       036092         30-DAY     A DAMAGED SECTION OF GASKET SEALING MATERIAL MAKING THE DOOR INDPERABLE.       ;
BRUNSWICK-2 05000324 011381 DURING NORMAL SURVEILLANr&- IT MAS DISCOVERED THAT THE SECONDARY CONTAIN REACTOR CONTAINMENT SYSTEMS 81-005/03L-0 021181 MENT 20' ELEVATION OUTER air LOCK PERSONNEL DOOR WAS NOT SEALING CUE To PENETRATIONS.PRIMRY CONTAINMNT 036092 30-DAY A DAMAGED SECTION OF GASKET SEALING MATERIAL MAKING THE DOOR INDPERABLE.
'  PERSONNEL ACCESS                                                 THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC. TECHNICA       !
PERSONNEL ACCESS THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.
COMPONENT FAILURE                                               L SPECIFICATIONS 3.6.S.I. 6.9.1.9B NATURAL END OF LIFE OTHER                                                                                                                                         j HIGH PERSONNEL TRAFFIC THROUGH tJCt, MANUFACTURED BY PROTECTED DOOR INDU STRIES. CAUSED GASKET TO BECOME DA1 AGED. GASKET WAS REPAIRED 8 COOR WAS       ;
TECHNICA COMPONENT FAILURE L SPECIFICATIONS 3.6.S.I. 6.9.1.9B NATURAL END OF LIFE OTHER j
RETURNED TO NORMAL OPERATION. DCOR MANUFACTURER FACTORY REPRESENTATIVE HAS INSPECTED D00R & HAS MADE RECGdMENDATIONS TO ASSIST IN DEVELOPING A     )
HIGH PERSONNEL TRAFFIC THROUGH tJCt, MANUFACTURED BY PROTECTED DOOR INDU STRIES. CAUSED GASKET TO BECOME DA1 AGED.
PRFVENTATIVE MAINTENANCE PROCEDURE TO INSPECT DOORS ON A REGULAR BASIS.     '
GASKET WAS REPAIRED 8 COOR WAS RETURNED TO NORMAL OPERATION. DCOR MANUFACTURER FACTORY REPRESENTATIVE HAS INSPECTED D00R & HAS MADE RECGdMENDATIONS TO ASSIST IN DEVELOPING A
BRUNSWICK-2                         05000324         011581     DURING NORMAL PLANT OPERATION A GROUP I ISOLATION SIGNAL WAS RECEIVED ON REACTOR TRIP SYSTEMS             81- 0 0 7/ 0 3L-0   021081       THE "B" RPS TRIP CHANNEL. ALL-REACTOR OPERATING PARAMETERS REMAINED NO RELAYS                               036093         30-DAY     RMAL DURING AND FOLLOWING THIS EVENT. THIS EVENT DID Nf1T AFFECT THE HEA OTHER                                                         LTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.3.2. 6.9.1.9B COMPONENT FAILURE NATURAL END OF LIFE GENERAL ELECTRIC CD.
)
THE *B" RPS TRIP CHANNEL RELAY COIL FAILED DUE TO AN INSULATION BREAKDOW N. THIS COIL. MODEL NO. P/M 12HFAS1A49F. IS DESIGNED TO BE CONSTANTLY E HERGIZED FOR CONTINUGUS SERVICE. THIS TYPE COIL IS UTILIZED THROUGHOUT THE RPS TRIP SYSTEM AND HAS NO PREVIOUS HISTORY OF SIMILAR FAILURES. RE LAY COIL WAS REPLACED.
PRFVENTATIVE MAINTENANCE PROCEDURE TO INSPECT DOORS ON A REGULAR BASIS.
BRUNSWICK-2                         05000324         011581     DURING THE PERFORMANCE OF MAIN STEAM LINE ISOLATION VALVE CLOSURE CHANNE.
BRUNSWICK-2 05000324 011581 DURING NORMAL PLANT OPERATION A GROUP I ISOLATION SIGNAL WAS RECEIVED ON REACTOR TRIP SYSTEMS 81- 0 0 7/ 0 3L-0 021081 THE "B" RPS TRIP CHANNEL. ALL-REACTOR OPERATING PARAMETERS REMAINED NO RELAYS 036093 30-DAY RMAL DURING AND FOLLOWING THIS EVENT.
MAIN STEAM SUPPLY SYS + CONT     81-006/03L-0 020S81           L FUNCTIONAL TEST. P.T. 1.3.1P-2 WHEN MSIV F028C WAS REOPENED MAIN STEA VALVES                               036167         30-DAY   M LINE "C" INDICATED MINIMUM FLOW. IT IS BELIEVED THAT A STEM-DISC SEPA         1 GLOBE                                                         RATION HAS DCCURRED IN THE OUTBOARD MSIV ON MAIN STEAM-LINE "C". BOTH M COMPONENT FAILURE                                               SIV's IN f1AIN STEAM LINE "C" WERE THEN SHUT AND DEACTIVATED. TECHNICAL OTHER                                                         SPECIFICATIONS 3.6.3. 6.9.1.9B.
THIS EVENT DID Nf1T AFFECT THE HEA OTHER LTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.3.2. 6.9.1.9B COMPONENT FAILURE NATURAL END OF LIFE GENERAL ELECTRIC CD.
THE *B" RPS TRIP CHANNEL RELAY COIL FAILED DUE TO AN INSULATION BREAKDOW N.
THIS COIL. MODEL NO. P/M 12HFAS1A49F. IS DESIGNED TO BE CONSTANTLY E HERGIZED FOR CONTINUGUS SERVICE. THIS TYPE COIL IS UTILIZED THROUGHOUT THE RPS TRIP SYSTEM AND HAS NO PREVIOUS HISTORY OF SIMILAR FAILURES. RE LAY COIL WAS REPLACED.
BRUNSWICK-2 05000324 011581 DURING THE PERFORMANCE OF MAIN STEAM LINE ISOLATION VALVE CLOSURE CHANNE.
MAIN STEAM SUPPLY SYS + CONT 81-006/03L-0 020S81 L FUNCTIONAL TEST. P.T.
1.3.1P-2 WHEN MSIV F028C WAS REOPENED MAIN STEA VALVES 036167 30-DAY M LINE "C" INDICATED MINIMUM FLOW.
IT IS BELIEVED THAT A STEM-DISC SEPA 1
GLOBE RATION HAS DCCURRED IN THE OUTBOARD MSIV ON MAIN STEAM-LINE "C".
BOTH M COMPONENT FAILURE SIV's IN f1AIN STEAM LINE "C" WERE THEN SHUT AND DEACTIVATED. TECHNICAL OTHER SPECIFICATIONS 3.6.3. 6.9.1.9B.
ROCKWELL~ MANUFACTURING CD.
ROCKWELL~ MANUFACTURING CD.
AT THIS TIME THE EXACT CAUSE OF THE MINIMUM STEAM FLOW IN MAIN STEAM LIN E "C" HAS NOT BEEN DETERMINED. AN INVESTIGATION WILL BE PERFORMED DURIN G A FUTURE OUTAGE. A SUPPLEMENT TO THIS REPORT WILL BE SUBMITTED FOLLOW ING A DETERMINATION AND REPAIR-OF THE PROBLEM CAUSING THIS EVENT.
AT THIS TIME THE EXACT CAUSE OF THE MINIMUM STEAM FLOW IN MAIN STEAM LIN E "C" HAS NOT BEEN DETERMINED. AN INVESTIGATION WILL BE PERFORMED DURIN G A FUTURE OUTAGE.
A SUPPLEMENT TO THIS REPORT WILL BE SUBMITTED FOLLOW ING A DETERMINATION AND REPAIR-OF THE PROBLEM CAUSING THIS EVENT.
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MAR 26, 1981                                                                                                                                         LER MONTHLY REPORT SORTED BY FACILITY                                                                                                                                           PAGE 21 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                                                                   DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 21 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                                                         REPORT DATE/                                                                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                                                                                       CONTEM NO. REPORT TYPE                                                                                   CAUSE DESCRIPTION I
EVENT DATE/
BRUNSWICK-2                                                                                                                               05000324     011981                                   WHILE PERFORMING PT 9.3A, HPCI SYSTEM COMPONENT TEST. IT WAS DETERMINED EMERG CORE COOLING SYS + Co*'                                                                                                         81-013/03L-0   020381                                   THAT THE PERIODIC TEST COULD HOT BE COMPLETED DUE TJ A FAILED MOTOR ON T VALVE OPERATORS                                                                                                                           036048       30-DAY                                   HE CST SUCTION VALVE, F004.                           THIS EVENT DID NOT AFFECT THE HEALTH OR SAF ELECTRIC MOTOR - DC                                                                                                                                                                           ETY OF THE PUBLIC AS THE SYSTEM WAS LINED UP TO USE THE SUPPRESSION POOL COMPONENT FAILURE                                                                                                                                                                                 FOR ITS WATER SOURCE.       TECHNICAL SPECIFICATIONS 3.51, 6.9.1.9C.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTEM NO.
REPORT TYPE CAUSE DESCRIPTION I
BRUNSWICK-2 05000324 011981 WHILE PERFORMING PT 9.3A, HPCI SYSTEM COMPONENT TEST. IT WAS DETERMINED EMERG CORE COOLING SYS + Co*'
81-013/03L-0 020381 THAT THE PERIODIC TEST COULD HOT BE COMPLETED DUE TJ A FAILED MOTOR ON T VALVE OPERATORS 036048 30-DAY HE CST SUCTION VALVE, F004.
THIS EVENT DID NOT AFFECT THE HEALTH OR SAF ELECTRIC MOTOR - DC ETY OF THE PUBLIC AS THE SYSTEM WAS LINED UP TO USE THE SUPPRESSION POOL COMPONENT FAILURE FOR ITS WATER SOURCE.
TECHNICAL SPECIFICATIONS 3.51, 6.9.1.9C.
ELECTRICAL LIMITORQUE CORP.
ELECTRICAL LIMITORQUE CORP.
THE MOTOR WHICH OPERATES THE F004 VALVE FAILED AND HAS BEEN SENT TO A SE RVICE CONTRACTOR FOR REPAIR.                               THE PLANT IS PRESENTLY ATTEMPTING-TO LOCAT l
THE MOTOR WHICH OPERATES THE F004 VALVE FAILED AND HAS BEEN SENT TO A SE RVICE CONTRACTOR FOR REPAIR.
'                                                                                                                                                                                                  E ANOTHER MOTOR IN THE INDUSTRY FOR USE UNTIL OURS IS REPAIRED. THIS IS j
THE PLANT IS PRESENTLY ATTEMPTING-TO LOCAT l
CONSIDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.
E ANOTHER MOTOR IN THE INDUSTRY FOR USE UNTIL OURS IS REPAIRED.
GRUNSWICK-2                                                                                                                               05000324     012881                                   FOLLOWING THE COMPLETION OF A PLANNED CONTROLLED RELEASE OF LIQUID RADIO                                                                     i I   LIQ RADIDACT WSTE MANAGMNT SYS                                                                                                         81-009/04L-0   021181                                   ACTIVE WASTE. THE RADWASTE SYSTEM LICUID EFFLUENT DISCH ARGE HIGH RANGE I                                                                     l INSTRUMENTATION + CONTROLS                                                                                                               036168       30-DAY                                   NDICATOR/ RECORDER, UTILIZED FOR THE RELEASE, WAS FOUND TO HAVE INDICATED l
THIS IS CONSIDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.
TRANSMITTER                                                                                                                                                                                     AND RECORDED A RELEASE FLOW RATE THAT WAS LESS THAN THE-ACTUAL CAUSING                                                                     '
j GRUNSWICK-2 05000324 012881 FOLLOWING THE COMPLETION OF A PLANNED CONTROLLED RELEASE OF LIQUID RADIO i
l  COMPONENT FAILURE                                                                                                                                                                               THE SPECIFIED MAXIMUM ALLOWED RELEASE RATE TO BE EXCEEDED. ENVIRONMENTA l   MECHANICAL                                                                                                                                                                                     L TECPMICAL-SPECIFICATIONS 3.5.1.E. 5.4.2B.
I LIQ RADIDACT WSTE MANAGMNT SYS 81-009/04L-0 021181 ACTIVE WASTE. THE RADWASTE SYSTEM LICUID EFFLUENT DISCH ARGE HIGH RANGE I l
l INSTRUMENTATION + CONTROLS 036168 30-DAY NDICATOR/ RECORDER, UTILIZED FOR THE RELEASE, WAS FOUND TO HAVE INDICATED TRANSMITTER AND RECORDED A RELEASE FLOW RATE THAT WAS LESS THAN THE-ACTUAL CAUSING l
COMPONENT FAILURE THE SPECIFIED MAXIMUM ALLOWED RELEASE RATE TO BE EXCEEDED. ENVIRONMENTA l
MECHANICAL L TECPMICAL-SPECIFICATIONS 3.5.1.E. 5.4.2B.
GENERAL ELECTRIC CO.
GENERAL ELECTRIC CO.
l                                                                                                                                                                                                   MECHANICAL LINKAGE BETWEEN FLOW PADDLE & TRANSMITTER BECAME LOOSE CAUSIN G THE FALSE FLOW INDICATION. PROBLEM WAS CORRECTED 3 INSTRUMENT RETURNE D TO NORMAL OPERATION. THIS IS CONSIDERED AN ISOLATED EVENT WITH NO FUR THER ACTION REQUIRED. PLANT PREVENTATIVE MAINTENANCE PROCEDURES WILL BE REVISED TO CALIBRATE THIS INDICATOR / RECORDER & TRANSMITTER QUARTERLY.
l MECHANICAL LINKAGE BETWEEN FLOW PADDLE & TRANSMITTER BECAME LOOSE CAUSIN G THE FALSE FLOW INDICATION. PROBLEM WAS CORRECTED 3 INSTRUMENT RETURNE D TO NORMAL OPERATION. THIS IS CONSIDERED AN ISOLATED EVENT WITH NO FUR THER ACTION REQUIRED. PLANT PREVENTATIVE MAINTENANCE PROCEDURES WILL BE REVISED TO CALIBRATE THIS INDICATOR / RECORDER & TRANSMITTER QUARTERLY.
CALVERT CLIFFS-1                                                                                                                         05000317     .122280                                   18C TECHNICIANS INVESTIGATING A GREATER THAN 0.1 VOLT DEVIATION BETWEEN ENGNRD SAFETY FEATR INSTR SYS                                                                                                         80-069/03L-0   012181                                   12 STEAM GENERATOR PRESSURE ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION + CONTROLS                                                                                                               033705       30-DAY                                   CHANNEL ZD AND OTHER CHANNELS DETERMINED THAT E/E CONVERTER WAS DEFECTIV INDICATOR                                                                                                                                                                                     E FOR CHANNEL ZG. E/E CONVERTER WAS REPL ACED AND CHANNEL' ZG RETURNED TO COMPONENT FAILURE                                                                                                                                                                                 SERVICE AT 1115. THE THREE REDUNDANT CHANNELS REMAINED OPERABLE. LER' OTHER                                                                                                                                                                                         S 79-70 AND 80-13 (U-1) DESCRIBE SIMILAR EVENTS.
CALVERT CLIFFS-1 05000317
VITRO ENGINEERING DIVISION j
.122280 18C TECHNICIANS INVESTIGATING A GREATER THAN 0.1 VOLT DEVIATION BETWEEN ENGNRD SAFETY FEATR INSTR SYS 80-069/03L-0 012181 12 STEAM GENERATOR PRESSURE ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION + CONTROLS 033705 30-DAY CHANNEL ZD AND OTHER CHANNELS DETERMINED THAT E/E CONVERTER WAS DEFECTIV INDICATOR E FOR CHANNEL ZG.
THE CAUSE FOR THE DEVIATION WAS CHANNEL D BISTABLE VOLTMETER HAVING ZERO
E/E CONVERTER WAS REPL ACED AND CHANNEL' ZG RETURNED TO COMPONENT FAILURE SERVICE AT 1115.
                                                                                                                                                                                                    -SHIFTED OUT OF TOLERANCE. PROBABLE CAUSE WAS REFUELING OUTAGE WORK REQ IRING CABINET POWER REMOVAL AND RESTORATION. THE BISTABLE (VITRO NO. 16 28-1042) METER WAS RECALIBRATED. NO FURTHER ACTION IS DEEMED HECESSARY.
THE THREE REDUNDANT CHANNELS REMAINED OPERABLE.
CALVERT CLIFFS-1                                                                                                                         05000317     122580                                   AT 0940. DURING HORMAL OPERATION, CONTROL' ROOM OPERATOR DISCOVERED #11 C COOL SYS FOR REAC AUX + CONT                                                                                                           80-072/03L-0   012381                                   OMPONENT COOLING HEAT EXCHANGER OUTLET THROTTLE VALVE (1-SW-5206-CV) WOU VALVE OPERATORS                                                                                                                           033706       30-DAY                                   LD NOT OPEN RENDERING HEAT EXCHANGER INOPERABLE (T.S. 3.7.3.1). #11 COM PNEUMATIC / DIAPHRAGM / CYLINDER                                                                                                                                                               PONENT COOLING HEAT EXCHANGER WAS RETURNED TO SERVICE AT 1820 ON 12-26-8 DESIGN / FABRICATION ERROR                                                                                                                                                                     0.   #12 CCMPONENT COOLING HEAT EXCHANGER REMAINED OPERABLE. LER 79-58 (
LER' OTHER S 79-70 AND 80-13 (U-1) DESCRIBE SIMILAR EVENTS.
CONSTRUCTION / INSTALLATION                                                                                                                                                                   U-1) DESCRIBES A SIMILAR OCCURRENCE.
VITRO ENGINEERING DIVISION THE CAUSE FOR THE DEVIATION WAS CHANNEL D BISTABLE VOLTMETER HAVING ZERO j
-SHIFTED OUT OF TOLERANCE. PROBABLE CAUSE WAS REFUELING OUTAGE WORK REQ IRING CABINET POWER REMOVAL AND RESTORATION. THE BISTABLE (VITRO NO. 16 28-1042) METER WAS RECALIBRATED. NO FURTHER ACTION IS DEEMED HECESSARY.
CALVERT CLIFFS-1 05000317 122580 AT 0940. DURING HORMAL OPERATION, CONTROL' ROOM OPERATOR DISCOVERED #11 C COOL SYS FOR REAC AUX + CONT 80-072/03L-0 012381 OMPONENT COOLING HEAT EXCHANGER OUTLET THROTTLE VALVE (1-SW-5206-CV) WOU VALVE OPERATORS 033706 30-DAY LD NOT OPEN RENDERING HEAT EXCHANGER INOPERABLE (T.S. 3.7.3.1).
#11 COM PNEUMATIC / DIAPHRAGM / CYLINDER PONENT COOLING HEAT EXCHANGER WAS RETURNED TO SERVICE AT 1820 ON 12-26-8 DESIGN / FABRICATION ERROR 0.
#12 CCMPONENT COOLING HEAT EXCHANGER REMAINED OPERABLE. LER 79-58 (
CONSTRUCTION / INSTALLATION U-1) DESCRIBES A SIMILAR OCCURRENCE.
BETTIS CORPORATION 1-CV-5206 WOULD NOT OPERATE BECAUSE THE KEY CONNECTING THE VALVE OPERATO R TO VALVE STEM HAD DROPPED FROM SHAFT DURING REASSEMBLY AFTER OUTAGE RE LATED MAINTENANCE. THE KEY WAS REINSTALLED, STAKED TO THE SHAFT AND THE OPERATOR REINSTALLED. THE VALVE WAS TESTED SATISFACTORILY.
BETTIS CORPORATION 1-CV-5206 WOULD NOT OPERATE BECAUSE THE KEY CONNECTING THE VALVE OPERATO R TO VALVE STEM HAD DROPPED FROM SHAFT DURING REASSEMBLY AFTER OUTAGE RE LATED MAINTENANCE. THE KEY WAS REINSTALLED, STAKED TO THE SHAFT AND THE OPERATOR REINSTALLED. THE VALVE WAS TESTED SATISFACTORILY.


1 PAGE 22 MAR 26, 1981                                                                 LER MOH1HLY REPORT SORTED BY FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                         DOCKET NO./   EVENT DATE/
1 MAR 26, 1981 LER MOH1HLY REPORT SORTED BY FACILITY PAGE 22 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                               REPORT DATE/                                       EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                             CONTROL NO. REPORT TYPE                                       CAUSE DESCRIPTION CALVERT CLIFFS-1                                                 0S000317     011381     AT 1110. STEAM GENERATOR (SG) #11 LEVEL CHANNEL "D" WAS PLACED DUT OF SE REACTOR TRIP SYSTEMS                                           81-006/03L-0 021281       RVICE PER TECHNICAL SPECIFICATION 3.3.1.1 TO CORRECT A PROBLEM WITH ITS VALVES                                                           036230     30-DAY     REFERENCE LEG. #11 SG LEVEL CHANNEL "D" WAS RETURNED TO SERVICE AT 1100 OTHER                                                                                 ON 1-14-81. THE THREE REDUNDANT CHANNELS REMAINED OPERABLE DURING THE E OTHER                                                                                   VENT. THIS IS NOT A REPETITIVE OCCURRENCE.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-1 0S000317 011381 AT 1110. STEAM GENERATOR (SG) #11 LEVEL CHANNEL "D" WAS PLACED DUT OF SE REACTOR TRIP SYSTEMS 81-006/03L-0 021281 RVICE PER TECHNICAL SPECIFICATION 3.3.1.1 TO CORRECT A PROBLEM WITH ITS VALVES 036230 30-DAY REFERENCE LEG. #11 SG LEVEL CHANNEL "D" WAS RETURNED TO SERVICE AT 1100 OTHER ON 1-14-81.
THE THREE REDUNDANT CHANNELS REMAINED OPERABLE DURING THE E OTHER VENT.
THIS IS NOT A REPETITIVE OCCURRENCE.
NOT APPLICABLE FISCHER & PORTER CO.
NOT APPLICABLE FISCHER & PORTER CO.
LEVEL TRANSMITTER EQUALIZING VALVE LEAK-THROUGH IS BEiIEVED TO HAVE CAUS D AN INDICATION DEVIATION AMONG REDUNDANT SAFETY CHANNELS. BOTH 1-LT-11 13D AND PARALLEL-CONNECTED 1-LT-1111 (CONTROL CHANNEL) WERE AFFECTED.         I NDICATION RETURNED TO NORMAL AFTER BLOUCOWN OF THE SHARED REFERENCE LEG AND TRANSMITTER PIPING. NO PREVENTIVE ACTION IS DEEMED HECESSARY.
LEVEL TRANSMITTER EQUALIZING VALVE LEAK-THROUGH IS BEiIEVED TO HAVE CAUS D AN INDICATION DEVIATION AMONG REDUNDANT SAFETY CHANNELS.
CALVERT CLIFFS-1                                                 05000317     011981     AT 0430. DURING THE PERFORMANCE OF SURVEILLANCE TESTING, 214 CONTAINMENT CNTHMNT HEAT REMOV SYS + CONT                                 81-005/03L-0   021781     COOLER UOULD NOT START IN SLOW SPEED (TECH SPEC 3.6.2.2). CORRECTIVE R CIRCUIT CLOSERS / INTERRUPTERS                                   036185     30-DAY     EPAIRS WERE t1ADE AND THE UNIT RETURNED TO SERVICE AT 2055.       THREE CONTAI STARTER                                                                               NMENT COOLERS REMAIFED OPERABLE DURING THE EVENT. THIS HAS NOT BEEN A R P ER SO M'i'         ERROR                                                             EPETITIVE EVENT.
BOTH 1-LT-11 13D AND PARALLEL-CONNECTED 1-LT-1111 (CONTROL CHANNEL) WERE AFFECTED.
MAIN)ENANLE & REPAIR PERSONNEL I-T-E CIRCUIT BREAKER THE SLOW SPEED MOTOR STARTER INTERLOCK CONTACT ASSEMBLY WAS FOUND TO BE INOPERATIVE DUE TO DAMAGE CAUSED BY OVER11GHTENED MOUNTING SCREWS.       THE CASE WAS CRACKED, PREVENTING CONTACTS FR0t' CLOSING.     THE PART WAS REPLAC ED WITH A SPARE. ELECTRICAL MAINTENANCE PERSONNEL WILL BE INSTRUCTED IN THESE CONSEQUENCES AND METHODS TO FREVENT SIMILAR REPORTS.
I NDICATION RETURNED TO NORMAL AFTER BLOUCOWN OF THE SHARED REFERENCE LEG AND TRANSMITTER PIPING. NO PREVENTIVE ACTION IS DEEMED HECESSARY.
CALVERT CLIFFS-1                                                 05000317     012381     DURING POWER OPERATION, A BROKEN HIPPLE WAS DISCOVERED ON VALVE CV-5178, COOL SYS FOR REAC AUX + CONT                                   81-010/03L-0   022081     SALT WATER EMERGENCY RETURN ISOLATION FROM ECCS PUMP ROOM COOLERS. ISOL VALVES                                                           036187     30-DAY     ATIO" 2 REPAIR RESULTED IN TEMPORARY LOSS OF REDUNDANCY IN SALT WATER, S BUTTERFLY                                                                             ERVICE WATER, & COMPONENT COOLING SYSTEMS PER TECH. SPEC.     3.7.3.1, 3.7.4 PERSONNEL ERROR                                                                           1, 8 3.7.5.1. VALVE WAS REPAIRED 8 AFFECTED SYSTEMS RETURNED TO NORMAL CONTRACT. 8 CONSULT. PERSONNEL                                                       ON 01/25. REDUNDANT COOLING SYSTEMS ret 1AINED OPERABLE DURING THIS EVENT.
CALVERT CLIFFS-1 05000317 011981 AT 0430. DURING THE PERFORMANCE OF SURVEILLANCE TESTING, 214 CONTAINMENT CNTHMNT HEAT REMOV SYS + CONT 81-005/03L-0 021781 COOLER UOULD NOT START IN SLOW SPEED (TECH SPEC 3.6.2.2).
MASONEILAN INTERNATI0HAL, INC.                                                             EVENT HAD NO EFFECT ON PUBLIC HEALTH OR SAFETY 8 WAS NONREPETITIVE.
CORRECTIVE R CIRCUIT CLOSERS / INTERRUPTERS 036185 30-DAY EPAIRS WERE t1ADE AND THE UNIT RETURNED TO SERVICE AT 2055.
THREE CONTAI STARTER NMENT COOLERS REMAIFED OPERABLE DURING THE EVENT.
THIS HAS NOT BEEN A R P ER SO M'i' ERROR EPETITIVE EVENT.
MAIN)ENANLE & REPAIR PERSONNEL I-T-E CIRCUIT BREAKER THE SLOW SPEED MOTOR STARTER INTERLOCK CONTACT ASSEMBLY WAS FOUND TO BE INOPERATIVE DUE TO DAMAGE CAUSED BY OVER11GHTENED MOUNTING SCREWS.
THE CASE WAS CRACKED, PREVENTING CONTACTS FR0t' CLOSING.
THE PART WAS REPLAC ED WITH A SPARE.
ELECTRICAL MAINTENANCE PERSONNEL WILL BE INSTRUCTED IN THESE CONSEQUENCES AND METHODS TO FREVENT SIMILAR REPORTS.
CALVERT CLIFFS-1 05000317 012381 DURING POWER OPERATION, A BROKEN HIPPLE WAS DISCOVERED ON VALVE CV-5178, COOL SYS FOR REAC AUX + CONT 81-010/03L-0 022081 SALT WATER EMERGENCY RETURN ISOLATION FROM ECCS PUMP ROOM COOLERS. ISOL VALVES 036187 30-DAY ATIO" 2 REPAIR RESULTED IN TEMPORARY LOSS OF REDUNDANCY IN SALT WATER, S BUTTERFLY ERVICE WATER, & COMPONENT COOLING SYSTEMS PER TECH. SPEC.
3.7.3.1, 3.7.4 PERSONNEL ERROR 1,
8 3.7.5.1.
VALVE WAS REPAIRED 8 AFFECTED SYSTEMS RETURNED TO NORMAL CONTRACT. 8 CONSULT. PERSONNEL ON 01/25. REDUNDANT COOLING SYSTEMS ret 1AINED OPERABLE DURING THIS EVENT.
MASONEILAN INTERNATI0HAL, INC.
EVENT HAD NO EFFECT ON PUBLIC HEALTH OR SAFETY 8 WAS NONREPETITIVE.
NIPPLE WAS BROKEN OFF OF THE VALVE BY A LEAD BRICK WHICH FELL DURING CON STRUCTION OF A-LEAK SHIELD WALL. VALVE WAS ISOLATED AND THE NIPPLE WAS R EPLACED. TO PREVENT RECURRENCE. INSTRUCTIONS HAVE BEEN ISSUED TO PERSONN EL, ADDRESSING PROPER METHOD OF STACKING LEAD BRICK AND ATTENTIVENESS WH ILE PERFORMING THIS WORK NEAR SAFETY-RELATED EQUIPitENT.
NIPPLE WAS BROKEN OFF OF THE VALVE BY A LEAD BRICK WHICH FELL DURING CON STRUCTION OF A-LEAK SHIELD WALL. VALVE WAS ISOLATED AND THE NIPPLE WAS R EPLACED. TO PREVENT RECURRENCE. INSTRUCTIONS HAVE BEEN ISSUED TO PERSONN EL, ADDRESSING PROPER METHOD OF STACKING LEAD BRICK AND ATTENTIVENESS WH ILE PERFORMING THIS WORK NEAR SAFETY-RELATED EQUIPitENT.
CALVERT CLIFFS-1                                                 05000317     020381     DURING NORMAL POWER OPERATION OF U-1 AND REFUELING OPERATIONS ON U-2, DI FIRE PROTECTION SYS + CONT                                     81-008/01T-0   021781     SCOVERED THAT WHEN A NUMBER OF FIRE HOSE STATIONS WERE ISOLATED, BACKUP COMPONENT CODE NOT APPLICABLE                                     036186     2-WEEK     FIRE HOSES WERE NOT ROUTED AS REQUIRED BY T.S. 3.7.11.4.A. BACKUP FIRE SUBCOMPONENT NOT APPLICABLE                                                           HOSES WERE THEN ROUTED TO ALL AFFECTED HOSE STATIONS. BACKUP FIRE HOSE PERSONNEL ERROR                                                                         STATIONS WERE AVAILABLE HEAR MOST AFFECTED LOCATIONS.       ALSO, FIRE WATCHE LICENSED 2 SENIOR OPERATORS                                                           S WERE STATIONED AT VARIOUS LOCATIONS DURING THIS EVENT. THIS IS A NOM-ITEM NOT APPLICABLE                                                                     REPETITIVE EVENT AND HAD NO IMPACT ON PUBLIC HEALTH OR SAFETY.
CALVERT CLIFFS-1 05000317 020381 DURING NORMAL POWER OPERATION OF U-1 AND REFUELING OPERATIONS ON U-2, DI FIRE PROTECTION SYS + CONT 81-008/01T-0 021781 SCOVERED THAT WHEN A NUMBER OF FIRE HOSE STATIONS WERE ISOLATED, BACKUP COMPONENT CODE NOT APPLICABLE 036186 2-WEEK FIRE HOSES WERE NOT ROUTED AS REQUIRED BY T.S.
THE SHIFT SUPERVISOR HAD BEEN MISINFORMED OF THE STATUS OF THE FIRE PROT ECTION SYSTEM. UPON DISCOVERY OF THIS PROBLEM, BACKUP FIRE HOSES WERE R OUTED AS REQUIRED BY T.S. 3.7.11.4.A. THIS EVENT HAS BEEN REVIEWED WITH THE PLANT FIRE PROTFerION INSPECTOR AND THE SHIFT SUPERVISOR INVOLVED.
3.7.11.4.A.
BACKUP FIRE SUBCOMPONENT NOT APPLICABLE HOSES WERE THEN ROUTED TO ALL AFFECTED HOSE STATIONS. BACKUP FIRE HOSE PERSONNEL ERROR STATIONS WERE AVAILABLE HEAR MOST AFFECTED LOCATIONS.
ALSO, FIRE WATCHE LICENSED 2 SENIOR OPERATORS S WERE STATIONED AT VARIOUS LOCATIONS DURING THIS EVENT.
THIS IS A NOM-ITEM NOT APPLICABLE REPETITIVE EVENT AND HAD NO IMPACT ON PUBLIC HEALTH OR SAFETY.
THE SHIFT SUPERVISOR HAD BEEN MISINFORMED OF THE STATUS OF THE FIRE PROT ECTION SYSTEM. UPON DISCOVERY OF THIS PROBLEM, BACKUP FIRE HOSES WERE R OUTED AS REQUIRED BY T.S.
3.7.11.4.A.
THIS EVENT HAS BEEN REVIEWED WITH THE PLANT FIRE PROTFerION INSPECTOR AND THE SHIFT SUPERVISOR INVOLVED.
ALL OPERATIONS PERSUANEL WILL BE INFORMED OF Ti;E DETAILS OF THIS EVENT.
ALL OPERATIONS PERSUANEL WILL BE INFORMED OF Ti;E DETAILS OF THIS EVENT.


MAR 26, 1981                                                                                                           LER MONTHLY REPORT SORTED BY FACILITY                                                                                                     PAGE 23 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /             DOCKET NO./                                                     EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 23 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                       REPORT DATE/                                                                                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                 CONTROL NO.                                                     REPORT TYPE                                                                                                 CAUSE DESCRIPTION CALVERT CLIFFS-2                                               05000318                                                     122680                       AT 1945, WHILE INVESTIGATING ABNORMAL CONTAINMENT AIR PARTICULATE AND GA AIRBORNE RADIDACT MONITOR SYS                       80-059/03L-0                                                           012681                         SEOUS READINGS, FOUND CONTAINTIENT ATMOSPHERE SAMPLE ISOL ATION VALVE SHUT VALVE OPERATORS                                                     033707                                                 30-DAY                           (TECHNICAL SPECIFICATION 3.4.6.1). VALVE WAS REOPENED AND GASEOUS READ PNEUM ATIC/DI APHR AGM/CYLIt' DER                                                                                                                         INGS RETURNED TO NOPMALs HOWEVER, APD REMAINED INOPERABLE (REFERENCE (U-PER3ONNEL ERROR                                                                                                                                           2) LER 80-60).                             GRAL SAMPLES TAKEN BOTH PRIOR TO AND DURING EVENT. CTMT LICENSED & SENIOR OPERATORS                                                                                                                               SUMP LEVEL ALARM OPERABLE. NOT REPETITIVE.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-2 05000318 122680 AT 1945, WHILE INVESTIGATING ABNORMAL CONTAINMENT AIR PARTICULATE AND GA AIRBORNE RADIDACT MONITOR SYS 80-059/03L-0 012681 SEOUS READINGS, FOUND CONTAINTIENT ATMOSPHERE SAMPLE ISOL ATION VALVE SHUT VALVE OPERATORS 033707 30-DAY (TECHNICAL SPECIFICATION 3.4.6.1).
VALVE WAS REOPENED AND GASEOUS READ PNEUM ATIC/DI APHR AGM/CYLIt' DER INGS RETURNED TO NOPMALs HOWEVER, APD REMAINED INOPERABLE (REFERENCE (U-PER3ONNEL ERROR
: 2) LER 80-60).
GRAL SAMPLES TAKEN BOTH PRIOR TO AND DURING EVENT.
CTMT LICENSED & SENIOR OPERATORS SUMP LEVEL ALARM OPERABLE. NOT REPETITIVE.
MASONEILAN INTERNATIONAL, INC.
MASONEILAN INTERNATIONAL, INC.
OPERATOR INADVERTENILY SHUT SAMPLE ISOLATION VALVE AFTER DRAINING CTMT S
OPERATOR INADVERTENILY SHUT SAMPLE ISOLATION VALVE AFTER DRAINING CTMT S UMP AT APPROXIMATELY 2300 ON 12-25-80.
,                                                                                                                                                                UMP AT APPROXIMATELY 2300 ON 12-25-80. ALL LICENSED OPERATORS TO BE MAD E AWARE OF THIS EVENT. ALSO, DURING CUR ~ENT GUTAGE, ONE OF THE TWO CTMT SUMP VALVE HAND SWITCHES WILL BE MADE SPRING RETURN TO CLOSE (REFERENCE FFCR 80-85).
ALL LICENSED OPERATORS TO BE MAD E AWARE OF THIS EVENT.
CALVERT CLIFFS-2                                               05000318                                                     122680                       AT 1945,AFTER RETURNING CONTAINMENT (CTMT) AIR PARTICULATE (APD) AND GAS AIRBORNE RADIDACT MONITOR SYS                       80-060/03L-0                                                           012681                         EOUS MONITORS TO SERVICE (REF. LER 80-59 U-2), APD REMAINED INOPERABLE.
ALSO, DURING CUR ~ENT GUTAGE, ONE OF THE TWO CTMT SUMP VALVE HAND SWITCHES WILL BE MADE SPRING RETURN TO CLOSE (REFERENCE FFCR 80-85).
INSTRUMENTATION + CONTROLS                                         033708                                                 30-DAY                         APD WAS REPAIRED AND RETURNED TO SERVICE AT 1330 ON 12-30-80. GRAB SAMP OTHER                                                                                                                                                     LES TAKEN PRIOR TO AND DURING EVENT.                                         CTMT SUMP LEVEL ALARM AND GASEOUS COMPONENT FAILURE                                                                                                                                         MONITOR MERE OPERABLE DURING THE EVENT. THIS HAS NOT BEEN A REPETITIVE NATURAL END OF LIFE                                                                                                                                       EVENT.
CALVERT CLIFFS-2 05000318 122680 AT 1945,AFTER RETURNING CONTAINMENT (CTMT) AIR PARTICULATE (APD) AND GAS AIRBORNE RADIDACT MONITOR SYS 80-060/03L-0 012681 EOUS MONITORS TO SERVICE (REF. LER 80-59 U-2), APD REMAINED INOPERABLE.
INSTRUMENTATION + CONTROLS 033708 30-DAY APD WAS REPAIRED AND RETURNED TO SERVICE AT 1330 ON 12-30-80.
GRAB SAMP OTHER LES TAKEN PRIOR TO AND DURING EVENT.
CTMT SUMP LEVEL ALARM AND GASEOUS COMPONENT FAILURE MONITOR MERE OPERABLE DURING THE EVENT.
THIS HAS NOT BEEN A REPETITIVE NATURAL END OF LIFE EVENT.
WESTINGHOUSE ELECTRIC CORP.
WESTINGHOUSE ELECTRIC CORP.
A3.R PARTICULATE' DETECTOR JUNCTION BOX CONNECTOR (DEUTSCH DS07-12S-059) F AILED RESULTING IN ABNORMAL HIGH INDICATION. CONNECTOR WEAR FROM HANDLI NG OURiF6 PREVENTIVE AND CORRECTIVE t1AINTENANCE CONTRIBUTED TO END-OF-LI FE FAILURL WITH LOOSENED CONNECTIO;45. NO PREVENTIVE ACTION IS DEEMED NE CESS ARY A7 THIS tit 1E.
A3.R PARTICULATE' DETECTOR JUNCTION BOX CONNECTOR (DEUTSCH DS07-12S-059) F AILED RESULTING IN ABNORMAL HIGH INDICATION. CONNECTOR WEAR FROM HANDLI NG OURiF6 PREVENTIVE AND CORRECTIVE t1AINTENANCE CONTRIBUTED TO END-OF-LI FE FAILURL WITH LOOSENED CONNECTIO;45. NO PREVENTIVE ACTION IS DEEMED NE CESS ARY A7 THIS tit 1E.
CALVERT CLIFFS-2                                               05000318                                                     010781                         AT 0930. CHANNEL B REACTOR PROTECTIVE SYSTEM TRIP UNITS FOR HI POWER, TH REACTOR TRIP SYSTEMS                                 81-001/03L-0                                                           020581                         ERMAL MARGIN / LOW PRESSURE AND AXIAL FLUX OFFSET WERE BYPASSED FOR TROUBL INSTRUMENTATION + CONTROLS                                           036026                                                 30-DAY                         ESH00 TING THE LINEAR POWER RANGE INSTRUMENT. THE DETECTOR CUTPUT WAS FA OTHER                                                                                                                                                     ULTY; THEREFORE, CHANNEL B HI POWER, TM/LP AND AFD TRIP UNITS WERE PLACE COMPONENT FAILURE                                                                                                                                         D IN THE TRIPPED CONDITION AT 1255 ON 1/8/81 PER TECHNICAL SPECIFICATION NATURAL END OF LIFE                                                                                                                                       3.3.1.1                               THE THREE REDUNDANT CHANNELS WERE OPERABLE.             LER'S 79-50 AND OTHER                                                                                                                                                     80-05 (U-2) REPORT EARLIER SYMPTOMS OF THE PROBLEM.
CALVERT CLIFFS-2 05000318 010781 AT 0930. CHANNEL B REACTOR PROTECTIVE SYSTEM TRIP UNITS FOR HI POWER, TH REACTOR TRIP SYSTEMS 81-001/03L-0 020581 ERMAL MARGIN / LOW PRESSURE AND AXIAL FLUX OFFSET WERE BYPASSED FOR TROUBL INSTRUMENTATION + CONTROLS 036026 30-DAY ESH00 TING THE LINEAR POWER RANGE INSTRUMENT. THE DETECTOR CUTPUT WAS FA OTHER ULTY; THEREFORE, CHANNEL B HI POWER, TM/LP AND AFD TRIP UNITS WERE PLACE COMPONENT FAILURE D IN THE TRIPPED CONDITION AT 1255 ON 1/8/81 PER TECHNICAL SPECIFICATION NATURAL END OF LIFE 3.3.1.1 THE THREE REDUNDANT CHANNELS WERE OPERABLE.
THE UPPER SUBCHANNEL DETECTOR'S FIELD CABLE CONNECTOR (KING ELECTRONICS CO.,                 INC. SKH5905) MAS FOUND LOOSENED, MAKING INTERMITTENT CONTACT.                           THE CONNECTOR WILL BE REPLACED DURING THE CURRENT REFUELING OUTAGE. THIS H AS NOT BEEN A REPETITIVE FAILURE; IT IS CONSIDERED TO BE DUE TO WEAR AND HANDLING DURING ITS SERVICE. N3 PREVENTIVE ACTION IS NECESSARY.
LER'S 79-50 AND OTHER 80-05 (U-2) REPORT EARLIER SYMPTOMS OF THE PROBLEM.
l   CALVERT CLIFFS-2                                               05000318                                                     011381                         AT 1115. DURING THE PERFORMANCE OF SURVEILLANCE TESTING, #1? DIESEL GENE EMERG GENERATOR SYS + CONTROLS                       81-006/03L-0                                                           021281                         RATOR SUITCHGEAR UGULD NOT CLOSE IN ON 821 4KV BUS PER THE REQUIREMENTS CIRCUIT CLOSERS / INTERRUPTERS                                       036189                                                 30-DAY                         OF TECHNICAL SPECIFICATION 3.8.1.1. THE DIESEL WAS DECLARED INOPERABLE A SWITCHGEAR                                                                                                                                               ND THE REDUNDANT POWER SOURCES VERIFIED. #12 DIESEL GENERATOR WAS TESTE OTHER                                                                                                                                                     D AND RETURNED TO SERVICE AT 1415. THIS IS NOT A REPETITIVE OCCURRENCE.
THE UPPER SUBCHANNEL DETECTOR'S FIELD CABLE CONNECTOR (KING ELECTRONICS CO.,
INC. SKH5905) MAS FOUND LOOSENED, MAKING INTERMITTENT CONTACT.
THE CONNECTOR WILL BE REPLACED DURING THE CURRENT REFUELING OUTAGE.
THIS H AS NOT BEEN A REPETITIVE FAILURE; IT IS CONSIDERED TO BE DUE TO WEAR AND HANDLING DURING ITS SERVICE. N3 PREVENTIVE ACTION IS NECESSARY.
l CALVERT CLIFFS-2 05000318 011381 AT 1115. DURING THE PERFORMANCE OF SURVEILLANCE TESTING, #1? DIESEL GENE EMERG GENERATOR SYS + CONTROLS 81-006/03L-0 021281 RATOR SUITCHGEAR UGULD NOT CLOSE IN ON 821 4KV BUS PER THE REQUIREMENTS CIRCUIT CLOSERS / INTERRUPTERS 036189 30-DAY OF TECHNICAL SPECIFICATION 3.8.1.1.
THE DIESEL WAS DECLARED INOPERABLE A SWITCHGEAR ND THE REDUNDANT POWER SOURCES VERIFIED. #12 DIESEL GENERATOR WAS TESTE OTHER D AND RETURNED TO SERVICE AT 1415.
THIS IS NOT A REPETITIVE OCCURRENCE.
NOT APPLICABLE GENERAL ELECTRIC CO.
NOT APPLICABLE GENERAL ELECTRIC CO.
CONTINUITY OF THE CLOSING CIRCUIT INTERLOCKS WAS VERIFIED. THE SWITCHGE AR (G.E. CO. TYPE At1H-4.76-250-ID) MAS CYCLED IN TEST AND NORt1AL POSITIO NS.                 CONCLUSION: A HIGH RESISTANCE EXISTED AT A SECONDARY DISCONNECT WHI CH CLEARED UPON REINSERTING THE SWITCHGEAR. DISCONNECT CONTACT INSPECTI ON IS PART OF EXISTING PM PROCEDURE.
CONTINUITY OF THE CLOSING CIRCUIT INTERLOCKS WAS VERIFIED. THE SWITCHGE AR (G.E. CO. TYPE At1H-4.76-250-ID) MAS CYCLED IN TEST AND NORt1AL POSITIO NS.
CONCLUSION: A HIGH RESISTANCE EXISTED AT A SECONDARY DISCONNECT WHI CH CLEARED UPON REINSERTING THE SWITCHGEAR. DISCONNECT CONTACT INSPECTI ON IS PART OF EXISTING PM PROCEDURE.


MAR 26, 1981                                                     LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 24 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMFONENT/           DOCKET NO./         EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 24 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMFONENT/
COMP 0HENT SUBCODE/CAUSE CODE / LER NO./                     REPORT DATE/                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO.         REFORT TYPE                                   CAUSE DESCRIPTION CALVERT CLIFFS-2                               05000318           011381       AT 1025. DURING NORMAL OPERATION. ENGINEERED SAFETY FEATURES (ESFAS) CHA ENCHRD SAFETY FEATR INSTR SYS               81- 0 0 8/ 0 3 L-0   021281       NNEL "ZD" WAS DEENERGIZED FOR MAINTENANCE ON #22 STEAM GENERATOR PRES $UR INSTRUMENTATION + CONTROLS                       036191           30-DAY       E AND BLOCK MODULES (TECH. SPEC. 3.3.2.1). THE THREE REDUNDANT CHANNELS OTHER                                                                         REMAINED OPERABLE DURING THIS EVENT. ESFAS CHANNEL "ZD" WAS RETURNED T.
EVENT DATE/
COMPONENT FAILURE                                                             O SERVICE AT 1110. LER'S 05000317/80-69 AND 05000318/78-16 DESCRIBE SIM
COMP 0HENT SUBCODE/CAUSE CODE / LER NO./
'    INSTRUMENT                                                                   ILAR EVENTS.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REFORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-2 05000318 011381 AT 1025. DURING NORMAL OPERATION. ENGINEERED SAFETY FEATURES (ESFAS) CHA ENCHRD SAFETY FEATR INSTR SYS 81- 0 0 8/ 0 3 L-0 021281 NNEL "ZD" WAS DEENERGIZED FOR MAINTENANCE ON #22 STEAM GENERATOR PRES $UR INSTRUMENTATION + CONTROLS 036191 30-DAY E AND BLOCK MODULES (TECH. SPEC.
3.3.2.1).
THE THREE REDUNDANT CHANNELS OTHER REMAINED OPERABLE DURING THIS EVENT.
ESFAS CHANNEL "ZD" WAS RETURNED T.
COMPONENT FAILURE O SERVICE AT 1110.
LER'S 05000317/80-69 AND 05000318/78-16 DESCRIBE SIM INSTRUMENT ILAR EVENTS.
VITRO ENGINEERING DIVISI0H
VITRO ENGINEERING DIVISI0H
                                                                                ' TECHNICIANS. INVESTIGATING A DEVIATION IN INDICATIGN AMONG PRES $URE CHAN HELS. FOUND #22 "ZD" SG PRESSURE BISTABLE METER WOULD NOT CALIBRATE. DUR ING THE METER REPLACEMENT 2-E/E-1023A (TRANSMATION MODEL 230IT) FAILED G           1 IVING A LOW OUTPUT. IT IS BELIEVED THAT THIS INSTRUMENT CONTRIBUTED TO T HE DEVIATION IN INDICATION. BOTH INSTRUMENTS WERE REPLACED WITH SPARES.
' TECHNICIANS. INVESTIGATING A DEVIATION IN INDICATIGN AMONG PRES $URE CHAN HELS. FOUND #22 "ZD" SG PRESSURE BISTABLE METER WOULD NOT CALIBRATE. DUR ING THE METER REPLACEMENT 2-E/E-1023A (TRANSMATION MODEL 230IT) FAILED G 1
OALVERT CLIFFS-2                               05000318           011881       AT 0847.WITH THE REACTOR COOLANT SYSTEM (RCS) AT 220 DEGREES F AND 230 P OTHR INST SYS REQD FOR SAFETY               81-005/01T-0         012981       SIA. A PRESSURE TRANSMITTER FAILED HIGH CAUSING POWER RELIEF VALVE RC-40           '
IVING A LOW OUTPUT. IT IS BELIEVED THAT THIS INSTRUMENT CONTRIBUTED TO T HE DEVIATION IN INDICATION. BOTH INSTRUMENTS WERE REPLACED WITH SPARES.
INS 1RUNENTATION + CONTROLS                     036027           2-WEEK       4-ERV TO OPEN. AFTER THE OPERATOR VERIFIED THE OPEN VALVE. HE CLOSED TH TRANSMITTER                                                                 E BLOCKING VALVE TERMINATING THE DISCHARGE. RELIEF VALVE WAS OPEN IN LE PERSONNEL ERROR                                                               SS THAN ONE MINUTE AND RCS PRESSURE DECREASED LESS THAN 6 PSI.     THIS REP MAINTENANCE & REPAIR PERSONNEL                                               ORT IS BEING MADE PER IRE INSPECTION REPORT 317-79-23. THIS IS NOT A RE FISCHER 4 PORTER CO.                                                           PETITIVE OCCUR *.ENCE.
OALVERT CLIFFS-2 05000318 011881 AT 0847.WITH THE REACTOR COOLANT SYSTEM (RCS) AT 220 DEGREES F AND 230 P j
THE CAUSE OF nHE EVENT WAS A LOOSE OSCILLATOR / AMPLIFIER ASSEMBLY WITHIN TRANSMITTER 2-PT-103-1 (F3P CO. 50EP1041 BONS). THE ASSEMBLY MOUNTING SO REWS WERE FOUND LOOSE AND INTERMITTENT CONTACT THROUGH ITS CONNECTOR CAU SED SIGNAL CURRENT TO INCREASE DRIVING CONTROLLER 2-PIC-101-1 TO MAXIMUM PRESSURE INDICATION. NO REOCCURRENCE SINCE MOUNTING SCREWS TIGHTENED.
OTHR INST SYS REQD FOR SAFETY 81-005/01T-0 012981 SIA. A PRESSURE TRANSMITTER FAILED HIGH CAUSING POWER RELIEF VALVE RC-40 INS 1RUNENTATION + CONTROLS 036027 2-WEEK 4-ERV TO OPEN.
CALVERT CLIFFS-2                               05000318           01188'       AT 1730. WITH THE bMIT IN MODE 5. FOR A SCHEDULED REFUELING OUTAGE. #21 MAIN STEAM ISOL SYS + CONTROLS             81-007/03L-0         02178%       AND #22 MAIN STEAM ISOLATION VALVES FAILED TO SHUT IN </: 3.6 SECONDS AS VALVE OPERATORS                                 036190           30-DAY         REQUIRED BY TECHNICAL SPECIFICATION 4.7.1.5 DURING A ROUTINE TEST. THE HYCRAULIC                                                                     VALVES ARE ONLY REQUIRED TO OPERATE IN MODES 1. 2. AND 3. NO SIMILAR'E OTHER                                                                         VENTS HAVE BEEN REPORTED.
AFTER THE OPERATOR VERIFIED THE OPEN VALVE. HE CLOSED TH TRANSMITTER E BLOCKING VALVE TERMINATING THE DISCHARGE. RELIEF VALVE WAS OPEN IN LE PERSONNEL ERROR SS THAN ONE MINUTE AND RCS PRESSURE DECREASED LESS THAN 6 PSI.
THIS REP MAINTENANCE & REPAIR PERSONNEL ORT IS BEING MADE PER IRE INSPECTION REPORT 317-79-23.
THIS IS NOT A RE FISCHER 4 PORTER CO.
PETITIVE OCCUR *.ENCE.
THE CAUSE OF nHE EVENT WAS A LOOSE OSCILLATOR / AMPLIFIER ASSEMBLY WITHIN TRANSMITTER 2-PT-103-1 (F3P CO. 50EP1041 BONS).
THE ASSEMBLY MOUNTING SO REWS WERE FOUND LOOSE AND INTERMITTENT CONTACT THROUGH ITS CONNECTOR CAU SED SIGNAL CURRENT TO INCREASE DRIVING CONTROLLER 2-PIC-101-1 TO MAXIMUM PRESSURE INDICATION. NO REOCCURRENCE SINCE MOUNTING SCREWS TIGHTENED.
CALVERT CLIFFS-2 05000318 01188' AT 1730. WITH THE bMIT IN MODE 5. FOR A SCHEDULED REFUELING OUTAGE. #21 MAIN STEAM ISOL SYS + CONTROLS 81-007/03L-0 02178%
AND #22 MAIN STEAM ISOLATION VALVES FAILED TO SHUT IN </: 3.6 SECONDS AS VALVE OPERATORS 036190 30-DAY REQUIRED BY TECHNICAL SPECIFICATION 4.7.1.5 DURING A ROUTINE TEST.
THE HYCRAULIC VALVES ARE ONLY REQUIRED TO OPERATE IN MODES
: 1. 2. AND 3.
NO SIMILAR'E OTHER VENTS HAVE BEEN REPORTED.
NOT APPLICABLE GREER HYDRAULICS, INC.
NOT APPLICABLE GREER HYDRAULICS, INC.
THE SPECIFIC CAUSES OF THIS FAILURE ARE NOT KNOWN AT THIS TIME.     AH UPDA TED REPORT WILL BE ISSUED UPON COMPLETION OF THE INVESTIGATION.
THE SPECIFIC CAUSES OF THIS FAILURE ARE NOT KNOWN AT THIS TIME.
CALVERT CLIFFS-2                               05000318           012381       DURING MODE 6 OPERATION. SHUTDOWN COOLING FLOW WAS STOPPED FOR S MINUTES RESIDUAL HEAT REMOV SYS + CONT             81-003/03L-0         022081       . ACTIONS WERE TAKEN AS' REQUIRED BY TECH. SPEC. 3.9.8.A. AT 0655. VALV VALVES                                         036138           30-DAY       E POSITION INDICATION WAS LOST FOR MOV-652. A SHUTDOWN COOLING RETURN HE GLOBE                                                                       ADER ISOLATION VALVE. QUESTIONING THE ACTUAL VALVE POSITION. THE OPERAT OTHER                                                                       -OR STOPPED FLOW TEMPORARILY. AT 0700 VALVE POSITION INDICATION AND FLOW NOT APPLICABLE                                                                 WERE RESTORED. THERE WAS NO INCREASE IN DECAY HEAT LOAD OR DECREASE IN OTHER                                                                           RCS BORON CONCENTRATION DURING THIS NON-REPETITIVE EVENT.
AH UPDA TED REPORT WILL BE ISSUED UPON COMPLETION OF THE INVESTIGATION.
CAUSE OF THE LOSS OF VALVE POSITION INDICATION FOR MOV-652, WAS A MCC PO WER TRANFER. THE TRANSFER WAS OVER IN 5 MINUTES AND VALVE POSITION INDI
CALVERT CLIFFS-2 05000318 012381 DURING MODE 6 OPERATION. SHUTDOWN COOLING FLOW WAS STOPPED FOR S MINUTES RESIDUAL HEAT REMOV SYS + CONT 81-003/03L-0 022081
                                                                                ~ CATION AND SHUTDOWN COOLING WERE RESTORED. A RECENT PROBLEM WITH PT-103-1 CONTRIBUTED TO THE DECISION TO STOP FLOW. THIS PROBLEM HAS SINCE BEEN CORRECTED. LICENSED PERSONNEL WILL BE INFORMED OF THIS EVENT.
. ACTIONS WERE TAKEN AS' REQUIRED BY TECH. SPEC.
                .                                              .          ~-                       .        .    --            - . _ . . _-    . . _ _ __ ._
3.9.8.A.
AT 0655. VALV VALVES 036138 30-DAY E POSITION INDICATION WAS LOST FOR MOV-652. A SHUTDOWN COOLING RETURN HE GLOBE ADER ISOLATION VALVE.
QUESTIONING THE ACTUAL VALVE POSITION. THE OPERAT OTHER
-OR STOPPED FLOW TEMPORARILY. AT 0700 VALVE POSITION INDICATION AND FLOW NOT APPLICABLE WERE RESTORED.
THERE WAS NO INCREASE IN DECAY HEAT LOAD OR DECREASE IN OTHER RCS BORON CONCENTRATION DURING THIS NON-REPETITIVE EVENT.
CAUSE OF THE LOSS OF VALVE POSITION INDICATION FOR MOV-652, WAS A MCC PO WER TRANFER.
THE TRANSFER WAS OVER IN 5 MINUTES AND VALVE POSITION INDI
~ CATION AND SHUTDOWN COOLING WERE RESTORED. A RECENT PROBLEM WITH PT-103-1 CONTRIBUTED TO THE DECISION TO STOP FLOW. THIS PROBLEM HAS SINCE BEEN CORRECTED. LICENSED PERSONNEL WILL BE INFORMED OF THIS EVENT.
~-


MOR 26, 1981                                                               LER MONTHLY REPORT SORTED BY FACILITY                                                                                                   PAGE 25 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /               DOCKET NO / EVENT DATE/
MOR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 25 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                             REPORT DATE/                                                                                           EVENT DESCRIPTION /
DOCKET NO / EVENT DATE/
CAVSE SUBCODE/ MANUFACTURER                   CONTROL NO.           REPORT TYPE                                                                                           CAUSE DESCRIPTION C00PER-1                                             05000298                       112080                   THE REACTOR WAS IN A COLD SHUTDOWN CONDITION. WHILE PERFORMING ROUTINE MAIN STEAM ISOL SYS + CONTROLS                   80-049/03L-0                     121980                   SURVEILLANCE TEST PROCEDURE 6.3.9.4, MSIV 86A WAS FOUND TO HAVE A CLOSUR VALVES                                               033666                     30-DAY                     E TIME SLOWER THAN ALLDUED BY TECH. SPEC. 3.7.D. SEVEN OF THE EIGHT MSI GLOBE                                                                                                       V'S WERE WITH1N THE TECHNICAL SPECIFICATION LIMITS SO THIS OCCURRENCE PR COMPONENT FAILURE                                                                                           ESENTED HO ADVERSE CONSEQUENCES FROM THE STANDPOINT OF PUBLIC HEALTH AND OTHER                                                                                                         SAFETY.   (REFERENCE LER 80-21)
COMPONENT SUBCODE/CAUSE CODE / LER NO./
ROCKWELL-INTERNATIONAL THE CLOSURE TIME OF MSIV 86A WAS GREATER THAN 5 SECONDS. IMMEDIATE CORR ECTIVE ACTION WAS TO ADJUST CLOSING TIME FOR MSIV 86A. REASON FOR THIS CHANGE HAS NOT BEEN IDENTIFIED. FURTHER EVAL. WILL BE PERFORMED. VALVE IS AN AIR OPERATED ROCKWELL EDWARDS 24" ANGLE GLOBE VALVE, MODEL #1612-JMMY. RALPH A HILLER CO. SUPPLIED THE AIR OPERATOR #SA-A051.
REPORT DATE/
C00PER-1                                             05000298                       121680                   DURING SURVEILLANCE TESTING OF RHR MOTOR OPERATED VALVES, RHR-MO-25B, TH RESIDUAL HEAT REMOV Sfs + CONT                   80-050/03L-0                   011481                     E LOOP "B" INJECTION LINE INBOARD ISOLATION WOULD NOT OPEN.                                         THE "A" LOO WALVES                                               033709                     30-DAY                     P WAS OPERABLE AS WELL AS BOTH DIESEL GENERATORS. THE SUBJECT VALVE IS GATE                                                                                                       NORMALLY CLOSED AND IS REQUIRED TO OPEN FOR LPCI INJECTION. THERE WERE COMPONENT FAILURE                                                                                           NO ADVERSE AFFECTS TO THE PUBLIC HEALTH AND SAFETY. (RTS 3.5.A).
EVENT DESCRIPTION /
CAVSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION C00PER-1 05000298 112080 THE REACTOR WAS IN A COLD SHUTDOWN CONDITION. WHILE PERFORMING ROUTINE MAIN STEAM ISOL SYS + CONTROLS 80-049/03L-0 121980 SURVEILLANCE TEST PROCEDURE 6.3.9.4, MSIV 86A WAS FOUND TO HAVE A CLOSUR VALVES 033666 30-DAY E TIME SLOWER THAN ALLDUED BY TECH. SPEC.
3.7.D.
SEVEN OF THE EIGHT MSI GLOBE V'S WERE WITH1N THE TECHNICAL SPECIFICATION LIMITS SO THIS OCCURRENCE PR COMPONENT FAILURE ESENTED HO ADVERSE CONSEQUENCES FROM THE STANDPOINT OF PUBLIC HEALTH AND OTHER SAFETY.
(REFERENCE LER 80-21)
ROCKWELL-INTERNATIONAL THE CLOSURE TIME OF MSIV 86A WAS GREATER THAN 5 SECONDS.
IMMEDIATE CORR ECTIVE ACTION WAS TO ADJUST CLOSING TIME FOR MSIV 86A.
REASON FOR THIS CHANGE HAS NOT BEEN IDENTIFIED. FURTHER EVAL. WILL BE PERFORMED. VALVE IS AN AIR OPERATED ROCKWELL EDWARDS 24" ANGLE GLOBE VALVE, MODEL #1612-JMMY.
RALPH A HILLER CO. SUPPLIED THE AIR OPERATOR #SA-A051.
C00PER-1 05000298 121680 DURING SURVEILLANCE TESTING OF RHR MOTOR OPERATED VALVES, RHR-MO-25B, TH RESIDUAL HEAT REMOV Sfs + CONT 80-050/03L-0 011481 E LOOP "B" INJECTION LINE INBOARD ISOLATION WOULD NOT OPEN.
THE "A" LOO WALVES 033709 30-DAY P WAS OPERABLE AS WELL AS BOTH DIESEL GENERATORS. THE SUBJECT VALVE IS GATE NORMALLY CLOSED AND IS REQUIRED TO OPEN FOR LPCI INJECTION. THERE WERE COMPONENT FAILURE NO ADVERSE AFFECTS TO THE PUBLIC HEALTH AND SAFETY.
(RTS 3.5.A).
OTHER ANCHOR / DARLING VALVE CO.
OTHER ANCHOR / DARLING VALVE CO.
VALVE IS 24",   900#, ANCHOR / DARLING GATE VLV. CLOSING TORQUE SWITCH SET T 00 CLOSE TO MFG RECOMMENDED SETTING UHICH CAUSED VLV DISK TO STICK IN SE AT. VLV MANUALLY OPENED. CLOSE TORQUE SWITCH ADJUSTED TO LOWER SETTING I DENTICAL TO "A" LOOP ISOL VLV. VLV SATISF TESTED. EVAL BEING PERFORf1ED &
VALVE IS 24",
900#, ANCHOR / DARLING GATE VLV. CLOSING TORQUE SWITCH SET T 00 CLOSE TO MFG RECOMMENDED SETTING UHICH CAUSED VLV DISK TO STICK IN SE AT. VLV MANUALLY OPENED. CLOSE TORQUE SWITCH ADJUSTED TO LOWER SETTING I DENTICAL TO "A" LOOP ISOL VLV. VLV SATISF TESTED. EVAL BEING PERFORf1ED &
UPDTD LER WILL BE SUDMITTED IF DETERMINED HYDRAULIC LOCK COULD EXIST.
UPDTD LER WILL BE SUDMITTED IF DETERMINED HYDRAULIC LOCK COULD EXIST.
COOPER-1                                             05000298                       121680                   DURING ROUTINE SURVEILLANCE TESTING. THE HPCI TURBINE STOP VALVE WOULD N EMERG C5RE COOLING SYS + CONT                     80-051/03L-0                   011381                     OT OPEN. THE HPCI SYSTEM WAS DECLARED INOPERABLE. THE REDUNDANT SYSTEM, VALVE OPERATORS                                     033710                     30-DAY                     ADS. WAS OPERABLE AS WAS RCIC AND ALL THE LOW PRESSURE SYSTEMS,'WITH EXC HYDRAULIC                                                                                                   EPTION OF THE B-LOOP OF LPCI, WHICH WAS INOPERABLE FOR 2 HOURS 48 MINUTE PERSONNEL ERROR                                                                                             S DURING THE HPCI OUTAGE. AN EVENT OF A SIMILAR HATURE HAS OCCURRED (REF MAINTENANCE 8 REPAIR PERSONNEL                                                                             . LER 79-19) BUT CAUSE OF THIS OCCURRENCE IS NOT THE-SAME. THIS EVENT HA MILLER FLUID POWER CO.                                                                                       D NO ADVERSE AFFECT ON THE PUBLIC HEALTH AND SAFETY.
COOPER-1 05000298 121680 DURING ROUTINE SURVEILLANCE TESTING. THE HPCI TURBINE STOP VALVE WOULD N EMERG C5RE COOLING SYS + CONT 80-051/03L-0 011381 OT OPEN. THE HPCI SYSTEM WAS DECLARED INOPERABLE. THE REDUNDANT SYSTEM, VALVE OPERATORS 033710 30-DAY ADS. WAS OPERABLE AS WAS RCIC AND ALL THE LOW PRESSURE SYSTEMS,'WITH EXC HYDRAULIC EPTION OF THE B-LOOP OF LPCI, WHICH WAS INOPERABLE FOR 2 HOURS 48 MINUTE PERSONNEL ERROR S DURING THE HPCI OUTAGE. AN EVENT OF A SIMILAR HATURE HAS OCCURRED (REF MAINTENANCE 8 REPAIR PERSONNEL
. LER 79-19) BUT CAUSE OF THIS OCCURRENCE IS NOT THE-SAME. THIS EVENT HA MILLER FLUID POWER CO.
D NO ADVERSE AFFECT ON THE PUBLIC HEALTH AND SAFETY.
FAILURE OF THE STOP VALVE TO OPEN WAS CAUSED BY EXCESS TEFLON SEAL MATER IAL (MILLER FLUID POWER, "SHEF SEAL", PART NO. 110-ES006-1200) WHICH INT ERFERED WITH OPERATION OF RELAY VALVE ON HYDRAULIC ACTUATOR. GASKET MATE RIAL MAS INSTALLED BY MAINTENANCE PERSONNEL DURING 1980 REFUELING OUTAGE
FAILURE OF THE STOP VALVE TO OPEN WAS CAUSED BY EXCESS TEFLON SEAL MATER IAL (MILLER FLUID POWER, "SHEF SEAL", PART NO. 110-ES006-1200) WHICH INT ERFERED WITH OPERATION OF RELAY VALVE ON HYDRAULIC ACTUATOR. GASKET MATE RIAL MAS INSTALLED BY MAINTENANCE PERSONNEL DURING 1980 REFUELING OUTAGE
                                                                                                                                        . EXCESS SEAL MATERIAL WAS REMOVED. NO FURTHER ACTION IS PLANNED.
. EXCESS SEAL MATERIAL WAS REMOVED. NO FURTHER ACTION IS PLANNED.
COOPER-l                                             05000298                       123080                   DURING HORMAL SURVEILLANCE TESTINC OF THE RHR SERVICE WATER SYSTEM, SW-M RESIDUAL HEAT REMOV SYS + CONT                   80-052/D3L-0 012981                                       0-89A.-THE LOOP "A" SYSTEM THROTTLF. VALVE ON THE DISCHARGE OF THE "A" RH UALVE OPERATORS                                     033750                     30-DAY                       R HEAT EXCHANGER, AFTER OPENING TO THE MINIMUM FLOW POSITION WOULD NOT R ELECTRIC MOTOR - AC                                                                                         ESPOND TO THE REMOTE CONTROLLER. THE REDUNDANT LOOP WAS OPERABLE AS WEL OTHER                                                                                                       L AS BOTH DIESEL GENERATORS. THERE WERE NO ADVERSE EFFECTS TO THE PUBLI NOT APPLICABLE                                                                                             C HEALTH AND SAFETY. (RTS 3.5.B).
COOPER-l 05000298 123080 DURING HORMAL SURVEILLANCE TESTINC OF THE RHR SERVICE WATER SYSTEM, SW-M RESIDUAL HEAT REMOV SYS + CONT 80-052/D3L-0 012981 0-89A.-THE LOOP "A" SYSTEM THROTTLF. VALVE ON THE DISCHARGE OF THE "A" RH UALVE OPERATORS 033750 30-DAY R HEAT EXCHANGER, AFTER OPENING TO THE MINIMUM FLOW POSITION WOULD NOT R ELECTRIC MOTOR - AC ESPOND TO THE REMOTE CONTROLLER. THE REDUNDANT LOOP WAS OPERABLE AS WEL OTHER L AS BOTH DIESEL GENERATORS. THERE WERE NO ADVERSE EFFECTS TO THE PUBLI NOT APPLICABLE C HEALTH AND SAFETY.
(RTS 3.5.B).
LIMITORQUE CORP.
LIMITORQUE CORP.
SM-MO-89A IS A         18",                             3003 GLOBE VALVE WITH A LIMITORQUE SMB-3 MOTOR OPERA TOR. THE CAUSE OF THE PROBLEM IS UNKNOWN.                                       THE FAILURE COULD NOT BE REP EATED. RECORDERS ARE MONITORING OUTPUT OF THE CONTROLLER, FEEDBACK FROM THE VALVE POSITIONER, AND THE OPEN AND CLOSE CONTACTS ON THE OPERATOR M OTOR FOR 5 SUBSEQUENT VALVE OPERATIONS TO VERIFY OPERABILITY.
SM-MO-89A IS A 18",
3003 GLOBE VALVE WITH A LIMITORQUE SMB-3 MOTOR OPERA TOR.
THE CAUSE OF THE PROBLEM IS UNKNOWN.
THE FAILURE COULD NOT BE REP EATED.
RECORDERS ARE MONITORING OUTPUT OF THE CONTROLLER, FEEDBACK FROM THE VALVE POSITIONER, AND THE OPEN AND CLOSE CONTACTS ON THE OPERATOR M OTOR FOR 5 SUBSEQUENT VALVE OPERATIONS TO VERIFY OPERABILITY.


MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY                                                           PAGE 26 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./         EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 26 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/PANUFACTURER         CONTROL NO.         REPORT TYPE                                 CAUSE DESCRIPTION C00PER-1                                 05000298           010281     DURING NORMAL STEADY STATE OPERATION, HYDRAULIC SHOCK SUPPRESSOR RF-54 W SYSTEM CODE NOT APPLICABLE             81-001/03L-0         013081     AS DISCOVERED INOPERABLE PER RTS 3.6.H.3.
EVENT DATE/
HANGERS. SUPPORTS. SHOCK SUPPRSS           036169           30-DAY                                                   OTHER SEISMIC RESTRAINTS WERE.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
SNUBBERS                                                                AVAILABLE. THE REDUNDANT ADS AND RCIC SYSTEMS WERE OPERABLE.                         THERE WE PERSONNEL ERROR                                                        RE NO ADVERSE EFFECTS TO THE PUBLIC HEALTH AND SAFETY. PREVIOUS SIMILAR.
REPORT DATE/
EVENT REPORTED ON LER 80-45.
EVENT DESCRIPTION /
MAINTENANCE 4 REPAIR PERSONNEL
CAUSE SUBCODE/PANUFACTURER CONTROL NO.
!  ITT GRINNELL RF-SE IS A GRINNEL FIG. 200 HYDRAULIC SEISMIC SHOCK SUPPRESSOR. THIS SU PPRESSOR WAS INSTALLED W/ RESERVOIR CONNECTING PIPE AT HIGHER END OF RESE                       !
REPORT TYPE CAUSE DESCRIPTION C00PER-1 05000298 010281 DURING NORMAL STEADY STATE OPERATION, HYDRAULIC SHOCK SUPPRESSOR RF-54 W SYSTEM CODE NOT APPLICABLE 81-001/03L-0 013081 AS DISCOVERED INOPERABLE PER RTS 3.6.H.3.
RVOIR INSTEAD OF LOWER END.     SUPPRESSOR WAS REORIENTED PROPERLY.                     ALL OT HER SUPPRESSORS INSTALLED DURING 1980 REFUELING OUTAGE CHECKED FOR PROPE R INSTALL. OCC HAS BEEN REVIEWED WITH-APPROPRIATE STATION PERSONNEL.
OTHER SEISMIC RESTRAINTS WERE.
CRYSTAL RIVER-3                           05000302           121580 CNTHMNT AIR PURI + CLEANUP SYS         81-005/03L-0         021781     AT 1525 DURING HORTIAL OPERATION IT WAS DISCOVERED THAT THE MECHANICAL SE
HANGERS. SUPPORTS. SHOCK SUPPRSS 036169 30-DAY AVAILABLE. THE REDUNDANT ADS AND RCIC SYSTEMS WERE OPERABLE.
  -PUMPS                                      036097                      AL FOR BUILDING SPRAY PUMP BSP-1A WAS LEAKING GREATER THAN 6 GAL /HR.                         TH 30-DAY     IS CREATED AN EVENT CONTRARY TO TECH. SPEC. 3.6.2.1. MAINTENANCE WAS IN CENTRIFUGAL COMPONENT FAILURE                                                      ITIATED 8 OPERABILITY WAS RESTORED AT 1305 12/17/80. THERE WAS NO EFFEC MECHANICAL T ON THE PUBLIC HEALTH OR SAFETY.     THIS WAS FIRST OCCURRENCE FOR BSP-1A WORTHINGTON PUMP CORP.                                                  & THIS IS FIRST EVENT REPORTED UNDER THIS SPECIFICATION.
THERE WE SNUBBERS RE NO ADVERSE EFFECTS TO THE PUBLIC HEALTH AND SAFETY. PREVIOUS SIMILAR.
                                                                          .THE CAUSE OF THIS EVENT IS ATTRIBUTED TO A DEFECTIVE MECHANICAL SEAL. T HE SEAL WAS REPLACED AND FUNCTIONALLY TESTED SATISFACTORY. THE SEAL NAY HAVE BE5N DAMAGED DURING' IMPELLER MAINTENANCE ACTIVITIES. A REVIEW OF THE SUSPECTED MAINTENANCE PROCEDURE IS BEING CONDUCTED TO PREVENT RECURR ENCE.
PERSONNEL ERROR EVENT REPORTED ON LER 80-45.
CRYSTAL RIVER-3                           05000302           010781     AT 1210 DURING PERFORMANCE OF SP-511, QUARTERLY BATTERY CHECK (UNITS t 1 0FFSITF POWER SYSTEMS + CONTRL         81- 0 01/ 01 T- 0 020681           2), UNIT #2 BATTERY DID NOT MEET REQUIREMENTS OF T.S. SURVEILLANCE 4.8.
MAINTENANCE 4 REPAIR PERSONNEL ITT GRINNELL RF-SE IS A GRINNEL FIG. 200 HYDRAULIC SEISMIC SHOCK SUPPRESSOR. THIS SU PPRESSOR WAS INSTALLED W/ RESERVOIR CONNECTING PIPE AT HIGHER END OF RESE RVOIR INSTEAD OF LOWER END.
BATTERIES + CHARGERS                       036028           2-WEEK     1.1.1.C.2.B). AND WAS CONTRARY TO T.S. 3.8.1.1 SUBCOMPONENT NOT APPLICABLE                                                                                                     REDUNDANCY WAS PROVIDED OTHER                                                                    BY UNIT #1 BATT & BY DIESEL-1A 8 1B. AT 1700. THE D/G-1A FUEL DIL STOR NOT APPLICABLE                                                        AGE TANK HAD LESS THAN 400 GAL; DFP-1A 8 1C WERE NOT OPERATING BUT COULD OPERATE BY MANUAL CONTROL. STH OCCUR FOR UNIT 1 4 2 BATTERIES, 1ST FOR EXIDE INDUSTRIAL DIV DAY TANK LEVEL AND TRANSFER PUMPS. AND 21ST REPORT UNDER THIS SPEC.
SUPPRESSOR WAS REORIENTED PROPERLY.
THE SPECIFIC' GRAVITY OF ONE CELL HAD DECREASED BY 0.013 (MORE THAN 0.01 ALLOWABLE) FROM THE PREVIOUS READING.       FOLLOWING AN OVERNIGHT EQUALIZE C HARGE. OPERABILITY WAS RESTORED AT 0925 ON 1/8/81             ALSO, A MALADJUSTMEN T IN THE FUEL DIL TANK LEVEL SulTCH WAS CORRECTED & OPERABILITY WAS REST CRYSTAL RIVER-3 ORED AT 0730 ON 1/7/81.     T.S. WILL BE REVISED RE UNITS 18 2 BATTERIES.
ALL OT HER SUPPRESSORS INSTALLED DURING 1980 REFUELING OUTAGE CHECKED FOR PROPE R INSTALL.
05000302           010981   AT 2245 DURING NORMAL OPERATION. CONTAINMENT ISOLATION VALVE CAV-1 WOULD CNTHMNT ISOLATION SYS + CONT           81-002/03L-0         020681       NOT CLOSE AFTER SAMPLING THE PRESSURIZER STEAM SPACE.
OCC HAS BEEN REVIEWED WITH-APPROPRIATE STATION PERSONNEL.
VALVE OPERATORS                           036029           30-DAY                                                                                 THIS EVENT WAS C ELECTRIC MOTOR - AC                                                  OMTRARY TO TECHNICAL SPECIFICATION 3.6.3.1. THE AFFECTED PENETRATION WA COMPONENT FAILURE                                                      S ISOLATED BY USE OF MANUAL VALVES AND MAINTENANCE WAS INITIATED. THERE ELECTRICAL                                                              WAS NO EFFECT UPON THE GENERAL PUBLIC HEALTH CR SAFETY.                       THIS IS THE TH LIMITORQUE CORP.                                                        IRD OCCURRENCE FOR CAV-1 AND THE THIRTY-FIRST EVENT REPORTED UNDER THIS SPECIFICATION.
CRYSTAL RIVER-3 05000302 121580 AT 1525 DURING HORTIAL OPERATION IT WAS DISCOVERED THAT THE MECHANICAL SE CNTHMNT AIR PURI + CLEANUP SYS 81-005/03L-0 021781 AL FOR BUILDING SPRAY PUMP BSP-1A WAS LEAKING GREATER THAN 6 GAL /HR.
CAUSE OF EVENT ATTRIBUTED TO FAILED CONTACTS IN THE TORQUE SWITCH OF THE VALVE OPERATOR. SWITCH WAS REPLACED AND A FUNCTIONAL TEST OF THE VALVE WAS PERFORMED. OPERABILITY WAS RESTORED AT 0600 ON 1/10/81. NO FURTHE R CORRECTIVE ACTION DEEMED NECESSARY AT THIS TIME. A REVIEW OF FAILURE OF THE CONTAINMENT ISOLATION VALVES IS CURRENTLY BEING CONDUCTED.
TH
                                                                                                                              . . ~     . _ _ _ _ . _ _ _        _
-PUMPS 036097 30-DAY IS CREATED AN EVENT CONTRARY TO TECH. SPEC.
3.6.2.1.
MAINTENANCE WAS IN CENTRIFUGAL ITIATED 8 OPERABILITY WAS RESTORED AT 1305 12/17/80.
THERE WAS NO EFFEC COMPONENT FAILURE T ON THE PUBLIC HEALTH OR SAFETY.
THIS WAS FIRST OCCURRENCE FOR BSP-1A MECHANICAL
& THIS IS FIRST EVENT REPORTED UNDER THIS SPECIFICATION.
WORTHINGTON PUMP CORP.
.THE CAUSE OF THIS EVENT IS ATTRIBUTED TO A DEFECTIVE MECHANICAL SEAL.
T HE SEAL WAS REPLACED AND FUNCTIONALLY TESTED SATISFACTORY. THE SEAL NAY HAVE BE5N DAMAGED DURING' IMPELLER MAINTENANCE ACTIVITIES. A REVIEW OF THE SUSPECTED MAINTENANCE PROCEDURE IS BEING CONDUCTED TO PREVENT RECURR ENCE.
CRYSTAL RIVER-3 05000302 010781 AT 1210 DURING PERFORMANCE OF SP-511, QUARTERLY BATTERY CHECK (UNITS t 1 0FFSITF POWER SYSTEMS + CONTRL 81- 0 01/ 01 T- 0 020681 2), UNIT #2 BATTERY DID NOT MEET REQUIREMENTS OF T.S. SURVEILLANCE 4.8.
BATTERIES + CHARGERS 036028 2-WEEK 1.1.1.C.2.B). AND WAS CONTRARY TO T.S. 3.8.1.1 REDUNDANCY WAS PROVIDED SUBCOMPONENT NOT APPLICABLE BY UNIT #1 BATT & BY DIESEL-1A 8 1B.
AT 1700. THE D/G-1A FUEL DIL STOR OTHER AGE TANK HAD LESS THAN 400 GAL; DFP-1A 8 1C WERE NOT OPERATING BUT COULD NOT APPLICABLE OPERATE BY MANUAL CONTROL.
STH OCCUR FOR UNIT 1 4 2 BATTERIES, 1ST FOR EXIDE INDUSTRIAL DIV DAY TANK LEVEL AND TRANSFER PUMPS. AND 21ST REPORT UNDER THIS SPEC.
THE SPECIFIC' GRAVITY OF ONE CELL HAD DECREASED BY 0.013 (MORE THAN 0.01 ALLOWABLE) FROM THE PREVIOUS READING.
FOLLOWING AN OVERNIGHT EQUALIZE C HARGE. OPERABILITY WAS RESTORED AT 0925 ON 1/8/81 ALSO, A MALADJUSTMEN T IN THE FUEL DIL TANK LEVEL SulTCH WAS CORRECTED & OPERABILITY WAS REST ORED AT 0730 ON 1/7/81.
T.S. WILL BE REVISED RE UNITS 18 2 BATTERIES.
CRYSTAL RIVER-3 05000302 010981 AT 2245 DURING NORMAL OPERATION. CONTAINMENT ISOLATION VALVE CAV-1 WOULD CNTHMNT ISOLATION SYS + CONT 81-002/03L-0 020681 NOT CLOSE AFTER SAMPLING THE PRESSURIZER STEAM SPACE.
THIS EVENT WAS C VALVE OPERATORS 036029 30-DAY OMTRARY TO TECHNICAL SPECIFICATION 3.6.3.1.
THE AFFECTED PENETRATION WA ELECTRIC MOTOR - AC S ISOLATED BY USE OF MANUAL VALVES AND MAINTENANCE WAS INITIATED. THERE COMPONENT FAILURE WAS NO EFFECT UPON THE GENERAL PUBLIC HEALTH CR SAFETY.
THIS IS THE TH ELECTRICAL IRD OCCURRENCE FOR CAV-1 AND THE THIRTY-FIRST EVENT REPORTED UNDER THIS LIMITORQUE CORP.
SPECIFICATION.
CAUSE OF EVENT ATTRIBUTED TO FAILED CONTACTS IN THE TORQUE SWITCH OF THE VALVE OPERATOR. SWITCH WAS REPLACED AND A FUNCTIONAL TEST OF THE VALVE WAS PERFORMED. OPERABILITY WAS RESTORED AT 0600 ON 1/10/81.
NO FURTHE R CORRECTIVE ACTION DEEMED NECESSARY AT THIS TIME.
A REVIEW OF FAILURE OF THE CONTAINMENT ISOLATION VALVES IS CURRENTLY BEING CONDUCTED.
.. ~


MAR 26, 1981                                                                 LER MONTHLY REPORT SORTED BY FACILITY                                                                 PAGE 27 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /         DOCKET NO./       EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 27 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                   REPORT DATE/                                                                       EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO.       REPORT TYPE                                                                         CAUSE DESCRIPTION CRYSTAL RIVER-3                                         05000302                 011981             AT 0113 AFTER ROUTINE SAMPLING, POSITION INDICATION FOR CONTAINMENT ISOL.
EVENT DATE/
CNTNMNT ISOLATION SYS + CONT                         81-004/03L-0               021681             ATION VALVE CAV-2 WAS FOUND TO BE INOPERABLE CONTRARY TO TECH SPEC 3.6.3 INSTRUMENTATION + CONTROLS                               036096                   30-DAY               1 AT 0648 WHILE RETURNING CAV-126 TO SERVICE, .ITS POSITION INDICATION-INDICATOR                                                                                     WAS FOUND TO BE INOPERABLE CONTRARY TO T.S. 3.6.3.1 IN EACH CASE VALVE COMPONENT FAILURE                                                                                   WAS ISOLATED 8 MAINTENANCE PERFORMED. OPERABILITY RESTORED TO CAV-2 AT 0 OTHER                                                                                           600 3 TO CAV-126 AT 1327. NO EFFECT DN HEALTH OR SAFETY. 6TH OCCURRENCE OTHER                                                                                               FOR CAV-2, 2ND FOR CAV-126, & 32ND REPORTED UNDER THIS TECH SPEC.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
THE CAUSE OF THE FIRST OCCURRENCE IS UNKNOWN AT THIS TIME. AN ENGINEERI NG EVALUATION OF CAV-2 OPERATING PROBLEMS IS IN PROGRESS.                 THE SECOND OC CURRENCE WAS CAUSED BY A DEFECTIVE BREAKER IN THE MAIN POWER SUPPLY TO THE VALVE. THE BREAKER WAS REPLACED 8 CAV-126 WAS FUNCTIONALLY TESTED S ATISFACTORILY.
REPORT DATE/
CRYSTAL RIVER-3                                         05000302                 012381             AT 1710 DURING NORMAL OPERATION IT WAS DISCOVERED THAT THE BREAKER FOR C CONT ROOM HABITBLTY SYS + CONT                       81-006/03L-0               021981             ONTROL COMPLEX EMERGENCY VENTILATION FAN AHF-18A WAS OPEN.                 THIS CREATED CIRCUIT CLOSERS / INTERRUPTERS                           036156                   30-DAY               AN EVENT CONTRARY TO TECHNICAL SPECIFICATION 3.7 7.1. THE BREAKER WAS CIRCUIT BREAKER                                                                                 SHUT AND OPERABILITY CHECKS WERE PERFORMED. OPERABILITY WAS RESTORED AT PERSONNEL ERROR                                                                                       1804       THERE WAS NO EFFECT UPON THE HEALTH OR SAFETY OF THE GENERAL PUB OTHER                                                                                           LIC.       THIS IS THE FIRST OCCURRENCE FOR AHF-18A AND'THIS IS THE FIFTH EVE THOMPSON TANK 8 MFG. CO.                                                                             HT REPORTED UNDER THIS SPECIFICATION.
EVENT DESCRIPTION /
THE CAUSE OF THIS EVENT IS ATTRIBUTED TO INADVERTENT BUMPING OF THE BREA KER.       ALL PERSONNEL HAVE BEEN ADVISED TO EXERCISE EXTREME CAUTION WHILE WORKING AROUND ELECTRICAL BREAKERS.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
CRYSTAL RIVER-3                                         05000302                 012681             AT 1000 AFTER ROUTINE FILTER CHANGE, RADIATION MONITOR RM-A5 WOULD NOT R CONT ROOM HABITBLTY SYS + CONT                       81-007/03L-0               022381             ESTART. THIS CREATED AN EVENT CONTRARY TO TECHNICAL SPECIFICATION 3.7.7.
REPORT TYPE CAUSE DESCRIPTION CRYSTAL RIVER-3 05000302 011981 AT 0113 AFTER ROUTINE SAMPLING, POSITION INDICATION FOR CONTAINMENT ISOL.
CIRCUIT CLOSERS / INTERRUPTERS                           036231                   30-DAY             1. CONTROL COMPLEX VENTILATION WAS PLACED IN EMERGENCY MODE FULL RECIRC OTHER                                                                                           AND MAINTENANCE WAS INITIATED. OPERABILITY WAS RESTORED AT 1400. THER COMPONENT FAILURE                                                                                   E WAS NO EFFECT UPON THE HEALTH OR SAFETY OF THE GENERAL PUBLIC.                 THIS W OTHER                                                                                         AS THE FIRST OCCURRENCE OF THIS TYPE, THE FOURTH OCCURRENCE FOR RM-A5 AN TRAPELO                                                                                             D THE SIXTH EVENT REPORTED UNDER THIS SPECIFICATION.
CNTNMNT ISOLATION SYS + CONT 81-004/03L-0 021681 ATION VALVE CAV-2 WAS FOUND TO BE INOPERABLE CONTRARY TO TECH SPEC 3.6.3 INSTRUMENTATION + CONTROLS 036096 30-DAY 1 AT 0648 WHILE RETURNING CAV-126 TO SERVICE,.ITS POSITION INDICATION-INDICATOR WAS FOUND TO BE INOPERABLE CONTRARY TO T.S. 3.6.3.1 IN EACH CASE VALVE COMPONENT FAILURE WAS ISOLATED 8 MAINTENANCE PERFORMED. OPERABILITY RESTORED TO CAV-2 AT 0 OTHER 600 3 TO CAV-126 AT 1327. NO EFFECT DN HEALTH OR SAFETY. 6TH OCCURRENCE OTHER FOR CAV-2, 2ND FOR CAV-126, & 32ND REPORTED UNDER THIS TECH SPEC.
THE CAUSE OF THIS EVENT IS ATTRIBUTED TO A BLOWN FUSE. NO FAULT WAS DIS COVERED IN THE CIRCUIT. THE FUSE -WAS REPLACED AND OPERABILITY WAS RESTO RED. NO FURTHER CORRECTIVE ACTION DEEMED NECESSARY AT THIS TIME.
THE CAUSE OF THE FIRST OCCURRENCE IS UNKNOWN AT THIS TIME.
CRYSTAL RIVER-3                                         05000302                 012981             AT 1145 DURING PERFORMANCE OF SP-179. CONTAINMENT LEAKAGE TYPES "B"'t "C
AN ENGINEERI NG EVALUATION OF CAV-2 OPERATING PROBLEMS IS IN PROGRESS.
                                                                                                          "      IT WAS DISCOVERED THAT CONTAINMENT ISOLATION VALVES AHV-1C 3 1D WERE CNTHMNT' ISOLATION SYS + CONT                         81-003/01T-0               021281               ,
THE SECOND OC CURRENCE WAS CAUSED BY A DEFECTIVE BREAKER IN THE MAIN POWER SUPPLY TO THE VALVE.
VALVES                                                   036095                   2-WEEK             IMOP. CONTRARY TO T/S 3.6.3.1 VALVES WERE CLOSED & AN INVESTIGATION OF BUTTERFLY                                                                                     EVENT WAS INITIATED, AT 1340 IT WAS DETERMINED THAT LEAK RATE WAS CONTRA DESIGN / FABRICATION ERROR                                                                         RY TO T/S 3.6.1.2 & THAT T/S 3.0.3 APPLIED TO SITUATION. POWER REDUCTICH MANUFACTURING                                                                                   TOWARD HOT STANDBY WAS INIT. OPERABILITY WAS REST 0n!ED AT 1351 2 POWER R PRATT, HENRY CD.                                                                                     EDUCTION WAS HALTED. THERE WAS NO EFFECT UPON PUBLIC HEALTH I SAFETY.
THE BREAKER WAS REPLACED 8 CAV-126 WAS FUNCTIONALLY TESTED S ATISFACTORILY.
CRYSTAL RIVER-3 05000302 012381 AT 1710 DURING NORMAL OPERATION IT WAS DISCOVERED THAT THE BREAKER FOR C CONT ROOM HABITBLTY SYS + CONT 81-006/03L-0 021981 ONTROL COMPLEX EMERGENCY VENTILATION FAN AHF-18A WAS OPEN.
THIS CREATED CIRCUIT CLOSERS / INTERRUPTERS 036156 30-DAY AN EVENT CONTRARY TO TECHNICAL SPECIFICATION 3.7 7.1.
THE BREAKER WAS CIRCUIT BREAKER SHUT AND OPERABILITY CHECKS WERE PERFORMED. OPERABILITY WAS RESTORED AT PERSONNEL ERROR 1804 THERE WAS NO EFFECT UPON THE HEALTH OR SAFETY OF THE GENERAL PUB OTHER LIC.
THIS IS THE FIRST OCCURRENCE FOR AHF-18A AND'THIS IS THE FIFTH EVE THOMPSON TANK 8 MFG. CO.
HT REPORTED UNDER THIS SPECIFICATION.
THE CAUSE OF THIS EVENT IS ATTRIBUTED TO INADVERTENT BUMPING OF THE BREA KER.
ALL PERSONNEL HAVE BEEN ADVISED TO EXERCISE EXTREME CAUTION WHILE WORKING AROUND ELECTRICAL BREAKERS.
CRYSTAL RIVER-3 05000302 012681 AT 1000 AFTER ROUTINE FILTER CHANGE, RADIATION MONITOR RM-A5 WOULD NOT R CONT ROOM HABITBLTY SYS + CONT 81-007/03L-0 022381 ESTART. THIS CREATED AN EVENT CONTRARY TO TECHNICAL SPECIFICATION 3.7.7.
CIRCUIT CLOSERS / INTERRUPTERS 036231 30-DAY 1.
CONTROL COMPLEX VENTILATION WAS PLACED IN EMERGENCY MODE FULL RECIRC OTHER AND MAINTENANCE WAS INITIATED. OPERABILITY WAS RESTORED AT 1400.
THER COMPONENT FAILURE E WAS NO EFFECT UPON THE HEALTH OR SAFETY OF THE GENERAL PUBLIC.
THIS W OTHER AS THE FIRST OCCURRENCE OF THIS TYPE, THE FOURTH OCCURRENCE FOR RM-A5 AN TRAPELO D THE SIXTH EVENT REPORTED UNDER THIS SPECIFICATION.
THE CAUSE OF THIS EVENT IS ATTRIBUTED TO A BLOWN FUSE.
NO FAULT WAS DIS COVERED IN THE CIRCUIT.
THE FUSE -WAS REPLACED AND OPERABILITY WAS RESTO RED.
NO FURTHER CORRECTIVE ACTION DEEMED NECESSARY AT THIS TIME.
CRYSTAL RIVER-3 05000302 012981 AT 1145 DURING PERFORMANCE OF SP-179. CONTAINMENT LEAKAGE TYPES "B"'t "C IT WAS DISCOVERED THAT CONTAINMENT ISOLATION VALVES AHV-1C 3 1D WERE CNTHMNT' ISOLATION SYS + CONT 81-003/01T-0 021281 VALVES 036095 2-WEEK IMOP. CONTRARY TO T/S 3.6.3.1 VALVES WERE CLOSED & AN INVESTIGATION OF BUTTERFLY EVENT WAS INITIATED, AT 1340 IT WAS DETERMINED THAT LEAK RATE WAS CONTRA DESIGN / FABRICATION ERROR RY TO T/S 3.6.1.2 & THAT T/S 3.0.3 APPLIED TO SITUATION. POWER REDUCTICH MANUFACTURING TOWARD HOT STANDBY WAS INIT. OPERABILITY WAS REST 0n!ED AT 1351 2 POWER R PRATT, HENRY CD.
EDUCTION WAS HALTED. THERE WAS NO EFFECT UPON PUBLIC HEALTH I SAFETY.
CAUSE OF EVENT IS ATTRIBUTED TO FAILURE OF VALVE TO SEAL AT LOW AMBIENT TEMP DURING PURGE. CONDITIONS. INVESTIGATION OF EVE 4T HAS INCLUDED SOME L IMITED TESTING TO CONFIRM: EFFECTS OF LOW AMBIENT TEiT ? nFVELOPMENT OF A MECHANISM TO PREVENT RECURR. FURTHER CONTAINMENT PURGE AB0ve MUDE a E" L BE RESTRICTED TO TESTING OF DESIGN CHANGES IMPL FOR PROBLEM RESOLUTICH
CAUSE OF EVENT IS ATTRIBUTED TO FAILURE OF VALVE TO SEAL AT LOW AMBIENT TEMP DURING PURGE. CONDITIONS. INVESTIGATION OF EVE 4T HAS INCLUDED SOME L IMITED TESTING TO CONFIRM: EFFECTS OF LOW AMBIENT TEiT ? nFVELOPMENT OF A MECHANISM TO PREVENT RECURR. FURTHER CONTAINMENT PURGE AB0ve MUDE a E" L BE RESTRICTED TO TESTING OF DESIGN CHANGES IMPL FOR PROBLEM RESOLUTICH


MAR 26, 1981                                                       LER MONTHLY REPORT SORTED BY FACILITY                                               ' PACE 28 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./                 EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY
COMPONENT SUBCODE/CAUSE CODE / LER NO./                       REPORT DATE/                                   EVENT DESCRIPTION /
' PACE 28 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO.                 REPORT TYPE                                   CAUSE DESCRIPTION D. C. C00K-1                                     05000315           011281     UNIT IN MODE 1 AT 100% POWER.       AT 1100 HOURS. ROUTINE SAMPLING OF BIT AN EMERG CORE COOLING SYS + CONT         81-001/03L-0                 021381     D NORTH BAST REVEALED THE BORON CONCENTRATION IN BOTH TANKS WAS 19,300 P COMPONENT CODE NOT APPLICABLE                           036184     30-DAY     PM. THIS IS BELOW THE 20,000 PPM LOWER CONCENTRATION PERMITTED BY TECH SUBCOMPONENT NOT APPLICABLE                                                   SPEC. 3.5.4.1B. ACTION ITEM OF T.S. FULFILLED. BIT AND MIDDLE BAST WE OTHER                                                                         RE ABOVE 20,000 PPM AT 1326 HOURS.         THERE WAS NO EFFECT ON THE HEALTH AN NOT APPLICABLE                                                               D SAFETY OF THE PUBLIC. PREVIOUS OCCURRENCES 80-236,.79-299, 78-570.
DOCKET NO./
ITEM NOT APPLICABLE THE EXACT CAUSE OF THE DILUTION HAS NOT BEEN DETERMINED. TO INCREASE TH E BIT BORON CONCENTRATION, THE BIT WAS LINED UP TO RECIRCULATE WITH THE MIDDLE BAST AND THE BIT AND MIDDLE BAST WERE BOTH DETERMINED TO BE >/: 2 0,000 PPM AT 1326 HOURS.       THE NORTH BAST WAS >/: 20,000 PPM AT 1740 HOUR
EVENT DATE/
: 5. INVESTIGATION IS CONTINUING.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
D. C. C00K-2                                     05000316           120680     WHILE PULLING SHUTDOWN CONTROL RODS IN PREPARATION FOR GOING CRITICAL, R OTHR INST SYS REQD FOR SAFETY         80-035/03X-1                 022081     OD POSITION INDICATION FOR ROD N-9 DID NOT RESPOND PROPERLY. THE REACTO ELECTRICAL CONDUCTORS                                   033495     OTHER     R TRIP BREAKERS WERE OPENED.       THIS EVENT WAS NON-CONSERVATIVE IN RESPECT SUBCOMPONENT NOT APPLICABLE                                                   TO TECHNICAL SPECIFICATION 3.1.3.3.
REPORT DATE/
COMPONENT FAILURE ELECTRICAL OTHER THE PROBLEM WAS TRACED TO A CONNECTOR ON TOP OF THE ROD POSITION DETECTO R ASSEMBLY. A SPARE CABLE WAS SUBSTITUTED FOR THE ORIGINAL AND ROD POSI TION INDICATION FOR ROD N-9 WAS DECLARED OPERABLE. THE DEFECTIVE CONNEC TOR APPEARED TO HAVE BEEN STEPPED ON.         THE AREA ABOVE THE REACTOR HEAD I S A DIFFICULT AREA TO WORK IN.
EVENT DESCRIPTION /
D. C. C00K-2                                       05000316         010381     DURING NORMAL OPERATIONS, THE EAST MOTOR DRIVEN AUXILIARY FEED PUMP WAS FEEDWATER SYSTEMS + CONTROLS         81-002/03L-O                 012881     REMOVED FROM. SERVICE TO REPAIR THE EMERGENCY LEAKOFF LINE CHECK VALVE FW V A L'J ES                                               036050     30-DAY     -153, AND INSTALL A SPOOL PIECE IN PLACE OF THE-SUCTION STRAINER PER AN CHECK     .                                                                EMERGENCY DESIGN CHANGE. THIS CONSTITUTED AN INOPERABLE PUMP PER TECHNI COMPONENT FAILURE                                                             CAL SPECIFICATION 3.7.1.2. THE WEST PUMP REMAINED IN SERVICE AND THE AC MECHANICAL                                                                   TION REQUIREMENTS WERE MET. PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
DRESSER INDUST. VALVE & INST D CHECK VALVE FW-153 HAD SEAT LEAKAGE DURING A TEST OF THE WEST PUMP.               THA T ALLOWED OVERPRESSURIZATION OF THE SUCTION STRAINER OF EAST PUMP WHICH RESULTED IN A CRACK IN THE STRAINER CASING. THE CHECK VALVE DISC, DRESS ER PART NO. 7484A26GN WAS REPLACED AND THE SEAT WAS LAPPED. A SPOOL PIE CE WAS INSTALLED IN PLACE OF THE STRAINER.
REPORT TYPE CAUSE DESCRIPTION D. C.
D. C. C00K-2                                       05000316         010381     DURING NORMAL OPERATION, AN ANNUNCIATOR WAS RECEIVED WHICH INDICATED THE RESIDUAL HEAT REMOV SYS + CONT       81- 0 01/ 0 3 L- 0 012381                   LOSS OF CONTROL VOLTAGE TO THE WEST RHR PUMP. THUS MAKING THE TR AIN OF CIRCUIT CLOSERS / INTERRUPTERS                         036094     30-DAY     RHR INOPERABLE WHICH IS CONTRARY TO TECH SPEC 3.5.2.           THE REDUNDANT TRAI CIRCUIT BREAKER                                                             H OF RHR WAS AVAILABLE AND OPERABLE. THERE WAS NO EFFECT ON THE PUBLIC COMPONENT FAILLRE                                                             HEALTH OR SAFETY. THIS IS THE FIRST OCCURRENCE OF THIS NATURE AND THE T ELECTRICAL                                                                   OTAL TINE OF PUMP INOPERASILITY WAS 1 HOUR AND 46 MINUTES.
C00K-1 05000315 011281 UNIT IN MODE 1 AT 100% POWER.
ITE IMPERIAL CORPORATION THE CAUSE FOR THIS INCIDENT WAS DISCOVERED TO BE A LOOSE FUSE CLIP DN TH E MAIN CONTROL FUSES.       THE FUSE CLIP WAS PROPERLY ADJUSTED & THE BREAKER WAS CYCLED SEVERAL TIMES. PUMP WAS PLACED ON MINI-FLOW FOR OPERABILITY-
AT 1100 HOURS. ROUTINE SAMPLING OF BIT AN EMERG CORE COOLING SYS + CONT 81-001/03L-0 021381 D NORTH BAST REVEALED THE BORON CONCENTRATION IN BOTH TANKS WAS 19,300 P COMPONENT CODE NOT APPLICABLE 036184 30-DAY PM.
                                                                                . A STEP HAS BEEN ADDED TO MAINTENANCE INSPECTION PROCEDURE FOR 4KV CIR CUIT BREAKERS TO CHECK 4 ADJUST THESE FUSE CLIPS DURING EACH INSPECTION.
THIS IS BELOW THE 20,000 PPM LOWER CONCENTRATION PERMITTED BY TECH SUBCOMPONENT NOT APPLICABLE SPEC. 3.5.4.1B.
ACTION ITEM OF T.S.
FULFILLED. BIT AND MIDDLE BAST WE OTHER RE ABOVE 20,000 PPM AT 1326 HOURS.
THERE WAS NO EFFECT ON THE HEALTH AN NOT APPLICABLE D SAFETY OF THE PUBLIC. PREVIOUS OCCURRENCES 80-236,.79-299, 78-570.
ITEM NOT APPLICABLE THE EXACT CAUSE OF THE DILUTION HAS NOT BEEN DETERMINED. TO INCREASE TH E BIT BORON CONCENTRATION, THE BIT WAS LINED UP TO RECIRCULATE WITH THE MIDDLE BAST AND THE BIT AND MIDDLE BAST WERE BOTH DETERMINED TO BE >/: 2 0,000 PPM AT 1326 HOURS.
THE NORTH BAST WAS >/: 20,000 PPM AT 1740 HOUR 5.
INVESTIGATION IS CONTINUING.
D. C. C00K-2 05000316 120680 WHILE PULLING SHUTDOWN CONTROL RODS IN PREPARATION FOR GOING CRITICAL, R OTHR INST SYS REQD FOR SAFETY 80-035/03X-1 022081 OD POSITION INDICATION FOR ROD N-9 DID NOT RESPOND PROPERLY.
THE REACTO ELECTRICAL CONDUCTORS 033495 OTHER R TRIP BREAKERS WERE OPENED.
THIS EVENT WAS NON-CONSERVATIVE IN RESPECT SUBCOMPONENT NOT APPLICABLE TO TECHNICAL SPECIFICATION 3.1.3.3.
COMPONENT FAILURE ELECTRICAL OTHER THE PROBLEM WAS TRACED TO A CONNECTOR ON TOP OF THE ROD POSITION DETECTO R ASSEMBLY. A SPARE CABLE WAS SUBSTITUTED FOR THE ORIGINAL AND ROD POSI TION INDICATION FOR ROD N-9 WAS DECLARED OPERABLE. THE DEFECTIVE CONNEC TOR APPEARED TO HAVE BEEN STEPPED ON.
THE AREA ABOVE THE REACTOR HEAD I S A DIFFICULT AREA TO WORK IN.
D. C. C00K-2 05000316 010381 DURING NORMAL OPERATIONS, THE EAST MOTOR DRIVEN AUXILIARY FEED PUMP WAS FEEDWATER SYSTEMS + CONTROLS 81-002/03L-O 012881 REMOVED FROM. SERVICE TO REPAIR THE EMERGENCY LEAKOFF LINE CHECK VALVE FW V A L'J ES 036050 30-DAY
-153, AND INSTALL A SPOOL PIECE IN PLACE OF THE-SUCTION STRAINER PER AN CHECK EMERGENCY DESIGN CHANGE.
THIS CONSTITUTED AN INOPERABLE PUMP PER TECHNI COMPONENT FAILURE CAL SPECIFICATION 3.7.1.2.
THE WEST PUMP REMAINED IN SERVICE AND THE AC MECHANICAL TION REQUIREMENTS WERE MET.
PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
DRESSER INDUST. VALVE & INST D CHECK VALVE FW-153 HAD SEAT LEAKAGE DURING A TEST OF THE WEST PUMP.
THA T ALLOWED OVERPRESSURIZATION OF THE SUCTION STRAINER OF EAST PUMP WHICH RESULTED IN A CRACK IN THE STRAINER CASING.
THE CHECK VALVE DISC, DRESS ER PART NO. 7484A26GN WAS REPLACED AND THE SEAT WAS LAPPED.
A SPOOL PIE CE WAS INSTALLED IN PLACE OF THE STRAINER.
D. C. C00K-2 05000316 010381 DURING NORMAL OPERATION, AN ANNUNCIATOR WAS RECEIVED WHICH INDICATED THE RESIDUAL HEAT REMOV SYS + CONT 81- 0 01/ 0 3 L- 0 012381 LOSS OF CONTROL VOLTAGE TO THE WEST RHR PUMP. THUS MAKING THE TR AIN OF CIRCUIT CLOSERS / INTERRUPTERS 036094 30-DAY RHR INOPERABLE WHICH IS CONTRARY TO TECH SPEC 3.5.2.
THE REDUNDANT TRAI CIRCUIT BREAKER H OF RHR WAS AVAILABLE AND OPERABLE. THERE WAS NO EFFECT ON THE PUBLIC COMPONENT FAILLRE HEALTH OR SAFETY.
THIS IS THE FIRST OCCURRENCE OF THIS NATURE AND THE T ELECTRICAL OTAL TINE OF PUMP INOPERASILITY WAS 1 HOUR AND 46 MINUTES.
ITE IMPERIAL CORPORATION THE CAUSE FOR THIS INCIDENT WAS DISCOVERED TO BE A LOOSE FUSE CLIP DN TH E MAIN CONTROL FUSES.
THE FUSE CLIP WAS PROPERLY ADJUSTED & THE BREAKER WAS CYCLED SEVERAL TIMES.
PUMP WAS PLACED ON MINI-FLOW FOR OPERABILITY-
. A STEP HAS BEEN ADDED TO MAINTENANCE INSPECTION PROCEDURE FOR 4KV CIR CUIT BREAKERS TO CHECK 4 ADJUST THESE FUSE CLIPS DURING EACH INSPECTION.


LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 29 MAR 26, 1981 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /             DOCKET NO./         EVENT DATE/
LER MONTHLY REPORT SORTED BY FACILITY PAGE 29 MAR 26, 1981 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
REPORT DATE/                                  EVENT DESCRIPTION /
DOCKET NO./
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                         CAUSE DESCRIPTION CAUSE SUBCODE/ MANUFACTURER                 CONTROL NO.         REPORT TYPE 0500D316   0'1281     DURING NORMAL OPERATION, SG BLOWDOWN STARTUP FLASH TANK WAS IN SERV TO R D. C. C00K-2 PRCSS + EFF RADIOL MONITOR SYS                       81-001/04T-0         020281     EDUCE SECONDARY SYSTEM CHEMICAL CONTAMINATION FROM CONDENSER INLEAKAGE.
EVENT DATE/
INSTRUMENTATION + CONTROLS                                     036049     2-WEEK     ON 1/22/81 IT WAS DETERMINED THAT ON 1/12/81 AT ~ 2200 THERE HAD BEEN NO OTHER                                                                              FLOW THROUGH RAD MON. R-19 FROM #21 SG. NONCONSERVATIVE IN RESPECT TO A COMPONENT FAILURE                                                                    PPENDIX "B" T/S 2.4.2.C. UNIT IS EXPERIENCING A SMALL PRIMARY TO SECONDA RY LEAK. BLOUDOWN WAS STOPPED ON 1/13/81, AT 0318 1 0334 BLOWDOWN WAS AG OTHER BROOKS INSTRUMENT COMPANY                                                           AIN EST. THROUGH NORMAL BLOWDOWN TANK WHERE ADD'l EFFL' RAD MON. POSSIBLE THE LOSS OF FLOW TO R-19 FR0rt #21 STEAM GENERATOR WAS APPARENTLY DUE TO .
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION D.
C. C00K-2 0500D316 0'1281 DURING NORMAL OPERATION, SG BLOWDOWN STARTUP FLASH TANK WAS IN SERV TO R PRCSS + EFF RADIOL MONITOR SYS 81-001/04T-0 020281 EDUCE SECONDARY SYSTEM CHEMICAL CONTAMINATION FROM CONDENSER INLEAKAGE.
INSTRUMENTATION + CONTROLS 036049 2-WEEK ON 1/22/81 IT WAS DETERMINED THAT ON 1/12/81 AT ~ 2200 THERE HAD BEEN NO FLOW THROUGH RAD MON. R-19 FROM #21 SG. NONCONSERVATIVE IN RESPECT TO A OTHER PPENDIX "B" T/S 2.4.2.C. UNIT IS EXPERIENCING A SMALL PRIMARY TO SECONDA COMPONENT FAILURE RY LEAK. BLOUDOWN WAS STOPPED ON 1/13/81, AT 0318 1 0334 BLOWDOWN WAS AG OTHER BROOKS INSTRUMENT COMPANY AIN EST. THROUGH NORMAL BLOWDOWN TANK WHERE ADD'l EFFL' RAD MON. POSSIBLE THE LOSS OF FLOW TO R-19 FR0rt #21 STEAM GENERATOR WAS APPARENTLY DUE TO.
A BA0 DIAPHRAGM IN THE ROTO-METER'S FLOW REGULATOR. MANUFACTURED BY BRO OKS INSTRUMENT COMPANY-MODEL NUMBER 1358CC2CICAA.
A BA0 DIAPHRAGM IN THE ROTO-METER'S FLOW REGULATOR. MANUFACTURED BY BRO OKS INSTRUMENT COMPANY-MODEL NUMBER 1358CC2CICAA.
05000346     120580   (NP-33-80-115) DN 12/5/80 AT 1730 HRS. DURING SURVEILLANCE TESTING, SETP DAVIS-BESSE-1                                                                           OINT FOR BORATED WATER STORAGE TANK LOW LEVEL BISTABLE BA312 WAS FOUND 0-ENGN'RD SAFETY FEATR INSTR SYS                      80-090/03X-1        021381 033401     OTHER     UT OF TOLERANCE (00T). ON 12/6/80 AT 0750 HRS DURING TESTING, SETPOINT F INSTRUMENTATION + CONTROLS SWITCH                                                                          OR CONT AINMENT PRESSURE BIST ABLE B A309 MAS ALSO FOUND 00T. BOTH OCCURREN NO DANGER COMPONENT FAILURE                                                                  CES PLACED UNIT IN ACTION STATEMENT 9 0F TECH. SPEC. 3.3.2.1, INSTRUMENT TO HEALTH / SAFETY OF PUBLIC OR STATION PERSONNEL. REMAINING 3 SFAS CHANN ELS WERE OPERABLE. SEE LERS 78-39, 78-70, 78-119, 79-21 8 79-45.
DAVIS-BESSE-1 05000346 120580 (NP-33-80-115) DN 12/5/80 AT 1730 HRS. DURING SURVEILLANCE TESTING, SETP ENGN'RD SAFETY FEATR INSTR SYS 80-090/03X-1 021381 OINT FOR BORATED WATER STORAGE TANK LOW LEVEL BISTABLE BA312 WAS FOUND 0-INSTRUMENTATION + CONTROLS 033401 OTHER UT OF TOLERANCE (00T). ON 12/6/80 AT 0750 HRS DURING TESTING, SETPOINT F OR CONT AINMENT PRESSURE BIST ABLE B A309 MAS ALSO FOUND 00T. BOTH OCCURREN SWITCH CES PLACED UNIT IN ACTION STATEMENT 9 0F TECH. SPEC.
3.3.2.1, NO DANGER COMPONENT FAILURE TO HEALTH / SAFETY OF PUBLIC OR STATION PERSONNEL. REMAINING 3 SFAS CHANN INSTRUMENT ELS WERE OPERABLE. SEE LERS 78-39, 78-70, 78-119, 79-21 8 79-45.
CONSOLIDATED CONTROLS CORP.
CONSOLIDATED CONTROLS CORP.
CAUSE OF THESE OCCURRENCES CAN BE ATTRIBUTED TO A CCMPONENT FAILURE. BIS TABLES ARE SUBJECT TO INSTRU DRIFT. UPON FINDING BA312 3 BA309 OUT OF CA LIBRATION, THEY WERE IMMEDIATELY RECALIB. AS PER' TEST (ST 5031.01) PROCE       '
CAUSE OF THESE OCCURRENCES CAN BE ATTRIBUTED TO A CCMPONENT FAILURE. BIS TABLES ARE SUBJECT TO INSTRU DRIFT. UPON FINDING BA312 3 BA309 OUT OF CA LIBRATION, THEY WERE IMMEDIATELY RECALIB. AS PER' TEST (ST 5031.01) PROCE DURE TO WITHIH TECH SPEC LIMIT. VOLTAGE BETWEEN COMMON 1 GROUND WILL BE CHECKED ON A MONTHLY BASIS TO ENSURE AC VOLTAGE DOES NOT GO UNDETECTED.
DURE TO WITHIH TECH SPEC LIMIT. VOLTAGE BETWEEN COMMON 1 GROUND WILL BE CHECKED ON A MONTHLY BASIS TO ENSURE AC VOLTAGE DOES NOT GO UNDETECTED.
i DAVIS-BESSE-1 05000346 010681 (NP-33-81-02) OH-1/6/81 AT 1600 HRS. A CONTROL ROOM OPERATOR INTENDING T AC ONSITE POWER SYS + CONTROLS 81-003/03L-0 020381 0 MATCH A SWITCH FLAG POSITION WITH BREAKER INDICATION LIGHT, INADVERTEN CIRCUIT CLOSERS / INTERRUPTERS 036030 30-DAY TLY TRIPPED BREAKER HX02B WHICH DE-ENERGIZED VITAL BUS B, 1 0F 2 13.8 KV SWITCH (OTHER THAN SENSOR)
i DAVIS-BESSE-1                                                   05000346   010681     (NP-33-81-02) OH-1/6/81 AT 1600 HRS. A CONTROL ROOM OPERATOR INTENDING T 81-003/03L-0         020381     0 MATCH A SWITCH FLAG POSITION WITH BREAKER INDICATION LIGHT, INADVERTEN AC ONSITE POWER SYS + CONTROLS                                                      TLY TRIPPED BREAKER HX02B WHICH DE-ENERGIZED VITAL BUS B, 1 0F 2 13.8 KV CIRCUIT CLOSERS / INTERRUPTERS                                036030    30-DAY SWITCH (OTHER THAN SENSOR)                                                         BUSSES. THIS REDUCED ELEC DISTRIBUTION TO LESS THAN THAT REQ BY T.S. 3-
BUSSES. THIS REDUCED ELEC DISTRIBUTION TO LESS THAN THAT REQ BY T.S.
                                                                                                .8.1.1, 3.8.2.1 2 3.8.2.3,       THERE WAS HD DANGER TO THE HEALTH & SAFETY 0 PERSONNEL ERROR                                                                     F THE PUBLIC OR TO STATION PERSONNEE. THE BREAKERS WERE ALL RESTORED WI LICENSED 8 SENIOR OPERATORS                                                     THIN 15 MINUTES. THIS IS THE FIRST REPORT OF THIS TYPE PERSONNEL ERROR.
3-
ITEM NOT APPLICABLE                                                                 CAUSE WAS PERSONNEL ERROR BY OPERATOR. IN ATTEM* TING TO MATCH SWITCH FL AG COLOR WITH BREAKER. INDICATION, HE ACCIDENTALLY TURNED SUITCH THE WRON G DIRECTION EVEN THOUGH HE WAS AWARE OF ITS FUNCTION. RESTORATION OF BR EAKERS WAS ATTAINED WITHIN 15 MIN. OPERATIONS PERSONNEL BEING MADE'AWAR E OF OCCURRENCE TO EMPHASIZE NEED FOR ATTENTIVENESS DURING OPERATIONS.
.8.1.1, 3.8.2.1 2 3.8.2.3, THERE WAS HD DANGER TO THE HEALTH & SAFETY 0 PERSONNEL ERROR F THE PUBLIC OR TO STATION PERSONNEE.
05000346     010781     (NP-33-81-03) OH 1/7/81 AT 1632 HOURS, A CONTROL ROOM OPERATOR ATTEMPTED DAVIS-BESSE-1                                                                            TO START DECAY HEAT (DH) PUMP 1-1 AS A NORMAL STEP IN ESTABLISHING DH R EMERG CORE COOLING SYS + CONT                      81-004/03L-O          020681 CIRCUIT CLOSERS / INTERRUPTERS                               036031     30-DAY   EMOVAL FLOW FOLLOWING ENTRY INTO MODE 4. A SECOND ATTEMPT WAS SUCCESSFUL AFTER BREAKER WAS RACKED OUT AND THEN RACKED BACK IN. BEING IN MODE 4, CIRCUIT BREAKER-                                                                 STATION DID NOT ENTER ACTION STATEMENT OF TECH. SPEC. 3.5.3. THIS EVENT COMPONENT FAILURE                                                                     IS BEING REPORTED TO DOCUMENT A COMPONENT FAILURE. THERE WAS NO DANGER ELECTRICAL                                                                     TO HEALTH & SAFETY OF PUBLIC OR STATION PERSONNEL. (1 PREV. LER 78-011.)
THE BREAKERS WERE ALL RESTORED WI LICENSED 8 SENIOR OPERATORS THIN 15 MINUTES.
THIS IS THE FIRST REPORT OF THIS TYPE PERSONNEL ERROR.
ITEM NOT APPLICABLE CAUSE WAS PERSONNEL ERROR BY OPERATOR. IN ATTEM* TING TO MATCH SWITCH FL AG COLOR WITH BREAKER. INDICATION, HE ACCIDENTALLY TURNED SUITCH THE WRON G DIRECTION EVEN THOUGH HE WAS AWARE OF ITS FUNCTION. RESTORATION OF BR EAKERS WAS ATTAINED WITHIN 15 MIN.
OPERATIONS PERSONNEL BEING MADE'AWAR E OF OCCURRENCE TO EMPHASIZE NEED FOR ATTENTIVENESS DURING OPERATIONS.
DAVIS-BESSE-1 05000346 010781 (NP-33-81-03) OH 1/7/81 AT 1632 HOURS, A CONTROL ROOM OPERATOR ATTEMPTED EMERG CORE COOLING SYS + CONT 81-004/03L-O 020681 TO START DECAY HEAT (DH) PUMP 1-1 AS A NORMAL STEP IN ESTABLISHING DH R CIRCUIT CLOSERS / INTERRUPTERS 036031 30-DAY EMOVAL FLOW FOLLOWING ENTRY INTO MODE 4.
A SECOND ATTEMPT WAS SUCCESSFUL AFTER BREAKER WAS RACKED OUT AND THEN RACKED BACK IN. BEING IN MODE 4, CIRCUIT BREAKER-STATION DID NOT ENTER ACTION STATEMENT OF TECH. SPEC.
3.5.3.
THIS EVENT COMPONENT FAILURE IS BEING REPORTED TO DOCUMENT A COMPONENT FAILURE. THERE WAS NO DANGER ELECTRICAL TO HEALTH & SAFETY OF PUBLIC OR STATION PERSONNEL. (1 PREV. LER 78-011.)
WESTINGHOUSE ELECTRIC CORP.
WESTINGHOUSE ELECTRIC CORP.
CAUSE OF PUMP FAILING TO START CAN BE ATTRIBUTED TO A BREAKER PROBLEM. E LECTRICIANS RACKED OUT EREAKER. FINDING NO OBVIOUS PROBLEM, BREAKER WAS RACKED IN. A SECOND ATTEMPT TO START PUMP WAS THEN SUCCESSFUL. PUMP WAS DECLARED OPERABLE AT 1647 HRS THE SAME DAY & PLACED IN SERVICE. FURTHER INVESTIGATION UNDER MWO 31-1301 ON 1/13/81 DID HOT LOCATE SOURCE OF PROB
CAUSE OF PUMP FAILING TO START CAN BE ATTRIBUTED TO A BREAKER PROBLEM. E LECTRICIANS RACKED OUT EREAKER. FINDING NO OBVIOUS PROBLEM, BREAKER WAS RACKED IN. A SECOND ATTEMPT TO START PUMP WAS THEN SUCCESSFUL. PUMP WAS DECLARED OPERABLE AT 1647 HRS THE SAME DAY & PLACED IN SERVICE. FURTHER INVESTIGATION UNDER MWO 31-1301 ON 1/13/81 DID HOT LOCATE SOURCE OF PROB
    - ~ . - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . - _ _  _ _ _ .                  _          -              -                                  --                    .
- ~. - -


MAR 26, 1911                                             LER MONTHLY REPORT SORTED BY FACILTTY                                         PAGE 30 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./         EVENT DATE/
MAR 26, 1911 LER MONTHLY REPORT SORTED BY FACILTTY PAGE 30 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCOCE/CAUSE CODE? LER NO./             REPORT DATE/                                 EVENT DESCRIPTID%/
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.         REPORT TYPE                                 CAUSE DESCRIPTIC'1 i
EVENT DATE/
DAVIS-BESSE-1                           05000346         011481 REACTOR VESSEL INTERNALS                                            (NP-33-81-04) ON 1/14/81. REACTOR COOLANT SYS (RCS) CHLORIDE CONCENTRATI 81-005/03L-0         021381     DN WAS FOUND IN EXCESS OF STEADY STATE LIMIT OF 0.15 PPM. LEVEL WAS 0.6 COMPONENT CODE NOT APPLICABLE           036098         30-DAY     4 PPM. ON 1/ 18/8 1 LEVEL REACHED 1.28 PPM.     LIMIT WAS EXCEEDED FOR TWO D SUBCOMPONENT NOT APPLICABLE                                       AYS EACH TIME. ITS CAUSE WAS DETERM TO BE FROM USE OF SPOTCHECK IN CLEA DEFECTIVE PROCEDURES                                               HING REACTOR COOLANT PUMP (RCP) SEAL CAVITIES. TO FURTHER CLEAN SYS REQ NOT APPLICABLE                     <
COMPONENT SUBCOCE/CAUSE CODE? LER NO./
UIRED SOME HEATING TO DECOMPOSE SOLVENT SO THAT CHLORIDES COULD 6E REMOV ITEM NOT APPLICABLE                                                 ED BY DEMINERALIZATION. LIMITS EXCEEDED AGAIN ON 1/26/81 AND 1/27/81.
REPORT DATE/
CAUSE WAS A LACK OF ADEQUATE WARNING TO ANDICATE DETRIMENTAL EFFECTS TO SYS IF USED IMPROPERLY. "SPOTCHECK" IS LABELED AS NUCLEAR GRADE & CHLOR IDE FREE. IT IS IN FACT A CHLORINATED HYDROCARBON WHICH WHEN HEATED DEC OMPOSES TO CHLORIDES. ADMIN MEMO NO. 4 WAS ISSUED TO PROV SPECIFIC INSTR DAVIS-BESSE-1                                                        UC FOR USE OF ANY SOLVENT THAT COULD COME IN CONTACT WITH REACT COOL SYS 05000346         011981     (NP-33-81-05) ON 1/19/81. AT 1550 HRS DURIGG PERFORMANCE OF SAFETY FEATU ENGNRD SAFETY FEATR INSTR SYS       81-006/03L-0         021381     RES ACTUATION SYS (SFAS) GROUNDING TEST, TP 520.02, POWER WAS LOST TO SF COMPONENT CODE NOT APPLICABLE           036099         30-DAY     AS CHANNEL 1 CABINET. THIS MADE SFAS CHANNEL 1 CONTAINMENT RADIATION ING SUBCOMPONENT NOT APPLICABLE                                       PERABLE. UN :T ENTERED ACTION STATEMENT 9 0F TECH. SPEC. 3.3.2.1 WHICH WA DEFECTIVE PROCEDURES                                               S SATISFIED SINCE CONTAINMENT BISTABLE TRIPPED UPON LOSS OF POWER. THERE NOT APPLICABLE                                                     WAS NO DANGER TO HEALTH 3 SAFETY OF FUBLIC GR STATION PERSONNEL. REMAIN ITEM NOT APPLICABLE                                                 ING THREE CHANNELS WERE OPERABLE DURING THIS TIME.
EVENT DESCRIPTID%/
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTIC'1 i
DAVIS-BESSE-1 05000346 011481 (NP-33-81-04) ON 1/14/81. REACTOR COOLANT SYS (RCS) CHLORIDE CONCENTRATI REACTOR VESSEL INTERNALS 81-005/03L-0 021381 DN WAS FOUND IN EXCESS OF STEADY STATE LIMIT OF 0.15 PPM.
LEVEL WAS 0.6 COMPONENT CODE NOT APPLICABLE 036098 30-DAY 4 PPM.
ON 1/ 18/8 1 LEVEL REACHED 1.28 PPM.
LIMIT WAS EXCEEDED FOR TWO D SUBCOMPONENT NOT APPLICABLE AYS EACH TIME.
ITS CAUSE WAS DETERM TO BE FROM USE OF SPOTCHECK IN CLEA DEFECTIVE PROCEDURES HING REACTOR COOLANT PUMP (RCP) SEAL CAVITIES.
TO FURTHER CLEAN SYS REQ NOT APPLICABLE UIRED SOME HEATING TO DECOMPOSE SOLVENT SO THAT CHLORIDES COULD 6E REMOV ITEM NOT APPLICABLE ED BY DEMINERALIZATION. LIMITS EXCEEDED AGAIN ON 1/26/81 AND 1/27/81.
CAUSE WAS A LACK OF ADEQUATE WARNING TO ANDICATE DETRIMENTAL EFFECTS TO SYS IF USED IMPROPERLY.
"SPOTCHECK" IS LABELED AS NUCLEAR GRADE & CHLOR IDE FREE.
IT IS IN FACT A CHLORINATED HYDROCARBON WHICH WHEN HEATED DEC OMPOSES TO CHLORIDES. ADMIN MEMO NO. 4 WAS ISSUED TO PROV SPECIFIC INSTR UC FOR USE OF ANY SOLVENT THAT COULD COME IN CONTACT WITH REACT COOL SYS DAVIS-BESSE-1 05000346 011981 (NP-33-81-05) ON 1/19/81. AT 1550 HRS DURIGG PERFORMANCE OF SAFETY FEATU ENGNRD SAFETY FEATR INSTR SYS 81-006/03L-0 021381 RES ACTUATION SYS (SFAS) GROUNDING TEST, TP 520.02, POWER WAS LOST TO SF COMPONENT CODE NOT APPLICABLE 036099 30-DAY AS CHANNEL 1 CABINET. THIS MADE SFAS CHANNEL 1 CONTAINMENT RADIATION ING SUBCOMPONENT NOT APPLICABLE PERABLE. UN :T ENTERED ACTION STATEMENT 9 0F TECH. SPEC. 3.3.2.1 WHICH WA DEFECTIVE PROCEDURES S SATISFIED SINCE CONTAINMENT BISTABLE TRIPPED UPON LOSS OF POWER. THERE NOT APPLICABLE WAS NO DANGER TO HEALTH 3 SAFETY OF FUBLIC GR STATION PERSONNEL. REMAIN ITEM NOT APPLICABLE ING THREE CHANNELS WERE OPERABLE DURING THIS TIME.
CAUSE WAS LACK OF PROPER WARNING IN PROCEDURE TP 520.02 8 VENDOR'S TEST OUTLINE. INSTRU 8 CONTROLS PERSONNEL WERE INSTALLING A JUMPER BETWEEN TE RMINAL 12 0F TB121 8 INSTRU GROUND. IN ATTEMPT, AN ARC OCCURRED, 8 SUPPL Y FUSE FROM PANEL Y-1 BLE
CAUSE WAS LACK OF PROPER WARNING IN PROCEDURE TP 520.02 8 VENDOR'S TEST OUTLINE. INSTRU 8 CONTROLS PERSONNEL WERE INSTALLING A JUMPER BETWEEN TE RMINAL 12 0F TB121 8 INSTRU GROUND. IN ATTEMPT, AN ARC OCCURRED, 8 SUPPL Y FUSE FROM PANEL Y-1 BLE


==W. PROCEDURE==
==W. PROCEDURE==
DID NOT CONT AIN A WARNING THAT TER DAVIS-BESSE-1                                                        MINAL 12 WAS 118 VAC SUPPLY TO SFAS CAB. MOD T-5361 WRITTEN TO PROCEDURE 05000346         012281     (NP-33-81-06) ON 1/22/81, AT 0850 HRS. STATION PERSONNEL REPORTED THAT D OTHER ENGNRD SAFETY FEATR SYS       81-007/03L-O         022081     00R 306 (FUEL HANDLING AREA, ELEVATION 585) WAS PARTIALLY OPEN. WITH DO OTHER COMPONENTS                       036159           30-DAY     OR OPEN, SPENT FUEL POOL EMERG VENTILATION SYS WOULD NOT HAVE BEEN ABLE SUBCOMPONENT NOT APPLICA6LE                                       TO MAINTAIN SPENT FUEL POOL AREA AT A NEG PRESS OF >/= 1/8" WATER' GAUGE.
DID NOT CONT AIN A WARNING THAT TER MINAL 12 WAS 118 VAC SUPPLY TO SFAS CAB. MOD T-5361 WRITTEN TO PROCEDURE DAVIS-BESSE-1 05000346 012281 (NP-33-81-06) ON 1/22/81, AT 0850 HRS. STATION PERSONNEL REPORTED THAT D OTHER ENGNRD SAFETY FEATR SYS 81-007/03L-O 022081 00R 306 (FUEL HANDLING AREA, ELEVATION 585) WAS PARTIALLY OPEN.
COMPONENT FAILURE                                                   ACTION STATEMENT OF T/S 3.9.1.2 PROHIBITS FUEL HANDLING OPER & MOVEMENT MECHANICAL                                                         S OF LOADS OVER POOL WITHOUT AN OPER SYS.     THESE RESTRICTIONS WERE N3T V OTHER                                                               IOLATED. NO. DANGER TO HEALTH / SAFETY OF PUBLIC OR STATION PERSONNEL.
WITH DO OTHER COMPONENTS 036159 30-DAY OR OPEN, SPENT FUEL POOL EMERG VENTILATION SYS WOULD NOT HAVE BEEN ABLE SUBCOMPONENT NOT APPLICA6LE TO MAINTAIN SPENT FUEL POOL AREA AT A NEG PRESS OF >/= 1/8" WATER' GAUGE.
THE DOOR WAS IMMEDIATELY CLOSED AND LATCHED. THE CAUSE OF 1HE FINDING W AS A DOOR CLOSURE WHICH NEEDED ADJUSTMENT. IT WAS NOT CLOSING HARD ENOU GH TO LATCH THE DOOR. MAINTENANCE WORK ORDER 81-1187-009 WAS ISSUED THE SAME DAY TO CHECK AND ADJUST THE CLOSURE.
COMPONENT FAILURE ACTION STATEMENT OF T/S 3.9.1.2 PROHIBITS FUEL HANDLING OPER & MOVEMENT MECHANICAL S OF LOADS OVER POOL WITHOUT AN OPER SYS.
DAVIS-BESSE-1                           05000346         012781     (HP-33-81-08) 1/27/81, a 2222 HRS, 345 KV SWITCHYARD BUS K TRIPPED 8 LOC OFFSITE POWER SYSTEMS + CONTRL     81- 0 0 8/ 3 3 L-0   022681     KED OUT, DE-ENERGIZING STARTUP TRANSFORMER 02. PLANT WAS IN MODE 5.       IT TRANSFORMERS                             036157         30-DAY     WAS RETURNED TO SERVICE 1/28/81. ON 2/1/81, 3 0620 HRS, A SIMILAR INSTAN SUBCOMPONENT NOT APFLICABLE                                       CE OCC IN WHICH J BUS TRIPPED 8 LOCKED OUT DE-ENERGIZING STARTUP TRANSFO EXTERNAL CAUSE                                                     RMER 01   STATION WAS IN MODE 3. STATION ENTERED ACTION STATEMENT OF T/
THESE RESTRICTIONS WERE N3T V OTHER IOLATED.
                                                                                                                                                    ~
NO. DANGER TO HEALTH / SAFETY OF PUBLIC OR STATION PERSONNEL.
NOT APPLICABLE                                                     S 3.8.1.1 AT 2ND OCC. NO DANGER TO PUBLIC OR STATION _PERS. IN BOTH CAS OTHER                                                               ES, AN AUTOMATIC TRANSFER OF LOADS TO OPERABLE STARTUP TRANSFORMER OCC.
THE DOOR WAS IMMEDIATELY CLOSED AND LATCHED.
                                                                      "K" BUS TRIP OCCURRED DUE TO ACTION FROM DIRECTIONAL GROUND CURRENT RELA Y8 THAT C PHASE LIGHTNING ARRESTER ON STARTUP TRANS. (SU XFMR) 02 APPEA RED CHARRED. B PHASE LIGHTNING ARRESTER ON SU XFMR Of HAD FAULTED.       UNDE R MMO 81-1400 SU XFMR 02 WAS RETURNED TO SERVICE AT 2331 HRS ON 1/28/81.
THE CAUSE OF 1HE FINDING W AS A DOOR CLOSURE WHICH NEEDED ADJUSTMENT. IT WAS NOT CLOSING HARD ENOU GH TO LATCH THE DOOR.
MAINTENANCE WORK ORDER 81-1187-009 WAS ISSUED THE SAME DAY TO CHECK AND ADJUST THE CLOSURE.
DAVIS-BESSE-1 05000346 012781 (HP-33-81-08) 1/27/81, a 2222 HRS, 345 KV SWITCHYARD BUS K TRIPPED 8 LOC OFFSITE POWER SYSTEMS + CONTRL 81- 0 0 8/ 3 3 L-0 022681 KED OUT, DE-ENERGIZING STARTUP TRANSFORMER 02. PLANT WAS IN MODE 5.
IT TRANSFORMERS 036157 30-DAY WAS RETURNED TO SERVICE 1/28/81. ON 2/1/81, 3 0620 HRS, A SIMILAR INSTAN SUBCOMPONENT NOT APFLICABLE CE OCC IN WHICH J BUS TRIPPED 8 LOCKED OUT DE-ENERGIZING STARTUP TRANSFO EXTERNAL CAUSE RMER 01 STATION WAS IN MODE 3.
STATION ENTERED ACTION STATEMENT OF T/
~,
NOT APPLICABLE S 3.8.1.1 AT 2ND OCC.
NO DANGER TO PUBLIC OR STATION _PERS.
IN BOTH CAS OTHER ES, AN AUTOMATIC TRANSFER OF LOADS TO OPERABLE STARTUP TRANSFORMER OCC.
"K" BUS TRIP OCCURRED DUE TO ACTION FROM DIRECTIONAL GROUND CURRENT RELA Y8 THAT C PHASE LIGHTNING ARRESTER ON STARTUP TRANS. (SU XFMR) 02 APPEA RED CHARRED. B PHASE LIGHTNING ARRESTER ON SU XFMR Of HAD FAULTED.
UNDE R MMO 81-1400 SU XFMR 02 WAS RETURNED TO SERVICE AT 2331 HRS ON 1/28/81.
UNDER MWO 81-1426, SU XFMR 01 WAS RETURNED TO NORMAL a 1920 HRS 2/1/81
UNDER MWO 81-1426, SU XFMR 01 WAS RETURNED TO NORMAL a 1920 HRS 2/1/81


MAR 26, 1981                                                           LER MONTHLY REPORT SORTED BY FACILITY                                                             PAGE 31 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./     EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 31 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                                           EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.     REPORT TYPE                                             CAUSE DESCRIPTION DAVIS-BESSE-1                                           0S00'346       012881     (NP-33-81-07) ON 1/28/81 AT 0330 HRS. DURING PERFORMANCE OF DIESEL-GENE EMERG GENERATOR SYS + CONTROLS                 81-0 0' / 43L-0   022781     RATOR MONTHLY TEST ST 5081.01 D/G 1-2 COULD NOT BE STARTED WITH LEFT SI MOTORS                                             03t158       30-DAY     DE SET OF AIR START MOTORS. IT WOULD START WITH RIGHT SIDE MOTORS. STA SUECOMPONENT NOT APPLICABLE                                         TION WAS IN MODE 5. 8 REQUIREf1ENTS OF TECH. SPEC. 3.8.1.2 WERE BEING MET COMPONENT FAILURE                                                           . THERE WAS NO 3 ANGER TO THE HEALTH 8 SAFETY OF THE PUBLIC OR STATION P MECHANICAL                                                           ERSONNEL.               D/G 1-1 AND 1-2 WERE OPERABLE DURING THIS TIME.             THIS EVENT I INGERSOLL-RAND CD                                                           S BEING REPORTED TO DOCUt ENT A COT 1P0HENT FAILURE.
EVENT DATE/
CAUSE OF OCCURRENCE WAS FAILURE OF ONE AIR STt.RT MOTOR. AIR START MOTOR HAD A BROKEN SDLENDID DRIVE SHAFT.                   BREAK IS CONSIDERED A RANDOM FAILUR E. UNDER T1AINT EN ANCE WORK ORDER 81-1406. AIR START MOTOR WAS REPLACED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
EMERGENCY DIESEL GENERATOR 1-2 WAS SUCCESSFULLY TESTED UNDER ST 5081.01 AND LECLARED OPERABLE AT 1415 HOURS ON JANUARY 18. 1981 DRESDEN-1                                               0S000010       121080     DURING UNIT OUTAGE WHILE PROCESSING WATER INTO HOLD-UP TANK. OPERATORS C LIQ RADICACT WSTE MANAGMNT 5YS                 81-001/03L-0     020981     HECKED 1ANK LEVELS AT EACN ADDITION. BUT DID NOT SAMPLE TANK UNTIL IT WA OTHER COMPONENTS                                   036100       30-DAY     S 95% FULL.               A PERIOD OF 131 HOURS HAD ELAPSED WITHOUT SAMPLING. WHICH E SUBCOMPONENT NOT APPLICABLE                                         XCEEDED TECH. SPEC. 4.8.D. THAT REQUIRES SAMPLING EVERY 72 HRS. UNLESS N PERSONNEL ERROR                                                             0 TANK AD?ITIONS HAVE BEEN MADE SINCE LAST SAMPLE. NO EFFECT ON HEALTH NONLIC. OPERATIONS PER$0NNEL                                         OR SAFETY OF PUDLIC SINCE NO TANK RELEASE OCCURRED. SIMILAR EVENT 0CCUR ITEM NOT APPLICABLE                                                         RED AS REPORTED DY R.O. 880-04. DOCKET 050-010.
REPORT DATE/
CAUSE DUE TO FAILURE OF PERSONNEL TO FOLLOW PROCEDURE GOVERNING SAMPLING OF RADWASTE STORAGE TANKS.                 PERSONNEL REIN $TRUCTED ON HEED FOR CAREFUL EXAMINATION OF CONDITIONS AND FREQUENCY FOR SAMPLING OF SUBJECT TANKS.
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION DAVIS-BESSE-1 0S00'346 012881 (NP-33-81-07) ON 1/28/81 AT 0330 HRS. DURING PERFORMANCE OF DIESEL-GENE EMERG GENERATOR SYS + CONTROLS 81-0 0' / 43L-0 022781 RATOR MONTHLY TEST ST 5081.01 D/G 1-2 COULD NOT BE STARTED WITH LEFT SI MOTORS 03t158 30-DAY DE SET OF AIR START MOTORS.
IT WOULD START WITH RIGHT SIDE MOTORS.
STA SUECOMPONENT NOT APPLICABLE TION WAS IN MODE 5.
8 REQUIREf1ENTS OF TECH. SPEC. 3.8.1.2 WERE BEING MET COMPONENT FAILURE
. THERE WAS NO 3 ANGER TO THE HEALTH 8 SAFETY OF THE PUBLIC OR STATION P MECHANICAL ERSONNEL.
D/G 1-1 AND 1-2 WERE OPERABLE DURING THIS TIME.
THIS EVENT I INGERSOLL-RAND CD S BEING REPORTED TO DOCUt ENT A COT 1P0HENT FAILURE.
CAUSE OF OCCURRENCE WAS FAILURE OF ONE AIR STt.RT MOTOR.
AIR START MOTOR HAD A BROKEN SDLENDID DRIVE SHAFT.
BREAK IS CONSIDERED A RANDOM FAILUR E.
UNDER T1AINT EN ANCE WORK ORDER 81-1406. AIR START MOTOR WAS REPLACED.
EMERGENCY DIESEL GENERATOR 1-2 WAS SUCCESSFULLY TESTED UNDER ST 5081.01 AND LECLARED OPERABLE AT 1415 HOURS ON JANUARY 18. 1981 DRESDEN-1 0S000010 121080 DURING UNIT OUTAGE WHILE PROCESSING WATER INTO HOLD-UP TANK. OPERATORS C LIQ RADICACT WSTE MANAGMNT 5YS 81-001/03L-0 020981 HECKED 1ANK LEVELS AT EACN ADDITION. BUT DID NOT SAMPLE TANK UNTIL IT WA OTHER COMPONENTS 036100 30-DAY S 95% FULL.
A PERIOD OF 131 HOURS HAD ELAPSED WITHOUT SAMPLING. WHICH E SUBCOMPONENT NOT APPLICABLE XCEEDED TECH. SPEC.
4.8.D.
THAT REQUIRES SAMPLING EVERY 72 HRS. UNLESS N PERSONNEL ERROR 0 TANK AD?ITIONS HAVE BEEN MADE SINCE LAST SAMPLE.
NO EFFECT ON HEALTH NONLIC. OPERATIONS PER$0NNEL OR SAFETY OF PUDLIC SINCE NO TANK RELEASE OCCURRED. SIMILAR EVENT 0CCUR ITEM NOT APPLICABLE RED AS REPORTED DY R.O.
880-04. DOCKET 050-010.
CAUSE DUE TO FAILURE OF PERSONNEL TO FOLLOW PROCEDURE GOVERNING SAMPLING OF RADWASTE STORAGE TANKS.
PERSONNEL REIN $TRUCTED ON HEED FOR CAREFUL EXAMINATION OF CONDITIONS AND FREQUENCY FOR SAMPLING OF SUBJECT TANKS.
SIGNS HAVE BEEN POSTED IN THE AREA 0F TANKS TO REf11ND PERSONNEL OF SAMPL ING REQUIREMENT. NO FURTHER CORRECTIVE ACTION DEET 1ED NECESSARY.
SIGNS HAVE BEEN POSTED IN THE AREA 0F TANKS TO REf11ND PERSONNEL OF SAMPL ING REQUIREMENT. NO FURTHER CORRECTIVE ACTION DEET 1ED NECESSARY.
DRESDEN-2                                               05000237       121980     DURING NORTIAL UNIT OPER ATION. WHILE CONDUCTING ROUTINE OPERATOR ROUNDS.
DRESDEN-2 05000237 121980 DURING NORTIAL UNIT OPER ATION. WHILE CONDUCTING ROUTINE OPERATOR ROUNDS.
ENGNRD SAFETY FEATR INSTR S'S                 80-048/03L-0     011481     THE ISOLATION VALVE TO PRESSURE SWITCH PS-1628B. USED IN THE AUTOMATIC B VALVES                                             033667       30-DAY     LOWDOWN SYSTEM. WAS FOUND CLOSED. MINIMAL EFFECT ON PUBLIC HEALTH AND 5 GATE                                                                 AFETY BECAUSE THE REM 41HING SWITCHES WERE AVAILABLE TO PERFORT1 THEIR INT-PERSONNEL ERROR                                                             ENDED SAFETY FUNCTION.               SIMILAR OCCURRENCEI         R.0, 880-026/03L-0.
ENGNRD SAFETY FEATR INSTR S'S 80-048/03L-0 011481 THE ISOLATION VALVE TO PRESSURE SWITCH PS-1628B. USED IN THE AUTOMATIC B VALVES 033667 30-DAY LOWDOWN SYSTEM. WAS FOUND CLOSED. MINIMAL EFFECT ON PUBLIC HEALTH AND 5 GATE AFETY BECAUSE THE REM 41HING SWITCHES WERE AVAILABLE TO PERFORT1 THEIR INT-PERSONNEL ERROR ENDED SAFETY FUNCTION.
MAINTENANCE 8 REPAIR. PERSONNEL STATIC-0-RING REASON FUR VALVE BEING CLOSED IS UNKNOWN. BUT CAN BE ATTRIBUTED TO PERs0 NNEL ERROR.               IM:1EDIATE CORRECTIVE ACTION WAS.TC OPEN THE VALVE.             INSrRUM ENT MECHANIC SURVEILLANCE INDICATES VALVE WAS OPENED AFTER COMPLETION OF TESTS.
SIMILAR OCCURRENCEI R.0, 880-026/03L-0.
DRESDEN-2                                               0S000237       122980     UNIT 2 WAS AT STEADY POWER OPERATION. AND DTS 1600-2 " SECONDARY CONTAINM CNTHMNT ISOLATION SYS + CONT                   80-049/03L-0     012281     ENT LEAK RATE TEST" HAD BEEN PERFORMED. AT THE COMPLETION OF THE TEST.
MAINTENANCE 8 REPAIR. PERSONNEL STATIC-0-RING REASON FUR VALVE BEING CLOSED IS UNKNOWN. BUT CAN BE ATTRIBUTED TO PERs0 NNEL ERROR.
VALVE OPERATORS                                   033711         30-DAY     THE REACTOR BUILDING VENTILATION ISOLATION VALVE 2A-5742 UOULD NOT DPEN, PHEUMATIC/ DIAPHRAGM / CYLINDER                                       THERE WAS NO HAZARD TO PUBLIC BECAUSE STANDBY GAS TREATMENT SYSTEM WAS COMPONENT FAILURE                                                           RUNNING AND THE OTHER THREE ISOLATION VALVES HERE OPERABLE. THERE HAS B INSTRUMENT                                                           EEN NO PREVIOUS REPORT OF AN EVENT.0F THIS TYPE.
IM:1EDIATE CORRECTIVE ACTION WAS.TC OPEN THE VALVE.
INSrRUM ENT MECHANIC SURVEILLANCE INDICATES VALVE WAS OPENED AFTER COMPLETION OF TESTS.
DRESDEN-2 0S000237 122980 UNIT 2 WAS AT STEADY POWER OPERATION. AND DTS 1600-2 " SECONDARY CONTAINM CNTHMNT ISOLATION SYS + CONT 80-049/03L-0 012281 ENT LEAK RATE TEST" HAD BEEN PERFORMED.
AT THE COMPLETION OF THE TEST.
VALVE OPERATORS 033711 30-DAY THE REACTOR BUILDING VENTILATION ISOLATION VALVE 2A-5742 UOULD NOT DPEN, PHEUMATIC/ DIAPHRAGM / CYLINDER THERE WAS NO HAZARD TO PUBLIC BECAUSE STANDBY GAS TREATMENT SYSTEM WAS COMPONENT FAILURE RUNNING AND THE OTHER THREE ISOLATION VALVES HERE OPERABLE. THERE HAS B INSTRUMENT EEN NO PREVIOUS REPORT OF AN EVENT.0F THIS TYPE.
UT. YANKEE NUCLEAR POWER CORP.
UT. YANKEE NUCLEAR POWER CORP.
THE FOUR WAY DIRECTIONAL CONTROL SOLENOID VALVE IN VALVE A0-2A-5742 OPER-ATOR STUCK IN THE " CLOSED" POSITION DUE.TO ACCUMULATION OF DIRT-IN THE V ALVE INTERN ALS.               THE SOLEHOID VALVE AND COIL WERE REPLACED AND A0-2A-574 2 WAS TESTED FOR PROPER OPERATION PRIOR TO RETURNING TO SERVICE. NO FUR THER CORRECTIVE ACTION REQUIRED.
THE FOUR WAY DIRECTIONAL CONTROL SOLENOID VALVE IN VALVE A0-2A-5742 OPER-ATOR STUCK IN THE " CLOSED" POSITION DUE.TO ACCUMULATION OF DIRT-IN THE V ALVE INTERN ALS.
THE SOLEHOID VALVE AND COIL WERE REPLACED AND A0-2A-574 2 WAS TESTED FOR PROPER OPERATION PRIOR TO RETURNING TO SERVICE. NO FUR THER CORRECTIVE ACTION REQUIRED.


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i MAR 26, 1981
MAR 26, 1981                                                                                 - LER MONTHLY REPORT SORTED BY FACILITY                                                   PAGE 32 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS'                                                               ,
- LER MONTHLY REPORT SORTED BY FACILITY PAGE 32 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS'
          . FACILITY / SYSTEM / COMPONENT /                               DOCKET NO./               EVENT TATE /                                                                                           -
. FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                 REPORT DATE/                                             EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                 CONTROL NO.                 REPORT TYPE                                               CAUSE DESCRIPTION i     DRESDEN-2                                                                       05000237-       123180           DURING NORMAL OPERATION, WHILE PERFORMING DRYME8.L HI PRESSURE CONTAINMEN.
EVENT TATE /
ENERG CORE COOLING SYS + CONT                                       80-050/03L-0 012681                         Y SPRAY INTERLOCK SURVEILLANCE. THE 1501-62D PRESSURE SWITCH ACTUATED AT INSTRUMENTATION + CONTROLS                                                     033712         30-DAY             44.2 INCHES OF WATER PRESSURE. TECHNICAL SPECIFICATION LIMIT IS LESS T           '
COMPONENT SUBCODE/CAUSE CODE / LER NO./
SWITCH                                                                                                           HAN OR EQUAL TO 41.6 INCHES OF WATER INCREASING. THE HEALTM AND SAFETY COMPONENT FAILURE                                                                                                 OF THE GENERAL.PUBLIC WAS NOT AFFECTED, SINCE REDUNDANT INSTRUMENTATION MECHANICAL                                                                                                       WAS AVAILABLF. THIS IS THE FIRST OCCURRENCE OF THIS TYPE.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION i
DRESDEN-2 05000237-123180 DURING NORMAL OPERATION, WHILE PERFORMING DRYME8.L HI PRESSURE CONTAINMEN.
ENERG CORE COOLING SYS + CONT 80-050/03L-0 012681 Y SPRAY INTERLOCK SURVEILLANCE. THE 1501-62D PRESSURE SWITCH ACTUATED AT INSTRUMENTATION + CONTROLS 033712 30-DAY 44.2 INCHES OF WATER PRESSURE. TECHNICAL SPECIFICATION LIMIT IS LESS T SWITCH HAN OR EQUAL TO 41.6 INCHES OF WATER INCREASING. THE HEALTM AND SAFETY COMPONENT FAILURE OF THE GENERAL.PUBLIC WAS NOT AFFECTED, SINCE REDUNDANT INSTRUMENTATION MECHANICAL WAS AVAILABLF. THIS IS THE FIRST OCCURRENCE OF THIS TYPE.
ITEM NOT APPLICABLE _
ITEM NOT APPLICABLE _
THE CAUSE WAS MISALIGNMENT OF THE ACTUATING ARM AND MICROSWITCH ADJUSTIN G SCREu BEING SET TOO HIGH. THE ACTUATING BAR WAS REALIGNED AND THE MIC ROSWITCH ADJUSTED. THE PRESSU?.E OWITCH WILL CONTINUE TO BE CHECKED PER THE SURVEILLANCE SCHEDULE.
THE CAUSE WAS MISALIGNMENT OF THE ACTUATING ARM AND MICROSWITCH ADJUSTIN G SCREu BEING SET TOO HIGH.
DRESDEN                         .
THE ACTUATING BAR WAS REALIGNED AND THE MIC ROSWITCH ADJUSTED. THE PRESSU?.E OWITCH WILL CONTINUE TO BE CHECKED PER THE SURVEILLANCE SCHEDULE.
05000237         010481-           DURING A REACTOR SCRAM, REQUIRED BY~I.E.-BULLETIN 80-17, SUPP. 4 FAILED.
DRESDEN.
UTHR INST SYS REQD FOR SAFETY                                       81-001/03L-0 .012881                         TO RECEIVE CRD VOLUME HI-HI LEVEL AL ARM OH 3 0F THE 4 CHANNELS. THE SA INSTRUMENTATION + CONTROLS                                                     036032-       .30-DAY           FETY SIGNIFICANCE OF THIS EVENT WAS MINIMAL SINCE IT DID NOT AFFECT THE-SENSOR / DETECTOR / ELEMENT                                                                                     SCRAM FUNCTION, THE CONTROL ROOM AL ARM CAME UP, AND THE SCRAM DISCHARGE DESIGN / FABRICATION ERROR                                                                                       INSTRUMENT VOLUME LEVEL SWITCHES WERE OPERABLE. PUBLIC HEALTH AND SAFET l'         CONSTRUCTION / INSTALLATION                                                                                     Y WERE. HOT"AFFECTED. PREVIOUS OCCURRENCE DOCKET 50-237, 80-46/03L.
05000237 010481-DURING A REACTOR SCRAM, REQUIRED BY~I.E.-BULLETIN 80-17, SUPP. 4 FAILED.
1 NORTEC THE CAUSE IS ATTRIBUTED TO TRANSDUCER PL ACEMENT AND MOUNTING, AND NOISE DUE TO HIGH GAIN. THE SCRAM DISCHARGE VOLUME WILL BE HYDROLIZED. TRANSD       i UCERS MOVED AND BETTER MOUNTING BRACKETS INSTALLED PRIOR TO STARTUP.-
UTHR INST SYS REQD FOR SAFETY 81-001/03L-0.012881 TO RECEIVE CRD VOLUME HI-HI LEVEL AL ARM OH 3 0F THE 4 CHANNELS. THE SA INSTRUMENTATION + CONTROLS 036032-
DRESDEN-2                                                                       05000237         010581           DURING UNIT 2 REFUELING OUTAGE, LPCI TEST SPRAY VALVE FAILED TO SHUT ELE ENERG CORE COOLING SYS + CONT                                       81-002/03L-0               012981           CTRICALLY. CNE SET OF THERMAL CONTACTS !!OULD NOT- RESET.       THE SAFETY SIG     f
.30-DAY FETY SIGNIFICANCE OF THIS EVENT WAS MINIMAL SINCE IT DID NOT AFFECT THE-SENSOR / DETECTOR / ELEMENT SCRAM FUNCTION, THE CONTROL ROOM AL ARM CAME UP, AND THE SCRAM DISCHARGE DESIGN / FABRICATION ERROR INSTRUMENT VOLUME LEVEL SWITCHES WERE OPERABLE. PUBLIC HEALTH AND SAFET l'
      ~ VALVE OPERATORS                                                                 036192         30-DAY ELECTRIC MOTOR - AC                                                                                            NIFICANCE WAS MINIMAL SINCE THE VALVE COULD BE MANUALLY SHUT AND THE REA_
CONSTRUCTION / INSTALLATION Y WERE. HOT"AFFECTED.
        -COMPONENT FAILURE CTOR WAS IN COLD SHUTDOWN. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFE ELECTRICAL TY. - THIS IS THE FIRST OCCURRENCE OF THIS TYPE FOR THIS VALVE.
PREVIOUS OCCURRENCE DOCKET 50-237, 80-46/03L.
LIMIl0RQUE CORP.
1 NORTEC THE CAUSE IS ATTRIBUTED TO TRANSDUCER PL ACEMENT AND MOUNTING, AND NOISE DUE TO HIGH GAIN.
                                                                                                                        'THE CAUSE-OF FAILURF. WAS STUCK AUXILIARY-CONTACTS. THE AUXILIARY CONTAC TS WERE REPLACED AND VALVE OPERATID PROPERLY. MOTOR CONTACTOR BREAKER C.
THE SCRAM DISCHARGE VOLUME WILL BE HYDROLIZED. TRANSD i
UCERS MOVED AND BETTER MOUNTING BRACKETS INSTALLED PRIOR TO STARTUP.-
DRESDEN-2 05000237 010581 DURING UNIT 2 REFUELING OUTAGE, LPCI TEST SPRAY VALVE FAILED TO SHUT ELE ENERG CORE COOLING SYS + CONT 81-002/03L-0 012981 CTRICALLY. CNE SET OF THERMAL CONTACTS !!OULD NOT-RESET.
THE SAFETY SIG f
~ VALVE OPERATORS 036192 30-DAY NIFICANCE WAS MINIMAL SINCE THE VALVE COULD BE MANUALLY SHUT AND THE REA_
ELECTRIC MOTOR - AC CTOR WAS IN COLD SHUTDOWN. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFE
-COMPONENT FAILURE TY. - THIS IS THE FIRST OCCURRENCE OF THIS TYPE FOR THIS VALVE.
ELECTRICAL LIMIl0RQUE CORP.
'THE CAUSE-OF FAILURF. WAS STUCK AUXILIARY-CONTACTS. THE AUXILIARY CONTAC TS WERE REPLACED AND VALVE OPERATID PROPERLY. MOTOR CONTACTOR BREAKER C.
OMPARTMENTS WILL CONTINUE TO BE CHECKED DURING OUTAGES PER ESTABLISHED P ROCEDURES.
OMPARTMENTS WILL CONTINUE TO BE CHECKED DURING OUTAGES PER ESTABLISHED P ROCEDURES.
DRESDEN-2                                                                       05000237         011781           DURING LOCAL LEAK ' RATE TESTING OF' CONTAINMENT VENT LINE, THE. MEASURED LE CNTNMNT ISOLATION SYS + CONT                                         81-005/03L-0               012981           AKAGE WAS 1715.55 SCFH WHICH EXCEEDS TECH. SPEC. 4.7.A FOR SINGLE ISOLAT VALVES                                                                         036101         30-DAY           ION (29.38 SCFH). INVESTIGATION SHOWED LEAKAGE THROUGH A0-2-1601-23. N BUTTERFLY                                                                                                       O LEAKAGE WAS DETECTED THROUGH ANY OTHER VALVE. -THE SAFETY SIGNIFICANCE COMPONENT FAILHRE                                                                                                 WAS MINIMAL SINCE ALL LEAKAGE WAS CONTAINED IN THE VENT LINE. SIMILAR NATURAL END OF LIFE                                                                                             EVENTS: 50-249/80-07.       HEALTH AND SAFETY OF THE PUBLIC WAS NOT.AFFECTED PRATT, HENRY CD.
DRESDEN-2 05000237 011781 DURING LOCAL LEAK ' RATE TESTING OF' CONTAINMENT VENT LINE, THE. MEASURED LE CNTNMNT ISOLATION SYS + CONT 81-005/03L-0 012981 AKAGE WAS 1715.55 SCFH WHICH EXCEEDS TECH. SPEC. 4.7.A FOR SINGLE ISOLAT VALVES 036101 30-DAY ION (29.38 SCFH).
                                                                                                            ',            VALVE A0-2-1601-23 WILL BE REPAIRED BEFORE START-UP OF THE UNIT. A SUPP LEMENTAL REPORT WILL BE SENT AFTER INVESTIGATION OF THE VALVE FAILURE M0 DE HAS BEEN COMPLETED.
INVESTIGATION SHOWED LEAKAGE THROUGH A0-2-1601-23.
.                                                                                                                                                                                                            4 c .    ,w.... ,.---<..m                 , -
N BUTTERFLY O LEAKAGE WAS DETECTED THROUGH ANY OTHER VALVE. -THE SAFETY SIGNIFICANCE COMPONENT FAILHRE WAS MINIMAL SINCE ALL LEAKAGE WAS CONTAINED IN THE VENT LINE.
                                                ,,.y.w..   ,.w-..,%,         , , _ . ,    ec,                   , . . , .    .3   . + . -       ~ m~_~,e---,-y             ,-c.-.-       - ,      , - .
SIMILAR NATURAL END OF LIFE EVENTS:
50-249/80-07.
HEALTH AND SAFETY OF THE PUBLIC WAS NOT.AFFECTED PRATT, HENRY CD.
VALVE A0-2-1601-23 WILL BE REPAIRED BEFORE START-UP OF THE UNIT.
A SUPP LEMENTAL REPORT WILL BE SENT AFTER INVESTIGATION OF THE VALVE FAILURE M0 DE HAS BEEN COMPLETED.
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MAR 26, 1981                                                                                           LER MONTHLY REPORT SCRTED BY FACILITY                                           PAGE 33 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                     DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 33 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                           REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                                         CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION DRESDEN-2                                                                                   05000237     012381     DURING UNIT 2 REFUELING OUTAGE, LLRT PERFORMED ON THE FEEDWATER CHECK VA FEEDWATER SYSTEMS + CONTROLS                                                             81-006/01T-0   020581     LVES MEASURED THROUGH LEAKAGE IN EXCESS OF THAT ALLOWED BY TECH. SPEC. 4 VALVES                                                                                     036193     2-MEEK     .7.A FOR: (1) A SINGLE PENETRATION (29.38 SCFH), (2) TOTAL PENETRATION A CHECK                                                                                                             ND ISOL ATION VALVE LEAKAGE (176.29 SCFH) AND (3) TOTAL CONTAINMENT LEAKA COMPONENT FAILURE                                                                                                 GE (783 SOFH). THIS WAS OF MINIMAL SAFETY SIGNIFICANCE SINCE THE FEEDWA MECHANICAL                                                                                                       TER LINE IS CAPABLE OF BEING ISOLATED BY A MOTOR OPERATED VALVE UPSTREAM CRANE COMPANY                                                                                                       OF THE CHECK VALVES. SIMILAR EVENT:     50-237/30-06.
EVENT DATE/
THE FEEDWATER CHECK VALVES HAVE NOT BEEN REPAIRED AS OF THIS DATE. A SU PPLEMENTAL REPORT WILL BE SENT WHEN ALL REPAIRS AND CORRECTIVE ACTIONS H AVE BEEN COMPLETED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
DRESDEN-3                                                                                   05000249     121980     DURING NORMAL OPERATION, WHILE PERFORMING LPCI VALVE OPERABILITY SURVEIL EMERG CORE COOLING SYS + CONT                                                           80-045/03L-0   011381     LANCE, THE DRYt' ELL SPR AY HEADER OUTBCERD ISOL ATION VALVE WOULD NOT CLOSE VALVE OPERATORS                                                                             033668     30-DAY       FROM THE CONTROL ROOM. THE HEALTH AND SAFETY OF'THE GENERAL PUBLIC WAS ELECTRIC MOTOR - AC                                                                                                 NOT ENDANGERED BECAUSE THE INBOARD ISOLATION VALVE WAS OPERABLE AND MAI COMPONENT FAILURE                                                                                                 NTAINED CLOSED UNTIL THE OUTBOARD VALVE WAS S*UT.       THIS IS THE FIRST OCC ELECTRICAL                                                                                                       URRENCE OF THIS TYPE FOR THIS VAltf.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION DRESDEN-2 05000237 012381 DURING UNIT 2 REFUELING OUTAGE, LLRT PERFORMED ON THE FEEDWATER CHECK VA FEEDWATER SYSTEMS + CONTROLS 81-006/01T-0 020581 LVES MEASURED THROUGH LEAKAGE IN EXCESS OF THAT ALLOWED BY TECH. SPEC. 4 VALVES 036193 2-MEEK
.7.A FOR: (1) A SINGLE PENETRATION (29.38 SCFH), (2) TOTAL PENETRATION A CHECK ND ISOL ATION VALVE LEAKAGE (176.29 SCFH) AND (3) TOTAL CONTAINMENT LEAKA COMPONENT FAILURE GE (783 SOFH).
THIS WAS OF MINIMAL SAFETY SIGNIFICANCE SINCE THE FEEDWA MECHANICAL TER LINE IS CAPABLE OF BEING ISOLATED BY A MOTOR OPERATED VALVE UPSTREAM CRANE COMPANY OF THE CHECK VALVES.
SIMILAR EVENT:
50-237/30-06.
THE FEEDWATER CHECK VALVES HAVE NOT BEEN REPAIRED AS OF THIS DATE.
A SU PPLEMENTAL REPORT WILL BE SENT WHEN ALL REPAIRS AND CORRECTIVE ACTIONS H AVE BEEN COMPLETED.
DRESDEN-3 05000249 121980 DURING NORMAL OPERATION, WHILE PERFORMING LPCI VALVE OPERABILITY SURVEIL EMERG CORE COOLING SYS + CONT 80-045/03L-0 011381 LANCE, THE DRYt' ELL SPR AY HEADER OUTBCERD ISOL ATION VALVE WOULD NOT CLOSE VALVE OPERATORS 033668 30-DAY FROM THE CONTROL ROOM.
THE HEALTH AND SAFETY OF'THE GENERAL PUBLIC WAS ELECTRIC MOTOR - AC NOT ENDANGERED BECAUSE THE INBOARD ISOLATION VALVE WAS OPERABLE AND MAI COMPONENT FAILURE NTAINED CLOSED UNTIL THE OUTBOARD VALVE WAS S*UT.
THIS IS THE FIRST OCC ELECTRICAL URRENCE OF THIS TYPE FOR THIS VAltf.
GENERAL ELECTRIC CO.
GENERAL ELECTRIC CO.
SUSPECTED CAUSE OF FAILURE WAS A STUCK PLUNGER ON CLOSING COIL OF VLV MO TOR BREAKER. PLUNGER WAS FREED BY MOVING CLOSING COIL BY HAND. VLV WAS CYCLED SEVERAL TIMES WHILE MONITORING COIL.       NO PROBLEMS WERE NOTED. I N ADDITION, SINCE FAILURE TO OPER, VLV HAS BEEN CYCLED GN THREE DIFFEREN T OCCASIONS AS PART OF REQ'D SURV. NO FURTHER ACTION DEEMED NECESSARY.
SUSPECTED CAUSE OF FAILURE WAS A STUCK PLUNGER ON CLOSING COIL OF VLV MO TOR BREAKER.
DRESDEN-3                                                                                   05000249     122380     DURING UNIT SHUTDOWN, WHILE TESTING GROUP 2 AND 3 ISOLATION CIRCUITRY. S RESIDUAL HEAT REMOV SYS + CONT                                                           80-048/03L-0   012081     HUTDOWN COOLING SYSTEM INBOARD ISOLATION VALVE DID NOT CLOSE. VALVE CLO CIRCUIT CLOSERS / INTERRUPTERS                                                             033713     30-DAY     SED AFTER RESETTING THERMAL OVERLOADS AND ADJUSTING BREAKER D002 INTERLD CONTACTOR                                                                                                         CK. THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WAS NOT ENDANGERED SINC COMPONENT FAILURE                                                                                                 E PRIMARY CONTAINMENT INTEGRITY WAS NOT REQUIRED AND ALL OTHER SHUTDOMM ELECTRICAL                                                                                                       COOLING SYSTEM ISOLATION VALVES FUNCTIONED AS DESIGNED. THIS IS THE FIR GENERAL ELECTRIC CO.                                                                                               ST OCCURRENCE OF THIS TYPE FOR THE VALVE.
PLUNGER WAS FREED BY MOVING CLOSING COIL BY HAND.
VLV WAS CYCLED SEVERAL TIMES WHILE MONITORING COIL.
NO PROBLEMS WERE NOTED.
I N ADDITION, SINCE FAILURE TO OPER, VLV HAS BEEN CYCLED GN THREE DIFFEREN T OCCASIONS AS PART OF REQ'D SURV.
NO FURTHER ACTION DEEMED NECESSARY.
DRESDEN-3 05000249 122380 DURING UNIT SHUTDOWN, WHILE TESTING GROUP 2 AND 3 ISOLATION CIRCUITRY. S RESIDUAL HEAT REMOV SYS + CONT 80-048/03L-0 012081 HUTDOWN COOLING SYSTEM INBOARD ISOLATION VALVE DID NOT CLOSE.
VALVE CLO CIRCUIT CLOSERS / INTERRUPTERS 033713 30-DAY SED AFTER RESETTING THERMAL OVERLOADS AND ADJUSTING BREAKER D002 INTERLD CONTACTOR CK.
THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WAS NOT ENDANGERED SINC COMPONENT FAILURE E PRIMARY CONTAINMENT INTEGRITY WAS NOT REQUIRED AND ALL OTHER SHUTDOMM ELECTRICAL COOLING SYSTEM ISOLATION VALVES FUNCTIONED AS DESIGNED. THIS IS THE FIR GENERAL ELECTRIC CO.
ST OCCURRENCE OF THIS TYPE FOR THE VALVE.
THE THERMAL OVERLOADS WERE RESET AND BREAKER DOOR INTERLOCK WAS ADJUSTED
THE THERMAL OVERLOADS WERE RESET AND BREAKER DOOR INTERLOCK WAS ADJUSTED
                                                                                                                    . VALVE WAS TAKEN OUT OF SERVICE IN THE CLOSED POSITION.         INVESTIGATION IS CONTINUING ON THE EXACT CAUSE OF FAILURE.
. VALVE WAS TAKEN OUT OF SERVICE IN THE CLOSED POSITION.
DRESDEN-3                                                                                   35000249     122580     DURING NORMAL GNIT OPERATION, AIR WAS DISCOVERED BLOWING FROM AIR START EMERG GENERATOR SYS + CONTROLS                                                           80-049/03L-0   011981     REGULATOR VALVE FOR THE UNIT 3 DIESEL GENERATOR. DIESEL GENERATOR WAS D VALVES                                                                                     033714     30-DAY     ECLARED IHOPERABLE, AND ALL REQUIRED SURVEILLANCES PERFORMED.         EVENT OF DIAPHRAGM                                                                                                       MINIMAL SAFETY SIGNIFICANCE SINCE THE 2/3 DIESEL GENERATOR WAS CAPABLE O COMPONENT FAILURE                                                                                                 F PROVIDING EMERGENCY POWER. FIRST EVENT OF THIS TYPE AT DRESDEN STATIO MECHANICAL                                                                                                       N.
INVESTIGATION IS CONTINUING ON THE EXACT CAUSE OF FAILURE.
PARKERSBURG RIG & REEL THE CAUSE WAS A BAD SEAL IN THE AIR START REGULATOR VALVE. THE REGULATO R VALVE WAS REPLACED, AND THE UNIT 3 DIESEL GENERATOR WAS DEMONSTRATED T 0 BE OPERABLE. NO FURTHER ACTION DEEMED NECESSARY.
DRESDEN-3 35000249 122580 DURING NORMAL GNIT OPERATION, AIR WAS DISCOVERED BLOWING FROM AIR START EMERG GENERATOR SYS + CONTROLS 80-049/03L-0 011981 REGULATOR VALVE FOR THE UNIT 3 DIESEL GENERATOR. DIESEL GENERATOR WAS D VALVES 033714 30-DAY ECLARED IHOPERABLE, AND ALL REQUIRED SURVEILLANCES PERFORMED.
                    ._..___-_.m_ _. ___ ______ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ ___. _                                                                  + - "
EVENT OF DIAPHRAGM MINIMAL SAFETY SIGNIFICANCE SINCE THE 2/3 DIESEL GENERATOR WAS CAPABLE O COMPONENT FAILURE F PROVIDING EMERGENCY POWER.
FIRST EVENT OF THIS TYPE AT DRESDEN STATIO MECHANICAL N.
PARKERSBURG RIG & REEL THE CAUSE WAS A BAD SEAL IN THE AIR START REGULATOR VALVE.
THE REGULATO R VALVE WAS REPLACED, AND THE UNIT 3 DIESEL GENERATOR WAS DEMONSTRATED T 0 BE OPERABLE. NO FURTHER ACTION DEEMED NECESSARY.
-.m
+ - "


MAR 26, 1981                                               LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 34 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/ DOCKET NO./         EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 34 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/
COMPONENT SUSCODE/CAUSE CODE / LER NO./               REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE EUBCODE/ MANUFACTURER     CONTROL NO.         REPORT TYPE                                 CAUSE DESCRIPTION DRESDEN-3                                 05000249         010281     DURING STEADY STATE OPERATION ON 2 JAN 81, IT WAS DETERMINED THAT A SURV SYSTEM CODE NOT APPLICABLE           81-004/03L-0         012881     EILL ANCE TH AT WAS TO BE PERFORMED NO L ATER THAN 1 JAN. 81 WAS NOT PERF0 INSTRUMENTATIch + CONTROLS                 036052           30-DAY     MED. THE PROCEDU2E (DIS 500-8, EHC LOW OIL PRESSURE SCRAM) IS REQUIRED OTHER                                                                 TO BE PERFORMED BY TABLE 4.1.1 OF THE TECHNICAL SPECIFICATIONS AND THE F PERSONNEL ERROR                                                       REQUENCY INTERVAL EXCEEDED THAT DEFINED IN TECH. SPECS.       THERE WAS NO EF MAINTENANCE
EVENT DATE/
* REPAIR PERSONNEL                                       FECT ON THE PUBLIC HEALTH OR SAFETY.     SIMILAR OCCURRENCE; R.O. 879-049/0 ITEM NOT APPLICA5tE                                                   3L-0.
COMPONENT SUSCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE EUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION DRESDEN-3 05000249 010281 DURING STEADY STATE OPERATION ON 2 JAN 81, IT WAS DETERMINED THAT A SURV SYSTEM CODE NOT APPLICABLE 81-004/03L-0 012881 EILL ANCE TH AT WAS TO BE PERFORMED NO L ATER THAN 1 JAN. 81 WAS NOT PERF0 INSTRUMENTATIch + CONTROLS 036052 30-DAY MED.
THE PROCEDU2E (DIS 500-8, EHC LOW OIL PRESSURE SCRAM) IS REQUIRED OTHER TO BE PERFORMED BY TABLE 4.1.1 OF THE TECHNICAL SPECIFICATIONS AND THE F PERSONNEL ERROR REQUENCY INTERVAL EXCEEDED THAT DEFINED IN TECH. SPECS.
THERE WAS NO EF MAINTENANCE
* REPAIR PERSONNEL FECT ON THE PUBLIC HEALTH OR SAFETY.
SIMILAR OCCURRENCE; R.O.
879-049/0 ITEM NOT APPLICA5tE 3L-0.
THE CAUSE WAS DUE TO PERSONNEL ERROR BY FAILING TO ACCOUMT FOR THE NEW Y EARS DAY HOLIDAY WHEN SCHEDULING SURVEILLANCES. THE SURVEILLANCE WAS PE RFORMED ON THE DAY OF DISCOVERY. THE CAUSE OF THE OCCURRENCE WAS REVIEW ED WITH ALL PERSONMEL INVOLVED. NO FURTHER CORRECTIVE ACTION NECESSARY.
THE CAUSE WAS DUE TO PERSONNEL ERROR BY FAILING TO ACCOUMT FOR THE NEW Y EARS DAY HOLIDAY WHEN SCHEDULING SURVEILLANCES. THE SURVEILLANCE WAS PE RFORMED ON THE DAY OF DISCOVERY. THE CAUSE OF THE OCCURRENCE WAS REVIEW ED WITH ALL PERSONMEL INVOLVED. NO FURTHER CORRECTIVE ACTION NECESSARY.
DRESDEN-3                                 05000249         011381     DURING HORMAL OPERATION WITH REACTOR LEVEL INSTRUMENT SURVEILLANCE IN PR CNTHMNT ISOLATION SYS + CONT         81-002/03L-0         012881     OGRESS, LEVEL SWITCM LIS 3-263-58A TRIPPED AT LESS THAN THE TECHNICAL SP INSTRUMEhTATION + CONTROLS                 036051           30-DAY     ECIFICATION lit 1IT (TABLE 3.2.1) 0F 84 INCHES. THE SAFETY SIGNIFICANCE O SWITCH COMPONENT FAILURE F THIS EVENT WAS MINIMAL SINCE THE REMAINING THREE INSTRUMENTS WERE OPER ABLE. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY. PREVIOUS DCCURRE INSTRUMENT                                                           NCES:   R.O. 76-57/03L, DOCKET 50-237; 77-51/03L. 80-23/0LL AND 80-24/03L YARWAY CORP.                                                           DOCKET 50-249.
DRESDEN-3 05000249 011381 DURING HORMAL OPERATION WITH REACTOR LEVEL INSTRUMENT SURVEILLANCE IN PR CNTHMNT ISOLATION SYS + CONT 81-002/03L-0 012881 OGRESS, LEVEL SWITCM LIS 3-263-58A TRIPPED AT LESS THAN THE TECHNICAL SP INSTRUMEhTATION + CONTROLS 036051 30-DAY ECIFICATION lit 1IT (TABLE 3.2.1) 0F 84 INCHES. THE SAFETY SIGNIFICANCE O SWITCH F THIS EVENT WAS MINIMAL SINCE THE REMAINING THREE INSTRUMENTS WERE OPER COMPONENT FAILURE ABLE.
THE CAUSE IS ATTRIBUTED TO SETPOINT DRIFT. THE INSTRUMENT WAS IMMEDIATE LY ADJUSTED AND TESTED, WITH SATISFACTORY RESULTS. SUBSEQUENT TESTS WER E PERFORMED, AND EACH TIME THE RESULTS WERE SATISFACTORY. DIS 500-2 WIL L CONTINUE TO BE DONE MONTHLY.
THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY.
DUANE ARNOLD                               05000331         071280     FOLLOWING A PLANT SHUTDOWN THE RCIC SYSTEM WAS BEING USED TO CONTROL REA SAFETY RELATED DISPLAY INSTR         80-029/01X-1         020581     CTOR PRESSURE. DUE TO OPERATION OF THE RCIC SYSTEM SUPPRESSIDH CHAMBER COMPONEMT CODE NOT APPLICABLE             033748           OTHER     WATER LEVEL BEGAN INCREASING AND OPERATIONS PERSONNEL INDICATED AC' ION T SUBCOMPONENT NOT APPLICABLE                                           O LOWER THE WATER LEVEL. DURING THE WATER' LEVEL REDUCTION, THE SUPPRESS OTHER NOT APPLICABLE                                                        ION CHAMBER LOW WATER LEVEL ALARM DID HOT ANNUNCIATE AND THE WATER VOLUM E WAS INADVERTENTLY REDUCED TO 57,000 CUBIC FEET. THE TECH. SPEC. 3.7.A ITEM NOT APPLICABLE                                                     1 NINIMUM VOLUME IS 58,000 CUBIC FEET. NO PREVIOUS OCCURRENCES.
PREVIOUS DCCURRE INSTRUMENT NCES:
HUMAN ENGINEERING DESIGN DEFICIENCY WITH A CONTRIBUTING CAUSE OF INSTRUM ENT FAILURE. THE MINIMUM REQUIRED WATER VOLUME WAS RESTORED APPROXIMATE LY 14 MINUTES AFTER DISCOVERY OF LOW WATER CONDITION. ALARM CONNECTIONS RESOLDERED 8 TESTED SATISFACTORILY. REDUNDANT TORUS WATER LEVEL INDICA DUANE ARNOLD TIONS TO BE INSTALLED ON FRONT PANEL TO IMPROVE MONITORING CAPABILITY.
R.O.
05000331         121580     DURING NORMAL OPERATION IT WAS DISCOVERED THAT SURVEILLANCE TESTING REQU RESIDUAL HEAT REMOV SYS + CONT       80-066/03L-0         011481     IRED BY TECH. SPEC. 3.5.G.1 WHEN ONE STANDBY DIESEL GENERATOR IS INOPERA ENGINES, INTERNAL COMBUSTION               033670           30-DAY     BLE WAS NOT PROPERLY COMPLETED. FOLLOU7NG REMOVAL OF 1G-21 DIESEL FROM SUBCOMPONENT NOT APPLICABLE                                           SERVICE FOR MAINTENANCE. THE "B" CORE SPRAY SYSTEM WAS NOT TESTED.                                     THE PERSONNEL ERROR                                                       "A" CORE SPRAY SYSTEM AND ALL OTHER SYSTEMS REQUIRED TO BE TESTED WERE T LICENSED 8 SENIOR OPERATORS                                           ESTED WITH SATISFACTORY RESULTS. THERE HAVE BEEN NO PREVIOUS SIMILAR OC ITEM NOT APPLICABLE                                                   CURRENCES.
76-57/03L, DOCKET 50-237; 77-51/03L. 80-23/0LL AND 80-24/03L YARWAY CORP.
OPERATOR ERROR. OPER. PERSONNEL DID HOT VERIFY ALL REQUIRED SURV. TESTI                                   '
DOCKET 50-249.
NG HAD BEEN PROPERLY COMPLETED. OPER PERS UERE REINSTRUCTED BY MEETING
THE CAUSE IS ATTRIBUTED TO SETPOINT DRIFT.
                                                                        & MEMORANDUM ON THE NEED FOR STRICT ADHERENCE TO PLANT PROCEDURES 8 T/S REQMTS. ALSO IN FUTURE STA'S WILL HELP REVIEW SURV TESTING DOCUMENT PAC KAGES TO PREVENT RECURRENCE.
THE INSTRUMENT WAS IMMEDIATE LY ADJUSTED AND TESTED, WITH SATISFACTORY RESULTS. SUBSEQUENT TESTS WER E PERFORMED, AND EACH TIME THE RESULTS WERE SATISFACTORY. DIS 500-2 WIL L CONTINUE TO BE DONE MONTHLY.
DUANE ARNOLD 05000331 071280 FOLLOWING A PLANT SHUTDOWN THE RCIC SYSTEM WAS BEING USED TO CONTROL REA SAFETY RELATED DISPLAY INSTR 80-029/01X-1 020581 CTOR PRESSURE.
DUE TO OPERATION OF THE RCIC SYSTEM SUPPRESSIDH CHAMBER COMPONEMT CODE NOT APPLICABLE 033748 OTHER WATER LEVEL BEGAN INCREASING AND OPERATIONS PERSONNEL INDICATED AC' ION T SUBCOMPONENT NOT APPLICABLE O LOWER THE WATER LEVEL.
DURING THE WATER' LEVEL REDUCTION, THE SUPPRESS OTHER ION CHAMBER LOW WATER LEVEL ALARM DID HOT ANNUNCIATE AND THE WATER VOLUM NOT APPLICABLE E WAS INADVERTENTLY REDUCED TO 57,000 CUBIC FEET.
THE TECH. SPEC. 3.7.A ITEM NOT APPLICABLE 1 NINIMUM VOLUME IS 58,000 CUBIC FEET.
NO PREVIOUS OCCURRENCES.
HUMAN ENGINEERING DESIGN DEFICIENCY WITH A CONTRIBUTING CAUSE OF INSTRUM ENT FAILURE.
THE MINIMUM REQUIRED WATER VOLUME WAS RESTORED APPROXIMATE LY 14 MINUTES AFTER DISCOVERY OF LOW WATER CONDITION. ALARM CONNECTIONS RESOLDERED 8 TESTED SATISFACTORILY. REDUNDANT TORUS WATER LEVEL INDICA TIONS TO BE INSTALLED ON FRONT PANEL TO IMPROVE MONITORING CAPABILITY.
DUANE ARNOLD 05000331 121580 DURING NORMAL OPERATION IT WAS DISCOVERED THAT SURVEILLANCE TESTING REQU RESIDUAL HEAT REMOV SYS + CONT 80-066/03L-0 011481 IRED BY TECH. SPEC. 3.5.G.1 WHEN ONE STANDBY DIESEL GENERATOR IS INOPERA ENGINES, INTERNAL COMBUSTION 033670 30-DAY BLE WAS NOT PROPERLY COMPLETED. FOLLOU7NG REMOVAL OF 1G-21 DIESEL FROM SUBCOMPONENT NOT APPLICABLE SERVICE FOR MAINTENANCE. THE "B" CORE SPRAY SYSTEM WAS NOT TESTED.
THE PERSONNEL ERROR "A" CORE SPRAY SYSTEM AND ALL OTHER SYSTEMS REQUIRED TO BE TESTED WERE T LICENSED 8 SENIOR OPERATORS ESTED WITH SATISFACTORY RESULTS. THERE HAVE BEEN NO PREVIOUS SIMILAR OC ITEM NOT APPLICABLE CURRENCES.
OPERATOR ERROR.
OPER. PERSONNEL DID HOT VERIFY ALL REQUIRED SURV. TESTI NG HAD BEEN PROPERLY COMPLETED. OPER PERS UERE REINSTRUCTED BY MEETING
& MEMORANDUM ON THE NEED FOR STRICT ADHERENCE TO PLANT PROCEDURES 8 T/S REQMTS.
ALSO IN FUTURE STA'S WILL HELP REVIEW SURV TESTING DOCUMENT PAC KAGES TO PREVENT RECURRENCE.


MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 35 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 35 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION DUANE ARNOLD                               05000331     121680     DURING SURV. TESTING SUPPRESSION CHAMBER PURGE INLET VALVE CV-4308 WOULD CNTNMNT ISOLATION SYS + CONT           80-065/03L-0   011481     NOT CYCLE. CV-4308 IS A CONTAINMENT ISOLATION VLV REQUIRED TO BE OPERA VALVE OPERATORS                           033669     30-DAY     BLE BY T/S SECTION 3.7.D.1. WHILE THIS PROBLEM WAS BEING INVESTIGATED A PNEUMATIC / DIAPHRAGM / CYLINDER                               SOLENDID VLV ASSOCIATED WITH VLV OPERATOR FOR CV-4308 WAS JARRED 1 CV-4 COMPONENT FAILURE                                                 303 BEGAN WORKING PROPERLY. VIV WAS CONSIDERED OPER. BUT FURTHER MAINT.
EVENT DATE/
MECHANICAL                                                     ACTION INITIATED. MAINT. ACTION COMPLETED WITHIN 8 HOURS.         NO PREVIOUS MILLER FLUID POWER CO.                                             SIMILAR OCCURRENCES WITH CV-4308.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
AIR SUPPLY SOLENOID VLV FOR CV-4308 WAS DISASSEMBLED 8 INSPECTED WITH NO PROBLEMS FOUND. CV-4308 OPER. DISASSEMBLED & PISTON WAS FOUND TO BE ST ICKING. OPER. WAS CLEANED, LUBRICATED 8 REASSEMBLED.     CV-4303 WAS TESTE D SAT. VLV OPER. MANUFACTURED BY MILLER FLUID POWER. OILER WILL BE ADD ED TO THE OPERATOR DURING 1981 REFUEL TO PRECLUDE RECURRENCE.
REPORT DATE/
DUANE ARNOLD                               05000331     122680     DURING NORMAL OPERATION, REACTOR WATER CLEANUP SYSTEM TO MAIN CONDENSER REAC COOL CLEANUP SYS + CONT           80-067/03L-0   012181     CONTROL VALVE CV-2729 DEVELOPED A BODY LEAK. THE LEAK WAS SPRAYING WATE VALVES                                     033715     30-DAY     R ON ELECTRICAL EQUIPMENT WHICH RESULTED IN THE REACTOR WATER CLEANUP (R GATE                                                         WCU) SYSTEM ISOLATING. REACTOR WATER CONDUCTIVITY SAMPLING WAS SHIFTED COMPONENT FAILURE                                                 TO THE REACTOR RECIRCULATION SYSTEM SAMPLE POINT IN ORDER TO SATISFY THE MECHANICAL                                                     S AMPLING REQUIREMENTS OF TECHNICAL SPECIFICATION 3.6.B.3.A. NO PREVIOU ACF INDUSTRIES INC.                                               S SIMILAR OCCURRENCES HAVE BEEN RECORDED.
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION DUANE ARNOLD 05000331 121680 DURING SURV. TESTING SUPPRESSION CHAMBER PURGE INLET VALVE CV-4308 WOULD CNTNMNT ISOLATION SYS + CONT 80-065/03L-0 011481 NOT CYCLE.
CV-4308 IS A CONTAINMENT ISOLATION VLV REQUIRED TO BE OPERA VALVE OPERATORS 033669 30-DAY BLE BY T/S SECTION 3.7.D.1.
WHILE THIS PROBLEM WAS BEING INVESTIGATED A PNEUMATIC / DIAPHRAGM / CYLINDER SOLENDID VLV ASSOCIATED WITH VLV OPERATOR FOR CV-4308 WAS JARRED 1 CV-4 COMPONENT FAILURE 303 BEGAN WORKING PROPERLY. VIV WAS CONSIDERED OPER. BUT FURTHER MAINT.
MECHANICAL ACTION INITIATED. MAINT. ACTION COMPLETED WITHIN 8 HOURS.
NO PREVIOUS MILLER FLUID POWER CO.
SIMILAR OCCURRENCES WITH CV-4308.
AIR SUPPLY SOLENOID VLV FOR CV-4308 WAS DISASSEMBLED 8 INSPECTED WITH NO PROBLEMS FOUND.
CV-4308 OPER. DISASSEMBLED & PISTON WAS FOUND TO BE ST ICKING.
OPER. WAS CLEANED, LUBRICATED 8 REASSEMBLED.
CV-4303 WAS TESTE D SAT.
VLV OPER. MANUFACTURED BY MILLER FLUID POWER.
OILER WILL BE ADD ED TO THE OPERATOR DURING 1981 REFUEL TO PRECLUDE RECURRENCE.
DUANE ARNOLD 05000331 122680 DURING NORMAL OPERATION, REACTOR WATER CLEANUP SYSTEM TO MAIN CONDENSER REAC COOL CLEANUP SYS + CONT 80-067/03L-0 012181 CONTROL VALVE CV-2729 DEVELOPED A BODY LEAK.
THE LEAK WAS SPRAYING WATE VALVES 033715 30-DAY R ON ELECTRICAL EQUIPMENT WHICH RESULTED IN THE REACTOR WATER CLEANUP (R GATE WCU) SYSTEM ISOLATING. REACTOR WATER CONDUCTIVITY SAMPLING WAS SHIFTED COMPONENT FAILURE TO THE REACTOR RECIRCULATION SYSTEM SAMPLE POINT IN ORDER TO SATISFY THE MECHANICAL S AMPLING REQUIREMENTS OF TECHNICAL SPECIFICATION 3.6.B.3.A.
NO PREVIOU ACF INDUSTRIES INC.
S SIMILAR OCCURRENCES HAVE BEEN RECORDED.
THE LEAK WAS CAUSED BY HIGH VELOCITY WATER FLOW THROUGH THE VALVE WHICH RESULTED IN A HOLE BEING ERODED IN THE VALVE BODY. THE VALVE BODY WAS WE LD kEPAIRED AN7 HYDR 0 STATICALLY TESTED WITH SATISFACTORY RESULTS. THE VA LVE WAS MANUF/L " RED BY ACF INDUSTRIES. A REPLACEMENT VALVE WILL BE INST ALLED DURIHF 'HE '981 REFUELING OUTAGE.
THE LEAK WAS CAUSED BY HIGH VELOCITY WATER FLOW THROUGH THE VALVE WHICH RESULTED IN A HOLE BEING ERODED IN THE VALVE BODY. THE VALVE BODY WAS WE LD kEPAIRED AN7 HYDR 0 STATICALLY TESTED WITH SATISFACTORY RESULTS. THE VA LVE WAS MANUF/L " RED BY ACF INDUSTRIES. A REPLACEMENT VALVE WILL BE INST ALLED DURIHF 'HE '981 REFUELING OUTAGE.
DUANE ARHOLD                               05000331     010181     DURING N0? MAL POWEk OPERATION, THE "B" DRYWELL PARTICUL ATE RADI ATION ELE 81-001/03L-0   013081     MENT, RE     C1B, Ef* LD NOT RESPOND TO A SOURCE CHECK. REDUNDANT ELEMENT, REAC COOL PRES BOUN LEAK DETEC INSTRUMENTATION + CONTROLS               036053     30-DAY     RE 8101A *50 PS' IOUSLY BEEN DECLARED INOP. IODINE 8 GASEQUS RAD MONITO OTHER                                                         RS RESPONDE; ~~~ cRLY. TECH SPEC. 3.6.C.2 NECESSITATES BOTH SUMP 8 AIR S
DUANE ARHOLD 05000331 010181 DURING N0? MAL POWEk OPERATION, THE "B" DRYWELL PARTICUL ATE RADI ATION ELE REAC COOL PRES BOUN LEAK DETEC 81-001/03L-0 013081 MENT, RE C1B, Ef* LD NOT RESPOND TO A SOURCE CHECK.
                                                                                        ~
REDUNDANT ELEMENT, IOUSLY BEEN DECLARED INOP. IODINE 8 GASEQUS RAD MONITO INSTRUMENTATION + CONTROLS 036053 30-DAY RE 8101A *50 PS' OTHER RS RESPONDE; ~~~ cRLY. TECH SPEC. 3.6.C.2 NECESSITATES BOTH SUMP 8 AIR S
COMPONENT FAILURE                                                 AMPLING SYSTEM 5 BE OPERABLE DURING REACTOR OPERATION. A7 DAY LCO WAS IN MECHANICAL                                                   ITIATED IN ACCORDANCE WITH THIS TECH SPEC. MOISTURE CARRYOVER TO RE 8101 NUCLEAR MEASUREMENTS CORP.                                       A/B IS A RECURRINC PROBLEM. SEE LER 80-038, 78-09, 77-04, AND 77-03.
~
MOISTURE CARRIED OVER TO THE PARTICULATE FILTER FROM THE DRYWELL SAMPLIN G POINT CAUSED THE FILTER TO FAIL. THE FAILED FILTER INADEQUATELY REMOV ED PARTICULATE FROM THE AIRSTREAM AND THE DETECTOR WAS SUBSEQUENTLY CONT AMINATED. DETECTOR WAS DECONTAMINATED AND FILTER REPLACED. RE 8101B WA S SOURCE CHECKED-SAT. RE 8101B IS MFG BY NMC. INITIATED DESIGN REVIEW.
COMPONENT FAILURE AMPLING SYSTEM 5 BE OPERABLE DURING REACTOR OPERATION. A7 DAY LCO WAS IN MECHANICAL ITIATED IN ACCORDANCE WITH THIS TECH SPEC. MOISTURE CARRYOVER TO RE 8101 NUCLEAR MEASUREMENTS CORP.
DUANE ARHOLD                               05000331     010681     DURING SURVEILLANCE TESTING. TURBINE BUILDING HIGH TEMPERATURE SWITCH TI MAIN STEAM ISOL SYS + CONTROLS         81-002/03L-0   020581     5 4477, ZONE 2. TRIPPED AT GREATER THAN 204 DEGREES F. TECHNICAL SPECIFI INSTRUMENTATION + CONTROLS               n36194     30-DAY     CATION TABLE-3-A REQUIRES THE SETPOINT BE LESS THAN OR EQUAL TO 200 DEGR SWITCH                                                       EES F. THE INSTFUMENT TOLERANCE IS +/- 4 DEGREES F. REDUNDANT SWITCHES'
A/B IS A RECURRINC PROBLEM. SEE LER 80-038, 78-09, 77-04, AND 77-03.
* COMPONENT FAILURE                                                 IN LOGIC WERE TESTED AND FOUND TO BE IN TOLERANCE. THIS SWITCH IS PART INSTRUMENT                                                     OF THE LOGIC WHICH ISOLATES THE MAIN STEAM LINES ON TURBINE BUILDING HI ROSEMONT ENGINEERING CD.                                         GH TEMP. REPETITIVE OCCURRENCE FOR THIS TYPE SWITCH (R0 80-025, 78-028).
MOISTURE CARRIED OVER TO THE PARTICULATE FILTER FROM THE DRYWELL SAMPLIN G POINT CAUSED THE FILTER TO FAIL.
THE FAILED FILTER INADEQUATELY REMOV ED PARTICULATE FROM THE AIRSTREAM AND THE DETECTOR WAS SUBSEQUENTLY CONT AMINATED. DETECTOR WAS DECONTAMINATED AND FILTER REPLACED. RE 8101B WA S SOURCE CHECKED-SAT. RE 8101B IS MFG BY NMC. INITIATED DESIGN REVIEW.
DUANE ARHOLD 05000331 010681 DURING SURVEILLANCE TESTING. TURBINE BUILDING HIGH TEMPERATURE SWITCH TI MAIN STEAM ISOL SYS + CONTROLS 81-002/03L-0 020581 5 4477, ZONE 2.
TRIPPED AT GREATER THAN 204 DEGREES F. TECHNICAL SPECIFI INSTRUMENTATION + CONTROLS n36194 30-DAY CATION TABLE-3-A REQUIRES THE SETPOINT BE LESS THAN OR EQUAL TO 200 DEGR SWITCH EES F.
THE INSTFUMENT TOLERANCE IS +/- 4 DEGREES F.
REDUNDANT SWITCHES' COMPONENT FAILURE IN LOGIC WERE TESTED AND FOUND TO BE IN TOLERANCE. THIS SWITCH IS PART INSTRUMENT OF THE LOGIC WHICH ISOLATES THE MAIN STEAM LINES ON TURBINE BUILDING HI ROSEMONT ENGINEERING CD.
GH TEMP. REPETITIVE OCCURRENCE FOR THIS TYPE SWITCH (R0 80-025, 78-028).
INSTRUMENT DRIFT, TIS 4477 WAS RECALIBRATED AND TESTED SATISFACTORILY PR IOR TO BEING RETURNED TO SERVICE. TIS 4477 IS A ROSEMOUNT SERIES 3000A TEMPERATURE INDICATING SWITCH. NO FURTHER CORRECTIVE ACTION IS PLANNED AT THIS TIME.
INSTRUMENT DRIFT, TIS 4477 WAS RECALIBRATED AND TESTED SATISFACTORILY PR IOR TO BEING RETURNED TO SERVICE. TIS 4477 IS A ROSEMOUNT SERIES 3000A TEMPERATURE INDICATING SWITCH. NO FURTHER CORRECTIVE ACTION IS PLANNED AT THIS TIME.
t
t


MAE 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY                                                 PAGE 36 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                 DOCEET NO./   EVENT DATE/
MAE 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 36 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                       REPORT DATE/                               EVENT DESCRIPTION /
DOCEET NO./
CAUSE SUBCODE/ MANUFACTURER                     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION DUANE ARNOLD                                           05000331         010881 DURING NORMAL POWER OPERATION, THE "B" DRYWELL PARTICULATE RADIATION ELE REAC COOL PRES BOUN LEAK DETEC                       81-303/03L-0       020581 MENT, RE 3101B, WAS UNRESPONSIVE TO A SOURCE CHECK.
EVENT DATE/
INSTRUMENTATION + CONTROLS                               036054                                                                       REDUNDANT ELEMENT R 30-DAY E 8101A, HAD PREVIOUSLY BEEN DECLARED IHOPERABLE. MOISTURE ON THE RADIA SENSOR / DETECTOR / ELEMENT COMPONENT FAILURE                                                              TION ELEMENT AND PARTICULATE DETECTOR IS A RECURRING PROBLEM. SEE RO 77
COMPONENT SUBCODE/CAUSE CODE / LER NO./
                                                                                                                                          -03, 77-04, 78-09, 80-038, AND 81-001 INSTRUMENT NUCLEAR MEASUREMENTS CORP.
REPORT DATE/
CONDENSATE WHICH HAD COLLECTED ON RE 8101B AND ITS PARTICULATE DETECTOR CAUSED SENSOR FAILURE. A NEW RADIATION ELEMENT, MYLAR WINDOW, AND BETA PHOSPHOR WERE INSTALLED TO RETURN THE DETECTOR TO OPERATION. RE 8101B W AS SOURCE CHECKED-SAT PRIOR TO RETURN TO SERVICE. RE 8101B IS AM NMC MO
EVENT DESCRIPTION /
                                                    -DUANE ARNOLD                                                05000331          011181 DEL RAK-221F RADIATION ELEMENT. DESIGN REVIEW HAS BEEN INITIATED.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
DURING NORMAL POWER OPERATION, THE "B" DRYWELL PARTICULATE RADIATION MON REAC COOL PRES BOUN LEAK DETEC                       Si-004/03L-0       020581 INSTRUMENTATION + CGNTROLS                              036195          30-DAY ITOR FAILED DOWNSCALE. REDUNDANT RADIATION MONITOR ELEMENT RE 8101A HAD SENSOR / DETECTOR / ELEMENT                                                    PREVIOUSLY BEEN DECLARED INOPERABLE. THIS PLACED THE PLANT IN A 7-DAY LC COMPONENT FAILURE                                                              0 IN ACCORDANCE WITH TECH. SPEC. 3.6.C.2 WHICH REQUIRES BOTH THL SUMP AN OTHER                                                                          D AIR SAMPLING SYSTEMS BE OPERABLE DURING REACTOR POWER OPERATION. MOIST NUCLEAR MEASUREMENTS CORP.
REPORT TYPE CAUSE DESCRIPTION DUANE ARNOLD 05000331 010881 DURING NORMAL POWER OPERATION, THE "B" DRYWELL PARTICULATE RADIATION ELE REAC COOL PRES BOUN LEAK DETEC 81-303/03L-0 020581 MENT, RE 3101B, WAS UNRESPONSIVE TO A SOURCE CHECK.
URE ON THE DETECTOR IS A REPETITIVE PROBLEM. SEE LER'S 81-003, 81-001, 80-038, 78-09, 77-04, AND 77-03.
REDUNDANT ELEMENT R INSTRUMENTATION + CONTROLS 036054 30-DAY E 8101A, HAD PREVIOUSLY BEEN DECLARED IHOPERABLE. MOISTURE ON THE RADIA SENSOR / DETECTOR / ELEMENT TION ELEMENT AND PARTICULATE DETECTOR IS A RECURRING PROBLEM.
CAUSE WAS DETERMINED TO BE CONDENSATE ON RE 8101B. THE MOISTURE WAS REM OVED FROM THE DETECTOR PRIOR TO BEING REINSTALLED. DETECTOR WAS SOURCE C HECKED-SAT. RE 8101B IS AN NMC MODEL RAK-221F RADIATION ELEMENT. DESIGN REVIEu HAS BEEN INITIATED. AS AN INTERIM MEASURE HP PERSONNEL ARE EXAMIN DUANE ARNOLD                                                                    ING THE PARTICULATE AND IODINE FILTERS ONCE PER DAY.
SEE RO 77 COMPONENT FAILURE
05000331         011381 DURING SURVEILLANCE TESTING CONDENSATE STORAGE TANK (CST) tT-5B LOW LEVE CONDENSATE STORAGE FACILITIES                       81-005/03L-0       020581 INSTRUMENTATION + CONTROLS                              036178          30-DAY L $ WITCH LS-5219 UAS FOUND INOPERABLE. THIS SWITCH PROVIDES A LOW LEVEL SWITCH                                                                          ALARM FOR THE CST'S AND SHIFTS HPCI PUMP SUCTION TO TORUS ON CST LOW LE VEL. TECH SPEC 3.2-B REQUIRES THIS SWITCH BE OPERABLE DURING REACTOR PO COMPONENT FAILURE ELECTRICAL                                                                    WER OPERATION. LS 5218 WAS TESTED AND FOUND OPERATING SAT. THIS PROBLE G-W CONTROLLER                                                                  M IS PRESENTLY THE SUBJECT OF A DESIGN REVIEW. REPETITIVE OCCURRENCE.
-03, 77-04, 78-09, 80-038, AND 81-001 INSTRUMENT NUCLEAR MEASUREMENTS CORP.
SEE LER 80-045 AND LER 76-038.
CONDENSATE WHICH HAD COLLECTED ON RE 8101B AND ITS PARTICULATE DETECTOR CAUSED SENSOR FAILURE. A NEW RADIATION ELEMENT, MYLAR WINDOW, AND BETA PHOSPHOR WERE INSTALLED TO RETURN THE DETECTOR TO OPERATION. RE 8101B W AS SOURCE CHECKED-SAT PRIOR TO RETURN TO SERVICE. RE 8101B IS AM NMC MO DEL RAK-221F RADIATION ELEMENT. DESIGN REVIEW HAS BEEN INITIATED.
MOISTURE ON THE PROBE'S LEADS WITHIN THE TERMINAL BOX CAUSED THE TRIP SI GNAL TO BE GROUNDED. THE MOISTURE WAS REMOVED FROM THE LEADS AND TERMIN AL BOX, AND THE STAKE-ONS WERE FILLED WITH RTV TO HELP KEEP THE MOISTURE AWAY FROM THE LEADS. A DESIGN REVIEW IS PRESENTLY UNDERWAY TO DETERMIN EDWIN I. HATCH-1                                        05000321                E HOW TO ALLEVIATE THE MOISTURE PROBLEM IN THE TERMINAL BOX.
-DUANE ARNOLD 05000331 011181 DURING NORMAL POWER OPERATION, THE "B" DRYWELL PARTICULATE RADIATION MON REAC COOL PRES BOUN LEAK DETEC Si-004/03L-0 020581 ITOR FAILED DOWNSCALE. REDUNDANT RADIATION MONITOR ELEMENT RE 8101A HAD INSTRUMENTATION + CGNTROLS 036195 30-DAY PREVIOUSLY BEEN DECLARED INOPERABLE. THIS PLACED THE PLANT IN A 7-DAY LC SENSOR / DETECTOR / ELEMENT 0 IN ACCORDANCE WITH TECH. SPEC. 3.6.C.2 WHICH REQUIRES BOTH THL SUMP AN COMPONENT FAILURE D AIR SAMPLING SYSTEMS BE OPERABLE DURING REACTOR POWER OPERATION. MOIST OTHER URE ON THE DETECTOR IS A REPETITIVE PROBLEM. SEE LER'S 81-003, 81-001, NUCLEAR MEASUREMENTS CORP.
121980 ON 12/19/80, WITH REACTOR SHUTDOMN, RCIC SYS WAS BEING USED TO CONTROL REAC CORE ISOL COOL SYS + CONT                       80-123/03L-0       011581 REACTOR WATER LEVEL.
80-038, 78-09, 77-04, AND 77-03.
VALVES                                                  033673                                        AFTER THREE STARTS TURBINE TRIP & THROTTLE VALVE F 30-DAY AILED TO 0?EN ON FOURTH START. THEN ON 12/26/80, DURING TURBINE EXHAUST GATE                                                                           PRESSURE INSTRUMENT FUNCTIONAL TEST 1 CALIBRATION, TRIP & THROTTLE VALV COMPONENT FAILURE                                                               E FAILED TO TRIP. RCIC WAS DECL ARED INOPERABLE AFTER EACH INCIDENT. TH MECHANICAL VERRY STEAM TURBINE COMPANY IS IS A REPETITIVE EVENT AS LAST REPORTED ON RO 50-321/1979-02.                               PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
CAUSE WAS DETERMINED TO BE CONDENSATE ON RE 8101B.
FIRST FAILURE WAS DUE TO A GALL ON VALVE POPPET & VALVE BODY CAUSING VAL VE TO STICK. GALL WAS REMOVED 8 VALVE RETURNED TO SERVICE ON DECEMBER 2 5, 1980.
THE MOISTURE WAS REM OVED FROM THE DETECTOR PRIOR TO BEING REINSTALLED. DETECTOR WAS SOURCE C HECKED-SAT. RE 8101B IS AN NMC MODEL RAK-221F RADIATION ELEMENT. DESIGN REVIEu HAS BEEN INITIATED. AS AN INTERIM MEASURE HP PERSONNEL ARE EXAMIN ING THE PARTICULATE AND IODINE FILTERS ONCE PER DAY.
DUANE ARNOLD 05000331 011381 DURING SURVEILLANCE TESTING CONDENSATE STORAGE TANK (CST) tT-5B LOW LEVE CONDENSATE STORAGE FACILITIES 81-005/03L-0 020581 L $ WITCH LS-5219 UAS FOUND INOPERABLE. THIS SWITCH PROVIDES A LOW LEVEL INSTRUMENTATION + CONTROLS 036178 30-DAY ALARM FOR THE CST'S AND SHIFTS HPCI PUMP SUCTION TO TORUS ON CST LOW LE SWITCH VEL.
TECH SPEC 3.2-B REQUIRES THIS SWITCH BE OPERABLE DURING REACTOR PO COMPONENT FAILURE WER OPERATION. LS 5218 WAS TESTED AND FOUND OPERATING SAT.
THIS PROBLE ELECTRICAL M IS PRESENTLY THE SUBJECT OF A DESIGN REVIEW. REPETITIVE OCCURRENCE.
G-W CONTROLLER SEE LER 80-045 AND LER 76-038.
MOISTURE ON THE PROBE'S LEADS WITHIN THE TERMINAL BOX CAUSED THE TRIP SI GNAL TO BE GROUNDED. THE MOISTURE WAS REMOVED FROM THE LEADS AND TERMIN AL BOX, AND THE STAKE-ONS WERE FILLED WITH RTV TO HELP KEEP THE MOISTURE AWAY FROM THE LEADS. A DESIGN REVIEW IS PRESENTLY UNDERWAY TO DETERMIN E HOW TO ALLEVIATE THE MOISTURE PROBLEM IN THE TERMINAL BOX.
EDWIN I. HATCH-1 05000321 121980 ON 12/19/80, WITH REACTOR SHUTDOMN, RCIC SYS WAS BEING USED TO CONTROL REAC CORE ISOL COOL SYS + CONT 80-123/03L-0 011581 REACTOR WATER LEVEL.
AFTER THREE STARTS TURBINE TRIP & THROTTLE VALVE F VALVES 033673 30-DAY AILED TO 0?EN ON FOURTH START.
THEN ON 12/26/80, DURING TURBINE EXHAUST GATE PRESSURE INSTRUMENT FUNCTIONAL TEST 1 CALIBRATION, TRIP & THROTTLE VALV COMPONENT FAILURE E FAILED TO TRIP.
RCIC WAS DECL ARED INOPERABLE AFTER EACH INCIDENT.
TH MECHANICAL IS IS A REPETITIVE EVENT AS LAST REPORTED ON RO 50-321/1979-02.
PUBLIC VERRY STEAM TURBINE COMPANY HEALTH AND SAFETY WERE NOT AFFECTED.
FIRST FAILURE WAS DUE TO A GALL ON VALVE POPPET & VALVE BODY CAUSING VAL VE TO STICK.
GALL WAS REMOVED 8 VALVE RETURNED TO SERVICE ON DECEMBER 2 5,
1980.
SECOND FAILURE WAS CAUSED BY A LIMIT SWITCH HAVING BEEN SET WR ONG DURING REPAIR OF PREVIOUS INCIDENT. SWITCH WAS RESET 4 RCIC PROVEN OPERABLE ON DECEMBER 26, 1980.
SECOND FAILURE WAS CAUSED BY A LIMIT SWITCH HAVING BEEN SET WR ONG DURING REPAIR OF PREVIOUS INCIDENT. SWITCH WAS RESET 4 RCIC PROVEN OPERABLE ON DECEMBER 26, 1980.


d MAR 26, 1981                                             LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 37 PROCESSED DURING MARCH, 1951 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET HO./   EVENT DATE/
d MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 37 PROCESSED DURING MARCH, 1951 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER HO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET HO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION EDWIN I. HATCH-1                             05000321     122380     WHILE THE UNIT WAS IN STEADY STATE OPERATION,RESEARCH FOR AND PREPARATI0 SYSTEM CODE NOT APPLICABLE               80-127/03L-0   011331     N OF THE UNIT 1 FIVE-YEAR ISI REPORT REVEALED A LACK OF HARD DOCUMENTATI COMPONENT CODE NOT APPLICABLE               033675     30-DAY     ON PROVING VISUAL INSPECTION OF AT LEAST $0% OF THE UNIT 1 CLASS 1 VALVE SUBCOMPONENT NOT APPLICABLE                                     (GREATER THAN 3" IN DIAMETER) INTERNALS AS REQUIRED SY TECH SPECS 4.6.K DEFECTIVE PROCEDURES                                               . THIS EVENT IS NONREPETITIVE. THE HEALTH AND SAFETY OF THE PUBLIC WER NOT APPLICABLE                                                 E UNAFFECTED.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER HO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-1 05000321 122380 WHILE THE UNIT WAS IN STEADY STATE OPERATION,RESEARCH FOR AND PREPARATI0 SYSTEM CODE NOT APPLICABLE 80-127/03L-0 011331 N OF THE UNIT 1 FIVE-YEAR ISI REPORT REVEALED A LACK OF HARD DOCUMENTATI COMPONENT CODE NOT APPLICABLE 033675 30-DAY ON PROVING VISUAL INSPECTION OF AT LEAST $0% OF THE UNIT 1 CLASS 1 VALVE SUBCOMPONENT NOT APPLICABLE (GREATER THAN 3" IN DIAMETER) INTERNALS AS REQUIRED SY TECH SPECS 4.6.K DEFECTIVE PROCEDURES
. THIS EVENT IS NONREPETITIVE. THE HEALTH AND SAFETY OF THE PUBLIC WER NOT APPLICABLE E UNAFFECTED.
ITEM NOT APPLICABLE PLANT PROCEDURES HAVE NOT STRESSED INSPECTION OF CLASS 1 VALVE (GREATER THAN 3") INTERNAL
ITEM NOT APPLICABLE PLANT PROCEDURES HAVE NOT STRESSED INSPECTION OF CLASS 1 VALVE (GREATER THAN 3") INTERNAL


==S. PROCEDURE==
==S. PROCEDURE==
S FOR UNIT 1 WILL BE REVISED SO A QC INSPE CTION OF APPLICABLE VALVE INTERNALS WILL BE DONE UHEN THE VALVE IS DISAS SEMBLED FOR MAINTENANCE. UNIT 2 PROCEDURES WILL BE REVIEWED AND AN UPDA TED REPORT SUBMITTED.                                                    ..
S FOR UNIT 1 WILL BE REVISED SO A QC INSPE CTION OF APPLICABLE VALVE INTERNALS WILL BE DONE UHEN THE VALVE IS DISAS SEMBLED FOR MAINTENANCE. UNIT 2 PROCEDURES WILL BE REVIEWED AND AN UPDA TED REPORT SUBMITTED.
EDWIN I. HATCH-1                             O$000321     122850     WITH THE PLANT AT A STEADY STATE OF OPERATION, WHILE PERFORMING HNP-t-39 AIR COND, HEAT, COOL, VENT SYSTEM       80-124/03t-0   011581     37, CONTROL ROOM AIR INTAKE ISOLATION VALVE OPERABILITY, THE 1Z41-F012 V UALVES                                     033674     30-DAY     ALVE FAILED TO MEET ACCEPTABLE CLOSING TIME CRITERIA PER TECH. SPECS. 3.
EDWIN I. HATCH-1 O$000321 122850 WITH THE PLANT AT A STEADY STATE OF OPERATION, WHILE PERFORMING HNP-t-39 AIR COND, HEAT, COOL, VENT SYSTEM 80-124/03t-0 011581 37, CONTROL ROOM AIR INTAKE ISOLATION VALVE OPERABILITY, THE 1Z41-F012 V UALVES 033674 30-DAY ALVE FAILED TO MEET ACCEPTABLE CLOSING TIME CRITERIA PER TECH. SPECS. 3.
DIAPHRAGM                                                     12.B. PLANT OPERATION WAS NOT AFFECTED AS A RESULT OF THIS EVENT. THIS COMPONENT FAILURE                                                   WAS NOT A REPETITIVE OCCURRENCE. PUBLIC HEALTH AND SAFETY WERE NOT AFF ELECTRICAL                                                     ECTED BY THIS INCIDENT.
DIAPHRAGM 12.B.
PLANT OPERATION WAS NOT AFFECTED AS A RESULT OF THIS EVENT.
THIS COMPONENT FAILURE WAS NOT A REPETITIVE OCCURRENCE. PUBLIC HEALTH AND SAFETY WERE NOT AFF ELECTRICAL ECTED BY THIS INCIDENT.
ASCD THE CAUSE OF THE VALVE FAILING TO CLOSE IN THE DESIRED LENGTH OF TIME WA 5 DUE TO A FAULTY PILOT SOLENOID OPERATOR. THE PILOT SOLENDID WAS REPLA CED AND HNP-t-3973 PERFORMED SATISFACTORILY.
ASCD THE CAUSE OF THE VALVE FAILING TO CLOSE IN THE DESIRED LENGTH OF TIME WA 5 DUE TO A FAULTY PILOT SOLENOID OPERATOR. THE PILOT SOLENDID WAS REPLA CED AND HNP-t-3973 PERFORMED SATISFACTORILY.
i EDWIN I. HATCH-1                             0$000321     123080     ON DECEMBER 30, 1980, WHILE AT 637 MUE AND PERFORMING HIGH DRYMELL PRESS                             '
i EDWIN I. HATCH-1 0$000321 123080 ON DECEMBER 30, 1980, WHILE AT 637 MUE AND PERFORMING HIGH DRYMELL PRESS REACTOR TRIP SYSTEMS 80-128/03L-0 012781 URE FUNCTION TEST, HNP-1-3002, PER TECH. SPECS. 3.1-1 B & C.
REACTOR TRIP SYSTEMS                     80-128/03L-0   012781     URE FUNCTION TEST, HNP-1-3002, PER TECH. SPECS. 3.1-1 B & C. ONE OF THE RELAYS                                     033718     30-DAY     DRYUELL HIGH PRESSURE RELAYS, 1C71-K43, DID NOT FUNCTION PROPERLY. THIS CONTROL, SEALED                                                 RELAY FAILED AGAIN ON JANUARY 1, 1981     PRICR TO THESE FAILURES, THIS W COMPONENT FAILURE                                                 AS A NON-REPETITIVE EVENT. SAFE PLANT OPERATION WAS NOT AFFECTED NOR WA ELECTRICAL                                                     S THERE ANY EFFECT ON THE HEALTH ANU SAFETY OF THE PUBLIC DUE TO THIS EV GENERAL ELECTRIC CD.                                               ENT.
ONE OF THE RELAYS 033718 30-DAY DRYUELL HIGH PRESSURE RELAYS, 1C71-K43, DID NOT FUNCTION PROPERLY. THIS CONTROL, SEALED RELAY FAILED AGAIN ON JANUARY 1,
THE FIRST EVENT WAS CAUSED BY BROKEN INSULATION ON THE RELAY, PREVENTING THE RELAY CONTACTS FROM DE-ENERGIZING. IT WAS REPAIRED AND FUNCTIONALL Y TESTED WITH SATISFACTORY RESULTS. THE SECOND FAILURE WAS DUE TO A COI L FAILURE. THE RELAY WAS REPLACED AND RETURNED TO SERVICE.
1981 PRICR TO THESE FAILURES, THIS W COMPONENT FAILURE AS A NON-REPETITIVE EVENT.
EDWIN I. HATCH-1                             0$000321     010181     WITH THE REACTOR AT 401 MWE, A LEAK OF MORE THAN FIVE (S) GPM DEVELOPED COOLANT RECIRC SYS + CONTROLS           81-002/03L-0   012781     IN THE DRYWELL. PER TECHNICAL SPECIFICATIONS 3.6.G.1,       THE REACTOR WAS B PUMPS                                       036034     30-DAY     ROUGHT TO COLD SHUTDOUN WITHIN 36 HOURS. THIS IS A NON-REPET?TIVE EVENT CENTRIFUGAL                                                   . SAFE PLANT OPERATION WAS NOT AFFECTED HOR WAS THERE ANY EFFECT ON THE COMPONENT FAILURE                                                 HEALTH AND SAFETY OF THE PUBLIC.
SAFE PLANT OPERATION WAS NOT AFFECTED NOR WA ELECTRICAL S THERE ANY EFFECT ON THE HEALTH ANU SAFETY OF THE PUBLIC DUE TO THIS EV GENERAL ELECTRIC CD.
ENT.
THE FIRST EVENT WAS CAUSED BY BROKEN INSULATION ON THE RELAY, PREVENTING THE RELAY CONTACTS FROM DE-ENERGIZING.
IT WAS REPAIRED AND FUNCTIONALL Y TESTED WITH SATISFACTORY RESULTS.
THE SECOND FAILURE WAS DUE TO A COI L FAILURE. THE RELAY WAS REPLACED AND RETURNED TO SERVICE.
EDWIN I. HATCH-1 0$000321 010181 WITH THE REACTOR AT 401 MWE, A LEAK OF MORE THAN FIVE (S) GPM DEVELOPED COOLANT RECIRC SYS + CONTROLS 81-002/03L-0 012781 IN THE DRYWELL.
PER TECHNICAL SPECIFICATIONS 3.6.G.1, THE REACTOR WAS B PUMPS 036034 30-DAY ROUGHT TO COLD SHUTDOUN WITHIN 36 HOURS.
THIS IS A NON-REPET?TIVE EVENT CENTRIFUGAL
. SAFE PLANT OPERATION WAS NOT AFFECTED HOR WAS THERE ANY EFFECT ON THE COMPONENT FAILURE HEALTH AND SAFETY OF THE PUBLIC.
INSTRUMENT DYROM JACKSON PUMPS. INC.
INSTRUMENT DYROM JACKSON PUMPS. INC.
THE CAUSE OF THE EVENT WAS A MECHANICAL SEAL LEAKING WATER FROM THE REAC TOR RECIRC PUMP, IB31-C001A. THE SEAL WAS REPLACED, FUNCTIONALLY TESTED AND RETURNED TO SERVICE.
THE CAUSE OF THE EVENT WAS A MECHANICAL SEAL LEAKING WATER FROM THE REAC TOR RECIRC PUMP, IB31-C001A.
THE SEAL WAS REPLACED, FUNCTIONALLY TESTED AND RETURNED TO SERVICE.


MAR 2G, 1991 '
MAR 2G, 1991 '
LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 38 4-                                                     PROCESSED DURING MARCH, 1981 FOR POWER REACTORS i             FACILITY / SYSTEM / COMPONENT /           DOCKET NO./           EVENT DATE/
LER MONTHLY REPORT SORTED BY FACILITY PAGE 38 4-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS i
COMPONENT SUBCODE/CAUSE CODE / LER NO./                         REPORT DATE/                                   EVENT DESCRIPTION /
FACILITY / SYSTEM / COMPONENT /
CAUSE SUBCODE/ MANUFACTURER               CONTROL NO.           REPORT TYPE                                   CAUSE DESCRIPTION l
DOCKET NO./
l         EDWIN I. HATCH-1                                   05000321             010681     OH l
EVENT DATE/
SYSTEM CODE NOT APPLICABLE                                                              1-6-81. WITH UNIT I IN STEADY STATE POWER OPER
COMPONENT SUBCODE/CAUSE CODE / LER NO./
* WITH UNIT II SHUTDOW 81-004/03L-0           012951     N FOR REFUELING, A QA AUDIT OF HATCH PROCEDURE PROGRAM SHOWED THAT HNP-8 COMPONENT CODE NOT APPLICABLE                     036107               30-DAY     18. " TEMPORARY PROCEDURE CHANGE" DID NOT FULLY MEET T. S. SECTION 6.8.3.
REPORT DATE/
SUBCOMPONENT NOT APPLICABLE                                                       C REQUIREMENT THAT TEMP CHANGES BE DOCUMENTED, PRB REVIEWED 8 AFPROVED B DEFECTIVE PROCEDURES                                                               Y PLANT MANAGER WITHIN 14 DAYS OF IMPLEMENTATION. IT ONLY REQUIRED THAT MBT APPLICABLE                                                                       THEY BE DOCUMENTED A PRB REVIEWED WITHIN 14 DAYS. THIS IS A NON-REPETI ITEM NOT APPLICABLE                                                               TIVE EVENT AND POSED NO THREAT TG THE PUBLIC.
EVENT DESCRIPTION /
REQUIREMENT FCR PLANT MANAGERS SIGNATURE ON PROCEDURE REVISION REQUEST W AS DELETED ON 3-10-80. HNP-818 " TEMPORARY PROCEDURE CHANGE" WAS REVISED-TO REQUIRE THE PLANT MANAGERS' SIGNATURE GN THE PROCEDURE REVISION REGU EST SHEET IN ACCORDANCE WITH TECH. SPEC. SECTION 6.8.3.C.           THE SRO CHANG ED FROCEDURES WERE SIGNED BY THE PL ANT MANAGER.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
1 EDWIN I. HATCH-1                                   05000321             011981     DURING NORMAL OPERATION, WHILE PERFORMING STANDBY LIQUID CONTROL (SBLC)
REPORT TYPE CAUSE DESCRIPTION l
OTHER ENGNRD SAFETY FEATR SYS                   61-006/03L-0           021081     PUMP OPERABILITY AND RELIEF VALVE TEST PROCEDURE, HNP-1-3702, SBLC "A" D VALVES                                             036108               30-DAY     ISCHARGE RELIEF VALVE. 1C41-F029A. OPERATED AT 1200 PSIG. THE ACCEPTABL ANGLE COMPONENT FAILURE E RANGE IS 1325 +/- 75 PSIG PER TECH SPECS 4.4.A.2.A. THE REDUNDANT LOO P "B" WAS OPERABLE. THIS IS A REPETITIVE EVENT AS LAST REPORTED ON REPO MECHANICAL                                                                       RTABLE OCCURRENCE REPORT NO. 50-321/1980-010. SAFE PLANT OPERATION & PU LONEGAN, J.         E. COMPANY                                                     BLIC HEALTH AND SAFETY WERE NOT AFFECTED BY THIS EVENT.
l EDWIN I. HATCH-1 05000321 010681 OH 1-6-81. WITH UNIT I IN STEADY STATE POWER OPER
* WITH UNIT II SHUTDOW l
SYSTEM CODE NOT APPLICABLE 81-004/03L-0 012951 N FOR REFUELING, A QA AUDIT OF HATCH PROCEDURE PROGRAM SHOWED THAT HNP-8 COMPONENT CODE NOT APPLICABLE 036107 30-DAY
: 18. " TEMPORARY PROCEDURE CHANGE" DID NOT FULLY MEET T.
S. SECTION 6.8.3.
SUBCOMPONENT NOT APPLICABLE C REQUIREMENT THAT TEMP CHANGES BE DOCUMENTED, PRB REVIEWED 8 AFPROVED B DEFECTIVE PROCEDURES Y PLANT MANAGER WITHIN 14 DAYS OF IMPLEMENTATION.
IT ONLY REQUIRED THAT MBT APPLICABLE THEY BE DOCUMENTED A PRB REVIEWED WITHIN 14 DAYS.
THIS IS A NON-REPETI ITEM NOT APPLICABLE TIVE EVENT AND POSED NO THREAT TG THE PUBLIC.
REQUIREMENT FCR PLANT MANAGERS SIGNATURE ON PROCEDURE REVISION REQUEST W AS DELETED ON 3-10-80.
HNP-818 " TEMPORARY PROCEDURE CHANGE" WAS REVISED-TO REQUIRE THE PLANT MANAGERS' SIGNATURE GN THE PROCEDURE REVISION REGU EST SHEET IN ACCORDANCE WITH TECH. SPEC. SECTION 6.8.3.C.
THE SRO CHANG ED FROCEDURES WERE SIGNED BY THE PL ANT MANAGER.
EDWIN I. HATCH-1 05000321 011981 DURING NORMAL OPERATION, WHILE PERFORMING STANDBY LIQUID CONTROL (SBLC) 1 OTHER ENGNRD SAFETY FEATR SYS 61-006/03L-0 021081 PUMP OPERABILITY AND RELIEF VALVE TEST PROCEDURE, HNP-1-3702, SBLC "A" D
VALVES 036108 30-DAY ISCHARGE RELIEF VALVE. 1C41-F029A. OPERATED AT 1200 PSIG.
THE ACCEPTABL ANGLE E RANGE IS 1325 +/- 75 PSIG PER TECH SPECS 4.4.A.2.A.
THE REDUNDANT LOO COMPONENT FAILURE P "B" WAS OPERABLE. THIS IS A REPETITIVE EVENT AS LAST REPORTED ON REPO MECHANICAL RTABLE OCCURRENCE REPORT NO. 50-321/1980-010.
SAFE PLANT OPERATION & PU LONEGAN, J.
E. COMPANY BLIC HEALTH AND SAFETY WERE NOT AFFECTED BY THIS EVENT.
THE CAUSE OF THE EVENT WAS SETPOINT DRIFT ON SBLC PUMP "A" RELIEF VALVE.
THE CAUSE OF THE EVENT WAS SETPOINT DRIFT ON SBLC PUMP "A" RELIEF VALVE.
1C41-F029A. THE VALVE WAS RESET TO 1350 PSIG PER SBLC PUMP OPERABILITY AND RELIEF VALVE TEST PROCEDURE. HNP-1-3702. THE SYSTEM WAS RETESTED S ATISFACTORILY AND RETURNED TO SERVICE.
1C41-F029A.
EDWIN I. HATCH-2                                   05000366             040480   WITH THE UNIT IN COLD 5HUTDOWN, A LEAK RATE TEST WAS PERFORMED ON THE AD EMERG CORE COOLING SYS + CONT                   80-045/01X-3           021781   S VALVES AIR SUPPLY ACCUMULATOR CHECK VALVES.           THE AE DETERMINED THAT TH VALVES                                             030767               OTHER CHECK                                                                            E LEAKAGC RATES THAT WERE FOUND WERE UNACCEPTABLE AND THAT A LOSS OF AIR DESIGN / FABRICATION ERROR                                                            SUPPLY COULD LEAD TO ADS INOPERABILITY. LEAKAGE RATES FOR CORRESPONDIN G UNIT 1 VALVES ARE UNKNOWN. THIS EVENT CAUSED NO THREAT TO PUBLIC HEAL CONSTRUCTION / INSTALLATION                                                       TH OR SAFETY.     THIS IS A NONREPETITIVE EVENT FOR THESE VALVES.
THE VALVE WAS RESET TO 1350 PSIG PER SBLC PUMP OPERABILITY AND RELIEF VALVE TEST PROCEDURE. HNP-1-3702.
ROCKWELL-INTERNATIONAL CAUSE OF THIS EVENT IS BELIEVED TO BE HEAT DAMAGE FROM INSTALLATION WELD ING. THESE VALVES WERE TO BE REPLACED WITH SOFT-SEATED VALVES DURING TH E CURRENT REFUELING OUTAGE, HOWEVER, PARTS ARE UNAVAILABLE AT THIS TIME, INSTALLATION WILL BE DEL AYED UNTIL NEXT REFUELING OUT AG
THE SYSTEM WAS RETESTED S ATISFACTORILY AND RETURNED TO SERVICE.
EDWIN I. HATCH-2 05000366 040480 WITH THE UNIT IN COLD 5HUTDOWN, A LEAK RATE TEST WAS PERFORMED ON THE AD EMERG CORE COOLING SYS + CONT 80-045/01X-3 021781 S VALVES AIR SUPPLY ACCUMULATOR CHECK VALVES.
THE AE DETERMINED THAT TH VALVES 030767 OTHER E LEAKAGC RATES THAT WERE FOUND WERE UNACCEPTABLE AND THAT A LOSS OF AIR CHECK SUPPLY COULD LEAD TO ADS INOPERABILITY. LEAKAGE RATES FOR CORRESPONDIN DESIGN / FABRICATION ERROR G UNIT 1 VALVES ARE UNKNOWN.
THIS EVENT CAUSED NO THREAT TO PUBLIC HEAL CONSTRUCTION / INSTALLATION TH OR SAFETY.
THIS IS A NONREPETITIVE EVENT FOR THESE VALVES.
ROCKWELL-INTERNATIONAL CAUSE OF THIS EVENT IS BELIEVED TO BE HEAT DAMAGE FROM INSTALLATION WELD ING.
THESE VALVES WERE TO BE REPLACED WITH SOFT-SEATED VALVES DURING TH E CURRENT REFUELING OUTAGE, HOWEVER, PARTS ARE UNAVAILABLE AT THIS TIME, INSTALLATION WILL BE DEL AYED UNTIL NEXT REFUELING OUT AGE.
PROCEDURES F OR BOTH UNITS HAVE BEEN REVISED TO INFORM OPERATORS OF THIS FATLURE MODE EDWIN I.' HATCH-2' 05000366 011981 ON JANUARY 19, 1981, WHILE IN COLD SHUTDOWN AND PERFORMING CRD HCU PRESS OTHR INST SYS REQD FOR SAFETY 61-008/03L-0 021281 URE INDICATOR AND SWITCH CALIBRATION, HNP-2-5329, PER TECH SPECS 4.1.3.5 INSTRUMENTATIDH + CONTROLS 036174 30-DAY
.B.2.,
62 0F 137 PRESSURE SWITCHES WERE FOUND OUT OF TOLERANCE OF 955 +/
SWITCH
- 15 PSIG.
ACTUATION PRESSURE OF THESE SUITCHES WAS APPROXIMATELY'935 P COMPONENT FAILURE SIG.
THERE WAS NO EFFECT ON SAFE PLANT OPERATION NOR WERE THERE ANY EFF INSTRUMENT ECT ON H/S OF PUBLIC DUE TO THIS EVENT.
THIS IS A REPETITIVE EVENT AS L BARKSDALE COMPANY AST REPORTED ON REPORTABLE OCCURRENCE REPORT NO. 50-366/1980-076.
THE CAUSE OF THIS EVENT HAS BEEN ATTRIBUTED TO SETPOINT DRIFT.
THE PRES SURE SWITCHES WERE RECALIBRATED AND RETURNED TO SERVICE.
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y


==E. PROCEDURE==
l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 39 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
S F EDWIN   I.' HATCH-2'                                                              OR BOTH UNITS HAVE BEEN REVISED TO INFORM OPERATORS OF THIS FATLURE MODE 05000366             011981    ON JANUARY 19, 1981, WHILE IN COLD SHUTDOWN AND PERFORMING CRD HCU PRESS OTHR INST SYS REQD FOR SAFETY                  61-008/03L-0           021281    URE INDICATOR AND SWITCH CALIBRATION, HNP-2-5329, PER TECH SPECS 4.1.3.5 INSTRUMENTATIDH + CONTROLS                        036174              30-DAY    .B.2., 62 0F 137 PRESSURE SWITCHES WERE FOUND OUT OF TOLERANCE OF 955 +/
DOCKET NO./
SWITCH                                                                           - 15 PSIG. ACTUATION PRESSURE OF THESE SUITCHES WAS APPROXIMATELY'935 P COMPONENT FAILURE                                                                 SIG. THERE WAS NO EFFECT ON SAFE PLANT OPERATION NOR WERE THERE ANY EFF INSTRUMENT                                                                      ECT ON H/S OF PUBLIC DUE TO THIS EVENT. THIS IS A REPETITIVE EVENT AS L BARKSDALE COMPANY                                                                AST REPORTED ON REPORTABLE OCCURRENCE REPORT NO. 50-366/1980-076.
EVENT DATE/
THE CAUSE OF THIS EVENT HAS BEEN ATTRIBUTED TO SETPOINT DRIFT.           THE PRES SURE SWITCHES WERE RECALIBRATED AND RETURNED TO SERVICE.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
ce  t e        +            w  ,        e              w  yev    y we            -
REPORT DwiE/
                                                                                                                                                  --t y            m              .
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-2 05000366 012681 DURING REACTOR SHUTDOWN FOR REFUELING.THE R.P.V.
HYDRO VALVE LINEUP PER RESIDUAL HEAT REMOV SYS + CONT 81-005/01T-0 020981 HNP-2-1230 WAS BEING PERFORMED WHEN IT WAS DISCOVERED AT APPROXIMATELY 1 COMPONENT CODE NOT APPLICABLE 036109 2-WEEK 430 THAT BOTH CORE SPRAY MANUAL INJECTION VALVES HAD BEEN CLOSED AT APPR SUBCOMPONENT NOT APP 6ICABLE OXIMATELY 0900 RENDERING BOTH CORE SPRAY LOOPS INOPERABLE.
THIS WAS IN DEFECTIVE PROCEDURES VIOLATION OF TECH. SPECS.
3.5.3.1.B.2.B.
THIS IS NOT A REPETITIVE EVENT NOT APPLICABLE AND THERE WERE NO EFFECTS ON PUBLIC HEALTH OR SAFETY.
ITEM NOT APPLICABLE THIS EVENT WAS CAUSED BY PROCEDURE HNP-2-1230 BEING PERFORMED TO SUPPORT R.P.V.
HEAD TENSIGNING.
THE PROCEDURE CALLED FOR CORE SPRAY MANUAL-INJ ECTION VALVES 2E21-F007A 8 B TO BE CLOSED.
THE VALVES WERE IMMEDIATELY REOPENED AND HNP-2-1230 WAS CHANGED TO REQUIRE 2E21-F007A 8 B TO BE IN T HE OPEN POSITION.
FITZPATRICK-1 05000333 020580 DURING ROUTINE SHUTDOWN AND COOLDOWN OPERATIONS, THE PLANT STACK GAS MON-PRCSS + EFF RADIOL MONITOR SYS 80-020/04X-1 013081 ITORING SYSTEf1 WAS INOPERABLE DUE TO FREEZE UP OF THE SAMPLE LINE.
CONT INSTRUMENTATION + CONTROLS 030342 OTHER INUOUS MONITORING 15 REQUIRED BY ETS 2.3.A.9 WITH DEGRADED MODE OPERATIO OTHER H PERMIT 7CD FOR 10 DAYS.
NO SIGNIFICANT HAZARD EXISTED.
OTHER NOT APPLICABLE ITEM NOT APPLICABLE COLD WEATHER CONDITIONS IN CONJUNCTION WITH HUMID AIR AND WATER VAPOR FR CM CONDENSER AIR REMOVAL SYSTEM RESULTED IN SAMPLE LINE FREEZE UP.
BLOW DOWN OF THE SAMPLE LINE WITH DRY NITROGEN CLEARED THE LINE WITHIN 1 HOU R.
INSPECTION OF LINE DURING REFUEL OUTAGE DID NOT INDICATE ANY HEAT TR ACE PROBLEM.
SECOND SAMPLE PROBE WAS INSTALLED AS BACKUP.
FITZPATRICK-1 05000333 061080 DURING NORMAL SHUTDOWN AND DURING SURVEILLANCE TESTING, FOLLOWING ROUTIN EMERG GENERATOR SYS + CONTROLS 80-056/03X-1 020281 E PREVENTIVE MAINTENANCE WORK, EMERGENCY DIESEL GENERATOR "C"
TRIPPED ON CIRCUIT CLOSERS / INTERRUPTERS 031597 OTHER HIGH CIRCULATING CURRdNT. SUBSEQUENT TESTS COULD NOT DUPLICATE THE PRO SWITCH (OTHER THAN SENSOR)
BLEN.
THE OTHER EDG SYSTEM WAS OPERABLE MEETING TECHNICAL SPECIFICATI0H COMPONENT FAILURE 3.9.D REQUIREMENTS. THE EVENT DID NOT REFRESENT A SIGNIFICANT HAZARD T ELECTRICAL 0 THE PUBLIC HEALTH AND SAFETY.
CUTLER-HAMMER THE CAUSE WAS DUE TO HIGH RESISTANCE CONTACTS ON THE REGULATORY DROOP SW ITCH RESULTING IN TRIP.
THIS DETERMINATION WAS MADE FOLLCMING A RECURRE NCE ON 1/6/81 (SEE LER 81-004 ). SWITCHES WERE REPLACED. NO ADDITIONAL ACTION IS REQUIRED.
FITZPATRICK-1 05002533 122980 DURING NORMAL OPERATION, WHILE PERFORMING SURV5ILLANCE TO SATSIFY TECH.
REACTOR TRIP SYSTEMS 80-096/03L-0 012781 SPEC. TABLE 4.2-1, REACTOR LEVEL SUITCH 02-3-LIS-101B WAS FOUND SET 2.3 i
INSTRUMENTATION + CONTROLS 033716 30-DAY INCHES BELOW THE +12.5 INCH REQUIREMENT. ON JANUARY 9, 1981 LIS-101B WA SWITCH S FOUND SET 0.5 INCHES ABOVE THE +58 INCH REQUIREMENT.
IN BOTH CASES TH COMPONENT FAILURE E OTHER'THREE SWITCHES WERE WITHIN TECH. SPEC. LIMITS AND LIS-101B WAS I HATURAL END OF LIFE MMEDIATELY CALIBRATED. NO SIGNIFICANT HAZARD EXISTED.
BARTON INSTRU CO.,
DIV 0F ITT l
CAUSE OF BOTH FAILURES IS ATTRIBUTED TO NORMAL WEAR AND TEAR (AGE).
AFT l
ER FIRST FAILURE, SURVEILLANCE WAS INCREASED TO WEEKLY.
AFTER SECOND FA ILURE, INSTRUMENT WAS REPLACED. NEW INSTRUMENT' TESTED SATISFACTORY AND
(
WAS RETURNED TO SERVICE. NO ADDITIONAL ACTION REQUIRED.
l


l MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                                 PAGE 39 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 40 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DwiE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION EDWIN I. HATCH-2                          05000366    012681    DURING REACTOR SHUTDOWN FOR REFUELING.THE R.P.V. HYDRO VALVE LINEUP PER RESIDUAL HEAT REMOV SYS + CONT         81-005/01T-0   020981    HNP-2-1230 WAS BEING PERFORMED WHEN IT WAS DISCOVERED AT APPROXIMATELY 1 COMPONENT CODE NOT APPLICABLE              036109      2-WEEK    430 THAT BOTH CORE SPRAY MANUAL INJECTION VALVES HAD BEEN CLOSED AT APPR SUBCOMPONENT NOT APP 6ICABLE                                    OXIMATELY 0900 RENDERING BOTH CORE SPRAY LOOPS INOPERABLE.              THIS WAS IN DEFECTIVE PROCEDURES                                            VIOLATION OF TECH. SPECS. 3.5.3.1.B.2.B. THIS IS NOT A REPETITIVE EVENT NOT APPLICABLE                                                    AND THERE WERE NO EFFECTS ON PUBLIC HEALTH OR SAFETY.
EVENT DATE/
* ITEM NOT APPLICABLE THIS EVENT WAS CAUSED BY PROCEDURE HNP-2-1230 BEING PERFORMED TO SUPPORT R.P.V. HEAD TENSIGNING.      THE PROCEDURE CALLED FOR CORE SPRAY MANUAL-INJ ECTION VALVES 2E21-F007A 8 B TO BE CLOSED. THE VALVES WERE IMMEDIATELY REOPENED AND HNP-2-1230 WAS CHANGED TO REQUIRE 2E21-F007A 8 B TO BE IN T HE OPEN POSITION.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
FITZPATRICK-1                              05000333    020580    DURING ROUTINE SHUTDOWN AND COOLDOWN OPERATIONS, THE PLANT STACK GAS MON-PRCSS + EFF RADIOL MONITOR SYS          80-020/04X-1  013081    ITORING SYSTEf1 WAS INOPERABLE DUE TO FREEZE UP OF THE SAMPLE LINE. CONT INSTRUMENTATION + CONTROLS                030342      OTHER      INUOUS MONITORING 15 REQUIRED BY ETS 2.3.A.9 WITH DEGRADED MODE OPERATIO OTHER                                                          H PERMIT 7CD FOR 10 DAYS. NO SIGNIFICANT HAZARD EXISTED.
REPORT DATE/
OTHER NOT APPLICABLE ITEM NOT APPLICABLE COLD WEATHER CONDITIONS IN CONJUNCTION WITH HUMID AIR AND WATER VAPOR FR CM CONDENSER AIR REMOVAL SYSTEM RESULTED IN SAMPLE LINE FREEZE UP.             BLOW DOWN OF THE SAMPLE LINE WITH DRY NITROGEN CLEARED THE LINE WITHIN 1 HOU R. INSPECTION OF LINE DURING REFUEL OUTAGE DID NOT INDICATE ANY HEAT TR ACE PROBLEM. SECOND SAMPLE PROBE WAS INSTALLED AS BACKUP.
EVENT DESCRIPTIOM/
FITZPATRICK-1                             05000333     061080    DURING NORMAL SHUTDOWN AND DURING SURVEILLANCE TESTING, FOLLOWING ROUTIN EMERG GENERATOR SYS + CONTROLS         80-056/03X-1  020281    E PREVENTIVE MAINTENANCE WORK, EMERGENCY DIESEL GENERATOR           "C" TRIPPED ON CIRCUIT CLOSERS / INTERRUPTERS             031597      OTHER      HIGH CIRCULATING CURRdNT. SUBSEQUENT TESTS COULD NOT DUPLICATE THE PRO SWITCH (OTHER THAN SENSOR)                                     BLEN. THE OTHER EDG SYSTEM WAS OPERABLE MEETING TECHNICAL SPECIFICATI0H COMPONENT FAILURE                                                  3.9.D REQUIREMENTS. THE EVENT DID NOT REFRESENT A SIGNIFICANT HAZARD T ELECTRICAL                                                      0 THE PUBLIC HEALTH AND SAFETY.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
CUTLER-HAMMER THE CAUSE WAS DUE TO HIGH RESISTANCE CONTACTS ON THE REGULATORY DROOP SW ITCH RESULTING IN TRIP. THIS DETERMINATION WAS MADE FOLLCMING A RECURRE NCE ON 1/6/81 (SEE LER 81-004 ) . SWITCHES WERE REPLACED. NO ADDITIONAL ACTION IS REQUIRED.
REPORT TYPE CAU5E DESCRIPTION FITZPATRICK-1 05000333 010681 DURING NORMAL OPERATION, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH.
FITZPATRICK-1                             05002533    122980    DURING NORMAL OPERATION, WHILE PERFORMING SURV5ILLANCE TO SATSIFY TECH.
CNTHMNT ISOLATION SYS + CONT 81-003/03L-0 020281 SPEC. lABLE 3.2-6, CONTAINMENT ISOLATION VALVE 16-1-A0V-102A WOULD NOT C VALVES 036056 30-DAY LOSE.
REACTOR TRIP SYSTEMS                    80-096/03L-0   012781    SPEC. TABLE 4.2-1,   REACTOR LEVEL SUITCH 02-3-LIS-101B WAS FOUND SET 2.3 i  INSTRUMENTATION + CONTROLS                033716      30-DAY    INCHES BELOW THE +12.5 INCH REQUIREMENT. ON JANUARY 9,          1981 LIS-101B WA SWITCH                                                          S FOUND SET 0.5 INCHES ABOVE THE +58 INCH REQUIREMENT. IN BOTH CASES TH COMPONENT FAILURE                                                E OTHER'THREE SWITCHES WERE WITHIN TECH. SPEC. LIMITS AND LIS-101B WAS I HATURAL END OF LIFE                                            MMEDIATELY CALIBRATED. NO SIGNIFICANT HAZARD EXISTED.
THE OTHER VALVE IN THE SAME LINE (A0V-1023) WAS CLOSED AND IS BEI GLOBE NG CHECXED DATLY AS REQUIRED BY TECH. SPEC.
BARTON INSTRU CO.,          DIV 0F ITT l                                                                    CAUSE OF BOTH FAILURES IS ATTRIBUTED TO NORMAL WEAR AND TEAR (AGE).             AFT l                                                                    ER FIRST FAILURE, SURVEILLANCE WAS INCREASED TO WEEKLY.          AFTER SECOND FA
3.7.D.
'                                                                    ILURE, INSTRUMENT WAS REPLACED. NEW INSTRUMENT' TESTED SATISFACTORY AND
THE PENETRATION IS A COMPONENT FAILURE SENSING LINE FOR TORUS PRESSURE WHICH IS ALSO AVAILABLE FROM ANOTHER PE.
(                                                                    WAS RETURNED TO SERVICE. NO ADDITIONAL ACTION REQUIRED.
NATURAL END OF LIFE NETRATION. NO SIGNIFICANT HAZARD EXISTED.
l    - -        .                                                                                                                        _              .
ASCO THE CAUSE OF FAILURE IS ATTRIBUTED TO HATURAL END OF LIFE CAGE).
THE LI NE REMAINS ISOLATED WHILE A NEW ENVIRONMENTALLY QUALIFIED REPLACEMENT IS PROCURRED. NO ACTION IN ADDITION TO VALVE REPLACEMENT IS REQUIRED.
FITZPATRICK-1 05000333 011081 DURING HORMAL OPERATION, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH.
EMERG GENERATOR SYS + CONTROLS 81-004/03L-0 020981 SPEC.
4.9.B.
EMERGENCY DIESEL GENERATOR "D" EXHIBITED LOAD SWINGS (HUNTI CIRCUIT CLOSERS / INTERRUPTERS 036197 30-DAY NG) AND THEN TRIPPED ON HIGH CIRCULATING CURRENT.
INITIAL OPERATION (ST SWITCH (OTHER THAH SENSOR)
ARTING AND FORCE PARALLELING WITH EDG-B) WAS SATISFACTORY. THE REDUNDAN COMPONENT FAILURE T EMERGENCY DIESEL SYSTEM AND OFFSITE POWER WERE AVAILABLE AND OPERABLE ELECTRICAL AT ALL TIMES.
NO SIGNIFICANT HAZARD EXISTED.
CUTLER-HAMMER CAUSE OF THE FAILURE WAS DEFECTIVE REGULATOR DROOP SWITCH.
OPERATION UN DER EMERGENCY CONDITIONS (LOCA OR LOSS OF NORMAL POWER) WOULD NOT HAVE B EEN AFFECTED BECAUSE THE SWITCH IS USED ONLY FOR TEST.
SWITCH WAS REPLA CED IN BOTH EMERGENCY POWER SYSTEMS. NO ADDITIONAL ACTION IS REQUIRED.
LER 30-056 IS A RELATED EVENT.
FITZPATRICK-1 05000333 011281 DURING NORMAL OPERATION, ROD BLOCK MUNITOR "B" FAILED TO NULL WHEN A CON ENGNRD SAFETY FEATR INSTR SYS 81-006/03L-0 021181 TROL ROD WAS SELECTED.
THE INSTRUMENT WAS REQUIRED TO BE OPERABLE BY TE RELAYS 03617S 30-DAY CHNICAL SPECIFICATION TABLE 3.2-3.
THE REDUNDANT ROD BLOCK MONITOR WAS MINIATURE VERIFIED OPERABLE AS REQUIRED. NO SIGNIFICANT HAZARD EXISTED.
COMPONENT FAILURE NATURAL END OF LIFE GENERAL ELECTRIC CO.
THE ROD BLOCK MONITOR DID NOT NULL BECAUSE A RELAY FAILED (DUE TO END OF-NATURAL LIFE) AND DID NOT ALLOW THE MONITOR TO RECOGNIZE THAT A CONTROL ROD WAS SELECTED. REPLACEMENT OF RELAY BOARD AND OPERABILITY TESTING R ESTORED THE INSTRUMENT TO SERVICE ON THE FOLLOWING DAY.
NO ADDITIONAL A CTION 15 REQUIRED.
FITZPATRICK-1 05000333 011281 7URING NORMAL OPERATION, AS PART OF A ROJTINE Q.A.
AUDIT, IT WAS DETERMI GAS RADIDACT WSTE MANAGMNT SYS 81-005/04L-0 020981 NED THAT ANNUAL TEST OF THE OFFGAS AUTOMATIC ISOLATION WAS NOT PERFORMED COMPONENT CODE NOT APPLICABLE 036177 30-DAY AS REQUIRED BY ENVIRONMENTAL TECHNICAL SPECIFICATICWS (ETS) 2.3.B.10.
SUBCOMPONEHT NOT APPLICABLE FOLLOWING DISCOVERY, THE ISOLATION FUNCTION WAS TESTtD ON 1/19/81 TEST OTHER S HAD BEEN PERFORMED AS REQUIRED BY OPERATING TECHNICAL SPECIFICATIONS (
NOT APPLICABLE OTS) 4.2.D, TABLE 4.2-4 AND TABLE 4.2-6 NOTE 4.
NO SIGNIFICANT HAZARD E ITEM NOT APPLICABLE XISTED.
CONFLICT BETWEEN ETS (2.3.B10) AND OPERATING T.S.
(TABLE 2-4 AND 4.2-6, NOTE 10) CAUSED MISSED SURVEILLANCE. TEST WAS CONDUCTED DURING FIRST 0U TAGE THAT PERNITTED. SURVEILLANCE TEST WAS REVISED TO REFLECT ETS REQUI REMENT AND CHANGE TO ETS MAY BE REQUESTED. NO ADDITIONAL ACTION IS REQU IRED.


MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY                                            PAGE 40 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                        DOCKET NO./  EVENT DATE/
MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 41 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                              REPORT DATE/                                    EVENT DESCRIPTIOM/
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                            CONTROL NO. REPORT TYPE                                      CAU5E DESCRIPTION FITZPATRICK-1                                                                05000333    010681        DURING NORMAL OPERATION, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH.
EVENT DATE/
CNTHMNT ISOLATION SYS + CONT                                              81-003/03L-0  020281        SPEC. lABLE 3.2-6, CONTAINMENT ISOLATION VALVE 16-1-A0V-102A WOULD NOT C VALVES                                                                        036056      30-DAY        LOSE.
COMPONEN T SUBCODE/CAUSE CODE / LER NO./
GLOBE                                                                                                          THE OTHER VALVE IN THE SAME LINE (A0V-1023) WAS CLOSED AND IS BEI COMPONENT FAILURE                                                                                        NG CHECXED DATLY AS REQUIRED BY TECH. SPEC. 3.7.D. THE PENETRATION IS A NATURAL END OF LIFE                                                                                    SENSING LINE FOR TORUS PRESSURE WHICH IS ALSO AVAILABLE FROM ANOTHER PE.
REPORT DATE/
ASCO                                                                                                    NETRATION. NO SIGNIFICANT HAZARD EXISTED.
EVENT DES'CRIPTION/
THE CAUSE OF FAILURE IS ATTRIBUTED TO HATURAL END OF LIFE CAGE). THE LI NE REMAINS ISOLATED WHILE A NEW ENVIRONMENTALLY QUALIFIED REPLACEMENT IS PROCURRED. NO ACTION IN ADDITION TO VALVE REPLACEMENT IS REQUIRED.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
FITZPATRICK-1                                                                05000333    011081        DURING HORMAL OPERATION, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH.
REPORT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 011381 DURING NORMAL OPERATION. WHILE CONDUCTING SURVEILLANCE TO SATISFY TECHNI EMERG CORE COOLINb SYS + CONT 81-007/03L-0 021281 CAL SPECIFICATION TABLE 4.2-2, CORE SPRAY PIPE PREAK D/P SWITCHES 14-DPI INSTRUMENTATION + CONTROLS 036176 30-DAY S-43A AND 43B WERE FOUND SET AT 1.08 AND 0.77 WHEN REQUIRED BY TECHNICAL-SWITCH SPECIFICATION TABLE 3.2-2 TO BE SET AT EQUAL TO OR LESS THAN 0.5.
EMERG GENERATOR SYS + CONTROLS                                            81-004/03L-0  020981        SPEC. 4.9.B. EMERGENCY DIESEL GENERATOR "D" EXHIBITED LOAD SWINGS (HUNTI CIRCUIT CLOSERS / INTERRUPTERS                                                036197      30-DAY        NG) AND THEN TRIPPED ON HIGH CIRCULATING CURRENT. INITIAL OPERATION (ST SWITCH (OTHER THAH SENSOR)
SUIT COMPONENT FAILURE CH 43A WAS ALSO FOUND SET AT 0.72 ON 1/23/81.
COMPONENT FAILURE                                                                                      ARTING AND FORCE PARALLELING WITH EDG-B) WAS SATISFACTORY. THE REDUNDAN ELECTRICAL                                                                                            T EMERGENCY DIESEL SYSTEM AND OFFSITE POWER WERE AVAILABLE AND OPERABLE AT ALL TIMES. NO SIGNIFICANT HAZARD EXISTED.
IN EACH CASE THE SWITCHES INSTRUMENT WERE IMMEDIATELY RECALIBRATED AND RETURNED TO SERVICE.
CUTLER-HAMMER CAUSE OF THE FAILURE WAS DEFECTIVE REGULATOR DROOP SWITCH.      OPERATION UN DER EMERGENCY CONDITIONS (LOCA OR LOSS OF NORMAL POWER) WOULD NOT HAVE B EEN AFFECTED BECAUSE THE SWITCH IS USED ONLY FOR TEST. SWITCH WAS REPLA CED IN BOTH EMERGENCY POWER SYSTEMS. NO ADDITIONAL ACTION IS REQUIRED.
NO SIGNIFICANT BARTON INSTRU CO., DIV 0F ITT HAZARD EXISTED.
FITZPATRICK-1                                                                                              LER 30-056 IS A RELATED EVENT.
INSTRUMENT DRIFT IS BELIEVED TO BE THE CASE.
05000333    011281        DURING NORMAL OPERATION, ROD BLOCK MUNITOR "B" FAILED TO NULL WHEN A CON ENGNRD SAFETY FEATR INSTR SYS                                              81-006/03L-0  021181        TROL ROD WAS SELECTED.
SURVEILLANCE HAS BEEN INCR EASED.
RELAYS                                                                        03617S      30-DAY                                    THE INSTRUMENT WAS REQUIRED TO BE OPERABLE BY TE MINIATURE                                                                                              CHNICAL SPECIFICATION TABLE 3.2-3. THE REDUNDANT ROD BLOCK MONITOR WAS COMPONENT FAILURE                                                                                      VERIFIED OPERABLE AS REQUIRED. NO SIGNIFICANT HAZARD EXISTED.
FITZPATRICK-1 05000333 011481 DURING NORMAL OPERATION. THE RESIDENT INSPECTOR NOTED.THAT DAILY REACTOR SYSTEM CODE NOT APPLICABLE 81-008/03L-0 021431 COOLANT LEAKAGE DETERMINATION REQUIRED BY TECH. SPEC. 4.6.D WAS NOT CAL COMPONENT CODE NOT APPLICADLE 036198 30-DAY CULATED ON 1/13/81 THE LEAKAGE RATE WAS IMMEDIATELY CALCULATED FOR A 3 SUBCOMPONENT NOT APPLICABLE 9 HOUR PERIOD INCLUDING 1/13/81 AND A PORTION OF 1/14/81 THE AVERAGE L PERSONNEL ERROR EAKAGE RATE OVER THE 39 HOUR PERIOD WAS 1.81 GPM AND 1.64 GPM COMPARED T LICENSED 2 SENIOR OPERATORS 0 TECH. SPEC. LIMITS OF 25 AND 5 GPM.
NATURAL END OF LIFE GENERAL ELECTRIC CO.
NO SIGNIFICANT HAZARD EXISTED.
THE ROD BLOCK MONITOR DID NOT NULL BECAUSE A RELAY FAILED (DUE TO END OF-NATURAL LIFE) AND DID NOT ALLOW THE MONITOR TO RECOGNIZE THAT A CONTROL ROD WAS SELECTED. REPLACEMENT OF RELAY BOARD AND OPERABILITY TESTING R ESTORED THE INSTRUMENT TO SERVICE ON THE FOLLOWING DAY. NO ADDITIONAL A FITZPATRICK-1                                                                                            CTION 15 REQUIRED.
ITEM NOT APPLICABLE PERSONNEL ERROR WAS THE CAUSE.
05000333    011281        7URING NORMAL OPERATION, AS PART OF A ROJTINE Q.A. AUDIT, IT WAS DETERMI GAS RADIDACT WSTE MANAGMNT SYS                                            81-005/04L-0  020981 COMPONENT CODE NOT APPLICABLE                                                036177      30-DAY        NED THAT ANNUAL TEST OF THE OFFGAS AUTOMATIC ISOLATION WAS NOT PERFORMED SUBCOMPONEHT NOT APPLICABLE                                                                              AS REQUIRED BY ENVIRONMENTAL TECHNICAL SPECIFICATICWS (ETS) 2.3.B.10.
IMMEDIATE CORRECTIVE ACTION, AS NOTED AB OVE, REVEALED LEAKAGE WAS WITHIN LIrlITS. ALTHOUGH THE ERROR IS CONSIDER ED AN ISOLATED EVENT, PERSONNEL RESPONSIBLE FOR CONDUCT AND REVIEW OF TH E SURVEILLANCE WILL BE REQUIRED TO REVIEW THIS LER TO PREVENT RECURRENCE FITZPATRICK-1 05000333 011581 DURING NORi1AL OPERATION. AS A RESULT OF ADMINISTRATIVE REVIEW, IT WAS DI FIRE PROTECTION SYS + CONT 81-009/03L-0 021681 SCOVERED THAT FIRE HOSE GASKET INSPECTION AND HOSE RERACK REQUIRED BY TE COMPONENT CODE NOT APPLICABLE 036199 30-DAY CH. SPEC. TABLE 4.12.3 ONCE EACH 1.5 YEARS HAD NOT BEEN COMPLETED WHEN R SUBCOMPONENT NOT APPLICABLE EQUIRED DURING PART OF 1979 AND 1980.
OTHER                                                                                                  FOLLOWING DISCOVERY, THE ISOLATION FUNCTION WAS TESTtD ON 1/19/81      TEST NOT APPLICABLE                                                                                        S HAD BEEN PERFORMED AS REQUIRED BY OPERATING TECHNICAL SPECIFICATIONS (
THE REQUIRED INSPECTION WAS COMPL PERSONNEL ERROR ETED FOUR (4) MONTHS AFTER THE DUE DATE.
OTS) 4.2.D, TABLE 4.2-4 AND TABLE 4.2-6 NOTE 4.
NO SIGNIFICANT HAZARD EXISTED.
ITEM NOT APPLICABLE                                                                                    XISTED.                                            NO SIGNIFICANT HAZARD E CONFLICT BETWEEN ETS (2.3.B10) AND OPERATING T.S. (TABLE 2-4 AND 4.2-6, NOTE 10) CAUSED MISSED SURVEILLANCE. TEST WAS CONDUCTED DURING FIRST 0U TAGE THAT PERNITTED. SURVEILLANCE TEST WAS REVISED TO REFLECT ETS REQUI REMENT IRED. AND CHANGE TO ETS MAY BE REQUESTED. NO ADDITIONAL ACTION IS REQU
LICENSED 2 SENIOR OPERATORS ITEM NOT APPLICABLE REVIEW OF RECORDS INDICATES THAT OUTDATED PROCEDURE DATA SHEETS WERE USE D FOR 8 ft0NTHS AFTER PROCEDURE REVISION.
 
THE CAUSE WAS PERSONNEL ERROR.
MAR 26. 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 41 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./     EVENT DATE/
It1 PROPER DATA SHEETS WERE NOT USED AFTER MAY, 1980.
COMPONEN T SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                                   EVENT DES'CRIPTION/
TO PREVENT RECURRE NCE, PERSONNEL INVOLVED WILL BE REQUIRED TO REVIEW THIS LER.
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.     REPORT TYPE                                     CAUSE DESCRIPTION FITZPATRICK-1                             05000333       011381     DURING NORMAL OPERATION. WHILE CONDUCTING SURVEILLANCE TO SATISFY TECHNI EMERG CORE COOLINb SYS + CONT         81-007/03L-0     021281     CAL SPECIFICATION TABLE 4.2-2, CORE SPRAY PIPE PREAK D/P SWITCHES 14-DPI INSTRUMENTATION + CONTROLS               036176       30-DAY     S-43A AND 43B WERE FOUND SET AT 1.08 AND 0.77 WHEN REQUIRED BY TECHNICAL-SWITCH                                                           SPECIFICATION TABLE 3.2-2 TO BE SET AT EQUAL TO OR LESS THAN 0.5. SUIT COMPONENT FAILURE                                                 CH 43A WAS ALSO FOUND SET AT 0.72 ON 1/23/81. IN EACH CASE THE SWITCHES INSTRUMENT                                                       WERE IMMEDIATELY RECALIBRATED AND RETURNED TO SERVICE. NO SIGNIFICANT BARTON INSTRU CO., DIV 0F ITT                                     HAZARD EXISTED.
NO ADDITIO NAL ACTION WILL DE REQUIRED.
INSTRUMENT DRIFT IS BELIEVED TO BE THE CASE.           SURVEILLANCE HAS BEEN INCR EASED.
FITZPATRICK-1 05000333 012481 DURING NORMAL SHUTD0'N, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH. S EMERG CORE COOLING SYS + CONT 81-013/03L-0 022081 PEC. 4.5.C.1 THE HPCI SYSTEM' FLOW SQUARE ROOT COMPUT ATION MODULE WAS FO INSlRUMENTATION + CONTROLS 036232 30-DAY UND OUT OF CALIBRATION. UHEN FLOW INDICATION WAS AT A RATED VALUE OF 42 COMPUTATION MODULE 50 GPM THE ACUTAL FLOW WOULD HAVE BEEH 4203 GPM.
FITZPATRICK-1                             05000333       011481     DURING NORMAL OPERATION. THE RESIDENT INSPECTOR NOTED.THAT DAILY REACTOR SYSTEM CODE NOT APPLICABLE             81-008/03L-0     021431     COOLANT LEAKAGE DETERMINATION REQUIRED BY TECH. SPEC. 4.6.D WAS NOT CAL COMPONENT CODE NOT APPLICADLE             036198       30-DAY     CULATED ON 1/13/81     THE LEAKAGE RATE WAS IMMEDIATELY CALCULATED FOR A 3 SUBCOMPONENT NOT APPLICABLE                                       9 HOUR PERIOD INCLUDING 1/13/81 AND A PORTION OF 1/14/81           THE AVERAGE L PERSONNEL ERROR                                                   EAKAGE RATE OVER THE 39 HOUR PERIOD WAS 1.81 GPM AND 1.64 GPM COMPARED T LICENSED 2 SENIOR OPERATORS                                     0 TECH. SPEC. LIMITS OF 25 AND 5 GPM. NO SIGNIFICANT HAZARD EXISTED.
THE SYST EM 'JAS ' NOT REQ COMPONENT FAILURE UIRED TO BE OPERABLE. NO SIGNIFICANT HAZARD EXISTED.
ITEM NOT APPLICABLE PERSONNEL ERROR WAS THE CAUSE.         IMMEDIATE CORRECTIVE ACTION, AS NOTED AB OVE, REVEALED LEAKAGE WAS WITHIN LIrlITS. ALTHOUGH THE ERROR IS CONSIDER ED AN ISOLATED EVENT, PERSONNEL RESPONSIBLE FOR CONDUCT AND REVIEW OF TH E SURVEILLANCE WILL BE REQUIRED TO REVIEW THIS LER TO PREVENT RECURRENCE FITZPATRICK-1                             05000333       011581     DURING NORi1AL OPERATION. AS A RESULT OF ADMINISTRATIVE REVIEW, IT WAS DI FIRE PROTECTION SYS + CONT             81-009/03L-0     021681     SCOVERED THAT FIRE HOSE GASKET INSPECTION AND HOSE RERACK REQUIRED BY TE COMPONENT CODE NOT APPLICABLE             036199       30-DAY     CH. SPEC. TABLE 4.12.3 ONCE EACH 1.5 YEARS HAD NOT BEEN COMPLETED WHEN R SUBCOMPONENT NOT APPLICABLE                                       EQUIRED DURING PART OF 1979 AND 1980.         THE REQUIRED INSPECTION WAS COMPL PERSONNEL ERROR                                                   ETED FOUR (4) MONTHS AFTER THE DUE DATE. NO SIGNIFICANT HAZARD EXISTED.
LICENSED 2 SENIOR OPERATORS ITEM NOT APPLICABLE REVIEW OF RECORDS INDICATES THAT OUTDATED PROCEDURE DATA SHEETS WERE USE D FOR 8 ft0NTHS AFTER PROCEDURE REVISION.         THE CAUSE WAS PERSONNEL ERROR.
It1 PROPER DATA SHEETS WERE NOT USED AFTER MAY, 1980.         TO PREVENT RECURRE NCE, PERSONNEL INVOLVED WILL BE REQUIRED TO REVIEW THIS LER.           NO ADDITIO NAL ACTION WILL DE REQUIRED.
FITZPATRICK-1                             05000333       012481     DURING NORMAL SHUTD0'N, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH. S EMERG CORE COOLING SYS + CONT         81-013/03L-0     022081     PEC. 4.5.C.1 THE HPCI SYSTEM' FLOW SQUARE ROOT COMPUT ATION MODULE WAS FO INSlRUMENTATION + CONTROLS               036232       30-DAY     UND OUT OF CALIBRATION. UHEN FLOW INDICATION WAS AT A RATED VALUE OF 42 COMPUTATION MODULE                                               50 GPM THE ACUTAL FLOW WOULD HAVE BEEH 4203 GPM.         THE SYST EM 'JAS ' NOT REQ COMPONENT FAILURE                                                 UIRED TO BE OPERABLE. NO SIGNIFICANT HAZARD EXISTED.
INSTRUMENT GENERAL ELECTRIC CO.
INSTRUMENT GENERAL ELECTRIC CO.
INSTRUMENT DRIFT IS BELIEVED TO BE THE CAUSE. FOLLOWING CALIBRATION THE INSTRUMENT WAS RETURNED TO SERVICE. NO ADDITIONAL ACTION ~IS REQUIRED.
INSTRUMENT DRIFT IS BELIEVED TO BE THE CAUSE.
FOLLOWING CALIBRATION THE INSTRUMENT WAS RETURNED TO SERVICE. NO ADDITIONAL ACTION ~IS REQUIRED.


t MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS                                                                             PAGE 42 FACILITY /SYSTEP/ COMPONENT /       DOCKET NO./                     EVENT DATE/
t MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS PAGE 42 FACILITY /SYSTEP/ COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                             REPORT DATE/
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER         CONTROL NO.                     REPORT TYPE                                     EVENT DESCRIPTION /
EVENT DATE/
                                                                                                                                    -CAUSE DESCRIPTION FT. CALHOUN-1                                           05000285             122780 REACTOR TRIP SYSTEMS                         80-033/03L-0                 122980       DURING  POWER OPERATION, ONE OF FOUR CURRENT LOOPS INDICATING PRESSURIZER INSTRUMENTATION + CONTROLS                             033717                           PRESSURE AND INPUT 30-DAY                                                                                                                                       ONE POWER SUPPLY                                                                          REACTOR PROTECTIVE SYSTEM AND          CHANNELTO     THE ONE SAFETY       THERMAL INJECTION           ACTUATION                       MARGIN          CH / LOW ,
COMPONENT SUBCODE/CAUSE CODE / LER NO./
t COMPONENT FAILURE                                                                      AHMEL FAILED LOW, PLACING THE SIAS IN HALF TRIP AND TRIPPING ONE TM/LP C ELECTRICAL                                                                           HANNEL OF THE RPS. THE RPS "B" GENERAL ELECTRIC CO.                                                                 .ESSURIZER PRESSURE.                   CHANNEL WOULD NOT HAVE TRIPPED ON HIGH PR ASSING "B"              THE RPS WAS PLACED IN TWO-0UT-OF-THREE LOGIC BY BYP CHANNEL TM/LP BISTABLE. TECH. SPEC. Z 15 APPLIES.
REPORT DATE/
AFTER INVESTIGATION, IT WAS DISCOVERED THAT THE CURRENT LOOP FUSE IN THE GE/MAC TYPE 570 POWER SUPPLY FOR THE B/ PIA-102Y LOOP HAD BLOWN.                                                           TPE FU SE WAS REPLACED AND THE LOOP RETURNED TO NORMAL AFTER COMPARING THE LOOP FT. CALHOUN-1                                                                                CURRENT WITH THE OTHER THREE LOOP CURRENTS t1EASURING THE SAME PR.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
05000285           011481       AS REQUIRED BY I.E. BULLETIN 79-01B, FT-236, CHARGING HEADER FLOW LACKS SAFETY RELATED DISPLAY INSTR               8 ?-0 01/01T-0                 011581                                                                                                                                                 '
REPORT TYPE EVENT DESCRIPTION /
INSTRUMENTATION + CONTROLS                              036033            2-WEEK      COMP' DED. ETE INFORMATION 10 qu ALIFY IT FOR THE HARSH RADIATION SERVICE INTEN TRANSMITTER                                                                                  THE TRANSMITTER DESIGN / FABRICATION ERROR                                                             ILIARY PRESSURIZER SPRAY.IS USED FOR LONG TERM CORE COOLING FLOW TO T DESIGN                                                                              DENT SITUATION, CHARGING HEADER  IF fHE TRANSMITTER SHOULD FAIL IN A POST ACCI PRESSURE, FOXBORO CO., THE                                                                       AND PJMP CURVES CAN BE USED TO DETERMINE Flou.HIGH PRESSURE INJECTION FLOW, A CGMPLETE INITS          MATERIALS OR QUALIFIED    LIFE. LIST IS NOT AVAILABLE TO DETERMINE RADIATION DOSE L IL. IT WILL                    ALTHOUGH THE TRANSMITTER IS NOT EXPECTED TO FA 981 REFUELING  BE REPL ACED WITH A QUALIFIED TRANSMITTER BY THE END OF THE1 OUTAGE.
-CAUSE DESCRIPTION FT. CALHOUN-1 05000285 122780 DURING POWER OPERATION, ONE OF FOUR CURRENT LOOPS INDICATING PRESSURIZER REACTOR TRIP SYSTEMS 80-033/03L-0 122980 PRESSURE AND INPUT INSTRUMENTATION + CONTROLS 033717 30-DAY REACTOR PROTECTIVE SYSTEM CHANNELTO THE THERMAL MARGIN / LOW ONE POWER SUPPLY AND ONE SAFETY INJECTION ACTUATION CH AHMEL FAILED LOW, PLACING THE SIAS IN HALF TRIP AND TRIPPING ONE TM/LP C t
FT. ST. VRAIN-1                                           05000267           0u0480 REACTOR VES. + APPURTENANCES             80-049/03X-1                     011381       DURING A MAINTENANCE SHUTDOWN, WHILE PERFORMING ROUTINE SURVEILLANCE TES OTHER COMPONENTS                                        032835                        TING OF PCRV RUPTURE DISC, M-11702, OT IER       G.
COMPONENT FAILURE ELECTRICAL HANNEL OF THE RPS. THE RPS "B" CHANNEL WOULD NOT HAVE TRIPPED ON HIGH PR GENERAL ELECTRIC CO.
'            SUBCOMPONENT NOT APPLICABLE                                                              THIS IS OUTSIDE THE 812 PSIG +/- ITS   1%SETPOINT    WAS ALLOWED BY FORTFOUND ST. VRAIN       TO BE                          TECH. 826 PSI S
.ESSURIZER PRESSURE.
OTHER NOT APPLICABLE                                                                      PEC. LSSS AC 7.5.2(B)1.3.3.2(C) AND   IS BEING REPORTED       PER FORT   ST. VRAIN                               TECH.                 SPEC.
THE RPS WAS PLACED IN TWO-0UT-OF-THREE LOGIC BY BYP ASSING "B" CHANNEL TM/LP BISTABLE. TECH. SPEC. Z 15 APPLIES.
CALMEC                                                                                                    THE REACTOR HAD NOT BEEN OVERPRESSURIZED DURING THIS SURVE-ILLANCE ON  PUBLICINTERVAL HEALTH ORAND  THERE WAS NO EFFECT ON PLANT OPERATION.
AFTER INVESTIGATION, IT WAS DISCOVERED THAT THE CURRENT LOOP FUSE IN THE GE/MAC TYPE 570 POWER SUPPLY FOR THE B/ PIA-102Y LOOP HAD BLOWN.
SAFETY.                                                               NO EFFECT RUPTURE DISC MOVEMENT SIMILAR REPCRT RO 79-15.
TPE FU SE WAS REPLACED AND THE LOOP RETURNED TO NORMAL AFTER COMPARING THE LOOP CURRENT WITH THE OTHER THREE LOOP CURRENTS t1EASURING THE SAME PR.0 FT. CALHOUN-1 05000285 011481 AS REQUIRED BY I.E.
EVILLE WASHER OPERATING POINT.SETPOINT GUT OF TOLERANCE DUE TO DRI THAT THE RUPTURE DISC SETPOINT IN          WASTWO     ADDITIONAL SNAP-0VER TESTS REVE TOLERANCE.
BULLETIN 79-01B, FT-236, CHARGING HEADER FLOW LACKS SAFETY RELATED DISPLAY INSTR 8 ?-0 01/01T-0 011581 COMP' ETE INFORMATION 10 qu ALIFY IT FOR THE HARSH RADIATION SERVICE INTEN INSTRUMENTATION + CONTROLS 036033 2-WEEK DED.
FT. ST. VRAIH-1                                           05000267           123080                                                                                                                                                   6 SPENT FUEL STORAGE FACILITIES              80-078/03L-0                    012981      DURING AN INTERNAL AUDIT OF SURVEILLANCE TESTS. IT WAS DISCOVERED THAT S INSTRUMENTATION + CONTROLS                              033740            30-DAY      R 5.7.2B-A, THE CALIBRATION AND FUNCTIONAL TEST OF FUEL STORAGE FACILITY INDICATOR                                                                               COOLING SYSTEM FLOW INDICATORS AND FLOW AND TEMPERATURE ALARMS, HAD NOT PERSONNEL ERROR LICENSED & SENIOR OPERATORS BEEN ING      COMPLETED THIS PERIOD. WITHIN REQUIRED INTERVAL. SPENT FUEL WAS IN STORAGE DUR OTHER                                                                                   ICATION AC 7.5.2(B)3. THIS IS REPORTABLE PER FORT ST. VRAIN TECHNICAL SPECIF HEALTH OR SAFETY.            NO ACCOMPANYING OCCURRENCE. NO EFFECT ON PUBLIC RESULTS ENGINEERING SUPERVISOR INCORRECTLY ASSUMED ALL SPENT                          FUEL HAD BE EN SHIPPED LANCE  TEST OFF SITE AND INFORMED SURVEILLANCE CLERK NOT TOISSUE SURVEIL AS SCHEDULED. WHEN SITUATION WAS DISCOVERED, SURVEILLANCE WA S ISSUED TEM.        AND COMPLETED. TEST RESULTS DISCLOSED NO PROBLEMS WITH THE SY
THE TRANSMITTER DESIGN / FABRICATION ERROR ILIARY PRESSURIZER SPRAY.IS USED FOR LONG TERM CORE COOLING FLOW TO T TRANSMITTER IF fHE TRANSMITTER SHOULD FAIL IN A POST ACCI DESIGN DENT SITUATION, CHARGING HEADER PRESSURE, FOXBORO CO.,
  --- ,  w-                           ,e'y 4 -r-. -y3y-         , , ,,                          . , - -          --
THE AND PJMP CURVES CAN BE USED TO DETERMINE Flou.HIGH PRESSURE INJECTION FLOW, A CGMPLETE MATERIALS LIST IS NOT AVAILABLE TO DETERMINE RADIATION DOSE L INITS OR QUALIFIED LIFE.
* Y     -*                      - - - - - - - - - - - - - - - - - - - - - - - - - - - -
ALTHOUGH THE TRANSMITTER IS NOT EXPECTED TO FA IL. IT WILL BE REPL ACED WITH A QUALIFIED TRANSMITTER BY THE END OF THE 981 1
REFUELING OUTAGE.
FT. ST. VRAIN-1 05000267 0u0480 DURING A MAINTENANCE SHUTDOWN, WHILE PERFORMING ROUTINE SURVEILLANCE TES REACTOR VES. + APPURTENANCES 80-049/03X-1 011381 TING OF PCRV RUPTURE DISC, M-11702, OTHER COMPONENTS 032835 OT IER G. THIS IS OUTSIDE THE 812 PSIG +/- ITS SETPOINT WAS FOUND TO BE 826 PSI SUBCOMPONENT NOT APPLICABLE 1% ALLOWED BY FORT ST. VRAIN TECH. S OTHER PEC. LSSS 3.3.2(C) AND IS BEING REPORTED PER FORT ST. VRAIN TECH. SPEC.
NOT APPLICABLE AC 7.5.2(B)1.
THE REACTOR HAD NOT BEEN OVERPRESSURIZED DURING THIS SURVE-CALMEC ILLANCE INTERVAL AND THERE WAS NO EFFECT ON PLANT OPERATION.
NO EFFECT ON PUBLIC HEALTH OR SAFETY.
SIMILAR REPCRT RO 79-15.
RUPTURE DISC MOVEMENT EVILLE WASHER OPERATING POINT.SETPOINT GUT OF TOLERANCE DUE TO DRIF THAT THE RUPTURE DISC SETPOINT WASTWO ADDITIONAL SNAP-0VER TESTS REVEA IN TOLERANCE.
FT. ST. VRAIH-1 05000267 123080 DURING AN INTERNAL AUDIT OF SURVEILLANCE TESTS. IT WAS DISCOVERED THAT S 6
SPENT FUEL STORAGE FACILITIES 80-078/03L-0 012981 R 5.7.2B-A, THE CALIBRATION AND FUNCTIONAL TEST OF FUEL STORAGE FACILITY INSTRUMENTATION + CONTROLS 033740 30-DAY INDICATOR COOLING SYSTEM FLOW INDICATORS AND FLOW AND TEMPERATURE ALARMS, HAD NOT PERSONNEL ERROR BEEN COMPLETED WITHIN REQUIRED INTERVAL. SPENT FUEL WAS IN STORAGE DUR LICENSED & SENIOR OPERATORS ING THIS PERIOD.
THIS IS REPORTABLE PER FORT ST. VRAIN TECHNICAL SPECIF OTHER ICATION AC 7.5.2(B)3.
NO ACCOMPANYING OCCURRENCE. NO EFFECT ON PUBLIC HEALTH OR SAFETY.
RESULTS ENGINEERING SUPERVISOR INCORRECTLY ASSUMED ALL SPENTFUEL HAD BE EN SHIPPED OFF SITE AND INFORMED SURVEILLANCE CLERK NOT TOISSUE SURVEIL LANCE TEST AS SCHEDULED. WHEN SITUATION WAS DISCOVERED, SURVEILLANCE WA S ISSUED AND COMPLETED. TEST RESULTS DISCLOSED NO PROBLEMS WITH THE SY TEM.
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MAR 26, 1981                                                   LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 43 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /       DOCKET NO./       EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 43 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO.       REPORT TYPE                                   CAUSE DESCRIPTION FT. ST. VRAIN-1                                   05000267     123080     FROM 1530 HOURS ON 12/30/80, UNTIL 0100 HOURS ON 12/31/80. WITH THE PLAN COOLANT RECIRC SYS + CONTROLS               81-001/03L-0       013081     T OPERATING AT APPROXINATELY 55% THERMAL POWER, THE OUTLET TEMPERATURE O INSTRUMENTATION + CONTROLS                         036103     30-DAY     F LOOP 2 PCRV COOLING WATER SYSTEM EXCEEDED 120 F. THIS CONSTITUTES OPE CONTROLLER                                                               RATION IN A DECRADED MODE OF LCO 4.2.15B 2 IS REPORTABLE PER FORT ST. VR PERSONNEL ERROR                                                           AIN TECHNICAL SPECIFICATION AC 7.5.2(B)2.       NO ACCOMPANYING OCCURRENCE OR LICENSED & SENIOR OPERATORS                                               PROBABLE CONSEQUENCES. NO EFFECT ON PUBLIC HEALTH & SAFETY           SIMILAR R FOXBORO CO., THE                                                           EPCRT R0 80-46.
EVENT DATE/
CAUSE FOR INCREASED TEMP. WAS COOLING WATER TEMP. CONTROLLER BEING SET A T A HIGHER THAN NORMAL SETPOINT FOLLOWING CALIBRATION. ON DISCOVERY OF HIGH TEMP, TEMP. CONTROLLER WAS RESET TO PROPER SETPOINT.         TEMP. DECREAS ED TO AN ACCEPTABLE VALUE BY 0100 HRS OH 12/31/80, 1 NO FURTHER DEGRADED MODE OF OPERATION WAS OBSERVED. OPERATORS WILL BE REINSTRUCTED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
FT. ST. VRAIN-1                                   05000267     010681     DURING TEST, IT WAS FOUND THAT ONE CHANNEL OF ID HELIUM CIRCULATOR DRAIN ENGNRD SAFETY FEATR INSTR SYS               81-003/03L-0       020331       MALFUNCTION WAS INOPERABLE. THIS EVENT CONSTITUTES OPERATION IN A DEGR INSTRUMENTATION + CONTROLS                         036057     30-DAY     ADED MODE OF LCO 4.4.1,   TABLE 4.4-3 AND 15 REPORTABLE PER FORT ST. VRAIN SWTTCH                                                                     TECHNICAL SPECIFICATION AC 7.5.2(B)2. NO EFFECT UPON PUBLIC HEALTH OR COMPONENT FAILURE                                                         SAFETY. NO ACCOMPANYING OCCURRENCE. REDUNDANT CHANNELS WERE-AVAILABLE ELECTRICAL                                                               AND OPERABLE. NO SIMILAR REPORTS.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION FT. ST. VRAIN-1 05000267 123080 FROM 1530 HOURS ON 12/30/80, UNTIL 0100 HOURS ON 12/31/80. WITH THE PLAN COOLANT RECIRC SYS + CONTROLS 81-001/03L-0 013081 T OPERATING AT APPROXINATELY 55% THERMAL POWER, THE OUTLET TEMPERATURE O INSTRUMENTATION + CONTROLS 036103 30-DAY F LOOP 2 PCRV COOLING WATER SYSTEM EXCEEDED 120 F.
THIS CONSTITUTES OPE CONTROLLER RATION IN A DECRADED MODE OF LCO 4.2.15B 2 IS REPORTABLE PER FORT ST. VR PERSONNEL ERROR AIN TECHNICAL SPECIFICATION AC 7.5.2(B)2.
NO ACCOMPANYING OCCURRENCE OR LICENSED & SENIOR OPERATORS PROBABLE CONSEQUENCES. NO EFFECT ON PUBLIC HEALTH & SAFETY SIMILAR R FOXBORO CO., THE EPCRT R0 80-46.
CAUSE FOR INCREASED TEMP. WAS COOLING WATER TEMP. CONTROLLER BEING SET A T A HIGHER THAN NORMAL SETPOINT FOLLOWING CALIBRATION. ON DISCOVERY OF HIGH TEMP, TEMP. CONTROLLER WAS RESET TO PROPER SETPOINT.
TEMP. DECREAS ED TO AN ACCEPTABLE VALUE BY 0100 HRS OH 12/31/80, 1 NO FURTHER DEGRADED MODE OF OPERATION WAS OBSERVED.
OPERATORS WILL BE REINSTRUCTED.
FT. ST. VRAIN-1 05000267 010681 DURING TEST, IT WAS FOUND THAT ONE CHANNEL OF ID HELIUM CIRCULATOR DRAIN ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 020331 MALFUNCTION WAS INOPERABLE.
THIS EVENT CONSTITUTES OPERATION IN A DEGR INSTRUMENTATION + CONTROLS 036057 30-DAY ADED MODE OF LCO 4.4.1, TABLE 4.4-3 AND 15 REPORTABLE PER FORT ST. VRAIN SWTTCH TECHNICAL SPECIFICATION AC 7.5.2(B)2.
NO EFFECT UPON PUBLIC HEALTH OR COMPONENT FAILURE SAFETY.
NO ACCOMPANYING OCCURRENCE. REDUNDANT CHANNELS WERE-AVAILABLE ELECTRICAL AND OPERABLE. NO SIMILAR REPORTS.
GENERAL ATOMIC CO.
GENERAL ATOMIC CO.
CAUSE OF THE CHANNEL INOPERABILITY WAS A BLOWN FUSE IN SWITCH McDULE. M0 DEL Su-2D. NO CAUSE FOR THE FUSE BLOWING COULD BE FOUND. FUSE WAS REPLAC ED 4 CHANNEL RETURNED TO SERVICE. FUSE IS A 0.5 AMP MINIATURE 8 NAS OPER ATED WITH'HO PROBLEMS SINCE REPLACEMENT. NUCLEAR PROJECTS DEPT. REQUESTE D TO EVAL. CIR. DESIGN TO DETERMINE IF BLOWN FUSE INDICATION IS FEASIBLE FT. ST. VRAIN-1                                   05000267     010781     WHILE PERFORMING SURVEILLANCE TEST SR 5.4.1.3.3C-R. THE TRIP SETTING ON COOLANT RECIRC SYS + CONTROLS               81-005/03L-0       020381     PDIS-21177. BEARING WATER DIFFERENTIAL PRESSURE SUITCH, WAS FOUND BELOW INSTRUMENTATION + CONTROLS                         036058     30-DAY     THE LIMIT OF LCO 4.4.1 TABLE 4.4.3. REPORTABLE PER TECH. SPEC. AC 7.5.
CAUSE OF THE CHANNEL INOPERABILITY WAS A BLOWN FUSE IN SWITCH McDULE. M0 DEL Su-2D. NO CAUSE FOR THE FUSE BLOWING COULD BE FOUND. FUSE WAS REPLAC ED 4 CHANNEL RETURNED TO SERVICE. FUSE IS A 0.5 AMP MINIATURE 8 NAS OPER ATED WITH'HO PROBLEMS SINCE REPLACEMENT. NUCLEAR PROJECTS DEPT. REQUESTE D TO EVAL. CIR. DESIGN TO DETERMINE IF BLOWN FUSE INDICATION IS FEASIBLE FT. ST. VRAIN-1 05000267 010781 WHILE PERFORMING SURVEILLANCE TEST SR 5.4.1.3.3C-R. THE TRIP SETTING ON COOLANT RECIRC SYS + CONTROLS 81-005/03L-0 020381 PDIS-21177. BEARING WATER DIFFERENTIAL PRESSURE SUITCH, WAS FOUND BELOW INSTRUMENTATION + CONTROLS 036058 30-DAY THE LIMIT OF LCO 4.4.1 TABLE 4.4.3.
SWITCH                                                                   2(B)1 8 AC 7.5.2(B)2. THE LCO SPECIFIES A TRIP SETTING OF EQUAL TO OR G COMPONENT FAILURE                                                         REATER THAN 475 PSID AND THE SWITCH TRIPPED AT 380 PSID. NO EFFECT nN P INSTRUMENT                                                               UBLIC HEALTH OR SAFETY. NO ACCOMPANYING OCCURRENCE. REDUNDANT SYSTEMS ITT-BARTON                                                                 WERE AVAILABLE 1 OPERABLE. SIMILAR EVENTS REPORTED AS RO 79-60 1 79-11 ONE ITT BARTON MODEL 288A PRESSURE DIFFERENTIAL INDICATING SWITCH HAD A SETPOINT LESS CONSERVATIVE THAN LCO 4.4.1 DUE TO INSTRUMENT DRIFT.           THE SWITCH WAS ADJUSTED TO THE CORRECT SETPOINT AND RETURNED TO SERVICE. SU RVEILLANCE TEST SUCCESSFULLY COMPLETED.
REPORTABLE PER TECH. SPEC. AC 7.5.
FT. ST. VRAIN-1                                   05000267     010781     DURING ANNUAL TESTING 1 CALIBRATION, 6 0F THE 12 HELIUM CIRCULATOR SEAL COOLANT RECIRC SYS + CONTROLS               81-006/03L-0       020381     MALFUNCTION PRESSURE DIFFERENTIAL-SWITCH UNITS WERE DISCOVERED TO HAVE A INSTRUMENTATION + CONTROLS                         036059     30-DAY       TRIP POINT OUTSIDE LIMITS OF LCO 4.4.1 TABLE 4.4-3. THESE ARE REPORTAB SWITCH                                                                   LE PER FORT ST. VRAIN TECH. SPECS. AC 7.5.2CB)1 8 AC 7.5.2(B)2.           NO EFFE COMPONENT FAILURE                                                         CT ON PUBLIC HEALTH OR SAFETY. REDUNDANT SYSTEM AVAILABLE 8 OPERABLE. $I INSTRUMENT                                                               MILAR REFORTS ARE RO 77-47, FINAL & PRELIMINARY REPORTS RO 78-27, 79-32.
SWITCH 2(B)1 8 AC 7.5.2(B)2.
BARTON INSTRU CO., DIV 0F ITT                                               79-56, 80-07. 80-16, 80-20, 80-26, 80-34, 80-41, 80-51, AND 80-72.
THE LCO SPECIFIES A TRIP SETTING OF EQUAL TO OR G COMPONENT FAILURE REATER THAN 475 PSID AND THE SWITCH TRIPPED AT 380 PSID.
NO EFFECT nN P INSTRUMENT UBLIC HEALTH OR SAFETY.
NO ACCOMPANYING OCCURRENCE. REDUNDANT SYSTEMS ITT-BARTON WERE AVAILABLE 1 OPERABLE. SIMILAR EVENTS REPORTED AS RO 79-60 1 79-11 ONE ITT BARTON MODEL 288A PRESSURE DIFFERENTIAL INDICATING SWITCH HAD A SETPOINT LESS CONSERVATIVE THAN LCO 4.4.1 DUE TO INSTRUMENT DRIFT.
THE SWITCH WAS ADJUSTED TO THE CORRECT SETPOINT AND RETURNED TO SERVICE. SU RVEILLANCE TEST SUCCESSFULLY COMPLETED.
FT. ST. VRAIN-1 05000267 010781 DURING ANNUAL TESTING 1 CALIBRATION, 6 0F THE 12 HELIUM CIRCULATOR SEAL COOLANT RECIRC SYS + CONTROLS 81-006/03L-0 020381 MALFUNCTION PRESSURE DIFFERENTIAL-SWITCH UNITS WERE DISCOVERED TO HAVE A INSTRUMENTATION + CONTROLS 036059 30-DAY TRIP POINT OUTSIDE LIMITS OF LCO 4.4.1 TABLE 4.4-3.
THESE ARE REPORTAB SWITCH LE PER FORT ST. VRAIN TECH. SPECS. AC 7.5.2CB)1 8 AC 7.5.2(B)2.
NO EFFE COMPONENT FAILURE CT ON PUBLIC HEALTH OR SAFETY. REDUNDANT SYSTEM AVAILABLE 8 OPERABLE. $I INSTRUMENT MILAR REFORTS ARE RO 77-47, FINAL & PRELIMINARY REPORTS RO 78-27, 79-32.
BARTON INSTRU CO., DIV 0F ITT 79-56, 80-07. 80-16, 80-20, 80-26, 80-34, 80-41, 80-51, AND 80-72.
ITT BARTON MODEL 289 PRESSURE DIFFERENTIAL SWITCHES FAILED TO ACTUATE AT TRIP POINT DUE TO DIRT ACCU *1ULATION IN ELECTRTCAL SWITCHES. AFFECTED $
ITT BARTON MODEL 289 PRESSURE DIFFERENTIAL SWITCHES FAILED TO ACTUATE AT TRIP POINT DUE TO DIRT ACCU *1ULATION IN ELECTRTCAL SWITCHES. AFFECTED $
WITCHES READJUSTED TO PROPER TRIP POINTS. SURVEILiANCE TEST SATISFACTOR ILY COMPLETED. TRIP SETTINGS BEING CHECKED ON A MONTHLY BASIS. REDESIG N OF SYSTEM BEING EVALUATED.
WITCHES READJUSTED TO PROPER TRIP POINTS. SURVEILiANCE TEST SATISFACTOR ILY COMPLETED.
TRIP SETTINGS BEING CHECKED ON A MONTHLY BASIS.
REDESIG N OF SYSTEM BEING EVALUATED.


t
t MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 44 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
,    MAR 26. 1981                                                             LER MONTHLY REPORT SORTED BY FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS                                       PAGE 44 FACILITY / SYSTEM / COMPONENT /             DOCKET NO./           EVENT DATE/
DOCKET NO./
COMPONENT SUBCODE/CAUSE CODE / LER NO./                           REPORT DATE/                                 EVENT DESCRIPTION /
EVENT DATE/
CAUSE SUBCODE/ MANUFACTURER                 CONTROL NO.           REPORT TYPE                                   CAUSE DESCRIPTION FT. ST. VRAIN-1                                     05000267             010881 COOLANT RECIRC SYS + CONTROLS                     81-007/01T-0           020381     WHILE EVALUATING PCRV COOLING WATER SYSTEM DATA IN PREPARATION OF A REPO COMPONENT CODE NOT APPLICABLE                              036201        2-WEEK      RTABLE OCCURRENCE. IT WAS DETERMINED THAT A VIOLATION OF AN LCO HAD OCCU SUBCOMPONENT NOT APPLICABLE                                                       RRED RATHER THAN OPERATION IN A DEGRADED MODE AS WAS ORIGINALLY BELIEVED PERSONNEL ERROR                                                                      . LOOP 2 INLET 3 OUTLET AVG. TEMP WAS < 100 F. FROM 0430 HRS ON 1/3/81 UNTIL 1000 HRS ON=1/10/81 CONTRARY TO LCO 4.2.15(E) 2 REPORT ABL E PER T/         '
COMPONENT SUBCODE/CAUSE CODE / LER NO./
LICENSED 8 SENIOR OPERATORS ITEM NOT APPLICABLE                                                                S AC 7.5.2(B32. PREVIOUS OPERATION < 100 F WAS REPORTED IN 79-07 2 77-28
REPORT DATE/
                                                                                            . NO CONSEQUENCES OF THIS EVENT 4 NO EFFECT ON PUBLIC HEALTH 1 SAFETY.
EVENT DESCRIPTION /
CAUSE OF THE EVENT WAS FAILURE TO MAINTAIN SUFFICIENT HEAT INPUT TO THE COOLING SYSTEM FROM THE SURGE TANK HEATING COILS. LOW HEAT INPUT ALLOWED C00 LINO WATER SYSTEM TEMP TO DECREASE BELOW LCO LIMIT WHILE REACTOR WAS SHUTDOWN. ALL LICENSED OPERATORS WILL BE REINSTRUCTED IN PCRV COOLING W FT. ST. VRAIN-1                                      05000267            011581      ATER SYSTEM OPERATION. EVAL OF EFFECTS ON TOP HEAD LINER MAT'l REQUESTED CIRCULATING WATER SYS + CON                       81-004/03L-0           021381     DURING A MAINTENANCE SNUTDOHN PERIOD. OPERATIONS PERSONNEL CHLORINATED T COMPONENT CODE NOT APPLICABLE                              036200                    HE CIRCULATING WATER SYSTEM AND COLLECTED THE PLANT LIQUID EFFLUENT SAMP 30-DAY     LE AS REQUIRED. THE SAMPLE INDICATED THAT THE RESIDUAL CHLORINE WAS IN SUBCOMPONENT NOT APPLICABLE                                                       EXCESS OF THE LCO NR 1.1 LIMIT. THIS IS REPORTABLE PER FORT ST. VRAIN T OTHER NOT APPLICABLE ECHNICAL SPECIFICATI0H AC 7.5.2(B)2. NO EFFECT ON PUBLIC HEALTH OR SAFE TY. NO ACCOMPANYING OCCURRENCE.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
ITEM NOT APPLICABLE CHLORINE CONSUMPTION IN CIRCULATING WATER SYSTEM IS A COMPLEX PROCESS DE PENDENT UPON SrVERAL VARIA3LES. AFTER HIGH RESIDUAL CHLORINE LEVEL IN PL ANT LIQUID EFFLUENT, PLANT CHEMIST CHECKED CHLORINATION SYSTE1 & COULD N OT IDENTIFY ANY CAUSE FOR HIGH CHLORINE LEVEL. SUBSEQUENT CHLORINATION 3 FT. ST. VRAIN-1                                      05000267                        SAMPLES DID NOT REVEAL A RECURRENCE OF THE HIGH CHLORINE LEVEL.
REPORT TYPE CAUSE DESCRIPTION FT. ST. VRAIN-1 05000267 010881 WHILE EVALUATING PCRV COOLING WATER SYSTEM DATA IN PREPARATION OF A REPO COOLANT RECIRC SYS + CONTROLS 81-007/01T-0 020381 RTABLE OCCURRENCE. IT WAS DETERMINED THAT A VIOLATION OF AN LCO HAD OCCU COMPONENT CODE NOT APPLICABLE 036201 2-WEEK RRED RATHER THAN OPERATION IN A DEGRADED MODE AS WAS ORIGINALLY BELIEVED SUBCOMPONENT NOT APPLICABLE
011781     DURING THE PERIOD FROM JANUARY 16, 1981 TO JANUARY 31, 1951. THE PLANT COOLANT RECIRC SYS + CONTROLS                     81-009/03L-0           021381 COMPONENT CODE NOT APPLICABLE                            036202        30-DAY WAS OPERATED IN A DEGRADED MODE OF LCO 4.2.10 ON FOUR OCCASICNS AND IN A SUBCOMPONENT NOT APPLICABLE                                                         DECRADED MODE OF LCO 4.2.11 ON ONE OCCASION. THESE EVENTS ARE REPORTABL OTHER                                                                                E PER FORT. ST. VRAIN TECH. SPEC. AC 7.5.2(B)2. THERE ARE NO PROBADLE CO NOT APPLICABLE                                                                    NSEQUENCES. THERE IS NO EFFECT ON PUBLIC HEALTH OR SAFETY. RELATED REPCR TS ARE: 77-36. 78-12, 78-18, 78-37     78-39, 79-01, 79-02. 79-24, 79-30 7 ITEM NOT APPLICABLE                                                                 9-45, 79-53. 80-11     80-19, 80-22, 30-25, 80-36, 80-59. 80-66,
. LOOP 2 INLET 3 OUTLET AVG. TEMP WAS < 100 F. FROM 0430 HRS ON 1/3/81 PERSONNEL ERROR UNTIL 1000 HRS ON=1/10/81 CONTRARY TO LCO 4.2.15(E) 2 REPORT ABL E PER T/
LICENSED 8 SENIOR OPERATORS S AC 7.5.2(B32. PREVIOUS OPERATION < 100 F WAS REPORTED IN 79-07 2 77-28 ITEM NOT APPLICABLE
. NO CONSEQUENCES OF THIS EVENT 4 NO EFFECT ON PUBLIC HEALTH 1 SAFETY.
CAUSE OF THE EVENT WAS FAILURE TO MAINTAIN SUFFICIENT HEAT INPUT TO THE COOLING SYSTEM FROM THE SURGE TANK HEATING COILS. LOW HEAT INPUT ALLOWED C00 LINO WATER SYSTEM TEMP TO DECREASE BELOW LCO LIMIT WHILE REACTOR WAS SHUTDOWN. ALL LICENSED OPERATORS WILL BE REINSTRUCTED IN PCRV COOLING W ATER SYSTEM OPERATION. EVAL OF EFFECTS ON TOP HEAD LINER MAT'l REQUESTED FT. ST. VRAIN-1 05000267 011581 DURING A MAINTENANCE SNUTDOHN PERIOD. OPERATIONS PERSONNEL CHLORINATED T CIRCULATING WATER SYS + CON 81-004/03L-0 021381 HE CIRCULATING WATER SYSTEM AND COLLECTED THE PLANT LIQUID EFFLUENT SAMP COMPONENT CODE NOT APPLICABLE 036200 30-DAY LE AS REQUIRED.
THE SAMPLE INDICATED THAT THE RESIDUAL CHLORINE WAS IN SUBCOMPONENT NOT APPLICABLE EXCESS OF THE LCO NR 1.1 LIMIT.
THIS IS REPORTABLE PER FORT ST. VRAIN T OTHER ECHNICAL SPECIFICATI0H AC 7.5.2(B)2.
NO EFFECT ON PUBLIC HEALTH OR SAFE NOT APPLICABLE TY.
NO ACCOMPANYING OCCURRENCE.
ITEM NOT APPLICABLE CHLORINE CONSUMPTION IN CIRCULATING WATER SYSTEM IS A COMPLEX PROCESS DE PENDENT UPON SrVERAL VARIA3LES. AFTER HIGH RESIDUAL CHLORINE LEVEL IN PL ANT LIQUID EFFLUENT, PLANT CHEMIST CHECKED CHLORINATION SYSTE1 & COULD N OT IDENTIFY ANY CAUSE FOR HIGH CHLORINE LEVEL. SUBSEQUENT CHLORINATION 3 SAMPLES DID NOT REVEAL A RECURRENCE OF THE HIGH CHLORINE LEVEL.
FT. ST. VRAIN-1 05000267 011781 DURING THE PERIOD FROM JANUARY 16, 1981 TO JANUARY 31, 1951. THE PLANT COOLANT RECIRC SYS + CONTROLS 81-009/03L-0 021381 WAS OPERATED IN A DEGRADED MODE OF LCO 4.2.10 ON FOUR OCCASICNS AND IN A COMPONENT CODE NOT APPLICABLE 036202 30-DAY DECRADED MODE OF LCO 4.2.11 ON ONE OCCASION. THESE EVENTS ARE REPORTABL SUBCOMPONENT NOT APPLICABLE E PER FORT. ST. VRAIN TECH. SPEC. AC 7.5.2(B)2. THERE ARE NO PROBADLE CO OTHER NSEQUENCES. THERE IS NO EFFECT ON PUBLIC HEALTH OR SAFETY. RELATED REPCR NOT APPLICABLE TS ARE: 77-36. 78-12, 78-18, 78-37 78-39, 79-01, 79-02. 79-24, 79-30 7
ITEM NOT APPLICABLE 9-45, 79-53. 80-11 80-19, 80-22, 30-25, 80-36, 80-59. 80-66,
* 80-75.
* 80-75.
IN ALL EVENTS, THE CAUSE WAS MOISTURE OUT-CASSING FROM THF. CORE GRAPHITE RESULTING FROM INCREASED POWER LEVEL. CORRECTIVE ACTION IN THE CASE OF LCO 4.2.10 DEGRADED MODE OPERATION WAS TO REDUCE AVERAGE CORE OUTLET TE MP BELOW 1200 F. MAKING THE LCO NOT APPLICABLE. PURIFICATION SYSTEM REM FT. ST. VRAIN-1                                                                      OVED MOISTURE TO CORRECT THE L CO 4.2.11 DEGRADED MODE OPERATION.
IN ALL EVENTS, THE CAUSE WAS MOISTURE OUT-CASSING FROM THF. CORE GRAPHITE RESULTING FROM INCREASED POWER LEVEL. CORRECTIVE ACTION IN THE CASE OF LCO 4.2.10 DEGRADED MODE OPERATION WAS TO REDUCE AVERAGE CORE OUTLET TE MP BELOW 1200 F. MAKING THE LCO NOT APPLICABLE. PURIFICATION SYSTEM REM OVED MOISTURE TO CORRECT THE L CO 4.2.11 DEGRADED MODE OPERATION.
05000267             012081     DURING A SHUTDOUN MAINTENANCE PERIOD, THE INSTRUMENT PERSONNEL PERFORMED ENGNRD SAFETY FEATR INSTR SYS                     81-005/03L-0           021981 INSTRUMENTATION + CONTROLS                              036233          30-DAY        THE PRIMARY COOL ANT PRESSURE SCRAM CALIBRATION AND FOUND THREE PRESSURE SENSOR / DETECTOR / ELEMENT                                                          TRANSMITTERS WERE INDICATING LOW PRES $URE 8 COULD HAVE CAUSED PRIMARY C COMPONENT FAILURE                                                                  00LANT HIGH PRESSURE SWITCHES TO TRIP ABOVE LIMITS OF LCO 4.4.1. TABLE 4
FT. ST. VRAIN-1 05000267 012081 DURING A SHUTDOUN MAINTENANCE PERIOD, THE INSTRUMENT PERSONNEL PERFORMED ENGNRD SAFETY FEATR INSTR SYS 81-005/03L-0 021981 THE PRIMARY COOL ANT PRESSURE SCRAM CALIBRATION AND FOUND THREE PRESSURE INSTRUMENTATION + CONTROLS 036233 30-DAY TRANSMITTERS WERE INDICATING LOW PRES $URE 8 COULD HAVE CAUSED PRIMARY C SENSOR / DETECTOR / ELEMENT 00LANT HIGH PRESSURE SWITCHES TO TRIP ABOVE LIMITS OF LCO 4.4.1.
                                                                                            .4-1     THIS IS BEING REPORTED PER FORT ST. VRAIN TECH. SPEC AC 7.5.2(B)1 INSTRUMENT                                                                           & AC 7.5.2(B)2. NO EFFECT ON PUBLIC HEALTH OR SAFETY. NO EFFECT ON PL' GENERAL ATOMIC CO.                                                                 ANT OPERATION. SIMILAR OCCURRENCES RO 79-57 AND RO 77-46.
TABLE 4 COMPONENT FAILURE
.4-1 THIS IS BEING REPORTED PER FORT ST. VRAIN TECH. SPEC AC 7.5.2(B)1 INSTRUMENT
& AC 7.5.2(B)2.
NO EFFECT ON PUBLIC HEALTH OR SAFETY.
NO EFFECT ON PL' GENERAL ATOMIC CO.
ANT OPERATION.
SIMILAR OCCURRENCES RO 79-57 AND RO 77-46.
LON PRESSURE SIGNALS WERE DUE TO INSTRUMENT DRIFT OF THE PRESSURE TRANSM ITTER. PRESSURE TRANSMITTERS WERE CALIBRATED 1 SURVEILLANCE TEST SUCCESS FULLY COMPLETED. ONCE A MONTH, ON A TEMPORARY BASIS. PRESSURE TRANSMITTE RS VOLTAGE OUTPUTS WILL BE CHECKED AGAINST REACTOR PRESSURE TO DETERf1INE IF FURTHER INSTRUMENT DRIFT IS OCCURRING.
LON PRESSURE SIGNALS WERE DUE TO INSTRUMENT DRIFT OF THE PRESSURE TRANSM ITTER. PRESSURE TRANSMITTERS WERE CALIBRATED 1 SURVEILLANCE TEST SUCCESS FULLY COMPLETED. ONCE A MONTH, ON A TEMPORARY BASIS. PRESSURE TRANSMITTE RS VOLTAGE OUTPUTS WILL BE CHECKED AGAINST REACTOR PRESSURE TO DETERf1INE IF FURTHER INSTRUMENT DRIFT IS OCCURRING.


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F MAR 26, 1981                                                       LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 45-PROCESSED DURING MARCH. 1981.FOR POWER REACTORS i
F MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 45-PROCESSED DURING MARCH. 1981.FOR POWER REACTORS i
FACILITY / SYSTEM / COMPONENT /         DOCKET NO./           EVENT DATE/
FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                       REPORT DATE/                                     EVENT DESCRIPTIDH/                                     r CAUSE SUBCODE/ MANUFACTURER             CONTROL NO.           REPORT TYPE                                     CAUSE DESCRIPTION'                                   1 FT. ST. VRAIN-1                               05000267                 012081   DURING THE ANNUAL CALIBRATION OF THE PRIMARY COOLANT DEWPOINT NOISTURE M OHITOR FLOW INSTRUMENTATION,-IT WAS DISCOVERED THAT FIVE OF THE SAMPLE F ENGNRD SAFETY FEATR INSTR SYS              81-010/03L-0              021981 INSTRUMENTATION + CONTROLS                     036234                 30-DAY   LOW CIRCUITS WERE OUT OF CALIBRATION EITHER BEFORE OR AFTER-THE CALIBRAT-               i ION PROCEDURE WAS COMPLETED. THIS IS REPORTABLE PER FORT ST. VRAIN TECH-S ENSOR/DET ECTOR/ EL EMENT COMPONENT FAILURE                                                               . SPEC. AC 7.5.2(B)1 AS' SETPOINTS BEING LESS CONSERVATIVE THAN REQUIRED INSTRUMENT                                                                     BY THE LCO AND BY TECH. SPEC. AC 7.5.2(B)2 AS A DEGRADED MODE OF THE LCO j           HASTINGS RAYDIST                                                                 . NO SIMILAR REPORTABLE OCCURRENCES.                                                   :
DOCKET NO./
'                                                                                            CAUSE OF FLOW TRANSMITTERS BEING OUT OF TOLERANCE WAS CHANGE OF THE INST               l RUMENT CHARACTERISTICS. THE CALIBRATION VALUES WERE REVISED AND THE FLO                 '
EVENT DATE/
W TRANSMITTERS RECALIBRATED. THE ALARM SETPOINT FUNCTIONAL TEST VALUES-r                                                                                            WERE ALSO CHANGED TO VERIFY FLOWS AS REQUIRED BY LOC 4.4.1 NOTE (T).
COMPONENT SUBCODE/CAUSE CODE / LER NO./
FT. ST. VRAIN-1                               05000267                 012181   ON JANUARY 21, 1981.'WITH THE REACTOR OPERATING AT APPROXIMATELY 40% THE i           OTHER AUX SYSTEMS + CONTROLS               .81-011/03L-0               021981   RMAL POWER, THE LIQUID HITROGEN STORAGE TANK LEVEL WAS DETERMINED TO BE
REPORT DATE/
;          COMPONENT CODE NOT APPLICABLE                 036235                 30-DAY   LESS THAN THE MINIMUM 650 GALLONS REQUIRED BY TECHNICAL SPECIFICATICHS.
EVENT DESCRIPTIDH/
;            SUBCOMPONENT NOT APPLICABLE                                                     DEGRADED MODE OF LCO 4.2.12. REPORTABLE PER FORT ST. VRAIN TECHNICAL-SP l           OTHER                                                                           ECIFICATION AC'7.5.2(B)2. N0' ACCOMPANYING OCCURRENCE OR PROBABLE CONSEQ
r CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
: i.          NOT APPLICABLE                                                                 UENCE. NO EFFECT ON THE PUBLIC HEALTH OR SAFETY. SIMILAR-0CCURRENCE RO ITEM NOT APPLICABLE                                                               80-39.
REPORT TYPE CAUSE DESCRIPTION' 1
;                                                                                            SYSTEM USAGE AND LATE DELIVERY OF A SCHEDULED LIQUID HITROGEN DELIVERY R               i t                                                                                           ESULTED IN LIQUID HITROGEN STORAGE TANK LEVEL BEING LESS THAN REQUIRED B Y TECHNICAL SPECIFICATIONS. RECEIPT OF THE SCHEDULED DELIVERY RESTORED STORAGE TANK LEVELS TO ACCEPTABLE ~ VALUES. A SECOND LOAD WAS ORDERED AND DELIVERED,TO TOP OFF THE STORAGE TANK.
FT. ST. VRAIN-1 05000267 012081 DURING THE ANNUAL CALIBRATION OF THE PRIMARY COOLANT DEWPOINT NOISTURE M ENGNRD SAFETY FEATR INSTR SYS 81-010/03L-0 021981 OHITOR FLOW INSTRUMENTATION,-IT WAS DISCOVERED THAT FIVE OF THE SAMPLE F INSTRUMENTATION + CONTROLS 036234 30-DAY LOW CIRCUITS WERE OUT OF CALIBRATION EITHER BEFORE OR AFTER-THE CALIBRAT-i S ENSOR/DET ECTOR/ EL EMENT ION PROCEDURE WAS COMPLETED. THIS IS REPORTABLE PER FORT ST. VRAIN TECH-COMPONENT FAILURE
FT. ST. VRAIN-1                               05000267                 020351   ON TUESDAY, FEBRUARY 3,     1981 AT 1115 HOURS, IT WAS DETERMINED'THAT THE OTHER SYSTEMS                               81-013/01T-0               021781   CONCENTR ATION OF TRITIUM IN AN UNRESTRICTED AREA FOLLOWING LIQUID WASTE -
. SPEC. AC 7.5.2(B)1 AS' SETPOINTS BEING LESS CONSERVATIVE THAN REQUIRED INSTRUMENT BY THE LCO AND BY TECH. SPEC. AC 7.5.2(B)2 AS A DEGRADED MODE OF THE LCO j
OTHER COMPONENTS                               036203                 2-WEEK   RELEASE 429. WHICH WAS MADE CH JANUARY.23 AND 24, 1981 EXCEEDED THE LIM SUBCOMPONENT NOT APPLICABLE                                                     IT SPECIFIED IN LCO 4.8.2(A). REPCRTABLE PER FORT ST. VRAIN TECH. SPEC.
HASTINGS RAYDIST
DESIGN / FABRICATION ERROR                                                         AC 7.5.2(A)2. HO' ACCOMPANYING OCCURRENCE. HO EFFECT ON PUBLIC HEALTH DESIGN                                                                         OR SAFETY. REPORTABLE OCCURRENCE RO 80-52 AND REPORT ABLE OCCURRENCE RO .
. NO SIMILAR REPORTABLE OCCURRENCES.
l           OTHER                                                                           80-67 DEAL WITH A RELATED SUBJECT AREA.                                               - i THE DESIGN OF THE FORT ST. VRAIN LIQUID WASTE DISCHARGE SYSTEM WAS INADE QUATE TO AVOID PROBLEMS ARISING FROM :THE EXISTENCE OF AN OIL' SEPARATOR 0 -
CAUSE OF FLOW TRANSMITTERS BEING OUT OF TOLERANCE WAS CHANGE OF THE INST l
l N THE LIQUID WASTE DISCHARGE LINE. LIQUID WASTE RELEASES SUSPENDED. BY                 '
RUMENT CHARACTERISTICS. THE CALIBRATION VALUES WERE REVISED AND THE FLO W TRANSMITTERS RECALIBRATED. THE ALARM SETPOINT FUNCTIONAL TEST VALUES-WERE ALSO CHANGED TO VERIFY FLOWS AS REQUIRED BY LOC 4.4.1 NOTE (T).
t                                                                                          PASS INSTALLED AROUND THE OIL SEPARATORJ SDP CHANGED TO PROVIDE FOR USE 0F BYPASS. FLUSH OF DEAD LEG PIPING.
r FT. ST. VRAIN-1 05000267 012181 ON JANUARY 21, 1981.'WITH THE REACTOR OPERATING AT APPROXIMATELY 40% THE i
H. B. ROBINSON-2                               05000261               '121680   SPECIAL REPORT - THE ENGINE DRIVEN FIRE PUMP WAS REMOVED FROM SERVICE TO FIRE PROTECTION SYS + CONT ~               80-000/13X-0               011481     CHANGE THE PRIME MOVER FROM A PROPANE ENGINE'TO A DIESEL ENGINE PER HRC-IN3TRUMENTATION + CONTROLS                     033752                 OTHER       REQUIREMENTS. BECAUSE OF THE CHANGE. THE OPERABILITY PERIODIC TEST HAD SWITCH                                                                           TO BE DELAYED. WHEN THE OPERABILITY TEST WAS PERFORMED, THE ENGINE DRI-COMPONENT FAILURE                                                               VEN FIRE PUMP FAILED TO START. ALTERNATE FIRE PUMP:WAS OPERABLE.                         ,
OTHER AUX SYSTEMS + CONTROLS
INSTRUMENT                                                                                                                                                             !
.81-011/03L-0 021981 RMAL POWER, THE LIQUID HITROGEN STORAGE TANK LEVEL WAS DETERMINED TO BE COMPONENT CODE NOT APPLICABLE 036235 30-DAY LESS THAN THE MINIMUM 650 GALLONS REQUIRED BY TECHNICAL SPECIFICATICHS.
MERCOID CORP                                                                                           -
SUBCOMPONENT NOT APPLICABLE DEGRADED MODE OF LCO 4.2.12.
THE PUMP FAILED TO START BECAUSE OF A DEFECTIVE PRESSURE SWITCH ON THE F -
REPORTABLE PER FORT ST. VRAIN TECHNICAL-SP l
IRE PUMP' CONTROLLER. A NEW PRESSURE SWITCH WAS INSTALLED AND THE ENGINE DRIVEN FIRE PUMP WAS VERIFIED TO BE OPERABLE ON 12/24/80. TIME LIMIT 0 F 7 DAYS FOR OPERABILITY TESTING PEh TECHNICAL SPECIFICATION 3.14.2.2.
OTHER ECIFICATION AC'7.5.2(B)2.
N0' ACCOMPANYING OCCURRENCE OR PROBABLE CONSEQ NOT APPLICABLE UENCE. NO EFFECT ON THE PUBLIC HEALTH OR SAFETY.
SIMILAR-0CCURRENCE RO i.
ITEM NOT APPLICABLE 80-39.
g SYSTEM USAGE AND LATE DELIVERY OF A SCHEDULED LIQUID HITROGEN DELIVERY R i
t ESULTED IN LIQUID HITROGEN STORAGE TANK LEVEL BEING LESS THAN REQUIRED B Y TECHNICAL SPECIFICATIONS. RECEIPT OF THE SCHEDULED DELIVERY RESTORED STORAGE TANK LEVELS TO ACCEPTABLE ~ VALUES. A SECOND LOAD WAS ORDERED AND DELIVERED,TO TOP OFF THE STORAGE TANK.
FT. ST. VRAIN-1 05000267 020351 ON TUESDAY, FEBRUARY 3, 1981 AT 1115 HOURS, IT WAS DETERMINED'THAT THE OTHER SYSTEMS 81-013/01T-0 021781 CONCENTR ATION OF TRITIUM IN AN UNRESTRICTED AREA FOLLOWING LIQUID WASTE -
OTHER COMPONENTS 036203 2-WEEK RELEASE 429. WHICH WAS MADE CH JANUARY.23 AND 24, 1981 EXCEEDED THE LIM SUBCOMPONENT NOT APPLICABLE IT SPECIFIED IN LCO 4.8.2(A).
REPCRTABLE PER FORT ST. VRAIN TECH. SPEC.
DESIGN / FABRICATION ERROR AC 7.5.2(A)2.
HO' ACCOMPANYING OCCURRENCE. HO EFFECT ON PUBLIC HEALTH DESIGN OR SAFETY.
REPORTABLE OCCURRENCE RO 80-52 AND REPORT ABLE OCCURRENCE RO.
l OTHER 80-67 DEAL WITH A RELATED SUBJECT AREA.
THE DESIGN OF THE FORT ST. VRAIN LIQUID WASTE DISCHARGE SYSTEM WAS INADE
- i QUATE TO AVOID PROBLEMS ARISING FROM :THE EXISTENCE OF AN OIL' SEPARATOR 0 -
l N THE LIQUID WASTE DISCHARGE LINE.
LIQUID WASTE RELEASES SUSPENDED. BY PASS INSTALLED AROUND THE OIL SEPARATORJ SDP CHANGED TO PROVIDE FOR USE t
0F BYPASS. FLUSH OF DEAD LEG PIPING.
H. B. ROBINSON-2 05000261
'121680 SPECIAL REPORT - THE ENGINE DRIVEN FIRE PUMP WAS REMOVED FROM SERVICE TO FIRE PROTECTION SYS + CONT ~
80-000/13X-0 011481 CHANGE THE PRIME MOVER FROM A PROPANE ENGINE'TO A DIESEL ENGINE PER HRC-IN3TRUMENTATION + CONTROLS 033752 OTHER REQUIREMENTS. BECAUSE OF THE CHANGE. THE OPERABILITY PERIODIC TEST HAD SWITCH TO BE DELAYED. WHEN THE OPERABILITY TEST WAS PERFORMED, THE ENGINE DRI-COMPONENT FAILURE VEN FIRE PUMP FAILED TO START.
ALTERNATE FIRE PUMP:WAS OPERABLE.
INSTRUMENT MERCOID CORP THE PUMP FAILED TO START BECAUSE OF A DEFECTIVE PRESSURE SWITCH ON THE F -
IRE PUMP' CONTROLLER. A NEW PRESSURE SWITCH WAS INSTALLED AND THE ENGINE DRIVEN FIRE PUMP WAS VERIFIED TO BE OPERABLE ON 12/24/80.
TIME LIMIT 0 F 7 DAYS FOR OPERABILITY TESTING PEh TECHNICAL SPECIFICATION 3.14.2.2.
i.
i.
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: m. mm.
                                                                                                                                                        ,m-w. +E,       - # .-- -- d
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.-- -- d


l MAR 26, 1981                                         LER MONTHLY REPORT SORTED BY FACILITY                                                       .PAGE 46-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./   EVENT DATE/
l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY
    -COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                               EVENT DESCRIPTION /
.PAGE 46-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION H. B. ROBINSON-2                         05000261     010981     ON 1/9/81. WITH UNIT AT 100% POWER, IT WAS DETERMINED THAT OPERATION OF OTHR INST SYS REQD FOR SAFETY         81-001/01T-0   012381     UNIT ON 1/7/81, WITH RPI SYSTEM INPUT TO TURBINE RUNBACK & AUTO ROD WITH INSTRUMENTATION + CONTROLS               036214       2-WEEK     DRAWAL DEFEATED 8 POWER RANGE CHANNEL N41 INPUT GUT-OF-SERVICE IS CONTRA SENSOR / DETECTOR / ELEMENT                                     RY TO ASSUMPTIONS IN SAFETY ANALYSIS PREPARED DURING FUEL RELCAD SAFETY DEFECTIVE PROCEDURES                                             EVALUATION. STILL THE PROBABILITY OF NOT SENSING A DROPPED ROD IS SMALL NOT APPLICABLE                                                 SINCE THREE OF THE POWER RANGE DETECTORS HERE OPERALLE. REPORTABLE PER T WESTINGHOUSE ELECTRIC CORP.                                     ECH. SPEC. 6.9.2.A(6). NO ADVERSE CONSEQUENCES RESULTED FROM CONDITION.
DOCKET NO./
H. B. ROBINSON UNIT 2 FSAR & FUEL RELOAD SAFETY EVALUATION IDENTIFIED TH AT ROD DROP ANALYSIS ASSUMES THAT TURBINE RUNBACK OCCURS 8 THAT AUTO RCD WITHDRAWAL IS DEFEATED. NO PROCEDURES EXISTED TO PREVENT BYPASSING BOTH SIMULTANEOUSL
EVENT DATE/
-COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION H.
B.
ROBINSON-2 05000261 010981 ON 1/9/81. WITH UNIT AT 100% POWER, IT WAS DETERMINED THAT OPERATION OF OTHR INST SYS REQD FOR SAFETY 81-001/01T-0 012381 UNIT ON 1/7/81, WITH RPI SYSTEM INPUT TO TURBINE RUNBACK & AUTO ROD WITH INSTRUMENTATION + CONTROLS 036214 2-WEEK DRAWAL DEFEATED 8 POWER RANGE CHANNEL N41 INPUT GUT-OF-SERVICE IS CONTRA SENSOR / DETECTOR / ELEMENT RY TO ASSUMPTIONS IN SAFETY ANALYSIS PREPARED DURING FUEL RELCAD SAFETY DEFECTIVE PROCEDURES EVALUATION. STILL THE PROBABILITY OF NOT SENSING A DROPPED ROD IS SMALL NOT APPLICABLE SINCE THREE OF THE POWER RANGE DETECTORS HERE OPERALLE. REPORTABLE PER T WESTINGHOUSE ELECTRIC CORP.
ECH. SPEC. 6.9.2.A(6). NO ADVERSE CONSEQUENCES RESULTED FROM CONDITION.
H.
B.
ROBINSON UNIT 2 FSAR & FUEL RELOAD SAFETY EVALUATION IDENTIFIED TH AT ROD DROP ANALYSIS ASSUMES THAT TURBINE RUNBACK OCCURS 8 THAT AUTO RCD WITHDRAWAL IS DEFEATED. NO PROCEDURES EXISTED TO PREVENT BYPASSING BOTH SIMULTANEOUSL


==Y. PROCEDURE==
==Y. PROCEDURE==
S ARE BEING DEVELOPED TO PROHIBIT HAVING BOTH RPI BOTTOM INDICATION SYSTEM 3 1 POWER RANGE DETECTOR 005'SIMULTANECUSLY H. B. ROBINS 0H-2                       05000261     011381     A REVIEW OF SERV'CE WATER SYSTEM REVEALED A POTENTI AL UNtt0NITORED RELEAS STATION SERV WATER SYS + CONT         81-002/01T-0   012781     E PATH TO ENVIR0uMENT. THIS IS DUE TO LACK OF RADIATION MONITORING ON S INSTRUMENTATION + CONTROLS               036215       2-WEEK     ERVICE WATER RETURN LINES FROM CONTAINMENT FOR 4 HVH MOTOR COOLERS (FAN CONTROLLER                                                     COOLER RETURHS ARE MONITORED). THEREFORE, AN UNMONITORED RELEASE PATH FO DESIGN / FABRICATION ERROR                                       R ACTIVITY FROM CONTAINMENT COULD RESULT WHEN POST ACCIDENT CONTAINMENT DESIGN                                                         PRESS IS ABOVE SERVICE WATER SYSTEMS PRESS & THERE EXISTS A SYS LEAK INS OTHER                                                           IDE CONT AINITENT. REPORTABLE PER TECH. SPEC. 6.9.2.A.(9).
S ARE BEING DEVELOPED TO PROHIBIT HAVING BOTH RPI BOTTOM INDICATION SYSTEM 3 1 POWER RANGE DETECTOR 005'SIMULTANECUSLY H.
B. ROBINS 0H-2 05000261 011381 A REVIEW OF SERV'CE WATER SYSTEM REVEALED A POTENTI AL UNtt0NITORED RELEAS STATION SERV WATER SYS + CONT 81-002/01T-0 012781 E PATH TO ENVIR0uMENT. THIS IS DUE TO LACK OF RADIATION MONITORING ON S INSTRUMENTATION + CONTROLS 036215 2-WEEK ERVICE WATER RETURN LINES FROM CONTAINMENT FOR 4 HVH MOTOR COOLERS (FAN CONTROLLER COOLER RETURHS ARE MONITORED). THEREFORE, AN UNMONITORED RELEASE PATH FO DESIGN / FABRICATION ERROR R ACTIVITY FROM CONTAINMENT COULD RESULT WHEN POST ACCIDENT CONTAINMENT DESIGN PRESS IS ABOVE SERVICE WATER SYSTEMS PRESS & THERE EXISTS A SYS LEAK INS OTHER IDE CONT AINITENT. REPORTABLE PER TECH. SPEC. 6.9.2.A.(9).
CONFIGURATION IS A RESULT OF ORIGINAL SYSTEM DESIGN. SERVICE WATER CYSTE M INSIDE CONTAINMLHT IS BEING INSPECTED DAILY FOR LEAKS. AS A FOLLOW-UP TO IE BULLETIN 80-24, SERVICE WATER SYSTEM TO CONTAINMENT, INCLUDING FAN COOLER PIPING CONFIGURATION, IS UNDERGOING A THOROUGH REVIEW. ADDITIONA L CORRECTIVE ACT13N IS EXPECTED AS A RESULT OF THIS REVIEW.
CONFIGURATION IS A RESULT OF ORIGINAL SYSTEM DESIGN. SERVICE WATER CYSTE M INSIDE CONTAINMLHT IS BEING INSPECTED DAILY FOR LEAKS. AS A FOLLOW-UP TO IE BULLETIN 80-24, SERVICE WATER SYSTEM TO CONTAINMENT, INCLUDING FAN COOLER PIPING CONFIGURATION, IS UNDERGOING A THOROUGH REVIEW. ADDITIONA L CORRECTIVE ACT13N IS EXPECTED AS A RESULT OF THIS REVIEW.
H. B. ROBINS 0H-2                       05000261     011481     ON JANUARY 24, 1981, IT WAS DETERMINED THAT BOTH CHANNELS OF HEAT TRACIN CHEM, VOL CONT + LIQ POISN SYS       81-003/01T-0   012881     G FOR BOTH BORIC ACID TRANSFER PUMPS WERE INOPERABLE CONTRARY TO TECH. S CIRCUIT CLOSERS / INTERRUPTERS           036216       2-WEEK     PEC. 3.2.3.B. A REDUCTICH OF REACTOR POWER WAS IMMEDIATELY COMMENCED. T CIRCUIT BREAKER                                               HE SITUATION WAS CORRECTED APPROXIMATELY FIVE MINUTES AFTER ITS DISCOVER DEFECTIVE PROCEDURES                                             Y AND THE UNIT WAS RETURNED TO FULL POWER.                   NO ADVERSE CONSEQUENCES RESU NOT APPLICABLE                                                 LTED FROM THIS CONDITIvN. THIS CONSTITUTES A REPORTABLE OCCURRENCE AS P WESTINGHOUSE ELECTRIC CORP.                                     ER TECHNICAL SPECIFICATION 6.9.2.A.2.
H. B.
ROBINS 0H-2 05000261 011481 ON JANUARY 24, 1981, IT WAS DETERMINED THAT BOTH CHANNELS OF HEAT TRACIN CHEM, VOL CONT + LIQ POISN SYS 81-003/01T-0 012881 G FOR BOTH BORIC ACID TRANSFER PUMPS WERE INOPERABLE CONTRARY TO TECH. S CIRCUIT CLOSERS / INTERRUPTERS 036216 2-WEEK PEC.
3.2.3.B.
A REDUCTICH OF REACTOR POWER WAS IMMEDIATELY COMMENCED. T CIRCUIT BREAKER HE SITUATION WAS CORRECTED APPROXIMATELY FIVE MINUTES AFTER ITS DISCOVER DEFECTIVE PROCEDURES Y AND THE UNIT WAS RETURNED TO FULL POWER.
NO ADVERSE CONSEQUENCES RESU NOT APPLICABLE LTED FROM THIS CONDITIvN.
THIS CONSTITUTES A REPORTABLE OCCURRENCE AS P WESTINGHOUSE ELECTRIC CORP.
ER TECHNICAL SPECIFICATION 6.9.2.A.2.
CONDITION WAS PRIMARILY CAUSED BY A MISLEADING STEP IN PROCEDURE USED TO TAKE "A" BORIC ACID TRANSFER PUMP 005 WHICH RESULTED IN DEENERGIZING OF HEAT TRACING TO BOTH BORIC ACID TRANSFER PUMPS. CONTRIBUTING TO CAUSE W AS FACT THAT OP FAILED TO VERIFY THAT ONLY DESIRED CIRCUIT WOULD BE DEEN ERGIZED PRIOR TO OPENING BREAKERS. REV PROC TO CLARIFY MISLEADING STEP.
CONDITION WAS PRIMARILY CAUSED BY A MISLEADING STEP IN PROCEDURE USED TO TAKE "A" BORIC ACID TRANSFER PUMP 005 WHICH RESULTED IN DEENERGIZING OF HEAT TRACING TO BOTH BORIC ACID TRANSFER PUMPS. CONTRIBUTING TO CAUSE W AS FACT THAT OP FAILED TO VERIFY THAT ONLY DESIRED CIRCUIT WOULD BE DEEN ERGIZED PRIOR TO OPENING BREAKERS. REV PROC TO CLARIFY MISLEADING STEP.
H. B. ROBINSON-2                         05000261     011681     AT 1228 HRS., DURING NORMAL OPER ON 1-16-81, INDICATION OF LEAKAGE TO CC PROCESS SAMPLING SYSTEMS             81-004/03L-0   021381     W SYS PROMPTED A RCS LEAK RATE TEST WHICH VERIFIED                     2.37 GPM LEAKAGE AT HEAT EXCHANGERS                         036217       30-DAY       1244 HRS. SUBSEQ INVESTIGATION REVEALED A LEAK PATH FROM PRESSURIZER T COOLER                                                         HROUGH PRES $URIZER LIQUID SPACE SAMPLE COOLER TO CCW SYS VIA A LEAKING T COMPONENT FAILURE                                               UBE BUNDLE IN SAMPLE COOLER. SAMPLE LINE ISOL & LEAKAGE TERMINATED AT 12 NATURAL END OF LIFE                                           45. LEAKAGE CONTRARY TO T.S. 3.1.5.2 8 REPORTABLE PER T.S. 6.9.2.B(2).
H.
SENTRY EQUIPMENT CORP.                                           LEAKAGE TOTALLY CONTAINED WITHIN A CLOSED PLANT RADIDACTIVE SYSTEM.
B. ROBINSON-2 05000261 011681 AT 1228 HRS., DURING NORMAL OPER ON 1-16-81, INDICATION OF LEAKAGE TO CC PROCESS SAMPLING SYSTEMS 81-004/03L-0 021381 W SYS PROMPTED A RCS LEAK RATE TEST WHICH VERIFIED 2.37 GPM LEAKAGE AT HEAT EXCHANGERS 036217 30-DAY 1244 HRS.
ROOT CAUSE OF EVENT WAS S*MPLE COOLER TUBE BUNDLE LEAKAGE BELIEVED DUE'T 0 NORMAL OPERATIONAL WEAR. IMMEDIATE CORRECTIVE ACTION TAKEN TO ELIMINA TE LEAKAGE WAS CLOSURE OF SAMPLE LINE ISOLATION VALVES. SAMPLE COOLER T
SUBSEQ INVESTIGATION REVEALED A LEAK PATH FROM PRESSURIZER T COOLER HROUGH PRES $URIZER LIQUID SPACE SAMPLE COOLER TO CCW SYS VIA A LEAKING T COMPONENT FAILURE UBE BUNDLE IN SAMPLE COOLER. SAMPLE LINE ISOL & LEAKAGE TERMINATED AT 12 NATURAL END OF LIFE 45.
'                                                                  UBE DUNDLE WAS SUBSEQ REPLACED TO PREVENT RECURRENCE. ADDL EVAL OF EVEN T WILL BE CONDUCTED TO DETERMINE IF FURTHER CORRECTIVE ACTION IS APPROP.
LEAKAGE CONTRARY TO T.S.
                                  -  -    -. w g                                                               _ _ _ _ __.__ _
3.1.5.2 8 REPORTABLE PER T.S.
6.9.2.B(2).
SENTRY EQUIPMENT CORP.
LEAKAGE TOTALLY CONTAINED WITHIN A CLOSED PLANT RADIDACTIVE SYSTEM.
ROOT CAUSE OF EVENT WAS S*MPLE COOLER TUBE BUNDLE LEAKAGE BELIEVED DUE'T 0 NORMAL OPERATIONAL WEAR.
IMMEDIATE CORRECTIVE ACTION TAKEN TO ELIMINA TE LEAKAGE WAS CLOSURE OF SAMPLE LINE ISOLATION VALVES.
SAMPLE COOLER T UBE DUNDLE WAS SUBSEQ REPLACED TO PREVENT RECURRENCE. ADDL EVAL OF EVEN T WILL BE CONDUCTED TO DETERMINE IF FURTHER CORRECTIVE ACTION IS APPROP.
w g


MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 47 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./     EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 47 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./           REPORY DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO.     REPORT TYPE                                   CAUSE DESCRIPTION H. B. ROBINSON-2                         05000261       0129?1     ON t/29/81, AT 0624 HOURS, A SPURIOUS SAFEGUARDS ACTUATION & REACTOR TRI-CHEM, VOL CONT + LIQ POISH SYS       81-005/01T-0     021281     P WERE RECEIVED FROM A HIGH STEAM FLOW SPIKE CAUSED BY TURBINE GOVERNOR PIPES, FITTINGS                           036136       2-WEEK     VALVE /E-H OIL PROBLEMS.-SHORTLY THEREAFTER. LETDOWN FLOW WAS RESTORED 3 LESS THAN 4 INCHES                                               RCS PRESSURE BEGAN DECREASING WITH CONTAINMENT PRESSURE 2 DEW POINT INCR COMPONENT FAILURE                                                 EASING. UPON CONTAINTIENT ENTRY, A LETDONN LINE DRAIN VALVE (CVCS-200E) W MECHANICAL                                                       AS FOUND PARTIALLY OPENED 1 LEAKING THROUGH WITH ITS PIPE END-CAP MISSIN EBASCO SERVICES INC.                                               G. LEAK RATE WITH LETDOUN UNISOLATED WAS ESTIMATED AT APPROX. 100 GPM.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORY DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION H.
B. ROBINSON-2 05000261 0129?1 ON t/29/81, AT 0624 HOURS, A SPURIOUS SAFEGUARDS ACTUATION & REACTOR TRI-CHEM, VOL CONT + LIQ POISH SYS 81-005/01T-0 021281 P WERE RECEIVED FROM A HIGH STEAM FLOW SPIKE CAUSED BY TURBINE GOVERNOR PIPES, FITTINGS 036136 2-WEEK VALVE /E-H OIL PROBLEMS.-SHORTLY THEREAFTER. LETDOWN FLOW WAS RESTORED 3 LESS THAN 4 INCHES RCS PRESSURE BEGAN DECREASING WITH CONTAINMENT PRESSURE 2 DEW POINT INCR COMPONENT FAILURE EASING. UPON CONTAINTIENT ENTRY, A LETDONN LINE DRAIN VALVE (CVCS-200E) W MECHANICAL AS FOUND PARTIALLY OPENED 1 LEAKING THROUGH WITH ITS PIPE END-CAP MISSIN EBASCO SERVICES INC.
G.
LEAK RATE WITH LETDOUN UNISOLATED WAS ESTIMATED AT APPROX. 100 GPM.
VALVE CVCS-200E IS A NORMALLY CLOSED DRAIN VALVE WITH A PIPE CAP DN 00TL ET. PROBABLE CAUSE IS ATTRIBUTED TO VALVE VIBRATING OPEN & PIPE CAP. WHI' CH WAS SERVING AS A PRESSURE BOUNDARY, FAILING TO HOLD FOLLOUING FIRST S I. APPROX. 4500-6000 GALS.. OF WATER LEAKED TO CONTAINMENT SUMP DURING EV ENT.
VALVE CVCS-200E IS A NORMALLY CLOSED DRAIN VALVE WITH A PIPE CAP DN 00TL ET. PROBABLE CAUSE IS ATTRIBUTED TO VALVE VIBRATING OPEN & PIPE CAP. WHI' CH WAS SERVING AS A PRESSURE BOUNDARY, FAILING TO HOLD FOLLOUING FIRST S I. APPROX. 4500-6000 GALS.. OF WATER LEAKED TO CONTAINMENT SUMP DURING EV ENT.
HADDAM NECK-1                           05000213       121780     DN 12/17/80, 1,023 FISH WERE IMPINGED ON THE INTAKE       SCREENS; 1,004 SPOTT ULTIMATE HEAT SINK FACILITIES         8 ?-0 01/04X-0   011381     AIL SHINERS WITH 19 OTHER FISH REPRESENTING 6 OTHER       SPECIES, 24 HOUR PER COMPONENT CODE NOT APPLICABLE             036236       OTHER     IOD. ON 12/18 8 12/19, 5,896 SPOTTAIL SHINERS WITH       80 OTHER FISH REPRES SUBCOMPONENT NOT APPLICABLE                                       ENTING 7 SPFCIES WERE IMPINGED, (22 HOUR PERIOD).         -SUBSEQUENT 24 HOUR C0 EXTERNAL CAUSE                                                   UNTS WERE 285, 436. 156 AND 394 FISH IMPINGED.
HADDAM NECK-1 05000213 121780 DN 12/17/80, 1,023 FISH WERE IMPINGED ON THE INTAKE SCREENS; 1,004 SPOTT ULTIMATE HEAT SINK FACILITIES 8 ?-0 01/04X-0 011381 AIL SHINERS WITH 19 OTHER FISH REPRESENTING 6 OTHER SPECIES, 24 HOUR PER COMPONENT CODE NOT APPLICABLE 036236 OTHER IOD.
ON 12/18 8 12/19, 5,896 SPOTTAIL SHINERS WITH 80 OTHER FISH REPRES SUBCOMPONENT NOT APPLICABLE ENTING 7 SPFCIES WERE IMPINGED, (22 HOUR PERIOD). -SUBSEQUENT 24 HOUR C0 EXTERNAL CAUSE UNTS WERE 285, 436. 156 AND 394 FISH IMPINGED.
NOT APPLICABLE ITEM NOT APPLICABLE INCREASED IMPINGEMENT RATES OF SPOTTAIL SHINER $ HAVE BEEN NOTED IN PREVI 005 YEARS DURING THE DECEMBER-JANUARY PERIOD. SCHOOLING HABIT OF THIS F ISH PLUS FREEZING OF TRIBUTARIES MAY HAVE RESULTED IN AN UNEVEN SPATIAL DISTRIBUTION IN THE RIVER.
NOT APPLICABLE ITEM NOT APPLICABLE INCREASED IMPINGEMENT RATES OF SPOTTAIL SHINER $ HAVE BEEN NOTED IN PREVI 005 YEARS DURING THE DECEMBER-JANUARY PERIOD. SCHOOLING HABIT OF THIS F ISH PLUS FREEZING OF TRIBUTARIES MAY HAVE RESULTED IN AN UNEVEN SPATIAL DISTRIBUTION IN THE RIVER.
HUMBOLDT BAY                             05000133       122280   WITH NUCLEAR UNIT SHUTDOWN, A BREAKER SUPPLYING ELECTRICAL POWER TO 1 0F AC ONSITE POWER SYS + CONTROLS       80-008/03L-0     012181       4 SCREEN WASH PUMPS IN ADJACENT FOSSIL UNITS FAILED. TIP OF A MOVABLE C CIRCUIT CLOSERS / INTERRUPTERS           033719       30-DAY   ONTACT HAD BROKEN OFF. THESE PUMPS ARE BACKUP SOURCES OF COOLING WATER T CONTACTOR                                                       0 SUPPRESSION POOL COOLER. ALL 4 PUMPS HAVE SAME TYPE BREAKER. THIS IS R COMPONENT FAILURE                                                 EPORTADLE UNDER T. S. IX.I.2.B.(2), & HAS BEEN SUBJECT OF LERS 80-0348 ELECTRICAL                                                       0-04. THERE WERE NO ADVERSE EFFECTS FROM THIS EVENT; ALTERNATE COOLING S
HUMBOLDT BAY 05000133 122280 WITH NUCLEAR UNIT SHUTDOWN, A BREAKER SUPPLYING ELECTRICAL POWER TO 1 0F AC ONSITE POWER SYS + CONTROLS 80-008/03L-0 012181 4 SCREEN WASH PUMPS IN ADJACENT FOSSIL UNITS FAILED. TIP OF A MOVABLE C CIRCUIT CLOSERS / INTERRUPTERS 033719 30-DAY ONTACT HAD BROKEN OFF. THESE PUMPS ARE BACKUP SOURCES OF COOLING WATER T CONTACTOR 0 SUPPRESSION POOL COOLER. ALL 4 PUMPS HAVE SAME TYPE BREAKER. THIS IS R COMPONENT FAILURE EPORTADLE UNDER T.
!  GENERAL ELECTRIC CO.                                             00RCES WERE AVAILABLE EVEN THOUGH NOT NEEDED BECAUSE OF LENGTH OF SHUTDW CONTACTS ARE BELIEVED TO HAVE FAILED FROM SHOCK OF REPEATED CYCLING (ERE               '
S.
AKER WAS OVER 22 YEARS OLD). BREAKER IS G.E. TYPE AK-1-15; CONTACT PART HUMBER 6372777G1, CONTACTS WERE REPLACED. FINAL ACTION IS TO REPLACE A LL SUCH BREAKERS WITH NEWER MODEL PRIOR TO POWER OPERATION.
IX.I.2.B.(2), & HAS BEEN SUBJECT OF LERS 80-0348 ELECTRICAL 0-04. THERE WERE NO ADVERSE EFFECTS FROM THIS EVENT; ALTERNATE COOLING S GENERAL ELECTRIC CO.
INDIAN POINT-2                           05000247       122380   DURING PERFORMANCE OF 1HE HYDRAULIC SNUBEER FUNCTIONAL TEST PROGRAM, IT-OTHER SYSTEMS                         80-017/03L-0     012081   WAS DETERMINED THAT 5 0F THE FIRST 10 SNUBBERS TESTED DID NOT MEET THE A HANGERS, SUPPORTS, SHOCK SUPPRSS         G33720       30-DAY   CCEPTANCE CRITERIA ESTABLISHED BY CON EDISDN FOR LOCK-UP RATE AND BLEED.
00RCES WERE AVAILABLE EVEN THOUGH NOT NEEDED BECAUSE OF LENGTH OF SHUTDW CONTACTS ARE BELIEVED TO HAVE FAILED FROM SHOCK OF REPEATED CYCLING (ERE AKER WAS OVER 22 YEARS OLD).
SNUBBERS                                                           THE FUNCTIONAL TEST PROGRAM-IS CONTINUING. UPON COMPLETION OF THE PROG COMPONENT FAILURE                                                 RAM, THE RESULTS WILL BE EVALUATED FOR APPROFRIATE ACTION. RELATED EVEN MECHANICAL                                                       T: LER 78-9.
BREAKER IS G.E.
BERGEN-PATTERSON PIPE SUPPORT PRELIMINARY RESULTS OF THE HYDRAULIC SNUBBER FUNCTIONAL TEST PROGRAM IND ICATE SEVERAL BERGEN-PATTERSON HYDRAULIC SNUBBERS MODEL HSSA-3-6, DID H OT MEET THE FUNCTIONAL TEST ACCEPTANCE CRITERIA. DEFECTIVE SNUBBERS WIL L BE REPLACED. A REVISED LER WILL BE SUBMITTED FOLLOWING TEST PROGRAM'C OMPLETION.
TYPE AK-1-15; CONTACT PART HUMBER 6372777G1, CONTACTS WERE REPLACED. FINAL ACTION IS TO REPLACE A LL SUCH BREAKERS WITH NEWER MODEL PRIOR TO POWER OPERATION.
w
INDIAN POINT-2 05000247 122380 DURING PERFORMANCE OF 1HE HYDRAULIC SNUBEER FUNCTIONAL TEST PROGRAM, IT-OTHER SYSTEMS 80-017/03L-0 012081 WAS DETERMINED THAT 5 0F THE FIRST 10 SNUBBERS TESTED DID NOT MEET THE A HANGERS, SUPPORTS, SHOCK SUPPRSS G33720 30-DAY CCEPTANCE CRITERIA ESTABLISHED BY CON EDISDN FOR LOCK-UP RATE AND BLEED.
_      ,          _.                          -                                      ,      _                      _m___
SNUBBERS THE FUNCTIONAL TEST PROGRAM-IS CONTINUING. UPON COMPLETION OF THE PROG COMPONENT FAILURE RAM, THE RESULTS WILL BE EVALUATED FOR APPROFRIATE ACTION. RELATED EVEN MECHANICAL T: LER 78-9.
BERGEN-PATTERSON PIPE SUPPORT PRELIMINARY RESULTS OF THE HYDRAULIC SNUBBER FUNCTIONAL TEST PROGRAM IND ICATE SEVERAL BERGEN-PATTERSON HYDRAULIC SNUBBERS MODEL HSSA-3-6, DID H OT MEET THE FUNCTIONAL TEST ACCEPTANCE CRITERIA.
DEFECTIVE SNUBBERS WIL L BE REPLACED. A REVISED LER WILL BE SUBMITTED FOLLOWING TEST PROGRAM'C OMPLETION.
w m


i MAR 26,.1981                                         LER MONTHLY REPORT SORTED MY FACILITY-                                           PAGE 48 PROCESSED DURING MARCH, 1981 FOR F0WER REACTORS                                                   i FACILITY / SYSTEM / COMPONENT /   DOCKET NO./   EVENT DATE/
i MAR 26,.1981 LER MONTHLY REPORT SORTED MY FACILITY-PAGE 48 PROCESSED DURING MARCH, 1981 FOR F0WER REACTORS i
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                               EVENT DESCRIPTION /                               '
FACILITY / SYSTEM / COMPONENT /
i CAUSE SUBCCDE/ MANUFACTURER     ' CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION f
DOCKET NO./
INDIAN POINT-2                           05000247     010681     DURING CYCLE 4/5 FUEL SHUFFLE OPERATIONS, GRID STRAP DAMAGE IN THE FORM REACTOR CORE                         81-002/99X-0   011581     0F TORN OR MISSING CORNERS HAS BEEN OBSERVED ON A NUMBER OF FUEL ASSEMBL FUEL ELEMENTS                           036204     OTHER     IES. NO DAMAGE TO THE FUEL CLADDING HAS BEEN IDENTIFIED.
EVENT DATE/
SUBCOMPONENT NOT APPLICABLE COMPONENT FAILURE
COMPONENT SUBCODE/CAUSE CODE / LER NO./
,        MECHANICAL WESTINGHOUSE ELECTRIC' CORP.
REPORT DATE/
EVENT DESCRIPTION /
i' CAUSE SUBCCDE/ MANUFACTURER
' CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION f
INDIAN POINT-2 05000247 010681 DURING CYCLE 4/5 FUEL SHUFFLE OPERATIONS, GRID STRAP DAMAGE IN THE FORM REACTOR CORE 81-002/99X-0 011581 0F TORN OR MISSING CORNERS HAS BEEN OBSERVED ON A NUMBER OF FUEL ASSEMBL FUEL ELEMENTS 036204 OTHER IES.
NO DAMAGE TO THE FUEL CLADDING HAS BEEN IDENTIFIED.
SUBCOMPONENT NOT APPLICABLE COMPONENT FAILURE MECHANICAL WESTINGHOUSE ELECTRIC' CORP.
THE CAUSE OF GRID STRAP DAMAGE TO WESTINGHOUSE 15 X 15 (9 GRID) FUEL ASS EMBLIES AND CORRECTIVE ACTIONS REQUIRED ARE UNDER EVALUATION. A REVISED LER WILL BE SUBMITTED FOLLOWING COMPLETION OF THESE EVALUATIONS.
THE CAUSE OF GRID STRAP DAMAGE TO WESTINGHOUSE 15 X 15 (9 GRID) FUEL ASS EMBLIES AND CORRECTIVE ACTIONS REQUIRED ARE UNDER EVALUATION. A REVISED LER WILL BE SUBMITTED FOLLOWING COMPLETION OF THESE EVALUATIONS.
INDIAN POINT-2                           05000247     011881     DURING A REFUELING MAINTENANCE OUTAGE. IT WAS NOTED IN THE COURSE OF CON OTHER COOLANT SUBSYS + CONTROL       81-004/03L-0   0Z1881     DUCTING SURVEILLANCE TEST PT-R35. INSERVICE VALVE TEST, THAT THE OPENING VALVES                                   036238     30-DAY       TIME FOR ONE OF THE TWC POWER OPERATED RELIEF VALVES, PCV-456 WAS 2.5 GLOBE                                                         SECONDS LONGER THAN PERMITTED BY THE TEST ACCEPT ANCE CRITERI A. THE REDU OTHER                                                           NDANT VALVE, PCV-455C, FUNCTIONED AS REQUIRED.
INDIAN POINT-2 05000247 011881 DURING A REFUELING MAINTENANCE OUTAGE. IT WAS NOTED IN THE COURSE OF CON OTHER COOLANT SUBSYS + CONTROL 81-004/03L-0 0Z1881 DUCTING SURVEILLANCE TEST PT-R35. INSERVICE VALVE TEST, THAT THE OPENING VALVES 036238 30-DAY TIME FOR ONE OF THE TWC POWER OPERATED RELIEF VALVES, PCV-456 WAS 2.5 GLOBE SECONDS LONGER THAN PERMITTED BY THE TEST ACCEPT ANCE CRITERI A.
THE REDU OTHER NDANT VALVE, PCV-455C, FUNCTIONED AS REQUIRED.
NOT APPLICABLE OTHER THE EVENT CAUSE AND REQUIRED CORRECTIVE ACTIONS ARE UNDER INVESTIGATION.
NOT APPLICABLE OTHER THE EVENT CAUSE AND REQUIRED CORRECTIVE ACTIONS ARE UNDER INVESTIGATION.
A REVISED LER WILL BE ISSUED FOLLOWING INVESTIGATION COMPLETION.
A REVISED LER WILL BE ISSUED FOLLOWING INVESTIGATION COMPLETION.
P INDIAN POINT-2                           05000247     011981     DURING A REFUELING MAINTENANCE OUTAGE, IT WAS NOTED IN THE COURSE OF CON COOL SYS FOR REAC AUX + CONT         81-003/03L-0   021881   . DUCTING SURVEILLANCE TEST PT-R35.-INSERVICE VALVE TEST THAT THE SHUTOFF' VALVES                                   036237     30-DAY       VALVE, NO. 822B, IN THE COMPONENT COOLING WATER RETURN FROM NO. 21 RHR GATE                                                         HEAT EXCHANGER. WOULD NOT FULLY OPEN (TECHNICAL SPECIFICATION 3.3).           THE OTHER                                                             REDUNDANT VALVE, NO. 822A, FUNCTIONED AS REQUIRED.
P INDIAN POINT-2 05000247 011981 DURING A REFUELING MAINTENANCE OUTAGE, IT WAS NOTED IN THE COURSE OF CON COOL SYS FOR REAC AUX + CONT 81-003/03L-0 021881
. DUCTING SURVEILLANCE TEST PT-R35.-INSERVICE VALVE TEST THAT THE SHUTOFF' VALVES 036237 30-DAY VALVE, NO. 822B, IN THE COMPONENT COOLING WATER RETURN FROM NO. 21 RHR GATE HEAT EXCHANGER. WOULD NOT FULLY OPEN (TECHNICAL SPECIFICATION 3.3).
THE OTHER REDUNDANT VALVE, NO. 822A, FUNCTIONED AS REQUIRED.
NOT APPLICABLE OTHER THE EVENT CAUSE AND REQUIRED CORRECTIVE ACTIONS ARE UNDER INVESTIGATION.
NOT APPLICABLE OTHER THE EVENT CAUSE AND REQUIRED CORRECTIVE ACTIONS ARE UNDER INVESTIGATION.
A REVISED LER WILL BE ISSUED FOLLOWING INVESTIGATION COMPLETION.
A REVISED LER WILL BE ISSUED FOLLOWING INVESTIGATION COMPLETION.
l INDIAN POINT-2                           05000'247   012081     DURING A REVIEW OF THE VIDEO INSPECTION TAPE OF FUEL ASSEMBLY NO. E-42,-
l INDIAN POINT-2 05000'247 012081 DURING A REVIEW OF THE VIDEO INSPECTION TAPE OF FUEL ASSEMBLY NO.
REACTOR CORE                         81-005/01T-0   020381     IT WAS DETERMINED THAT THERE WAS AN APPARENT CLAD PERFORATION ON A FUEL.
E-42,-
FUEL ELEMENTS                           036205     2-WEEK     ROD WITHIN THE ASSEMBLY. THIS DEFECT IS NOT EXPECTED TO DEGRADE DURING SUBCOMPONENT NOT APPLICABLE                                   FURTHER ASSEMBLY USE NOR WOULD IT BE EXPECTED TO RESULT IN SIGNIFICANT C COMPONENT FAILURE                                             00LANT ACTIVITY.
REACTOR CORE 81-005/01T-0 020381 IT WAS DETERMINED THAT THERE WAS AN APPARENT CLAD PERFORATION ON A FUEL.
FUEL ELEMENTS 036205 2-WEEK ROD WITHIN THE ASSEMBLY. THIS DEFECT IS NOT EXPECTED TO DEGRADE DURING SUBCOMPONENT NOT APPLICABLE FURTHER ASSEMBLY USE NOR WOULD IT BE EXPECTED TO RESULT IN SIGNIFICANT C COMPONENT FAILURE 00LANT ACTIVITY.
CORRUSION WESTINGHOUSE ELECTRIC CORP.
CORRUSION WESTINGHOUSE ELECTRIC CORP.
A PERFORATION OH A FUEL ROD WITHIN A WESTINGHOUSE 15 X 15 (9 GRID) FUEL ASSEMBLY H*S BEEN JUDGED T0-BE A HYDRIDE DEFECT. THE FUEL MANUFACTURER HAS REVIEUED THE DEFECT AND A DETERMINATION HAS BEEN MADE THAT NO CORREC-TIVE ACTION IS REQUIRED.
A PERFORATION OH A FUEL ROD WITHIN A WESTINGHOUSE 15 X 15 (9 GRID) FUEL ASSEMBLY H*S BEEN JUDGED T0-BE A HYDRIDE DEFECT. THE FUEL MANUFACTURER HAS REVIEUED THE DEFECT AND A DETERMINATION HAS BEEN MADE THAT NO CORREC-TIVE ACTION IS REQUIRED.


MAR 26, 1981                                         LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 49 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./     EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 49 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPCRT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION INDIAN POINT-3                           05000286   110980     SPECIAL REPORT - WHILE AT COLD SHUTDOWN, DURING' PERFORMANCE OF A RETEST EMERG CORE COOLING SYS + CONT       80-000/13X-0     120980     FOR A MODIFICATION TO THE ENGINEERED SAFETY FEATURES SYSTEM, TWO MESTING RELAYS                                   033751     OTHER     HOUSE MG-6 RELAYS IN TRAIN "A" FAILED TO LATCH MECHANICALLY AFTER RECEIP           '
EVENT DATE/
CONTROL, GENERAL PURPOSE                                       T OF THE SAFETY INJECTION ACTIVATION SIGNAL.       THIS CONDITION DOES NOT ON COMPONENT FAILURE                                               ITS OWN PREVENT THE SATISFACTORY OPERATION OF THE ENGINEERED SAFETY FEA ELECTRICAL                                                     TURES SYSTEM AND IS THEREFORE NOT REPORTABLE UNDER THE TECHNICAL SPECIFI WESTINGHOUSE ELECTRIC CORP.                                     CATIONS.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPCRT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION INDIAN POINT-3 05000286 110980 SPECIAL REPORT - WHILE AT COLD SHUTDOWN, DURING' PERFORMANCE OF A RETEST EMERG CORE COOLING SYS + CONT 80-000/13X-0 120980 FOR A MODIFICATION TO THE ENGINEERED SAFETY FEATURES SYSTEM, TWO MESTING RELAYS 033751 OTHER HOUSE MG-6 RELAYS IN TRAIN "A" FAILED TO LATCH MECHANICALLY AFTER RECEIP CONTROL, GENERAL PURPOSE T OF THE SAFETY INJECTION ACTIVATION SIGNAL.
THIS CONDITION DOES NOT ON COMPONENT FAILURE ITS OWN PREVENT THE SATISFACTORY OPERATION OF THE ENGINEERED SAFETY FEA ELECTRICAL TURES SYSTEM AND IS THEREFORE NOT REPORTABLE UNDER THE TECHNICAL SPECIFI WESTINGHOUSE ELECTRIC CORP.
CATIONS.
THE LATCH MECHANISMS ASSOCIATED WITH RELAYS CB-1 AND V-1 (WESTINGHOUSE S TYLE MG-6, MODEL NO. 289B36A11) WERE FOUND TO BE OUT OF ADJUSTMENT. THE SE WERE THEN READJUSTED TO PROVIDE MECHANICAL LATCH-UP FEATURE UPON SAFE TY INJECTION ACTIVATION SIGNAL, AS REQUIRED. NO SIMILAR EVENTS HAVE BEE N REPORTED TO DATE.
THE LATCH MECHANISMS ASSOCIATED WITH RELAYS CB-1 AND V-1 (WESTINGHOUSE S TYLE MG-6, MODEL NO. 289B36A11) WERE FOUND TO BE OUT OF ADJUSTMENT. THE SE WERE THEN READJUSTED TO PROVIDE MECHANICAL LATCH-UP FEATURE UPON SAFE TY INJECTION ACTIVATION SIGNAL, AS REQUIRED. NO SIMILAR EVENTS HAVE BEE N REPORTED TO DATE.
INDIAN POINT-3                           05000286   010881   WHILE OPERATING AT 100%, IT WAS IDENTIFIED THAT CUR SERVICE WATER RETURN CNTNMNT HEAT REMOV SYS + CONT       81-001/01T-0     012281     FROM THE CONTAINMENT FAN COOLER UNIT MOTOR COOLERS HAD NO DIRECT MEANS INSTRUMENTATION + CONTROLS               036206     2-WEEK     OF RADIATION MONITORING. THIS COULD LEAD TO A LEAKAGE OF RADI0 ACTIVITY CONTROLLER                                                     UPON THE. SIMULTANEOUS OCCURRENCE OF A LOCA, A MOTOR COOLER LEAK AND A CD DESIGN / FABRICATION ERROR                                     HTAINMENT PRESSURE BUILDUP. iHIS ASPECT OF THE SERVICE WATER SYSTEM IS DESIGN                                                         NOT INCLUDED IN'THE SAFETY ANALYSIS AND THE POTENTIAL FOR A FUTURE PROBL OTHER                                                           EM UNDER TECH SPEC 6.9.1.7.1 EXISTS.                                                 '
INDIAN POINT-3 05000286 010881 WHILE OPERATING AT 100%, IT WAS IDENTIFIED THAT CUR SERVICE WATER RETURN CNTNMNT HEAT REMOV SYS + CONT 81-001/01T-0 012281 FROM THE CONTAINMENT FAN COOLER UNIT MOTOR COOLERS HAD NO DIRECT MEANS INSTRUMENTATION + CONTROLS 036206 2-WEEK OF RADIATION MONITORING. THIS COULD LEAD TO A LEAKAGE OF RADI0 ACTIVITY CONTROLLER UPON THE. SIMULTANEOUS OCCURRENCE OF A LOCA, A MOTOR COOLER LEAK AND A CD DESIGN / FABRICATION ERROR HTAINMENT PRESSURE BUILDUP.
iHIS ASPECT OF THE SERVICE WATER SYSTEM IS DESIGN NOT INCLUDED IN'THE SAFETY ANALYSIS AND THE POTENTIAL FOR A FUTURE PROBL OTHER EM UNDER TECH SPEC 6.9.1.7.1 EXISTS.
A RADIATION MONITOR HAS BEEN ATTACHED TO THE RETURN PIPE IN ORDER TO DET ECT POTENTIAL RADI0 ACTIVE LEAKAGE INTO THE SERVICE WATER SYSTEM. ANALYS IS IS CURRENTLY UNDERWAY TO IN3 TALL A MORE PERMANENT SOLUTION TO THIS SI TUATION, PERFORMANCE OF THE PLANT WAS NOT AFFECTED BY THIS INCIDENT. H 0 SIMILAR EVENT HAS BEEN REPORTED TO DATE.
A RADIATION MONITOR HAS BEEN ATTACHED TO THE RETURN PIPE IN ORDER TO DET ECT POTENTIAL RADI0 ACTIVE LEAKAGE INTO THE SERVICE WATER SYSTEM. ANALYS IS IS CURRENTLY UNDERWAY TO IN3 TALL A MORE PERMANENT SOLUTION TO THIS SI TUATION, PERFORMANCE OF THE PLANT WAS NOT AFFECTED BY THIS INCIDENT. H 0 SIMILAR EVENT HAS BEEN REPORTED TO DATE.
INDIAN POINT-3                           05000286   011181     THE MAGNITUDE OF A PLANNED RELEASE WAS HIGHER THAN EXPECTED. THE RELEAS LIQ RADIDACT WSTE MANAGMNT SYS     81-001/04L-0     012181     E BEGAN AT 0038 AND LASTED UNTIL 0249 (131 MIN.). THE PEAK PERIOD WAS T PIPES FITTINGS                           036239     30-DAY     HE FIRST 10 MIN. WHEN ABOUT 25% OF THE ACTIVITY WAS RELEASED. ENVIRONME LESS THAN 4 INCHES                                             NTAL TECH. SPEC. LIMIT OF APP. B SECTION 2.4.2.A WAS NOT EXCEEDED. TOTA COMPONENT FAILURE                                               L NOBLE CAS RELEASED: 81.1 CI; 75.7% OF TECH. SPEC. LIMIT.       TOTAL IODINE MECHANICAL                                                     -131 RELEASED: 4.48E-6 CI; 0.02% OF TECH. SPEC. LIMIT.
INDIAN POINT-3 05000286 011181 THE MAGNITUDE OF A PLANNED RELEASE WAS HIGHER THAN EXPECTED. THE RELEAS LIQ RADIDACT WSTE MANAGMNT SYS 81-001/04L-0 012181 E BEGAN AT 0038 AND LASTED UNTIL 0249 (131 MIN.).
OTHER RELEASE OCCURRED WHILE PREPARING TO SAMPLE THE VOLUME CONTROL TANK.         .HE CAUSE WAS A LEAK IN A CONNECTING SAMPLING SYSTEM.
THE PEAK PERIOD WAS T PIPES FITTINGS 036239 30-DAY HE FIRST 10 MIN. WHEN ABOUT 25% OF THE ACTIVITY WAS RELEASED. ENVIRONME LESS THAN 4 INCHES NTAL TECH. SPEC. LIMIT OF APP. B SECTION 2.4.2.A WAS NOT EXCEEDED. TOTA COMPONENT FAILURE L NOBLE CAS RELEASED: 81.1 CI; 75.7% OF TECH. SPEC. LIMIT.
INDIAN POINT-3                           05000286   012481     WHILE OPERATING AT 100 PERCENT POWER, AT 0915 HOURS, THE OUTPUT FROM BAT EMERG GENERATOR SYS + CONTROLS     81-002/03L-0     021881     TERY CHARGER NO. 32 WAS OBSERVED TO BE DROPPING. AS THE CHARGER WAS NO BATTERIES + CHARGERS                     036207     30-DAY     LONGER CAPABLE OF SUPPLYING DC BUS LOADS FROM THE BATTERY, IT WAS DECLAR SUBCOMPONENT NOT APPLICABLE                                   ED INOPERABLE. TECH. SPEC. 3.7.A.6 REQUIRES ALL 3 BATTERY CHARGERS TO B DESIGN / FABRICATION ERROR                                     E OPERABLE WHEN THE REACTOR IS ABOVE COLD SHUTDOWN.       TECH. SPEC. 3.7.C.1 DESIGN                                                         REQUIRES DESCENT TO HOT SHUTDOWN UPON BATTERY CHARGER FAILURE. NO SIMI WESTINGHOUSE ELECTRIC CORP.                                     LAR EVENTS.
TOTAL IODINE MECHANICAL
DESCEN1 TO HOT SHUTDOWN WAS INITIATED, IN ACCORDANCE WITH THE REQUIREMEN TS OF TECH SPECS. AT 0930 HOURS THE VOLTAGE AND CURRENT CONTROLLER PC B OARD NO. S-1492A10G03 WAS REPLACED. BATTERY CHARGER NO. 32 WAS THEN DEC' LARED OPERABLE, AND THE PLANT RETURNED TO 1C0 PERCENT POWER.
-131 RELEASED: 4.48E-6 CI; 0.02% OF TECH. SPEC. LIMIT.
OTHER RELEASE OCCURRED WHILE PREPARING TO SAMPLE THE VOLUME CONTROL TANK.
.HE CAUSE WAS A LEAK IN A CONNECTING SAMPLING SYSTEM.
INDIAN POINT-3 05000286 012481 WHILE OPERATING AT 100 PERCENT POWER, AT 0915 HOURS, THE OUTPUT FROM BAT EMERG GENERATOR SYS + CONTROLS 81-002/03L-0 021881 TERY CHARGER NO. 32 WAS OBSERVED TO BE DROPPING. AS THE CHARGER WAS NO BATTERIES + CHARGERS 036207 30-DAY LONGER CAPABLE OF SUPPLYING DC BUS LOADS FROM THE BATTERY, IT WAS DECLAR SUBCOMPONENT NOT APPLICABLE ED INOPERABLE.
TECH. SPEC. 3.7.A.6 REQUIRES ALL 3 BATTERY CHARGERS TO B DESIGN / FABRICATION ERROR E OPERABLE WHEN THE REACTOR IS ABOVE COLD SHUTDOWN.
TECH. SPEC. 3.7.C.1 DESIGN REQUIRES DESCENT TO HOT SHUTDOWN UPON BATTERY CHARGER FAILURE. NO SIMI WESTINGHOUSE ELECTRIC CORP.
LAR EVENTS.
DESCEN1 TO HOT SHUTDOWN WAS INITIATED, IN ACCORDANCE WITH THE REQUIREMEN TS OF TECH SPECS.
AT 0930 HOURS THE VOLTAGE AND CURRENT CONTROLLER PC B OARD NO. S-1492A10G03 WAS REPLACED. BATTERY CHARGER NO. 32 WAS THEN DEC' LARED OPERABLE, AND THE PLANT RETURNED TO 1C0 PERCENT POWER.


MAR 26. 1981                                                               LER MONTHLY REPORT SORTED BY FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS                                             PAGE 50 FACILITY / SYSTEM / COMPONENT /             DOCKET NO./             EVENT DATE/
MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 50 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMP 9NENT SUBCODE/CAUSE CODE / LER NO./                             REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                 CONTROL NO.             REPORT TYPE                                 CAUSE DESCRIPTION JOSEPH M. FARLEY-1                                     05000348               110880 MAIN STEAM SUPPLY SYS + CONT                      80-079/03L-0 012381                ON 11/08/80 DURING PERFORMANCE OF FHP-1-STP-608.0 (MAIN STEAM LINE SAFET VALVES                                                  033671              30-DAY Y VALVE TEST) MAIN STEAM SAFETY VALVE Q1N11V010B FAILED TO MEET THE TECH GLOBE                                                                                NICAL SPECIFICATION 3.7.1.1 LIFT SETTING REQUIREMENTS (1101 PSIG ACTUAL-OTHER VS 1088 PSIG + 1 '4 REQUIRED). UPON DISCOVERY OF THE OUT OF SPEC. CONDITI
EVENT DATE/
'                                                                                        ON, THE VALVE WAS IMMEDIATELY ADJUSTED AND RETURNED TO SERVICE. HEALTH /
COMP 9NENT SUBCODE/CAUSE CODE / LER NO./
HOT APPLICABLE                                                                       SAFETY OF THE PUBLIC WERE NOT AFFECTED.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION JOSEPH M.
FARLEY-1 05000348 110880 ON 11/08/80 DURING PERFORMANCE OF FHP-1-STP-608.0 (MAIN STEAM LINE SAFET MAIN STEAM SUPPLY SYS + CONT 80-079/03L-0 012381 Y VALVE TEST) MAIN STEAM SAFETY VALVE Q1N11V010B FAILED TO MEET THE TECH VALVES 033671 30-DAY NICAL SPECIFICATION 3.7.1.1 LIFT SETTING REQUIREMENTS (1101 PSIG ACTUAL-GLOBE VS 1088 PSIG + 1 '4 REQUIRED). UPON DISCOVERY OF THE OUT OF SPEC. CONDITI OTHER ON, THE VALVE WAS IMMEDIATELY ADJUSTED AND RETURNED TO SERVICE. HEALTH /
HOT APPLICABLE SAFETY OF THE PUBLIC WERE NOT AFFECTED.
DRESSER INDUSTRIES, INC.
DRESSER INDUSTRIES, INC.
THIS INCIDENT IS ATTRIBUTABLE TO SETPOINT DRIFT. L ATE SUEMITT AL OF THIS LER IS DUE TO A PROCEDURAL INADEQ. WHICH FAILED TO ADEQ. SPECIFY IMMEDI ATE NOTIFICATION OF OUT OF SPEC. CONDITION TO OPER. PERSONNEL. THIS LAC K OF NOTIFICATION WAS DISCOVERED BY A QA AUDIT CN 12/30/80. A REVISION JOSEPH M. FARLEY-1                                    05000348                        WILL BE MADE TO SUR
THIS INCIDENT IS ATTRIBUTABLE TO SETPOINT DRIFT.
L ATE SUEMITT AL OF THIS LER IS DUE TO A PROCEDURAL INADEQ. WHICH FAILED TO ADEQ. SPECIFY IMMEDI ATE NOTIFICATION OF OUT OF SPEC. CONDITION TO OPER. PERSONNEL.
THIS LAC K OF NOTIFICATION WAS DISCOVERED BY A QA AUDIT CN 12/30/80.
A REVISION WILL BE MADE TO SUR


==V. PROCEDURE==
==V. PROCEDURE==
TO CLEARLY IDENTIFY NOTIFICATION REQMTS.
TO CLEARLY IDENTIFY NOTIFICATION REQMTS.
122580   AT 2350 ON 12/25/80, WITH THE PRESSURE VESSEL HEAD REMOVED FOR REFUELING RESIDUAL HEAT REMOV SYS + CONT                     80-080/03L-0             012881     . THE LOOP SUCTION VALVE FOR "B" TRAIN RHR CLOSED WHICH RESULTED IN THE WALVES                                                 033672               30-DAY     OPERATING "B" TRAIN RHR BECOMING INOPERABLE.
JOSEPH M.
GATE                                                                                                                                      TECH. SPEC. 3.9.8 REQUIRES OTHER AT LEAST ONE RHR LOOP TO BE IN OPERATION. TECH. SPEC. 3.9.8 ACTION STA TEMENT REQUIREMENTS WERE MET.     HEALTH / SAFETY OF THE PUBLIC WERE NOT AFFE NOT APPLICABLE                                                                       CTED BY THIS OCCURRENCE.
FARLEY-1 05000348 122580 AT 2350 ON 12/25/80, WITH THE PRESSURE VESSEL HEAD REMOVED FOR REFUELING RESIDUAL HEAT REMOV SYS + CONT 80-080/03L-0 012881 THE LOOP SUCTION VALVE FOR "B" TRAIN RHR CLOSED WHICH RESULTED IN THE WALVES 033672 30-DAY OPERATING "B" TRAIN RHR BECOMING INOPERABLE.
TECH. SPEC. 3.9.8 REQUIRES GATE AT LEAST ONE RHR LOOP TO BE IN OPERATION.
TECH. SPEC. 3.9.8 ACTION STA OTHER TEMENT REQUIREMENTS WERE MET.
HEALTH / SAFETY OF THE PUBLIC WERE NOT AFFE NOT APPLICABLE CTED BY THIS OCCURRENCE.
COPES-VULCAN, INC.
COPES-VULCAN, INC.
SUCTION VALVE WAS CLOSED BY A SIGNAL FROM REACTOR COOLANT SYS PRESSURE T RANSt1ITTER LOOP. LOOP WAS BEING DE-TERMINATED FROM ITS ELECT. PENETRATI ON WHILE ENERG. IN ORDER TO REPAIR PENETRATION WHEN INSTRUMENT LEADS WER.
SUCTION VALVE WAS CLOSED BY A SIGNAL FROM REACTOR COOLANT SYS PRESSURE T RANSt1ITTER LOOP.
E INADVERTENTLY SHORTED RESULTING IN CLOSING SIGNAL.       VLV WAS REOPENED &
LOOP WAS BEING DE-TERMINATED FROM ITS ELECT. PENETRATI ON WHILE ENERG. IN ORDER TO REPAIR PENETRATION WHEN INSTRUMENT LEADS WER.
JOSEPH M. FARLEY-1                                                                        RHR PUMP IB WAS RETURNED TO SERVICE AT 2355 ON 12/25/80.
E INADVERTENTLY SHORTED RESULTING IN CLOSING SIGNAL.
05000348             011681     AT 1429 OH 1-16-81, RHR FLOW WAS LOST AS A RESULT OF A LOSS OF POWER TO RESIDUAL HEAT REMOV SYS + CONT                     81- 0 01/ 0 3 L-0       021281     THE 1A RHR PU"F. (A LOSS OF POWER TO START-UP TRANSFORMER 1A DE-ENERGI CIRCUIT CLOSERS /IETERRUPrERS                         036102               30-DAY   ZED 416 0V. BUS 1F WHICH IN TURN CAUSED A LOSS OF POWER TO THE RHR PUMP).
VLV WAS REOPENED &
CIRCUIT BREAKER                                                                         TECH. SPEC. 3.4.1. IN PART, REQUIRES AT LEAST ONE RC LOOP TO BE IN OPER PERSONNEL ERROR                                                                       ATION WITH AN ASSOCIATED RC OR RHR PUMP. TECH. SPEC. 3.4.1 ACTION STATE MAINTENANCE 8 REPAIR f ERSONNEL                                                     MENT REQUIREMENTS WERE MET. HEALTH / SAFETY OF THE PUBLIC WERE NOT AFFECT OTHER                                                                                 ED.
RHR PUMP IB WAS RETURNED TO SERVICE AT 2355 ON 12/25/80.
POWER WAS LOST AS A RESULT OF A FEEDER BREAKER TO START-UP TRANSFORMER 1 A OPENING. NO RELAY TARGETS WERE ACTUATED ON START-UP TRANSFORMER SUPPLY BREAKER TO INDICATE REASON FOR TRIP. MAINT. ACTIVITY ONGOING IN VICINIT Y OF RELAY PROBABLY CAUSED BREAKER TO TRIP. DIESEL GENERATOR 1-2A ENERGI JOSEPH M. FARLEY-1 ZED BUS 1F 8 RHR PUMP WAS RESTARTED AT 1430 ON 1/16/8 1 05000348               020281   AS A RESULT OF INSPECTION ACTIVITIES ON THE J. M. FARLEY NUCLEAR PLANT U AC ONSITE POWER SYS + CONTROLS                     81-002/01T-0             020681   HIT 2. A GENERIC DEFICIENCY WAS IDENTIFIED WITH BROKEN PUFFER TUBES ON 4 CTRCUIT CLOSERS / INTERRUPTERS                         036055               2-WEEK     160V CIRCUIT BREAKERS. INVESTIGATION HAS REVEALED THAT FOLLOWING A TUBI CIRCUIT BREAKER                                                                     NG BREAK, THE TUBING INNER SUPPORT SPRING COULD MIGRATE FROM WITHIN THE COMPONENT FAILURE                                                                     TUBE TO ENERGIZED AREAS OF THE BREAKER CAUSING A PHASE TO GROUND FAULT.
JOSEPH M.
LLECTRICAL                                                                             THIS INFORMATION IS BEING SUBMITTED IN ACCORDANCE WITH TECH. SPEC. 6.9.
FARLEY-1 05000348 011681 AT 1429 OH 1-16-81, RHR FLOW WAS LOST AS A RESULT OF A LOSS OF POWER TO RESIDUAL HEAT REMOV SYS + CONT 81- 0 01/ 0 3 L-0 021281 THE 1A RHR PU"F.
AliIS CHALMERS                                                                         1.8.I AND 10 CFR 21.
(A LOSS OF POWER TO START-UP TRANSFORMER 1A DE-ENERGI CIRCUIT CLOSERS /IETERRUPrERS 036102 30-DAY ZED 416 0V. BUS 1F WHICH IN TURN CAUSED A LOSS OF POWER TO THE RHR PUMP).
THF 'UFFER TUBES BREAK AS A RESULT OF MATERIAL AGING. AS A PERMANENT CD RRECTIVE ACTION, PUFFER TUDES OF A DIFFERENT MATERIAL WILL BE USED TO RE PLACE ALL PUFFER TUBES. THE REPLACEMENT TUBES WILL BE EQUIPPED WITH COM PRESSION DEVICES TO RETAIN THE INNER SUPPORT SPRING IN THE EVENT OF TUBE FAILU?E.
CIRCUIT BREAKER TECH. SPEC.
3.4.1.
IN PART, REQUIRES AT LEAST ONE RC LOOP TO BE IN OPER PERSONNEL ERROR ATION WITH AN ASSOCIATED RC OR RHR PUMP.
TECH. SPEC. 3.4.1 ACTION STATE MAINTENANCE 8 REPAIR f ERSONNEL MENT REQUIREMENTS WERE MET.
HEALTH / SAFETY OF THE PUBLIC WERE NOT AFFECT OTHER ED.
POWER WAS LOST AS A RESULT OF A FEEDER BREAKER TO START-UP TRANSFORMER 1 A OPENING. NO RELAY TARGETS WERE ACTUATED ON START-UP TRANSFORMER SUPPLY BREAKER TO INDICATE REASON FOR TRIP. MAINT. ACTIVITY ONGOING IN VICINIT Y OF RELAY PROBABLY CAUSED BREAKER TO TRIP. DIESEL GENERATOR 1-2A ENERGI ZED BUS 1F 8 RHR PUMP WAS RESTARTED AT 1430 ON 1/16/8 1 JOSEPH M.
FARLEY-1 05000348 020281 AS A RESULT OF INSPECTION ACTIVITIES ON THE J. M. FARLEY NUCLEAR PLANT U AC ONSITE POWER SYS + CONTROLS 81-002/01T-0 020681 HIT 2. A GENERIC DEFICIENCY WAS IDENTIFIED WITH BROKEN PUFFER TUBES ON 4 CTRCUIT CLOSERS / INTERRUPTERS 036055 2-WEEK 160V CIRCUIT BREAKERS. INVESTIGATION HAS REVEALED THAT FOLLOWING A TUBI CIRCUIT BREAKER NG BREAK, THE TUBING INNER SUPPORT SPRING COULD MIGRATE FROM WITHIN THE COMPONENT FAILURE TUBE TO ENERGIZED AREAS OF THE BREAKER CAUSING A PHASE TO GROUND FAULT.
LLECTRICAL THIS INFORMATION IS BEING SUBMITTED IN ACCORDANCE WITH TECH. SPEC.
6.9.
AliIS CHALMERS 1.8.I AND 10 CFR 21.
THF 'UFFER TUBES BREAK AS A RESULT OF MATERIAL AGING.
AS A PERMANENT CD RRECTIVE ACTION, PUFFER TUDES OF A DIFFERENT MATERIAL WILL BE USED TO RE PLACE ALL PUFFER TUBES.
THE REPLACEMENT TUBES WILL BE EQUIPPED WITH COM PRESSION DEVICES TO RETAIN THE INNER SUPPORT SPRING IN THE EVENT OF TUBE FAILU?E.


MAR 26, 1981                                                     LER MONTHLY REPORT SORTED BY FACILITY                                                         PAGE St PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /     DOCKET NO./       EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE St PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 RFPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBC00E/ MANUFACTURER         CONTROL NO.       REPORT TYPE                                 CAUSE DESCRIPTION JOSEPH M. FARLEY-1                               05000348       020281     AT 1730 ON 2/2/81. RADIATION MONITOR R25B (FUEL STORAGE POOL AREA GASE00                                                           ,
EVENT DATE/
AIRBORNE RADIOACT MONITOR SYS             81-003/03L-0       022381     S ACTIVITY - VENTILATION SYSTEM ISOLATION) WAS DECLARED INOPERABLE DUE T                                                           '
COMPONENT SUBCODE/CAUSE CODE / LER NO./
PUMPS                                             036196       30-DAY     0 THE DRIVE BELT BREAKING. TECH. SPEC. SECTION 3.3.3.1 AND TABLE 3.3.6                                                             ,
RFPORT DATE/
VANE TYPE                                                             REQUIRES A MINIMUM OF TWO RADIATION MONITOR CHANNELS TO BE OPERABLE FOR                                                             ,
EVENT DESCRIPTION /
COMPONENT FAILURE                                                         THE FUEL STORAGE AREA. TECH. SPEC. 3.3.3.1 ACTION STATEMENT REQUIREMENT MECHANICAL                                                             S WERE MET. A SIMILAR OCCURRENCE WAS REPORTED IN LER 80-004/03L-0. HEA VICT0REEN INSTRUMENT DIV.                                                 LTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
CAUSE SUBC00E/ MANUFACTURER CONTROL NO.
R258 WAS DECL ARED INOPERABLE DUE TO ITS- DRIVE BELT BREAKING. THE BELT W AS REPLACED AND R25B WAS RETURNED TO SERVICE AT 1300 OH 2/5/81.
REPORT TYPE CAUSE DESCRIPTION JOSEPH M.
    %EWAUNEE-1                                       05000305       121280     WITH THE FACILITY AT 100% POWER, DURING THE TESTING OF 1B DIESEL GENERAT EMERG GENERATOR SYS + CONTROLS             80-042/03X-2 021281           OR (D/G), THE AIR START MOTORS FAILED TO DISENGAGE AFTER THE D/G STARTED VALVES                                           033512       OTHER       AND ALSO WHEN THE D/G WAS SHUTDOWN.           1A D/G WAS TESTED OPERABLE AND IB GLOBE                                                                 D/G WAS TAKEN OUT-OF-SERVICE PUTTING THE FACILITY UNDER LCO TECH. SPEC.
FARLEY-1 05000348 020281 AT 1730 ON 2/2/81. RADIATION MONITOR R25B (FUEL STORAGE POOL AREA GASE00 AIRBORNE RADIOACT MONITOR SYS 81-003/03L-0 022381 S ACTIVITY - VENTILATION SYSTEM ISOLATION) WAS DECLARED INOPERABLE DUE T PUMPS 036196 30-DAY 0 THE DRIVE BELT BREAKING.
COMPONENT FAILURE                                                         3.7.B.2 AND THUS REPORTABLE PER TECH. SPEC. 6.9.2.B.(2). THERE WAS NO E CORROSION                                                             FFECT ON PUBLIC SAFETY OR PLANT OPERATION.
TECH. SPEC. SECTION 3.3.3.1 AND TABLE 3.3.6 VANE TYPE REQUIRES A MINIMUM OF TWO RADIATION MONITOR CHANNELS TO BE OPERABLE FOR COMPONENT FAILURE THE FUEL STORAGE AREA.
TECH. SPEC. 3.3.3.1 ACTION STATEMENT REQUIREMENT MECHANICAL S WERE MET.
A SIMILAR OCCURRENCE WAS REPORTED IN LER 80-004/03L-0.
HEA VICT0REEN INSTRUMENT DIV.
LTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
R258 WAS DECL ARED INOPERABLE DUE TO ITS-DRIVE BELT BREAKING. THE BELT W AS REPLACED AND R25B WAS RETURNED TO SERVICE AT 1300 OH 2/5/81.
%EWAUNEE-1 05000305 121280 WITH THE FACILITY AT 100% POWER, DURING THE TESTING OF 1B DIESEL GENERAT EMERG GENERATOR SYS + CONTROLS 80-042/03X-2 021281 OR (D/G), THE AIR START MOTORS FAILED TO DISENGAGE AFTER THE D/G STARTED VALVES 033512 OTHER AND ALSO WHEN THE D/G WAS SHUTDOWN.
1A D/G WAS TESTED OPERABLE AND IB GLOBE D/G WAS TAKEN OUT-OF-SERVICE PUTTING THE FACILITY UNDER LCO TECH. SPEC.
COMPONENT FAILURE 3.7.B.2 AND THUS REPORTABLE PER TECH. SPEC. 6.9.2.B.(2).
THERE WAS NO E CORROSION FFECT ON PUBLIC SAFETY OR PLANT OPERATION.
WESTERN ENGINE CO.
WESTERN ENGINE CO.
CORROSION OF THE VALVE STEM AND DISC. FROM MOISTURE IN THE AIR SUPPLY. C AUSED VALVE TO STICK OPEN RESULTING IN A FAILURE OF AIR START MOTORS TO DISENGAGE. CORRODED PARTS WERE REPLACED 8 D/G RETURNED TO SERVICE WITHIN TIME LIMITS OF TECH. SPEC. 3.7.B.2. DESIGN CHANGE IS IN PROGRESS TO IN STALL AIR DRIERS IN D/G AIR START SYSTEM. NO FURTHER CORRECTIVE ACTIONS.
CORROSION OF THE VALVE STEM AND DISC. FROM MOISTURE IN THE AIR SUPPLY. C AUSED VALVE TO STICK OPEN RESULTING IN A FAILURE OF AIR START MOTORS TO DISENGAGE. CORRODED PARTS WERE REPLACED 8 D/G RETURNED TO SERVICE WITHIN TIME LIMITS OF TECH. SPEC.
KEWAUNEE-1                                       05000305       121680     DURING A REVIEW OF EQUIPMENT QUALIFICATIONS, AS REQUESTED BY IE BULLETIN CHEM. VOL CONT + LIQ POISN SYS             80-041/01X-2       020681     79-01B, THREE LIMIT SWITCHES HAVE BEEN IDENTIFIED THAT ARE NOT SEALED I INSTRUMENTATION + CONTROLS                       033430       OTHER     NSTALLATIONS. AND MAY BEC6FE SUBMERGED POST-LOCA. IN A SUBMERGED CONDIT SWITCH                                                                 ION THESE SWITCHES COULD DE SUSCEPTIBLE TO FAILURE POSSIBLY RESULTING IN DESIGN / FABRICATION ERROR                                                 AN INADVERTENT OPENING OF LETDOWN ISOLATION VALVES LD-4A/4B/4C UPON RES DESIGN                                                                 ET OF CONTAINMENT ISOLATION. EVENT IS REPORTABLE PER T.S. 6.9.2.A(9) &
3.7.B.2.
NAMCO CONTROLS                                                           IEB 79-01B. NO EFFECT ON PUBLIC SAFETY OR PLANT OPERATION.
DESIGN CHANGE IS IN PROGRESS TO IN STALL AIR DRIERS IN D/G AIR START SYSTEM. NO FURTHER CORRECTIVE ACTIONS.
AT DATE OF INSTALLATION, REQMT TO OPER IN A SUBMERGED CONDITION WAS NOT EVIDENT. TO ASSURE PROPER OPER OF ABOVE NAMED VLVS. CONTROL OPER HAVE B EEN INSTRUCTED TO PLACE CONTROL SWITCHES FOR LD-4A/4B/4C IN CLOSED POSIT IDH PRIOR TO RESETTING CONTAINMENT ISOL.           LIMIT SWITCHES WILL BE PROPERL Y SEALED DURING FJRST OUTAGE OF SUFFIC. DURATION AFTER RECEIPT OF EQUIP.
KEWAUNEE-1 05000305 121680 DURING A REVIEW OF EQUIPMENT QUALIFICATIONS, AS REQUESTED BY IE BULLETIN CHEM. VOL CONT + LIQ POISN SYS 80-041/01X-2 020681 79-01B, THREE LIMIT SWITCHES HAVE BEEN IDENTIFIED THAT ARE NOT SEALED I INSTRUMENTATION + CONTROLS 033430 OTHER NSTALLATIONS. AND MAY BEC6FE SUBMERGED POST-LOCA.
    %EWAUNEE-1                                       05000305       122380   WHEN ATTEMPTING TO RECIRCULATE BORIC ACID (BA) STORAGE TANKS PRIOR TO SA CHEM, VOL CONT + LIQ POISH SYS             80-043/03L-0       012281   MPLING, tA BA TRANSFER PUMP MOTOR TRIPPED ON OVERLOAD.                 TECH SPEC 3.2.C.
IN A SUBMERGED CONDIT SWITCH ION THESE SWITCHES COULD DE SUSCEPTIBLE TO FAILURE POSSIBLY RESULTING IN DESIGN / FABRICATION ERROR AN INADVERTENT OPENING OF LETDOWN ISOLATION VALVES LD-4A/4B/4C UPON RES DESIGN ET OF CONTAINMENT ISOLATION. EVENT IS REPORTABLE PER T.S. 6.9.2.A(9) &
PUMPS                                             033576       30-DAY     2 ALLOWS ONE BA TRANSFER PUMP OUT OF SERVICE 24 HOURS, PUTTING PLANT UND CENTRIFUGAL                                                           ER AN LCD REPORTABLE PER TECH. SPEC. 6.9.2.(B)2.             THIS EVENT IS SIMILAR COMPONENT FAILURE                                                           TO THAT REPORTED IN LER-80-043. THREE METHODS OF SUPPLYING BORATED WAT MECHANICAL                                                             ER TO REACTOR CORE WERE STILL AVAILABLE.           THERE WAS NO EFFECT ON PUBLIC GOULDS PUMPS INC.                                                         SAFETY OR FLANT OPERATION.
NAMCO CONTROLS IEB 79-01B.
PUMP MOTOR TRIP ON OVERLOAD HAS BEEN ATTRIBUTED TO BA CRYSTALLIZATION IN SEALS DURING PERIODS OF NON-USE.       SEAL DEGRADATION IS EVIDENT BY ABNOR MAL SEAL LEAKAGE. LEAKAGE DOES NOT PROHIBIT USE OF PUMP; PUMP WAS RESTA RTED AND RETURNED TO SERVICE WITHIN TIME LIMIT OF TS 3.2.C.2. PUMP SEAL S WILL BE REPLACED BY 2-1-81 NO FURTHER CORRECTIVE ACTIONS ARE REQUIRED
NO EFFECT ON PUBLIC SAFETY OR PLANT OPERATION.
AT DATE OF INSTALLATION, REQMT TO OPER IN A SUBMERGED CONDITION WAS NOT EVIDENT. TO ASSURE PROPER OPER OF ABOVE NAMED VLVS. CONTROL OPER HAVE B EEN INSTRUCTED TO PLACE CONTROL SWITCHES FOR LD-4A/4B/4C IN CLOSED POSIT IDH PRIOR TO RESETTING CONTAINMENT ISOL.
LIMIT SWITCHES WILL BE PROPERL Y SEALED DURING FJRST OUTAGE OF SUFFIC. DURATION AFTER RECEIPT OF EQUIP.
%EWAUNEE-1 05000305 122380 WHEN ATTEMPTING TO RECIRCULATE BORIC ACID (BA) STORAGE TANKS PRIOR TO SA CHEM, VOL CONT + LIQ POISH SYS 80-043/03L-0 012281 MPLING, tA BA TRANSFER PUMP MOTOR TRIPPED ON OVERLOAD.
TECH SPEC 3.2.C.
PUMPS 033576 30-DAY 2 ALLOWS ONE BA TRANSFER PUMP OUT OF SERVICE 24 HOURS, PUTTING PLANT UND CENTRIFUGAL ER AN LCD REPORTABLE PER TECH. SPEC. 6.9.2.(B)2.
THIS EVENT IS SIMILAR COMPONENT FAILURE TO THAT REPORTED IN LER-80-043.
THREE METHODS OF SUPPLYING BORATED WAT MECHANICAL ER TO REACTOR CORE WERE STILL AVAILABLE.
THERE WAS NO EFFECT ON PUBLIC GOULDS PUMPS INC.
SAFETY OR FLANT OPERATION.
PUMP MOTOR TRIP ON OVERLOAD HAS BEEN ATTRIBUTED TO BA CRYSTALLIZATION IN SEALS DURING PERIODS OF NON-USE.
SEAL DEGRADATION IS EVIDENT BY ABNOR MAL SEAL LEAKAGE.
LEAKAGE DOES NOT PROHIBIT USE OF PUMP; PUMP WAS RESTA RTED AND RETURNED TO SERVICE WITHIN TIME LIMIT OF TS 3.2.C.2.
PUMP SEAL S WILL BE REPLACED BY 2-1-81 NO FURTHER CORRECTIVE ACTIONS ARE REQUIRED


i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY                                                         PAGE 52 4
i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 52 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS 4
PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /       DOCKET NO./       EVENT DATE/
FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 REPORT DATE/                                           EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER           CONTROL NO.       REPORT TYPE                                             CAUSE DESCRIPTICH KEWAUNEE-1                                   0500030$         122980 REAC COOL CLEANUP SYS + CONT                                              THE RCS 02 SAMPLE TEST WAS PERFORMED ONLY TWICE DURING THE WEEK ENDING 1 80-044/03L-0       012881       2-26-80.       THIS IS NOT IN ACCORDANCE WITH THE SURVEILLANCE REQUIREMENTS 0 COMPONENT CODE NOT APPLICABLE               033721         30-DAY       F TECH. SPEC. 4.1.B 8 TABLE T.S. 4.1-2 WHICH REQUIRES SAMPLE TEST TO BE SUBCOMPONENT NOT APPLICABLE                                                                                                                                       l PERFORMED THREE TIMES PER WEEK, MININUM, WITH A MAXIMUM OF FOUR DAYS BET PERSONNEL ERROR OTHER                                                                    WEEN SAMPLE TESTS. MAXIMUM OF FOUR DAYS BETWEEN SAMPL E TESTS WAS NOT EX CEEDED.       SUBSEQUENT SAMPLE TESTS SHOWED 02 CONCENTRATIONS WITHIN T.S. LI ITEM NOT APPLICABLE                                                       MITS. THERE WAS NO EFFECT ON PUBLIC SAFETY OR PLANT OPERATION.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTICH KEWAUNEE-1 0500030$
122980 THE RCS 02 SAMPLE TEST WAS PERFORMED ONLY TWICE DURING THE WEEK ENDING 1 REAC COOL CLEANUP SYS + CONT 80-044/03L-0 012881 2-26-80.
THIS IS NOT IN ACCORDANCE WITH THE SURVEILLANCE REQUIREMENTS 0 COMPONENT CODE NOT APPLICABLE 033721 30-DAY F TECH. SPEC. 4.1.B 8 TABLE T.S. 4.1-2 WHICH REQUIRES SAMPLE TEST TO BE l
SUBCOMPONENT NOT APPLICABLE PERFORMED THREE TIMES PER WEEK, MININUM, WITH A MAXIMUM OF FOUR DAYS BET PERSONNEL ERROR WEEN SAMPLE TESTS. MAXIMUM OF FOUR DAYS BETWEEN SAMPL E TESTS WAS NOT EX OTHER CEEDED.
SUBSEQUENT SAMPLE TESTS SHOWED 02 CONCENTRATIONS WITHIN T.S.
LI ITEM NOT APPLICABLE MITS.
THERE WAS NO EFFECT ON PUBLIC SAFETY OR PLANT OPERATION.
FAILURE TO PERFORM SAMPLE TEST HAS BEEN ATTRIBUTED TO LACK OF SUFFICIENT INSTRUCTION, TO LAB PERSONNEL, BY CHEMISTRY SUPERVISION: THIS IS REPORT ABLE AS AN INADEQUACY IN IMPLEMENTATION OF PROCEDURAL CONTROLS (T.S. 6.9
FAILURE TO PERFORM SAMPLE TEST HAS BEEN ATTRIBUTED TO LACK OF SUFFICIENT INSTRUCTION, TO LAB PERSONNEL, BY CHEMISTRY SUPERVISION: THIS IS REPORT ABLE AS AN INADEQUACY IN IMPLEMENTATION OF PROCEDURAL CONTROLS (T.S. 6.9
                                                                                                                          .2.B.(3)).       PROCEDURE WAS REVIEWED WITH LAB PERSONNEL UITH EMPHASIS ON R KEWAUNEE-1 EQUIRED ANALYSIS. NO FURTHER CORRECTIVE ACTION IS REQUIRED.                               i 05000305         010781       DURING TESTING OF CONTAINMENT FAN COIL.(F/C) SERVICE WATER LOW FLOW ALAR CNTNMNT HEAT REMOV SYS + CONT             81-001/03L-0       020681       M. THE DISCHARGE VALVE ON 1B F/C UNIT WOULD NOT OPEN ON DEMAND. BY DEFI-UALVE OPERATORS                             036060         30-DAY       NITION THIS F/C UNIT WAS NOT OPERABLE, PLACING THE FACILITY UNDER LCO TE ELECTRIC MOTOR - AC                                                     CH. SPEC. 3.3.B.2.A (ONE F/C UNIT MAY BE OUT OF SERVICE FOR UP TO SEVEN COMPONENT FAILURE                                                         DAYS) AND THUS REPORTABLE PER TECH. SPEC. 6.9.2.B.(2). THE THREE REMAIN MECHANICAL LIMITORQUE CORP.                                                          ING F/C UNITS WERE OPERABLE. THERE WAS NO EFFECT ON PUBLIC SAFETY OR PL ANT CPERATION.
.2.B.(3)).
THE FAILURE OF THE MOTOR OPERATOR HAS BEEN ATTRIBUTED TO A LOOSE TORQUE ADJUSTMENT SWITCH.           THE VALVE WAS MANUALLY OPENED TO PLACE THE F/C UNIT-BACK IN SERVICE. THE SWITCH WAS READJUSTED AND THE OPERATOR TESTED SATI SFACTORILY WITHIN THE SEVEN DAY TIME LIMIT.                 THIS IS CONSIDERED AN ISOLA TED OCCURRENCE REQUIRING NO FURTHER CORRECTIVE ACTION.'
PROCEDURE WAS REVIEWED WITH LAB PERSONNEL UITH EMPHASIS ON R EQUIRED ANALYSIS. NO FURTHER CORRECTIVE ACTION IS REQUIRED.
KEWAUNEE-1                                                   011381       WHILE TESTING 1B DIESEL GENERATOR (D/G) OPERABLE FOR REMOVAL OF.1A D/G F EMERG GENERATOR SYS + CONTROLS             35000305-81-002/03L-0     . 021281      ROM SERVICE, 1B D/G FAILED TO START.              T.S. 3.7.B.2 ALLOWS ONE D/G TO BE MOTORS                                       036110         30-DAY SUBCOMPONENT NOT APPLICABLE OUT OF SERVICE FOR UP TO SEVEN DAYS PROVIDED THAT THE OTHER D/G IS TESTE D OPERABLE ON A DAILY B ASIS. ONE TRAIN OF EMERGENCY POWER WAS-STILL AVA COMPONENT FAILURE                                                         Ti. ABL E. THIS IS REPORTABLE PER T.S. 6.9.2.B.(2).               THERE WAS NO EFFECT 0 CORROSION                                                               N PUBLIC SAFETY OR PLANT OPERATION.
i KEWAUNEE-1 05000305 010781 DURING TESTING OF CONTAINMENT FAN COIL.(F/C) SERVICE WATER LOW FLOW ALAR CNTNMNT HEAT REMOV SYS + CONT 81-001/03L-0 020681 M.
THE DISCHARGE VALVE ON 1B F/C UNIT WOULD NOT OPEN ON DEMAND.
BY DEFI-UALVE OPERATORS 036060 30-DAY NITION THIS F/C UNIT WAS NOT OPERABLE, PLACING THE FACILITY UNDER LCO TE ELECTRIC MOTOR - AC CH. SPEC. 3.3.B.2.A (ONE F/C UNIT MAY BE OUT OF SERVICE FOR UP TO SEVEN COMPONENT FAILURE DAYS) AND THUS REPORTABLE PER TECH. SPEC. 6.9.2.B.(2).
THE THREE REMAIN MECHANICAL ING F/C UNITS WERE OPERABLE. THERE WAS NO EFFECT ON PUBLIC SAFETY OR PL LIMITORQUE CORP.
ANT CPERATION.
THE FAILURE OF THE MOTOR OPERATOR HAS BEEN ATTRIBUTED TO A LOOSE TORQUE ADJUSTMENT SWITCH.
THE VALVE WAS MANUALLY OPENED TO PLACE THE F/C UNIT-BACK IN SERVICE. THE SWITCH WAS READJUSTED AND THE OPERATOR TESTED SATI SFACTORILY WITHIN THE SEVEN DAY TIME LIMIT.
THIS IS CONSIDERED AN ISOLA TED OCCURRENCE REQUIRING NO FURTHER CORRECTIVE ACTION.'
KEWAUNEE-1 35000305-. 021281 ROM SERVICE, 1B D/G FAILED TO START.
T.S.
3.7.B.2 ALLOWS ONE D/G TO BE 011381 WHILE TESTING 1B DIESEL GENERATOR (D/G) OPERABLE FOR REMOVAL OF.1A D/G F EMERG GENERATOR SYS + CONTROLS 81-002/03L-0 MOTORS 036110 30-DAY OUT OF SERVICE FOR UP TO SEVEN DAYS PROVIDED THAT THE OTHER D/G IS TESTE SUBCOMPONENT NOT APPLICABLE D OPERABLE ON A DAILY B ASIS.
ONE TRAIN OF EMERGENCY POWER WAS-STILL AVA COMPONENT FAILURE Ti. ABL E.
THIS IS REPORTABLE PER T.S. 6.9.2.B.(2).
THERE WAS NO EFFECT 0 CORROSION N PUBLIC SAFETY OR PLANT OPERATION.
WESTERN ENGINE CD.
WESTERN ENGINE CD.
WATER IN AIR SUPPLY PREV AIR START MOTORS FROM ENGAGING PROPERLY.                   1A D/
WATER IN AIR SUPPLY PREV AIR START MOTORS FROM ENGAGING PROPERLY.
1A D/
G WAS IMMED VEP1FIED OPERABLE 8 1B D/G TAKEN OUT OF SERVs CHECK VLV WAS kEPLACED
G WAS IMMED VEP1FIED OPERABLE 8 1B D/G TAKEN OUT OF SERVs CHECK VLV WAS kEPLACED
* SOLEHOID 8 RELAY VLVS WERE CLEANED 8 REINSTALLED. EVENT SIMI LAR TO 80-042. A DESIGN CHANGE IS IN PROGRESS TO INSTALL AIR DRIER $ IN D/G AIR START SYSTEM. NO FURTHER CORRECTIVE ACTIONS ARE ANTICIPATED.
* SOLEHOID 8 RELAY VLVS WERE CLEANED 8 REINSTALLED. EVENT SIMI LAR TO 80-042.
KEWAUNEE-1                                   05000305         012281       DURING TESTING OF VALVE CC4003 (COMPONENT COOLING WATER INLET-TO 1B RESI l                                               COOL SYS FOR REAC AUX + CONT             81-003/03L-0       022088       DUAL HEAT EXCHANGER) FOLLOWING THE REINSTALLATION OF THE MOTOR OPERATOR.
A DESIGN CHANGE IS IN PROGRESS TO INSTALL AIR DRIER $ IN D/G AIR START SYSTEM. NO FURTHER CORRECTIVE ACTIONS ARE ANTICIPATED.
UALVE OPERATORS                             o 6240         30-DAY       THE SUPPLY THERMAL OVERLOADS TRIPPED. THIS PUT THE FACILITY UNDER LCO ELECTRIC MOTOR - AC-                                                     TECHNICAL SPECIFICATION 3.3.A.2.C (ONE RHR HEAT EXCHANGER MAY BE OUT OF PERSONNEL ERROR                                                           SERVICE FOR UP TO 48 HOURS) AND THUS IS REPORTABLE PER TECH. SPEC. 6.9.2 MAINTENANCE 8 REPAIR PERSONNEL                                           .B.2.     SINCE THIS VALVE WAS MANUALLY OPERABLE, 8 SECOND RHR HEAT EXCHANG LIMITORQUE CORP.                                                         ER WAS AVAILABLE, THERE WAS NO EFFECT OH PUBLIC SAFETY / PLANT OPERATION.
KEWAUNEE-1 05000305 012281 DURING TESTING OF VALVE CC4003 (COMPONENT COOLING WATER INLET-TO 1B RESI l
COOL SYS FOR REAC AUX + CONT 81-003/03L-0 022088 DUAL HEAT EXCHANGER) FOLLOWING THE REINSTALLATION OF THE MOTOR OPERATOR.
UALVE OPERATORS o 6240 30-DAY THE SUPPLY THERMAL OVERLOADS TRIPPED. THIS PUT THE FACILITY UNDER LCO ELECTRIC MOTOR - AC-TECHNICAL SPECIFICATION 3.3.A.2.C (ONE RHR HEAT EXCHANGER MAY BE OUT OF PERSONNEL ERROR SERVICE FOR UP TO 48 HOURS) AND THUS IS REPORTABLE PER TECH. SPEC. 6.9.2 MAINTENANCE 8 REPAIR PERSONNEL
.B.2.
SINCE THIS VALVE WAS MANUALLY OPERABLE, 8 SECOND RHR HEAT EXCHANG LIMITORQUE CORP.
ER WAS AVAILABLE, THERE WAS NO EFFECT OH PUBLIC SAFETY / PLANT OPERATION.
THE MOTOR OPERATOR FAILURE HAS BEEN ATTRIBUTED TO A WIRING ERROR BY A PL ANT ELECTRICIAN, WHICH RESULTED IN THE THERMAL OVERLOADS TRIPPING. THE WIRING FAULT WAS IDENTIFIED AND CORRECTED, AND THE VALVE /0PERATOR TESTED
THE MOTOR OPERATOR FAILURE HAS BEEN ATTRIBUTED TO A WIRING ERROR BY A PL ANT ELECTRICIAN, WHICH RESULTED IN THE THERMAL OVERLOADS TRIPPING. THE WIRING FAULT WAS IDENTIFIED AND CORRECTED, AND THE VALVE /0PERATOR TESTED
                                                                                                                          -SATISFACTORILY. THE PROCEDURE WAS REVIEWED WITH THE ELECTRICIAN. NO F
-SATISFACTORILY.
!                                                                                                                        URTHER CORRECTIVE ACTION IS NECESSARY.
THE PROCEDURE WAS REVIEWED WITH THE ELECTRICIAN. NO F URTHER CORRECTIVE ACTION IS NECESSARY.
i
i


MAR 26, 1981                                     LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 53 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPONEHT/ DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 53 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPONEHT/
COMPONENT SUBCODE/CAUSE CODE / LER NO./     REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER   CONTROL NO. REPORT TYPE                               CAUSE DESCRIPTION MAINE YANKEE                         05000309     060480     DURING 1980 REFUELING OUTAGE. A REACTOR VESSEL WALL SURVEILLANCE CAPSULE REACTOR VES. + APPURTENANCES     80-014/01X-1   021381     WAS REMOVED FROM THE REACTOR & SENT TO BATTELLE COLUMBUS LABORATORIES F VESSELS. PRESSURE                   033749     OTHER     OR ANALYSIS. RESULTS OF THAT ANALYSIS INDICATE A CONSIDERABLY HIGHER SH REACTOR VESSEL                                             IFT OF RT(NDT) THAN WAS ORIGINALLY PREDICTED. THE NEUTRON FLUENCE FOR T DEFECTIVE PROCEDURES                                       HE CAPSULE AS ANALYZED WAS 6.9E18 N/SQ. CM. (E) 1 MEV). THIS IS A FACTO NOT APPLICABLE                                             R OF 2.3 HIGHER THAN ORIGINAL ESTIMATE OF 3.0E18 N/SQ. CM. THIS RESULTS OTHER                                                       IN MORE LIMITING CURVES RELATIVE TO REACTOR VES HEATUP & C00LDOWN RATES.
EVENT DATE/
BATTELLE UTILIZED COMPUTER CODE DDT 3.5, UHICH USES TWO-DIMENSIONAL GEOM ETRY, 8 DELAY COMPUTER CODE WAS USED TO COMPLETE CALCULATIONS. ORIGINAL ANALYSIS UTILIZED A SIHGLE DIMENSIONAL CODE COMBIHATION OF ANISN-SHADRA C. DIFFERENCE COULD BE DUE TO CALCULATION PROGRAMS AND/OR ERRORS IN ORI GINAL METHODOLOGY. NEW HEATUP/COOLDOWN CURVES & T.S. CHANGES BEING FREP.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
MILLSTONE-2                         05000336     010181     DURING ROUTINE POWER OPERATION, THE OUTPUT FROM STEAM GENERATOR DIFFEREN REACTOR TRIP SYSTEMS             81-001/03L-0   012881     TIAL PRESSURE TRANSMITTER, PDT-121B, FAILED LOW CAUSING A LO4 FLOW TRIP INSTRUMENTATION + CONTROLS           036035     30-DAY     ON CHANNEL "B" 0F THE REACTOR PROTECTION SYSTEM.     THE CHANNEL WAS BYPAS$
REPORT DATE/
SWITCH                                                     ED AND THE UNIT OPERATED FOR 8 HOURS UNDER THE ACTION STATEMENT OF TECHN COMPONENT FAILURE                                           ICAL SPECIFICATION 3.3.1.1.. SIMILAR EVENTS: NONE ELECTRICAL METER DEVICES CD.
EVENT DESCRIPTION /
A DIRTY KNIFE SWITCH CONTACT CAUSED AN OPEN CIRCUIT BETWEEN THE DIFFEREN TIAL PRESSURE TRANSMITTER AND THE LOW FLOW TRIP BISTABLE RESULTING IN TH E CHANNEL TRIP. THE SWITCH CONTACTS WERE CLEANED AND THE SWITCH WAS RET URNED TO SERVICE. THE SWITCH WAS MANUFACTURED BY METER DEVICES CO.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
MILLSTONE-2                         05000336     010281     DURING A PLANT C00LDOWN, COHTAINMENT PRESSURE DECREASED BELOW NEGATIVE 1 CNTNMNT HEAT REMOV SYS + CONT     81-004/03L-0   013081     2 INCHES HG. CONTAINMENT COOLING WAS BEING SUPPLIED BY THREE CAR FANS IN VESSELS. PRESSURE                   036063     30-DAY     FAST WITH HORMAL AND EMERGENCY RBCCW COOLING. CONTAINMENT TEMPERATURE CONTAINMENT /DRYWELL                                       DROPPED FROM 103 TO 90 DEGREES F. THE PLAMT WAS OPERATED IN ACCORDANCE PERSONNEL ERROR                                             WITH TECHNICAL SPECIFICATION ACTION STATEMENT 3.6.1.4. THERE ARE NO SIM LICENSED 8 SENIOR OPERATORS                               ILAR INCIDENTS.
REPORT TYPE CAUSE DESCRIPTION MAINE YANKEE 05000309 060480 DURING 1980 REFUELING OUTAGE. A REACTOR VESSEL WALL SURVEILLANCE CAPSULE REACTOR VES. + APPURTENANCES 80-014/01X-1 021381 WAS REMOVED FROM THE REACTOR & SENT TO BATTELLE COLUMBUS LABORATORIES F VESSELS. PRESSURE 033749 OTHER OR ANALYSIS. RESULTS OF THAT ANALYSIS INDICATE A CONSIDERABLY HIGHER SH REACTOR VESSEL IFT OF RT(NDT) THAN WAS ORIGINALLY PREDICTED. THE NEUTRON FLUENCE FOR T DEFECTIVE PROCEDURES HE CAPSULE AS ANALYZED WAS 6.9E18 N/SQ. CM. (E) 1 MEV).
THIS IS A FACTO NOT APPLICABLE R OF 2.3 HIGHER THAN ORIGINAL ESTIMATE OF 3.0E18 N/SQ. CM. THIS RESULTS OTHER IN MORE LIMITING CURVES RELATIVE TO REACTOR VES HEATUP & C00LDOWN RATES.
BATTELLE UTILIZED COMPUTER CODE DDT 3.5, UHICH USES TWO-DIMENSIONAL GEOM ETRY, 8 DELAY COMPUTER CODE WAS USED TO COMPLETE CALCULATIONS. ORIGINAL ANALYSIS UTILIZED A SIHGLE DIMENSIONAL CODE COMBIHATION OF ANISN-SHADRA C.
DIFFERENCE COULD BE DUE TO CALCULATION PROGRAMS AND/OR ERRORS IN ORI GINAL METHODOLOGY. NEW HEATUP/COOLDOWN CURVES & T.S.
CHANGES BEING FREP.
MILLSTONE-2 05000336 010181 DURING ROUTINE POWER OPERATION, THE OUTPUT FROM STEAM GENERATOR DIFFEREN REACTOR TRIP SYSTEMS 81-001/03L-0 012881 TIAL PRESSURE TRANSMITTER, PDT-121B, FAILED LOW CAUSING A LO4 FLOW TRIP INSTRUMENTATION + CONTROLS 036035 30-DAY ON CHANNEL "B" 0F THE REACTOR PROTECTION SYSTEM.
THE CHANNEL WAS BYPAS$
SWITCH ED AND THE UNIT OPERATED FOR 8 HOURS UNDER THE ACTION STATEMENT OF TECHN COMPONENT FAILURE ICAL SPECIFICATION 3.3.1.1..
SIMILAR EVENTS: NONE ELECTRICAL METER DEVICES CD.
A DIRTY KNIFE SWITCH CONTACT CAUSED AN OPEN CIRCUIT BETWEEN THE DIFFEREN TIAL PRESSURE TRANSMITTER AND THE LOW FLOW TRIP BISTABLE RESULTING IN TH E CHANNEL TRIP.
THE SWITCH CONTACTS WERE CLEANED AND THE SWITCH WAS RET URNED TO SERVICE. THE SWITCH WAS MANUFACTURED BY METER DEVICES CO.
MILLSTONE-2 05000336 010281 DURING A PLANT C00LDOWN, COHTAINMENT PRESSURE DECREASED BELOW NEGATIVE 1 CNTNMNT HEAT REMOV SYS + CONT 81-004/03L-0 013081 2 INCHES HG. CONTAINMENT COOLING WAS BEING SUPPLIED BY THREE CAR FANS IN VESSELS. PRESSURE 036063 30-DAY FAST WITH HORMAL AND EMERGENCY RBCCW COOLING. CONTAINMENT TEMPERATURE CONTAINMENT /DRYWELL DROPPED FROM 103 TO 90 DEGREES F.
THE PLAMT WAS OPERATED IN ACCORDANCE PERSONNEL ERROR WITH TECHNICAL SPECIFICATION ACTION STATEMENT 3.6.1.4.
THERE ARE NO SIM LICENSED 8 SENIOR OPERATORS ILAR INCIDENTS.
BECHTEL CORP.
BECHTEL CORP.
CONTAINMENT COOLING WAS NOT CHANGED TO MATCH DECREASING HEAT LCADS DURIN G THE C00LDOWN. CAR FANS WERE SHIFTED TO SLOW WITH NORMAL RBCCW FLOW ON LY. CONT AINMENT PRESSURE INCREASED ABOVE NEGATIVE 12 INCHES HG WITHIN 1 0 MINUTES. OPERATORS HAVE BEEN CAUTIONED TO BALANCE CONTAIHMENT COOLING WITH HEAT LOADS DURING HEATUPS AND COOLDOWNS MILLSTOHE-2                         05000336     010281     DURING A DIESEL GENERATOR (D/G) RESPONSE TO A LOSS OF NORMAL POWER, A D/
CONTAINMENT COOLING WAS NOT CHANGED TO MATCH DECREASING HEAT LCADS DURIN G THE C00LDOWN.
STATION SERV WATER SYS + CONT     81-005/03L-0   013081     G SERVICE WATER FLANGE LEAKED. THE LEAK W'.TTED THE ENGINE CAUSING A DIE PIPES, FITTINGS                     036172     30-DAY     SEL TRIP.- THE LEAK ALSO WETTED THE AMPHEN0L PL JG CN THE WOODWARD GOVENO 6 TO 10 INCHES                                           R CAUSING THE PLUG TO FAIL. THE FACILITY OPERATED IN ACCORDANCE WITH TE DESIGN / FABRICATION ERROR                                 CHNICAL SPECIFICATION ACTION STATEMENT 3.8.1.1.D FOR APPROXIMATELY 6 HOU CONSTRUCTION / INSTALLATION                               RS. AT WHICH TIME OPERABILITY OF OTHER D/G WAS DEMONSTRATED & PLANT OPE FLAGG, C. N. CO.                                       R WITHIN ACTION STATEMENT 3.8.1.1.A UNTIL COLD SHUTDOWN WAS ACHIEVED.
CAR FANS WERE SHIFTED TO SLOW WITH NORMAL RBCCW FLOW ON LY.
CONT AINMENT PRESSURE INCREASED ABOVE NEGATIVE 12 INCHES HG WITHIN 1 0 MINUTES. OPERATORS HAVE BEEN CAUTIONED TO BALANCE CONTAIHMENT COOLING WITH HEAT LOADS DURING HEATUPS AND COOLDOWNS MILLSTOHE-2 05000336 010281 DURING A DIESEL GENERATOR (D/G) RESPONSE TO A LOSS OF NORMAL POWER, A D/
STATION SERV WATER SYS + CONT 81-005/03L-0 013081 G SERVICE WATER FLANGE LEAKED.
THE LEAK W'.TTED THE ENGINE CAUSING A DIE PIPES, FITTINGS 036172 30-DAY SEL TRIP.- THE LEAK ALSO WETTED THE AMPHEN0L PL JG CN THE WOODWARD GOVENO 6 TO 10 INCHES R CAUSING THE PLUG TO FAIL.
THE FACILITY OPERATED IN ACCORDANCE WITH TE DESIGN / FABRICATION ERROR CHNICAL SPECIFICATION ACTION STATEMENT 3.8.1.1.D FOR APPROXIMATELY 6 HOU CONSTRUCTION / INSTALLATION RS.
AT WHICH TIME OPERABILITY OF OTHER D/G WAS DEMONSTRATED & PLANT OPE FLAGG, C.
N.
CO.
R WITHIN ACTION STATEMENT 3.8.1.1.A UNTIL COLD SHUTDOWN WAS ACHIEVED.
DURING A RECENT:0UTAGE THE D/G SERVICE WATER PIPING WAS MODIFIF9. THE F AILED GASKET HAD BEEN IMPROPERLY COMPRESSED CAUSING THE GASKET TO BE BLO WN-0UT DURING THE SUDDEN PRESSURE SURGE WHEN THE D/G WAS STARTED. THE G ASKET AHD AMPHEN9L PLUG WERE REPLACED. A VERIFICATION OF PROPER COMPRES SION WAS MADE ON THE REMAINING FLANGES IN THE D/G ROOMS.
DURING A RECENT:0UTAGE THE D/G SERVICE WATER PIPING WAS MODIFIF9. THE F AILED GASKET HAD BEEN IMPROPERLY COMPRESSED CAUSING THE GASKET TO BE BLO WN-0UT DURING THE SUDDEN PRESSURE SURGE WHEN THE D/G WAS STARTED. THE G ASKET AHD AMPHEN9L PLUG WERE REPLACED. A VERIFICATION OF PROPER COMPRES SION WAS MADE ON THE REMAINING FLANGES IN THE D/G ROOMS.


MAR 26, 1981                                                                       LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE S4 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/                           DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE S4 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                 REPORT DATE/                                       EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                               CONTROL NO. REPORT TY?E                                       CAUSE DESCRIPTION MILLSTONE-2                                                       05000336             010381 DURING A ROUTINE CONTAINMENT INSPECTION A LEAK WAS FOUND AT A SOCKET WEL ENERG CORE COOLING SYS + CONT                                 81-002/03L-0           013081 D IN THE SAFETY INJECTION TEST HEADER NEAR RELIEF VALVE 2-51-466.       INVES PIPES FITTINGS                                                   036061             30-DAY TIGATION IDENTIFIED A SMALL CRACK-IN THE TOE OF THE WELD. SIMILAR PEPOR LESS THAN 4 INCHES                                                                         15: 80-27 (8'25/80), 77-37 (9/t7/77), 77-10 (3/21/77).
EVENT DATE/
COMP 0HENT FAILURE METALLURGICAL OTHER LOW CYCLE. HICH STRESS FATICUE CRACKING CAUSED BY IMPROPER SETTING OF RE LIEF VALVE 2-51-466.       THIS RELIEF VALVE WAS FOUND SET AT 100 PSIG VICE I TS PROPER SET'ING OF 48S PSIG. THIS CAUSED REPEATED OPENING / CLOSING CYC LES WITH ATTENDANT PIPING VIBRATION. THE VALVE WAS RESET AND THE AFFECT ED PIPINO REPLACED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
MILLSTONE-2                                                       0S0003$4             010681 DURING A ROUTINE INSPECTION, MAIN STEAM LINE SNUBBER 413019 WAS FOUND WI MAIN STEAM SUPPLY SYS + CONT                                 81-003/03L-0           013081 TH NO VISIBLE FLUID LEVEL. AT THE TIME OF THE DISCOVERY THE PLANT WAS I HANGERS,5UPPORTS,$ HOCK SUPPRSS                                 036062             30-DAY N A LOLD SHUIDOWN CONDITION. THE SNUBBER IS AN ITT GRINNELL, FIG. 200, SHUBBERS                                                                                   4 INCH BORE BY S INCH STROKE UNIT. SIMILAR LERS 77-47, 79-28, 80-12.
REPORT DATE/
DESION/ FABRICATION ERROR CONS 1RUCTION/ INSTALLATION ITT GRINNELL THE PLASTIC FLUID RESERVOIR DEFORMED DUE TO OVERHEATING WHEN INSULATING PADS WERE INSTALLED OVER A PORTION OF THE SNUBBER AFTER RELOCATION OF TH E HANGER AND SHUBBER DURING A RECENT OUTAGE. THE DEFECTIVE SHUBBER UAS REPLACED. AN INSPECTION WAS PERf 0RMED VERIFYING ADDITIONAL HANGER WORK HAS NOT CAUSED SIMILAR OCCURRENCES.
EVENT DESCRIPTION /
MILLSTONE-2                                                       05000336             010881 DURING A ROUTINE PLANT HEATUP, AN UNIDENTIFIED LEAKAGE IN EXCESS OF THAT COOLANT RECIRC SYS + CONTROLS                                 81-006/03L-0           020681   ALLOWED BY TECHNICAL SPECIFICATIONS EXISTED BECAUSE 2-RC-1S AND 2-RC-30.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
VALVES                                                           036111             30-DAY ,  NITROGEH ISOLATION VALVES TO THE PRESSURIZER, WERE LEFT OPEN.     THE PLA GLOBE                                                                                     NT WAS OPERATED IN ACCORDANCE WITH TECHNICAL SPECIFICATION ACTION STATEM DEFECTIVE PROCEDURES                                                                       ENT 3.4.6.2.B. SIMILAR EVENTS         NONE.
REPORT TY?E CAUSE DESCRIPTION MILLSTONE-2 05000336 010381 DURING A ROUTINE CONTAINMENT INSPECTION A LEAK WAS FOUND AT A SOCKET WEL ENERG CORE COOLING SYS + CONT 81-002/03L-0 013081 D IN THE SAFETY INJECTION TEST HEADER NEAR RELIEF VALVE 2-51-466.
INVES PIPES FITTINGS 036061 30-DAY TIGATION IDENTIFIED A SMALL CRACK-IN THE TOE OF THE WELD.
SIMILAR PEPOR LESS THAN 4 INCHES 15: 80-27 (8'25/80), 77-37 (9/t7/77), 77-10 (3/21/77).
COMP 0HENT FAILURE METALLURGICAL OTHER LOW CYCLE. HICH STRESS FATICUE CRACKING CAUSED BY IMPROPER SETTING OF RE LIEF VALVE 2-51-466.
THIS RELIEF VALVE WAS FOUND SET AT 100 PSIG VICE I TS PROPER SET'ING OF 48S PSIG.
THIS CAUSED REPEATED OPENING / CLOSING CYC LES WITH ATTENDANT PIPING VIBRATION. THE VALVE WAS RESET AND THE AFFECT ED PIPINO REPLACED.
MILLSTONE-2 0S0003$4 010681 DURING A ROUTINE INSPECTION, MAIN STEAM LINE SNUBBER 413019 WAS FOUND WI MAIN STEAM SUPPLY SYS + CONT 81-003/03L-0 013081 TH NO VISIBLE FLUID LEVEL.
AT THE TIME OF THE DISCOVERY THE PLANT WAS I HANGERS,5UPPORTS,$ HOCK SUPPRSS 036062 30-DAY N A LOLD SHUIDOWN CONDITION. THE SNUBBER IS AN ITT GRINNELL, FIG. 200, SHUBBERS 4 INCH BORE BY S INCH STROKE UNIT.
SIMILAR LERS 77-47, 79-28, 80-12.
DESION/ FABRICATION ERROR CONS 1RUCTION/ INSTALLATION ITT GRINNELL THE PLASTIC FLUID RESERVOIR DEFORMED DUE TO OVERHEATING WHEN INSULATING PADS WERE INSTALLED OVER A PORTION OF THE SNUBBER AFTER RELOCATION OF TH E HANGER AND SHUBBER DURING A RECENT OUTAGE.
THE DEFECTIVE SHUBBER UAS REPLACED. AN INSPECTION WAS PERf 0RMED VERIFYING ADDITIONAL HANGER WORK HAS NOT CAUSED SIMILAR OCCURRENCES.
MILLSTONE-2 05000336 010881 DURING A ROUTINE PLANT HEATUP, AN UNIDENTIFIED LEAKAGE IN EXCESS OF THAT COOLANT RECIRC SYS + CONTROLS 81-006/03L-0 020681 ALLOWED BY TECHNICAL SPECIFICATIONS EXISTED BECAUSE 2-RC-1S AND 2-RC-30.
VALVES 036111 30-DAY NITROGEH ISOLATION VALVES TO THE PRESSURIZER, WERE LEFT OPEN.
THE PLA GLOBE NT WAS OPERATED IN ACCORDANCE WITH TECHNICAL SPECIFICATION ACTION STATEM DEFECTIVE PROCEDURES ENT 3.4.6.2.B.
SIMILAR EVENTS NONE.
NOT APPLICABLE VELAN VALVE CORP.
NOT APPLICABLE VELAN VALVE CORP.
THE VALVES, 2-RC-IS AND 2-RC-30, WERE OUT OF POSITION DUE TO PROCEDURAL INADEQUACY.     THE SPECIFIC PROCEDURES WERE REVISED TO PREVENT RECURRENCE.
THE VALVES, 2-RC-IS AND 2-RC-30, WERE OUT OF POSITION DUE TO PROCEDURAL INADEQUACY.
THE SPECIFIC PROCEDURES WERE REVISED TO PREVENT RECURRENCE.
A GENERIC PROCEDURE WAS GEHERATED TO ESTABLISH A PROGRAM FOR INSURING P R0PER SYSTEM ALIGNMENTS FOLLOWING OUTAGES.
A GENERIC PROCEDURE WAS GEHERATED TO ESTABLISH A PROGRAM FOR INSURING P R0PER SYSTEM ALIGNMENTS FOLLOWING OUTAGES.
NINE MILE POINT-1                                                 05000220             121680 DURING HORMAL OPER, WHILE PERFORMING EMERGENCY VENTILATION SYSTEM (STAND CNTHMNT AIR PURI + CLEAHUP SYS                               80-032/03L-0           011681 BY GAS TREATMENT) HEPA FILTER COLD D.O.P. SURVEILLANCE TEST, OHE FILTER FILTERS                                                         033741             30-DAY BANK IN 911 BRANCH PRODUCED AN UNACCEPTABLE EFFICIENCY OF 8% LEAKAGE.                   E SUBCOMPONENT N-3T APPLICABLE                                                               FFICIENCY REQUIRED BY STATION TECH. SPECS. IS LESS TFAN 1% BYPASS LEAKAG DTHER                                                                                       E. THIS HAD NO SIGNIFICANT SAFETY OR ENVIRONMENTAL EFFECT SINCE OVERALL HOT APPLICABLE                                                                               BRANCH EFFICIENCY WAS ACCEPTABLE AND ALTERNATE REDUNDANT SYSTEM WAS PRO CAMBRIDGE FILTER CORP.                                                                     VEN OPERABLE. ALL OTHER TESTING INVOLVED FROVIDED ACCEPTABLE RESULTS.
NINE MILE POINT-1 05000220 121680 DURING HORMAL OPER, WHILE PERFORMING EMERGENCY VENTILATION SYSTEM (STAND CNTHMNT AIR PURI + CLEAHUP SYS 80-032/03L-0 011681 BY GAS TREATMENT) HEPA FILTER COLD D.O.P.
INSPECTION REVEALED THAT FILTER SEALING GASKET WAS DEFECTIVE.       EFFORTS T 0 RESEAL GASKET SURFACE WERE UNSUCCESSFUL SO A NEW FILTER UNIT WAS INSTA (LED. TEST RESULTS OF HEW FILTER WERE *?CEPTABLE. SURV TESTING ON THIS SYS CONTINUES ON A REGULAR BASIS OR AS LiRTAIN CONDITIONS HECESSITATE A S DESCRIBED IN TECHNICAL SPECIFICATIONS.
SURVEILLANCE TEST, OHE FILTER FILTERS 033741 30-DAY BANK IN 911 BRANCH PRODUCED AN UNACCEPTABLE EFFICIENCY OF 8% LEAKAGE.
4 ,-                      ,, . , , , .                                                                        t r         ~                       y -                    _ , - - - _ _ - -
E SUBCOMPONENT N-3T APPLICABLE FFICIENCY REQUIRED BY STATION TECH. SPECS. IS LESS TFAN 1% BYPASS LEAKAG DTHER E.
THIS HAD NO SIGNIFICANT SAFETY OR ENVIRONMENTAL EFFECT SINCE OVERALL HOT APPLICABLE BRANCH EFFICIENCY WAS ACCEPTABLE AND ALTERNATE REDUNDANT SYSTEM WAS PRO CAMBRIDGE FILTER CORP.
VEN OPERABLE. ALL OTHER TESTING INVOLVED FROVIDED ACCEPTABLE RESULTS.
INSPECTION REVEALED THAT FILTER SEALING GASKET WAS DEFECTIVE.
EFFORTS T 0 RESEAL GASKET SURFACE WERE UNSUCCESSFUL SO A NEW FILTER UNIT WAS INSTA (LED.
TEST RESULTS OF HEW FILTER WERE *?CEPTABLE.
SURV TESTING ON THIS SYS CONTINUES ON A REGULAR BASIS OR AS LiRTAIN CONDITIONS HECESSITATE A S DESCRIBED IN TECHNICAL SPECIFICATIONS.
4 t r
~
y


i                                                                                                                                                                                     ,
i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 55 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
MAR 26, 1981                                                         LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 55 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./         EVENT DATE/
DOCKET NO./
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 REPORT DATE/                                 EVENT DESCRIPTION /
EVENT DATE/
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO.         REPORT TYPE                                   CAUSE DESCRIPTION NENE MILE POINT-1                                   05000220           122480     DURING NORMAL OPERATIDH, THE LOSS OF A 115KV AUXILIARY POWER FEED TO AN AC ONSITE POWER SYS + CONTROLS         80-033/03L-0         012381     EMERGENCY POWER BUS WAS EXPERIENCED. THE EMERGENCY DIESEL GENERATOR AUT RELAYS                                         033742         30-DAY     OMATICALLY CAME INTO SERVICE AS REQUIRED. THIS HAD NO ADVERSE AFFECT ON SWITCHGEAR. PROTECTIVE                                                 SAFE OPERATION SINCE THESE COMPONENTS OPERATED AS DESIGNED.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION NENE MILE POINT-1 05000220 122480 DURING NORMAL OPERATIDH, THE LOSS OF A 115KV AUXILIARY POWER FEED TO AN AC ONSITE POWER SYS + CONTROLS 80-033/03L-0 012381 EMERGENCY POWER BUS WAS EXPERIENCED. THE EMERGENCY DIESEL GENERATOR AUT RELAYS 033742 30-DAY OMATICALLY CAME INTO SERVICE AS REQUIRED. THIS HAD NO ADVERSE AFFECT ON SWITCHGEAR. PROTECTIVE SAFE OPERATION SINCE THESE COMPONENTS OPERATED AS DESIGNED.
COMPONENT FAILURE OTHER GENERAL ELECTRIC CO.
COMPONENT FAILURE OTHER GENERAL ELECTRIC CO.
A CALIBRATION CHECK OF OVER-FREQUENCY PROTECTIVE RELAY FOR FEEDER BREAKE R REVEALED THAT TRIP SETPOINT WAS FOUND TOO CONSERVATIVELY CLOSE TO NOMI HAL FREQUENCY, THUS CAUSING A SPURIOUS TRIP OF BREAKER.         RELAY WAS PROPE RLY RECALIBRATED TO PREVENT RECURRENCE.         THIS TYPE OF REL AY WILL DE CALI BRATED ON REFUEL CYCLE FREQUENCY FOR FUTURE' PREVENTATIVE ACTION.
A CALIBRATION CHECK OF OVER-FREQUENCY PROTECTIVE RELAY FOR FEEDER BREAKE R REVEALED THAT TRIP SETPOINT WAS FOUND TOO CONSERVATIVELY CLOSE TO NOMI HAL FREQUENCY, THUS CAUSING A SPURIOUS TRIP OF BREAKER.
NINE MILE POINT-1                                   05000220           122980     DURING NORMAL OPERATION, 1U0 PROCEDURES (ONE A FUEL HANDLING PROCEDURE A SYSTEM CODE NOT APPLICABLE             80-034/03L-0         012881     ND ONE AN INSTRUMENT SURVEILLANCE PROCEDURE FOR GASEQUS SYSTEM LEAK RATE COMPONENT CODE NOT APPLICABLE                 033743         30-DAY     TESTING) WERE NOT SORC REVIEWED WITHIN THE SEVEN DAY TIME PERIOD FOR TE SUBCOMP0HENT NOT APPLICABLE                                           MPORARY CHANGES AS REQUIRED BY TECHNICAL SPECIFICATIONS. THIS HAD NO EN OTHER                                                                   VIRONMENTAL SAFETY EFFECTS.
RELAY WAS PROPE RLY RECALIBRATED TO PREVENT RECURRENCE.
NOT APPLICABLE ITEM NOT APPLICABLE THE TIME PERIOD FOR SORC REVIEW WAS EXCEEDED DUE TO AN OVERSIGHT OF THE DUE DATE REQUIRED. THE REVIEW WAS PERFCRMED SHORTLY THEREAFTER WITH ALL APPROVALS COMPLETED.     FOR FUTURE PREVENTION A TICKLER SYSTEM FOR ITEMS NEEDING SORC REVIEW IS BEING IMPLEMENTED.
THIS TYPE OF REL AY WILL DE CALI BRATED ON REFUEL CYCLE FREQUENCY FOR FUTURE' PREVENTATIVE ACTION.
WINE MILE POINT-1                                     05000220           010781     DURING HORMAL OPERATION, WHILE PERFORMING TFE MONTHLY SURVEILLANCE, AN E EMERG GENERATOR SYS + CONTROLS         81 - 0 01/ 0 3 L -0   020681   MERGENCY DIESEL GENERATOR OUTPUT BREAKER TRIPPED ON EXCESSIVE CURRENT DU INSTRUMENTATION + CONTROLS                     036171         30-DAY     E TO FAILURE OF THE GENERATOR VOLTAGE REGULATOR. THIS HAD NO ADVERSE EF.
NINE MILE POINT-1 05000220 122980 DURING NORMAL OPERATION, 1U0 PROCEDURES (ONE A FUEL HANDLING PROCEDURE A SYSTEM CODE NOT APPLICABLE 80-034/03L-0 012881 ND ONE AN INSTRUMENT SURVEILLANCE PROCEDURE FOR GASEQUS SYSTEM LEAK RATE COMPONENT CODE NOT APPLICABLE 033743 30-DAY TESTING) WERE NOT SORC REVIEWED WITHIN THE SEVEN DAY TIME PERIOD FOR TE SUBCOMP0HENT NOT APPLICABLE MPORARY CHANGES AS REQUIRED BY TECHNICAL SPECIFICATIONS. THIS HAD NO EN OTHER VIRONMENTAL SAFETY EFFECTS.
CONTROLLER                                                           FECT CH SAFETY SINCE THE ALTERNATE EMERGENCY DIESEL GENERATOR WAS PROVEN OTHER                                                                     OPERABLE.
NOT APPLICABLE ITEM NOT APPLICABLE THE TIME PERIOD FOR SORC REVIEW WAS EXCEEDED DUE TO AN OVERSIGHT OF THE DUE DATE REQUIRED. THE REVIEW WAS PERFCRMED SHORTLY THEREAFTER WITH ALL APPROVALS COMPLETED.
NOT APPLICABLE CAR-BEE IHC INVESTIGATION FOUND THAT PIECES OF BAILING WIRE USED IN THE AREA TO ATTA CH FRAMES FOR STRUCTURAL' FIRE PROOFING HAD FALLEN ON TOP OF CONTROL CABI NET & THROUGH PROTECTIVE SCREEN.       EVIDENCE OF SHDRTING WAS FOUND AT THE VOLTAGE REGULATOR CONTROL CIRCUIT CONTACTS, CAUSING PROTECTIVE FUSE TO B LOW & CONSEQUENTLY FAILURE OF THE VOLTAGE REGULATOR.
FOR FUTURE PREVENTION A TICKLER SYSTEM FOR ITEMS NEEDING SORC REVIEW IS BEING IMPLEMENTED.
NORTH ANNA-1                                         05000338           102980   OH OCTOBER 29, 1980. IT WAS DISCOVERED THAT THE VALVE INSERVICE-INSPECTI EMERG CORE COOLING SYS + CONT           80-094/03L-0         111980   ON PERIODIC TEST-1-PT-133.1B WAS NOT PERFORMED AS REQUIRED BY IWV PROGRA VALVES                                         033677         30-DAY   M. VALVES WERE SUBSEQUENTLY TESTED AND FUNCTIONED PROPERLY. THEREFORE, OTHER                                                                 THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED. THIS ITEM IS RE PERSONNEL ERROR                                                         PORTABLE PURSUANT TO TECH. SPEC. 6.9.1.9.C.
WINE MILE POINT-1 05000220 010781 DURING HORMAL OPERATION, WHILE PERFORMING TFE MONTHLY SURVEILLANCE, AN E EMERG GENERATOR SYS + CONTROLS 81 - 0 01/ 0 3 L -0 020681 MERGENCY DIESEL GENERATOR OUTPUT BREAKER TRIPPED ON EXCESSIVE CURRENT DU INSTRUMENTATION + CONTROLS 036171 30-DAY E TO FAILURE OF THE GENERATOR VOLTAGE REGULATOR. THIS HAD NO ADVERSE EF.
NDHLIC. OPERATICHS PERSONHEL GTHER THIS EVENT WAS CAUSED BY PERSONNEL ERROR. THE VALVES IN QUESTION WERE S UBSEQUENTLY TESTED WITH SATISFACTORY RESULTS.
CONTROLLER FECT CH SAFETY SINCE THE ALTERNATE EMERGENCY DIESEL GENERATOR WAS PROVEN OTHER OPERABLE.
NOT APPLICABLE CAR-BEE IHC INVESTIGATION FOUND THAT PIECES OF BAILING WIRE USED IN THE AREA TO ATTA CH FRAMES FOR STRUCTURAL' FIRE PROOFING HAD FALLEN ON TOP OF CONTROL CABI NET & THROUGH PROTECTIVE SCREEN.
EVIDENCE OF SHDRTING WAS FOUND AT THE VOLTAGE REGULATOR CONTROL CIRCUIT CONTACTS, CAUSING PROTECTIVE FUSE TO B LOW & CONSEQUENTLY FAILURE OF THE VOLTAGE REGULATOR.
NORTH ANNA-1 05000338 102980 OH OCTOBER 29, 1980. IT WAS DISCOVERED THAT THE VALVE INSERVICE-INSPECTI EMERG CORE COOLING SYS + CONT 80-094/03L-0 111980 ON PERIODIC TEST-1-PT-133.1B WAS NOT PERFORMED AS REQUIRED BY IWV PROGRA VALVES 033677 30-DAY M.
VALVES WERE SUBSEQUENTLY TESTED AND FUNCTIONED PROPERLY.
THEREFORE, OTHER THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED. THIS ITEM IS RE PERSONNEL ERROR PORTABLE PURSUANT TO TECH. SPEC.
6.9.1.9.C.
NDHLIC. OPERATICHS PERSONHEL GTHER THIS EVENT WAS CAUSED BY PERSONNEL ERROR.
THE VALVES IN QUESTION WERE S UBSEQUENTLY TESTED WITH SATISFACTORY RESULTS.
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MAR 26, 1981                                                                                                                                                                       LER MONTHLY REPORT SORTED BY FACILITY                                                               PACE 56 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                                                                                       DOCKET NO./       EVENT DATF/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PACE 56 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
i COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                                                                                   REPORT DATE/                                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                                                                                                           CGNTROL NO.       REPORT TYPE                                               CAUSE DESCRIPTION NORTH ANNA-1                                                                                                                             -              -
EVENT DATF/
05000338           122980               ON DECEMBER 29, 1980, WITH THE UNIT IN MODE 5. THREE MOTOR-OPERATED VALV-CNTHMNT HEAT 9EMOV SYS + CONT                                                                                                                             81-004/03L-0           012981               ES FAILED TO ACTUATE DURING THE CONTAINMENT DEPRESSURIZATION ACTUATION F VALVES                                                                                                                                                         036209             30-DAY               UNCTIONAL' TEST.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
BUTTERFLY                                                                                                                                                                                                                  THE HEALTH AND SAFETY OF THE GENERAL-PUBLIC WERE NOT AF COMPONENT FAILURE                                                                                                                                                                                      FECTED. SINCE REDUNDANT VALVES PROVIDED SIMILAR FUNCTIONS TO THE FAILED VALVES. THIS IS CONTRARY TO TECHNICAL SPECIFICATION 3.7.4.1 3.6.2.2 A ELECTRICAL                                                                                                                                                                                           HD REPORTABLE PURSUANT TO TECHNICAL SPECIFICATION 6.9.1.9 D. DEVIATION ALLIS CHALMERS                                                                                                                                                                                         REPORTS SUBMITTED ON 91-06-81 MOV-SW-105C FAILED TO OPERATE BECAUSE OF A LOOSE LEAD ON THE BREAKER / CON
REPORT DATE/
'                                                                                                                                                                                                                                          TROLLER. MOV-SW-108A FAILED TO OPERATE BECAUSE OF WATER IN THE MOTCR AN D THE CAUSE FOR MOV-RS-101A FAILURE TO OPERATE IS UNKNOWN.             EACH VALVE W AS REPAIRED AS REQUIRED, AND WILL BE RETESTED PRIOR TO ENTRY INTO MODE 4 NORTH ANNA-1                                                                                                                                                   ~ 05C00338           123180               DURING MODE 5 OPERATION, A PRESSURIZER POWER OPERATED RELIEF VALVE WAS D~
EVENT DESCRIPTION /
OTHER COOLANT SUBSYS + CONTROL                                                                                                                             81-002/03L-0 011581                         ECLARED INOPERABLE BECAUSE OF LOW HITROGEN GAS SUPPLY TANK PRESSURE IN 1 i                                   UALVES                                                                                                                                                         036208             30-DAY               -GN-TK-1A. A REACTOR COOL ANT SYSTEM VENT OF GREATER THAN 2.07 SQUARE IN l                                     OTHER                                                                                                                                                                                                 CHES WAS ESTABLISHED IN ACCORDANCE WITH TECH. SPEC. 3.4.9.3. THEREFORE, DESIGN / FABRICATION ERROR                                                                                                                                                                               -THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED. THIS ITEM IS RE
i CAUSE SUBCODE/ MANUFACTURER CGNTROL NO.
:                                    DESIGN                                                                                                                                                                                               PORTABLE PURSUANT TO LECH.. SPEC. 6.9.1.9.B.
REPORT TYPE CAUSE DESCRIPTION NORTH ANNA-1 05000338 122980 ON DECEMBER 29, 1980, WITH THE UNIT IN MODE 5. THREE MOTOR-OPERATED VALV-CNTHMNT HEAT 9EMOV SYS + CONT 81-004/03L-0 012981 ES FAILED TO ACTUATE DURING THE CONTAINMENT DEPRESSURIZATION ACTUATION F VALVES 036209 30-DAY UNCTIONAL' TEST.
1                                   STONE & WEBSTER ENG. CORP.
THE HEALTH AND SAFETY OF THE GENERAL-PUBLIC WERE NOT AF BUTTERFLY FECTED. SINCE REDUNDANT VALVES PROVIDED SIMILAR FUNCTIONS TO THE FAILED COMPONENT FAILURE VALVES.
                                                                                                                                                                                                                                      ~ THE PORV WAS DECLARED INOPERABLE DUE TO LOW NITROGEN PRESSURE CAUSED BY FREQUENT CYCLING OF THE VALVE TO REDUCE THE RCS PRESSURE TO ATMOSPHERIC WHEN THE UNIT WAS BEING PREPARED FOR REFUELING. A VENT PATH OF GREATER 1
THIS IS CONTRARY TO TECHNICAL SPECIFICATION 3.7.4.1 3.6.2.2 A ELECTRICAL HD REPORTABLE PURSUANT TO TECHNICAL SPECIFICATION 6.9.1.9 D.
                                                                                                                                                                                                                                        . THAN 2.07 SQUARE INCHES WAS ESTABLISHED AS PER' TECH. SPEC. 3.4.9.3.
DEVIATION ALLIS CHALMERS REPORTS SUBMITTED ON 91-06-81 MOV-SW-105C FAILED TO OPERATE BECAUSE OF A LOOSE LEAD ON THE BREAKER / CON TROLLER.
                                ' NORTH. ANNA-1                                                                                                                                                   05000338           018481               ON 1/4/81, WITH UNIT IN MODE 5. LOOP 3 REACTOR COOLANT FLOW PROTECTION C REACTOR TRIP SYSTEMS                                                                                                                                       81-003/03L-0           012981               HANNEL II (F-1435) WAS FOUND OUT OF TOLERANCE HIGH DURING THE 18 MONTH P.
MOV-SW-108A FAILED TO OPERATE BECAUSE OF WATER IN THE MOTCR AN D THE CAUSE FOR MOV-RS-101A FAILURE TO OPERATE IS UNKNOWN.
9
EACH VALVE W AS REPAIRED AS REQUIRED, AND WILL BE RETESTED PRIOR TO ENTRY INTO MODE 4 NORTH ANNA-1
                                  -INSTRUMENTATION + CONTROLS                                                                                                                                     036112-           30-DAY               ERIODIC CHANHEL CALIBRATION CHECK. WORST CASE WOULD HAVE CAUSED BOTH IN TRANSMITTER                                                                                                                                                                                           DICATOR & COMPUTER POINT TO READ 3.99% HIGHER THAN ACTUAL, RESULTING IN COMPONENT FAILURE                                                                                                                                                                                       A DELAYED REACTOR TRIP SIGNAL ON LOW FLOW FOR THAT CHANNEL. BECAUSE RED INSTRUMENT                                                                                                                                                                                         ' UNDANT LOOP' FLOW INSTRUMENTATION WAS OPERATIONAL, HEALTH / SAFETY OF PUBLI FOXBORO CO., THE                                                                                                                                                                                       C WAS NOT AFFECTED. REPORTABLE PURSUANT TO TECH. SPEC. 6.9.1.9.A.
~ 05C00338 123180 DURING MODE 5 OPERATION, A PRESSURIZER POWER OPERATED RELIEF VALVE WAS D~
THE CAUSE OF THE ERROR IN INDICATION WAS A VOLTAGE DRIFT IN THE FLOW TRA NSMITTER SERVING THE INSTRUMENT LOOP.       CORRECTIVE ACTION WAS TO PROPERLY'         1 RECALIBRATE THE CHANNEL IN ACCORDANCE WITH - APPROVED CALIBRATION PROCEDU RES AND RETURN IT TO SERVICE.
OTHER COOLANT SUBSYS + CONTROL 81-002/03L-0 011581 ECLARED INOPERABLE BECAUSE OF LOW HITROGEN GAS SUPPLY TANK PRESSURE IN 1 i
NORTH ANNA-1                                                                                                                                                   05000338           010681               WHILE PERFORMING TYPE "C" PENETRATION LEAK TESTING. IT WAS DETERMINED TO CNTHMNT ISOLATION SYS + CONT                                                                                                                               81-0 0 9/ 0 3 L-0     012881                 DATE THAT 14 VALVES HAD COMBINED LEAMAGE THAT-EXCEEDED. ALLOWABLE LIMITS             s VALVES-                                                                                                                                                         036113             30-DAY               . SINCE THE PENEfRATIONS CONTAINING THE LEAKING VALVES DID HAVE ADDDITI OTHER                                                                                                                                                                                                 ONAL ISOLATION VALVES OR'WERE IN CLOSED SYSTEMS, THE HEALTH AND SAFETY 0 COMPONENT FAILURE                                                                                                                                                                                       F THE PUBLIC WAS NOT JEOPARDIZED. THIS EVENT IS REPORTABLE PER TECHNICA.
UALVES 036208 30-DAY
OTHER                                                                                                                                                                                                 L SPECIFICATION 6.9.1.9.D.
-GN-TK-1A.
A REACTOR COOL ANT SYSTEM VENT OF GREATER THAN 2.07 SQUARE IN l
OTHER CHES WAS ESTABLISHED IN ACCORDANCE WITH TECH. SPEC.
3.4.9.3.
THEREFORE, DESIGN / FABRICATION ERROR
-THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED. THIS ITEM IS RE DESIGN PORTABLE PURSUANT TO LECH.. SPEC.
6.9.1.9.B.
1 STONE & WEBSTER ENG. CORP.
~ THE PORV WAS DECLARED INOPERABLE DUE TO LOW NITROGEN PRESSURE CAUSED BY FREQUENT CYCLING OF THE VALVE TO REDUCE THE RCS PRESSURE TO ATMOSPHERIC WHEN THE UNIT WAS BEING PREPARED FOR REFUELING. A VENT PATH OF GREATER 1
. THAN 2.07 SQUARE INCHES WAS ESTABLISHED AS PER' TECH. SPEC. 3.4.9.3.
' NORTH. ANNA-1 05000338 018481 ON 1/4/81, WITH UNIT IN MODE 5. LOOP 3 REACTOR COOLANT FLOW PROTECTION C REACTOR TRIP SYSTEMS 81-003/03L-0 012981 HANNEL II (F-1435) WAS FOUND OUT OF TOLERANCE HIGH DURING THE 18 MONTH P.
-INSTRUMENTATION + CONTROLS 036112-30-DAY ERIODIC CHANHEL CALIBRATION CHECK. WORST CASE WOULD HAVE CAUSED BOTH IN 9
TRANSMITTER DICATOR & COMPUTER POINT TO READ 3.99% HIGHER THAN ACTUAL, RESULTING IN COMPONENT FAILURE A DELAYED REACTOR TRIP SIGNAL ON LOW FLOW FOR THAT CHANNEL. BECAUSE RED INSTRUMENT
' UNDANT LOOP' FLOW INSTRUMENTATION WAS OPERATIONAL, HEALTH / SAFETY OF PUBLI FOXBORO CO., THE C WAS NOT AFFECTED. REPORTABLE PURSUANT TO TECH. SPEC. 6.9.1.9.A.
THE CAUSE OF THE ERROR IN INDICATION WAS A VOLTAGE DRIFT IN THE FLOW TRA NSMITTER SERVING THE INSTRUMENT LOOP.
CORRECTIVE ACTION WAS TO PROPERLY' 1
RECALIBRATE THE CHANNEL IN ACCORDANCE WITH - APPROVED CALIBRATION PROCEDU RES AND RETURN IT TO SERVICE.
NORTH ANNA-1 05000338 010681 WHILE PERFORMING TYPE "C" PENETRATION LEAK TESTING. IT WAS DETERMINED TO CNTHMNT ISOLATION SYS + CONT 81-0 0 9/ 0 3 L-0 012881 DATE THAT 14 VALVES HAD COMBINED LEAMAGE THAT-EXCEEDED. ALLOWABLE LIMITS s
VALVES-036113 30-DAY
. SINCE THE PENEfRATIONS CONTAINING THE LEAKING VALVES DID HAVE ADDDITI OTHER ONAL ISOLATION VALVES OR'WERE IN CLOSED SYSTEMS, THE HEALTH AND SAFETY 0 COMPONENT FAILURE F THE PUBLIC WAS NOT JEOPARDIZED. THIS EVENT IS REPORTABLE PER TECHNICA.
OTHER L SPECIFICATION 6.9.1.9.D.
OTHER VALVE LEAKAGE IS BELIEVED TO BE DUE TO DETERIORATION OF VALVE SEATS'AND.
OTHER VALVE LEAKAGE IS BELIEVED TO BE DUE TO DETERIORATION OF VALVE SEATS'AND.
IN THE CASE OF MOV-HV-100D, THE LIMIT SWITCH WAS IMPROPERLY SET PREVENTI NG FULL CLOSURE OF THE VALVE.       IN ALL CASES, VALVES WILL BE REWORKED OR ADJUSTED UNTIL TOTAL-CONTAINMENT TYPE "C" LEAKAGE IS ACCEPTABLE.
IN THE CASE OF MOV-HV-100D, THE LIMIT SWITCH WAS IMPROPERLY SET PREVENTI NG FULL CLOSURE OF THE VALVE.
l m--yi---q,.-           W           w--+g g                     .. af-     _____t___
IN ALL CASES, VALVES WILL BE REWORKED OR ADJUSTED UNTIL TOTAL-CONTAINMENT TYPE "C" LEAKAGE IS ACCEPTABLE.
l m--yi---q,.-
W w--+g g
af-t


MAR 26, 1981                                                                                               LER MONTHLY REPORT SORTED BY FACILITY                                       PAGE $7 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                 DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE $7 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                     CONTROL NO. REPORT TYPE                               CAUSE DESCRIPTION HORTH ANNA-1                                                                                   05000338     011381     ON JANUARY 13, 1981, WHILE IN MODE 6 OPERATION, THE PRESSURIZER PRESSURE REACTOR TRIP SYSTEMS                                                               81-006/03L-0   012981     TRANSMITTER PT 1457 WAS FOUND TO BE OUT OF CALIBRATION BY 100 MVAC. TH INSTRUMENTATION + CONTROLS                                                           036210     30-DAY     IS WOULD CAUSE THE HIGH PRESSURE REACTOR TRIP SIGNAL TO ENERGIZE 10 PSI TRANSMITTER                                                                                         HIGHER THAN THE ALLOWED SET POINT (2405 PSI RATHER THAN 2395 PSI). SINC COMPONENT FAILURE                                                                                           E THE UNIT WAS IN MODE 6,   THERE WAS NO EFFECT ON THE HEALTH AND SAFETY 0 ELECTRONIC                                                                                         F THE PUBLIC. THIS ITEM IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICATI WESTINGHOUSE ELECTRIC CORP.                                                                                   OH 6.9.1.9.A.
EVENT DATE/
THIS EVENT WAS CAUSED BY INSTRUMENT DRIFT. THE CHANNEL WAS RFCALIBRATED AND RETURNED TO SERVICE.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
NORTH ANNA-1                                                                                   05000338     011781     ON 1/17/81, WHILE IN REFUELING MODE,   "A" STEAM GENERATOR PROTECTION CHAN ENGNRD SAFETY FEATR INSTR SYS                                                     81-008/03L-0   021181     NEL II HARROW RANGE LEVEL TRANSMITTER LT-147S WAS FOUND TO BE OUT OF CAL INSTRUMENTATION + CONTROLS                                                           036115     30-DAY     IBRATION-LOW. WORST CASE WOULD HAVE CAUSED INDICATOR TO READ 2.7% LOWER TRANSMITTER                                                                                         THAN ACTUAL, RESULTING IN DELAYED TURBINE TRIP 8 FEEDWATER ISOLATION SI COMPONENT FAILURE                                                                                             GNALS ON HI-HI LEVEL FCR THAT CHANNEL. BECAUSE REDUNDANT HARROW RANGE L INSTRUMENT                                                                                         EVEL INSTRUMENTATION WAS EITHER OPERATIONAL OR IN TRIPPED CONDITION, HEA ROSEMOUNT, INC.                                                                                               LTH/ SAFETY OF PUBLIC NOT AFFECTED. REPORTABLE PER T.S. 6.9.1.9.A.
REPORT DATE/
THE CAUSE OF THE ERROR IN INDICATION WAS A VOLTAGE DRIFT IN THE LEVEL TR ANSMITTER SERVING THE INSTRUMENT LOOP. THE CHANNEL WAS SATISFACTORILY R ECALIBRATED AND RETURNED TO SERVICE.
EVENT DESCRIPTION /
NORTH ANNA-1                                                                                   05000338     011781     ON JANUARY 17, 1981, WITH UNIT 1 IN MODE 6, A LOSS OF POWER TO THE RADIA CREA MONITORING SYSTEMS                                                             81-011/03L-0   02118t     TION MONITOR COMMON ALARMS PANEL UAS EXPERIENCED FOR A PERIOD OF TIME OF INSTRUMENTATION + CONTROLS                                                           036116     30-DAY     LESS THAN FIVE MINUTES. SINCE THE POWER TO THE ALARMS WAS QUICKLY REST OTHER                                                                                               ORED WITHIN THE TIME REQUIREMENTS OF THE LCO, THE HEALTH AND SAFETY OF T PERSONNEL ERROR                                                                                               HE PUBLIC WERE NOT AFFECTED.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION HORTH ANNA-1 05000338 011381 ON JANUARY 13, 1981, WHILE IN MODE 6 OPERATION, THE PRESSURIZER PRESSURE REACTOR TRIP SYSTEMS 81-006/03L-0 012981 TRANSMITTER PT 1457 WAS FOUND TO BE OUT OF CALIBRATION BY 100 MVAC.
TH INSTRUMENTATION + CONTROLS 036210 30-DAY IS WOULD CAUSE THE HIGH PRESSURE REACTOR TRIP SIGNAL TO ENERGIZE 10 PSI TRANSMITTER HIGHER THAN THE ALLOWED SET POINT (2405 PSI RATHER THAN 2395 PSI).
SINC COMPONENT FAILURE E THE UNIT WAS IN MODE 6, THERE WAS NO EFFECT ON THE HEALTH AND SAFETY 0 ELECTRONIC F THE PUBLIC.
THIS ITEM IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICATI WESTINGHOUSE ELECTRIC CORP.
OH 6.9.1.9.A.
THIS EVENT WAS CAUSED BY INSTRUMENT DRIFT.
THE CHANNEL WAS RFCALIBRATED AND RETURNED TO SERVICE.
NORTH ANNA-1 05000338 011781 ON 1/17/81, WHILE IN REFUELING MODE, "A" STEAM GENERATOR PROTECTION CHAN ENGNRD SAFETY FEATR INSTR SYS 81-008/03L-0 021181 NEL II HARROW RANGE LEVEL TRANSMITTER LT-147S WAS FOUND TO BE OUT OF CAL INSTRUMENTATION + CONTROLS 036115 30-DAY IBRATION-LOW. WORST CASE WOULD HAVE CAUSED INDICATOR TO READ 2.7% LOWER TRANSMITTER THAN ACTUAL, RESULTING IN DELAYED TURBINE TRIP 8 FEEDWATER ISOLATION SI COMPONENT FAILURE GNALS ON HI-HI LEVEL FCR THAT CHANNEL.
BECAUSE REDUNDANT HARROW RANGE L INSTRUMENT EVEL INSTRUMENTATION WAS EITHER OPERATIONAL OR IN TRIPPED CONDITION, HEA ROSEMOUNT, INC.
LTH/ SAFETY OF PUBLIC NOT AFFECTED. REPORTABLE PER T.S.
6.9.1.9.A.
THE CAUSE OF THE ERROR IN INDICATION WAS A VOLTAGE DRIFT IN THE LEVEL TR ANSMITTER SERVING THE INSTRUMENT LOOP.
THE CHANNEL WAS SATISFACTORILY R ECALIBRATED AND RETURNED TO SERVICE.
NORTH ANNA-1 05000338 011781 ON JANUARY 17, 1981, WITH UNIT 1 IN MODE 6, A LOSS OF POWER TO THE RADIA CREA MONITORING SYSTEMS 81-011/03L-0 02118t TION MONITOR COMMON ALARMS PANEL UAS EXPERIENCED FOR A PERIOD OF TIME OF INSTRUMENTATION + CONTROLS 036116 30-DAY LESS THAN FIVE MINUTES. SINCE THE POWER TO THE ALARMS WAS QUICKLY REST OTHER ORED WITHIN THE TIME REQUIREMENTS OF THE LCO, THE HEALTH AND SAFETY OF T PERSONNEL ERROR HE PUBLIC WERE NOT AFFECTED.
MAINTENANCE a REPAIR PERSONNEL WESTINGHOUSE ELECTRIC CORP.
MAINTENANCE a REPAIR PERSONNEL WESTINGHOUSE ELECTRIC CORP.
THIS INCIDENT OCCURRED WITH AN ELECTRICIAN TRIPPING THE UNIT 1 480V BREA KER FOR THE COMMON RAD ALARM PANEL (AFTER VERIFYING UNIT 2-480V BREAKER CLOSED) BUT WITHOUT HAVING SWITCHED POWER TO UNIT 2 VIA A REMOTE SWITCH.
THIS INCIDENT OCCURRED WITH AN ELECTRICIAN TRIPPING THE UNIT 1 480V BREA KER FOR THE COMMON RAD ALARM PANEL (AFTER VERIFYING UNIT 2-480V BREAKER CLOSED) BUT WITHOUT HAVING SWITCHED POWER TO UNIT 2 VIA A REMOTE SWITCH.
CORRECTIVE ACTION INCLUDED RESTORING POWER AND INFORMING THE MAINTENANC E PERSONNEL OF THEIR ERROR.
CORRECTIVE ACTION INCLUDED RESTORING POWER AND INFORMING THE MAINTENANC E PERSONNEL OF THEIR ERROR.
NORTH ANNA-1                                                                                   05000338     011881     ON 1/18/81, WITH REFUELING OPERATIONS IN PROGRESS FUEL BLDG SUPPLY 8 EX QIR COND, HEAT, COOL, VENT SYSTEM                                                   81-012/03L-0   021781     HAUST FANS TRIPPED OUT ON THE FREEZE PROTECTION INTERLOCK & EXHAUST FAN BLOWERS                                                                               036114     30-DAY     SUCTION DAMPERS SWITCHED TO THEIR FAILED POSITION BYPASSING IODINE FILTE SUBCOMPONENT NOT APPLICABLE                                                                         R BANK WHEN CONTROL AIR WAS INADVERTENTLY ISOLATED. BECAUSE OPERATIONS EXTERNAL CAUSE                                                                                               WAS INITI ALLY UNAWARE OF REPOSITIONING, FUEL MOVEMENT WAS ALLOWED TO RES NOT APPLICABLE                                                                                       UME WITH FUEL BLDG EXHAUST AIR DIVERTED FROM FILTERS. PUBLIC HEALTH & S BUFFALO FORGE                                                                                                 AFETY WERE NOT AFFECTED. REPORTABLE PURSUANT TO TECH SPEC 6.9.1.9.B.
NORTH ANNA-1 05000338 011881 ON 1/18/81, WITH REFUELING OPERATIONS IN PROGRESS FUEL BLDG SUPPLY 8 EX QIR COND, HEAT, COOL, VENT SYSTEM 81-012/03L-0 021781 HAUST FANS TRIPPED OUT ON THE FREEZE PROTECTION INTERLOCK & EXHAUST FAN BLOWERS 036114 30-DAY SUCTION DAMPERS SWITCHED TO THEIR FAILED POSITION BYPASSING IODINE FILTE SUBCOMPONENT NOT APPLICABLE R BANK WHEN CONTROL AIR WAS INADVERTENTLY ISOLATED. BECAUSE OPERATIONS EXTERNAL CAUSE WAS INITI ALLY UNAWARE OF REPOSITIONING, FUEL MOVEMENT WAS ALLOWED TO RES NOT APPLICABLE UME WITH FUEL BLDG EXHAUST AIR DIVERTED FROM FILTERS. PUBLIC HEALTH & S BUFFALO FORGE AFETY WERE NOT AFFECTED. REPORTABLE PURSUANT TO TECH SPEC 6.9.1.9.B.
FANS TRIPPED BECAUSE OF LOW OUTDOOR TEMPERATURE. TO RAISE DUCT HEATING COIL DISCHARGE TEMP, STEAM VALVES WERE FAILED OPEN BY ISOLATING AIR TO A PANEL WHICH ALSO INADVERTENTLY ISOLATED AIR TO THE EXHAUST AIR DAMPERS.
FANS TRIPPED BECAUSE OF LOW OUTDOOR TEMPERATURE. TO RAISE DUCT HEATING COIL DISCHARGE TEMP, STEAM VALVES WERE FAILED OPEN BY ISOLATING AIR TO A PANEL WHICH ALSO INADVERTENTLY ISOLATED AIR TO THE EXHAUST AIR DAMPERS.
OPERATIONS HAD NO INDICATION DUE TO DESIGN OF DAMPER POSITION SWITCHES.
OPERATIONS HAD NO INDICATION DUE TO DESIGN OF DAMPER POSITION SWITCHES.
UPON DISCOVERY, DAMPERS WERE POSITIONED TO EXHAUST THROUGH THE FILTER.
UPON DISCOVERY, DAMPERS WERE POSITIONED TO EXHAUST THROUGH THE FILTER.


MAR 26, 1981                                                                     LER MONTHLY REPCRT SORTED BY FACILITY                                             PAGE 58 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                             DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPCRT SORTED BY FACILITY PAGE 58 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                   REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                 CONTROL NO. REPORT' TYPE                                 CAUSE DESCRIPTION NORTH ANNA-1                                                         05000338     012481     DURING THE LAST REFUELING OUTAGE, THE FIRST ROW OF TUBES IN EACH STEAM G REACTOR VES. + APPURTENANCES                                     81-007/99X-0   020481     ENERATOR WAS EXPLOSIVELY PLUGGED DUE TO OBSERVED DEFECTS IN THE TUBE MAN
EVENT DATE/
-HEAT EXCHANGERS                                                     03606S     OTHER     UFACTURING. ON JANUARY 15, 1981,     "C" STEAM GEMERATOR TUBE INS"ECTIONS R STEAM GENERATOR                                                                           EVEALED THE PLUG MISSING FROM THE TUBE AT ROW 1. COLUMN 12.         THE TUBE WA OTHER                                                                                       S REPLUGGED ON JANUARY 24, 1981       THIS INFORMATION IS BEING SUBMITTED TO NOT APPLICABLE                                                                             SATISFY THE REPORTING REQUIREMENTS OF TECHNICAL SPECIFICATION 4.4.S.S.A WESTINGHOUSE ELECTRIC CORP.                                                                 . HEALTH 8 SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED BY THIS EVENT THE TUBE PLUG FELL OUT DURING UNIT OPERATION BECAUSE OF A BAD SEAL WHICH CAN RESULT WHEN PLUGS ARE INSTALLED BY EXPLOSIVE CHARGE. CORRECTIVE AC TION WAS TO REPLUG THE TUBE MECHANICALLY.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
NORTH ANNA-2                                                         0S000339     123080     ON DECEMBER 30, 1980, WHILE OPERATING AT 100% POWER, THE BORON INJECTION EMERG CORE COOLING SYS + CONT                                     81-007/03L-0   012681       TANK AND THE UNIT'S BORIC ACID STORAGE TANK ("C" BAST) WERE SAMPLED AND ACCUMULATORS                                                         036211     30-DAY       FOUND TO CONTAIN A BORON CGNCENTRATION BELOW THE TECHNICAL SPECIFICATI0 SUBCOMPONENT NOT APPLICABLE                                                               N LIMIT r / 20,000 PPM. REDUNDANT SYSTEMS HAVING THE REQUIRED CAPABILITY COMPONENT FAILURE                                                                             FOR ret, TOR CONTROL WERE OPERABLE, AS A RESULT THE HEALTH AND SAFETY OF OTHER                                                                                       THE GENERAL PUBLIC WERE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUAN WESTINGHOUSE ELtCTRIC CORP.                                                                 T TO TECHNICAL SPECIFICATION 6.9.1.9.B.
REPORT DATE/
IHLEAKAGE FROM AN UNKNOUN SOURCE IS BELIEVED TO BE DILUTING BIT SOLUTION WHICH IS ON RECIRC UITH "C" BAST. BORIC ACID WAS BATCHED 8 TRANSFERRED TO "C" BAST UNTIL CHEMISTRY WAS RESTORED TO SPECS.         SAMPLING FREQUENCY OF TANK HAS BEE 4 CHANGED FROM UEEKLY TO DAILY 8 RESULTS ARE BEING PLOTTE D UNTIL LEAK IS FOUND 8 ISOLATED TO ENSURE CORRECT CHEMISTRY.
EVENT DESCRIPTION /
NORTH ANNA-2                                                         05000339     010681     ON JANUARY 6,   1981, DURING STEADY STATE OPERATION, A GREATER THAN 12 STE OTHR INST SYS REQD FOR SAFETY                                     81-005/03L-0   012881     P DISAGREEMENT WAS NOTED BETWEEN THE INDIVIDUAL ROD POSITION INDICATION INSTRUMENTATION + CONTROLS                                           036118     30-DAY     FOR ROD B08 IN CONTROL BANK "D" AND THE GROUP DEMAND POSITION. THE IRPI INDICATOR                                                                                   WAS IMMEDIATELY RECALIBRATED AND CORRECT INDICATION RESTORED, CONSEQUEN COMPONENT FAILURE                                                                           TLY THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED. THIS INSTRUMENT                                                                                 EVENT IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICATION 6.9.1.9.B.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT' TYPE CAUSE DESCRIPTION NORTH ANNA-1 05000338 012481 DURING THE LAST REFUELING OUTAGE, THE FIRST ROW OF TUBES IN EACH STEAM G REACTOR VES. + APPURTENANCES 81-007/99X-0 020481 ENERATOR WAS EXPLOSIVELY PLUGGED DUE TO OBSERVED DEFECTS IN THE TUBE MAN
-HEAT EXCHANGERS 03606S OTHER UFACTURING. ON JANUARY 15, 1981, "C" STEAM GEMERATOR TUBE INS"ECTIONS R STEAM GENERATOR EVEALED THE PLUG MISSING FROM THE TUBE AT ROW 1.
COLUMN 12.
THE TUBE WA OTHER S REPLUGGED ON JANUARY 24, 1981 THIS INFORMATION IS BEING SUBMITTED TO NOT APPLICABLE SATISFY THE REPORTING REQUIREMENTS OF TECHNICAL SPECIFICATION 4.4.S.S.A WESTINGHOUSE ELECTRIC CORP.
. HEALTH 8 SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED BY THIS EVENT THE TUBE PLUG FELL OUT DURING UNIT OPERATION BECAUSE OF A BAD SEAL WHICH CAN RESULT WHEN PLUGS ARE INSTALLED BY EXPLOSIVE CHARGE.
CORRECTIVE AC TION WAS TO REPLUG THE TUBE MECHANICALLY.
NORTH ANNA-2 0S000339 123080 ON DECEMBER 30, 1980, WHILE OPERATING AT 100% POWER, THE BORON INJECTION EMERG CORE COOLING SYS + CONT 81-007/03L-0 012681 TANK AND THE UNIT'S BORIC ACID STORAGE TANK ("C" BAST) WERE SAMPLED AND ACCUMULATORS 036211 30-DAY FOUND TO CONTAIN A BORON CGNCENTRATION BELOW THE TECHNICAL SPECIFICATI0 SUBCOMPONENT NOT APPLICABLE N LIMIT r / 20,000 PPM.
REDUNDANT SYSTEMS HAVING THE REQUIRED CAPABILITY COMPONENT FAILURE FOR ret, TOR CONTROL WERE OPERABLE, AS A RESULT THE HEALTH AND SAFETY OF OTHER THE GENERAL PUBLIC WERE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUAN WESTINGHOUSE ELtCTRIC CORP.
T TO TECHNICAL SPECIFICATION 6.9.1.9.B.
IHLEAKAGE FROM AN UNKNOUN SOURCE IS BELIEVED TO BE DILUTING BIT SOLUTION WHICH IS ON RECIRC UITH "C" BAST.
BORIC ACID WAS BATCHED 8 TRANSFERRED TO "C" BAST UNTIL CHEMISTRY WAS RESTORED TO SPECS.
SAMPLING FREQUENCY OF TANK HAS BEE 4 CHANGED FROM UEEKLY TO DAILY 8 RESULTS ARE BEING PLOTTE D UNTIL LEAK IS FOUND 8 ISOLATED TO ENSURE CORRECT CHEMISTRY.
NORTH ANNA-2 05000339 010681 ON JANUARY 6, 1981, DURING STEADY STATE OPERATION, A GREATER THAN 12 STE OTHR INST SYS REQD FOR SAFETY 81-005/03L-0 012881 P DISAGREEMENT WAS NOTED BETWEEN THE INDIVIDUAL ROD POSITION INDICATION INSTRUMENTATION + CONTROLS 036118 30-DAY FOR ROD B08 IN CONTROL BANK "D" AND THE GROUP DEMAND POSITION. THE IRPI INDICATOR WAS IMMEDIATELY RECALIBRATED AND CORRECT INDICATION RESTORED, CONSEQUEN COMPONENT FAILURE TLY THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED.
THIS INSTRUMENT EVENT IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICATION 6.9.1.9.B.
WESTINGHOUSE ELECTRIC CORP.
WESTINGHOUSE ELECTRIC CORP.
THE CAUSE OF THIS INDICATOR DISAGREEMENT WAS A VOLTAGE DRIFT IN THE SIGN AL CONDITIONING CARD. THIS IS A RECURRING PROBLEM AND IS GENERIC TO WES TINGHOUSE ANOLOG ROD POSITION INDICATION SYSTEMS. THE ROD POSITION INDI CATOR CHANNEL FOR B08 WAS SATISFACTORILY RECALIBRATED AND RETURNED TO SE RVICE.
THE CAUSE OF THIS INDICATOR DISAGREEMENT WAS A VOLTAGE DRIFT IN THE SIGN AL CONDITIONING CARD.
NORTH ANNA-2                                                         0S000339     010781     ON JANUARY 7,   1981. WITH UNIT AT 1% POWER, THE AVERAGE REACTOR COOLANT S OTHR INST SYS REQD FOR SAFETY                                     81-006/03L-O   020481     YSTEM TEMPERATURE WAS LESS THAN S41 F WITH THE REACTOR CRITICAL ON TWO O COMPONENT CODE NOT APPLICABLE                                       036064     30-DAY     CCASIONS. HOWEVER, ON EACH OCCASION, THE TEMPERATURE WAS RESTORED TO WI SUBCOMPONENT NOT APPLICABLE                                                               THIN ITS LIMITS (>/: S41 F) WITHIH IS MINUTES AS REQUIRED BY TECHNICAL S PERSONNEL ERROR                                                                             PECIFICATIONS. CONSEQUENTLY, THE HEALTH AND SAFETY OF THE PUBLIC WERE N LICENSED 8 SENIOR OPERATORS                                                               OT AFFECTED.
THIS IS A RECURRING PROBLEM AND IS GENERIC TO WES TINGHOUSE ANOLOG ROD POSITION INDICATION SYSTEMS.
THE ROD POSITION INDI CATOR CHANNEL FOR B08 WAS SATISFACTORILY RECALIBRATED AND RETURNED TO SE RVICE.
NORTH ANNA-2 0S000339 010781 ON JANUARY 7, 1981. WITH UNIT AT 1% POWER, THE AVERAGE REACTOR COOLANT S OTHR INST SYS REQD FOR SAFETY 81-006/03L-O 020481 YSTEM TEMPERATURE WAS LESS THAN S41 F WITH THE REACTOR CRITICAL ON TWO O COMPONENT CODE NOT APPLICABLE 036064 30-DAY CCASIONS. HOWEVER, ON EACH OCCASION, THE TEMPERATURE WAS RESTORED TO WI SUBCOMPONENT NOT APPLICABLE THIN ITS LIMITS (>/: S41 F) WITHIH IS MINUTES AS REQUIRED BY TECHNICAL S PERSONNEL ERROR PECIFICATIONS. CONSEQUENTLY, THE HEALTH AND SAFETY OF THE PUBLIC WERE N LICENSED 8 SENIOR OPERATORS OT AFFECTED.
ITEM NOT APPLICA6LE EACH EVENT WAS CAUSED BY OVERFEEDING OF THE STEAM GENERATORS. DUE TG FEE DWATER CONTROL PROBLEMS, AND DECREASING REACTOR COOLANT TEMPERATURES DUE TO XENON BUILDUP. CORRECTIVE ACTION WAS YO SECURE FEEDING THE STEAM GEN ERATORS, TO CLOSE THE CONDENSER STEAM DUMPS AND TO INCREASE REACTOR TEJP ERATURE BY DILUTION AND PULLING THE CONTROL RODS.
ITEM NOT APPLICA6LE EACH EVENT WAS CAUSED BY OVERFEEDING OF THE STEAM GENERATORS. DUE TG FEE DWATER CONTROL PROBLEMS, AND DECREASING REACTOR COOLANT TEMPERATURES DUE TO XENON BUILDUP. CORRECTIVE ACTION WAS YO SECURE FEEDING THE STEAM GEN ERATORS, TO CLOSE THE CONDENSER STEAM DUMPS AND TO INCREASE REACTOR TEJP ERATURE BY DILUTION AND PULLING THE CONTROL RODS.
e                                                                     m- - ,                  -s
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4 MAR 26, 1981                                                                                                                           LER MONTHLY REPORT SORTED BY FACILITY                                                         PAGE 59 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                 DOCKET NO./                                                     EVENT DATE/
i 4
COMPONENT SUBCC7E/CAUSE CODE / LER NO./                                                                                         REPORT DATE/                                           EVE     DESCRIPTION /
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 59 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
CAUSE SUBCODE/ MANUFACTURER                                     CONTROL NO.                                                     REPORT TYPE                                             CAUSL 1ESCRIPTION NORTH ANNA-2                                                               05000339                                                   010781     ON JANUARY 7,             1981, UNIT 2 WENT ON LINE AFTER AN EIGHT HOUR CUTAGE AND I SYSTEM CODE NOT APPLICABLE                                             81-008/03L-0                                                   020281     NCREASED POWER TO 30 PERCENT OF RATED THERMAL POWER.                     A PRIMARY COOLANT COMPONENT CODE NOT APPLICABLE                                                       036066                                             30-DAY     10 DINE ISOTOPIC ANALYSIS WAS NOT MADE WITHIN 2 TO 6 HOURS AS REQUIRED BY SUBCOMPONENT NOT APPLICABLE                                                                                                                       THE TECHNICAL SPECIFICATION FOR PCNER CHANGES EXCEEDING 15 PERCENT IN O PERSONNEL ERROR                                                                                                                                   NE HOUR.             THIS EVENT IS REPORTAELE PURSUANT TD-TECH. SPEC. 6.9.1.9.C. T LICENSED & SENIOR OPERATORS                                                                                                                     HE PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
DOCKET NO./
ITEM NOT APPLICABLE OPERATIONS PERSONNEL FAILED TO FOLLOW PROCEDURES AND TAILED TO NOTIFY CH EMISTRY PERSOMNZL THAT A PRIMARY COOLANT IODINE ISOTOPIC ANALYSIS WAS RE QUIRED.             A SAMPLE OF PRIMARY COOLANT WAS COLLECTED AND ANALYZED IMMEDIAT ELY AFTER THE NEED WAS IDENTIFIED. PERSONNEL INVOLVED WENE REINSTRUCTED TO ADHERE TO PROCEDUkE REQUIREMENTS.
EVENT DATE/
NORTH ANNA-2                                                               05000339                                                   010781     ON JANUARY             1, 1981 DURING MODE 1 OPERATION, THE FLUX TENALTY SUMMINO AM REACTOR TRIP SYSTEMS                                                 81-004/03X-1                                                     012981     PLIFIER (NM-432A) WAS FOUND TO BE FAILED DURING A LOOP CALIBRA(ION CHECK' INSTRUMENTATION + CONTROLS                                                         036117                                             OTHER           THE FAILED CHANNEL IJAS IN THE TRIP POSITION AND THE REMAINING CHANNEL COMPUTATION MODULE                                                                                                                               .WAS FUNCTIONING PROPERLY.                THEREFORE, THE HEALTH AND SAFETY OF THE PUBL COMPONENT FAILURE                                                                                                                                 IC WERE NOT AFFECTED. THIS ITEM IS REPORTABLE PURSUANT TO TECHNICAL SPE ELECTRONIO                                                                                                                                     CIFICATIDH 6.9.1.9.B.
COMPONENT SUBCC7E/CAUSE CODE / LER NO./
REPORT DATE/
EVE DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSL 1ESCRIPTION NORTH ANNA-2 05000339 010781 ON JANUARY 7, 1981, UNIT 2 WENT ON LINE AFTER AN EIGHT HOUR CUTAGE AND I SYSTEM CODE NOT APPLICABLE 81-008/03L-0 020281 NCREASED POWER TO 30 PERCENT OF RATED THERMAL POWER.
A PRIMARY COOLANT COMPONENT CODE NOT APPLICABLE 036066 30-DAY 10 DINE ISOTOPIC ANALYSIS WAS NOT MADE WITHIN 2 TO 6 HOURS AS REQUIRED BY SUBCOMPONENT NOT APPLICABLE THE TECHNICAL SPECIFICATION FOR PCNER CHANGES EXCEEDING 15 PERCENT IN O PERSONNEL ERROR NE HOUR.
THIS EVENT IS REPORTAELE PURSUANT TD-TECH. SPEC.
6.9.1.9.C.
T LICENSED & SENIOR OPERATORS HE PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
ITEM NOT APPLICABLE OPERATIONS PERSONNEL FAILED TO FOLLOW PROCEDURES AND TAILED TO NOTIFY CH EMISTRY PERSOMNZL THAT A PRIMARY COOLANT IODINE ISOTOPIC ANALYSIS WAS RE QUIRED.
A SAMPLE OF PRIMARY COOLANT WAS COLLECTED AND ANALYZED IMMEDIAT ELY AFTER THE NEED WAS IDENTIFIED. PERSONNEL INVOLVED WENE REINSTRUCTED TO ADHERE TO PROCEDUkE REQUIREMENTS.
NORTH ANNA-2 05000339 010781 ON JANUARY 1,
1981 DURING MODE 1 OPERATION, THE FLUX TENALTY SUMMINO AM REACTOR TRIP SYSTEMS 81-004/03X-1 012981 PLIFIER (NM-432A) WAS FOUND TO BE FAILED DURING A LOOP CALIBRA(ION CHECK' INSTRUMENTATION + CONTROLS 036117 OTHER
.WAS FUNCTIONING PROPERLY.
THEREFORE, THE HEALTH AND SAFETY OF THE PUBL THE FAILED CHANNEL IJAS IN THE TRIP POSITION AND THE REMAINING CHANNEL COMPUTATION MODULE COMPONENT FAILURE IC WERE NOT AFFECTED. THIS ITEM IS REPORTABLE PURSUANT TO TECHNICAL SPE ELECTRONIO CIFICATIDH 6.9.1.9.B.
WESTI*;GHOUSE EL ECTRIC CORP.
WESTI*;GHOUSE EL ECTRIC CORP.
THIS FAILURE WAS CAUSED BY A FAULTY HSA CARD (C3-141).                     THE CARD WAS REP LACED AND CALIBRATED. THE LOOP CALIBRATION CHECK WAS PERFORMED AND THE CHAMNEL RETURNED TO SERVICE.
THIS FAILURE WAS CAUSED BY A FAULTY HSA CARD (C3-141).
NORTH ANNA-2                                                               05000339                                                   010781     ON JANUARY 7,             1981, WITH THE UNIT IN MODE     1, THE CONTAINMENT PERSONNEL H REACTOR CONTAINMENT SYSTEMS                                           81- 0 0 9/ 0 3 L-0                                               012981     ATCH DUTER DOOR LEAKED AIR PAST ITS SEALS DURING A LEAK TEST.                       SINCE THE PENETRATIONS,PRIMRY CONTAINMNT                                                     036212                                             30-DAY     INNER DOOR REMAINED OPERABLE AND THE OUTER DOOR WAS REPAIRED WITHIN 24 PERSONNEL ACCESS                                                                                                                                 HOURS THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED. TH COMPONENT FAtLURE                                                                                                                                 IS IS CONTRARY TO TECHN1LAL SPECIFICATION 3.6.1.3 AND REPORTABLE PURSUAN MECHANICAL                                                                                                                                       T TO TECHNICAL SPECIFICATION 6.9.1.9.B.
THE CARD WAS REP LACED AND CALIBRATED. THE LOOP CALIBRATION CHECK WAS PERFORMED AND THE CHAMNEL RETURNED TO SERVICE.
* CHICAGO BREDGE 8 IRON COMPANY THE CAUSE OF THE LEAKING SEALS ON THE OUTER HATCH DOOR WAS DUE TO IMPROP ER FITUP OF THE DOOR SEALS TO THE FRAME.                   THE OUTER HATCH DOOR WAS ADJUS TED TO ALLOW THE SEALS TG MATE PROPERLY AND THE LEAK TEST WAS PERFORMED SATISFACTORILY.
NORTH ANNA-2 05000339 010781 ON JANUARY 7, 1981, WITH THE UNIT IN MODE 1,
NORTH ANNA-2                                                               05000339                                                   011381     ON JANUARY 13, 1981, WITH UNIT 2 AT '00 PERCENT POWER. AN OVERSPEED TRIP CONDNSATE + FEEDWTR SYS + CONT                                       81-010/03L-0                                                     021181     0F THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP OCCURRED DURING SURVEILL.
THE CONTAINMENT PERSONNEL H REACTOR CONTAINMENT SYSTEMS 81- 0 0 9/ 0 3 L-0 012981 ATCH DUTER DOOR LEAKED AIR PAST ITS SEALS DURING A LEAK TEST.
MECHANICAL FUNCTION UNITS                                                           036119                                             30-DAY     ANCE TESTING. THIS EVENT IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICAT-SUBCOMPONENI NOT APPLICABLE                                                                                                                     ION 6.9.1.9.B. TWO REDUNDANT MOTOR. DRIVEN AUXILIARY FEEDWATER PUMPS WER COMPONENT FAILURE                                                                                                                                 E OPERABLE.               THE ACTION STATEMENT OF THE LCO WAS MET. THE PUBLIC HEALTH MECHANICAL                                                                                                                                       AND SAFETY WERE NOT AFFECTED.                                                                     ,
SINCE THE PENETRATIONS,PRIMRY CONTAINMNT 036212 30-DAY INNER DOOR REMAINED OPERABLE AND THE OUTER DOOR WAS REPAIRED WITHIN 24 PERSONNEL ACCESS HOURS THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED.
TH COMPONENT FAtLURE IS IS CONTRARY TO TECHN1LAL SPECIFICATION 3.6.1.3 AND REPORTABLE PURSUAN MECHANICAL T TO TECHNICAL SPECIFICATION 6.9.1.9.B.
CHICAGO BREDGE 8 IRON COMPANY THE CAUSE OF THE LEAKING SEALS ON THE OUTER HATCH DOOR WAS DUE TO IMPROP ER FITUP OF THE DOOR SEALS TO THE FRAME.
THE OUTER HATCH DOOR WAS ADJUS TED TO ALLOW THE SEALS TG MATE PROPERLY AND THE LEAK TEST WAS PERFORMED SATISFACTORILY.
NORTH ANNA-2 05000339 011381 ON JANUARY 13, 1981, WITH UNIT 2 AT '00 PERCENT POWER. AN OVERSPEED TRIP CONDNSATE + FEEDWTR SYS + CONT 81-010/03L-0 021181 0F THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP OCCURRED DURING SURVEILL.
MECHANICAL FUNCTION UNITS 036119 30-DAY ANCE TESTING. THIS EVENT IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICAT-SUBCOMPONENI NOT APPLICABLE ION 6.9.1.9.B.
TWO REDUNDANT MOTOR. DRIVEN AUXILIARY FEEDWATER PUMPS WER COMPONENT FAILURE E OPERABLE.
THE ACTION STATEMENT OF THE LCO WAS MET.
THE PUBLIC HEALTH MECHANICAL AND SAFETY WERE NOT AFFECTED.
WOODWARD GOVERNOR CD.
WOODWARD GOVERNOR CD.
THE TURBINE GOVERNOR FAILED TO CONTROL THE TURBINE SPEED PROPERLY. THE CAUSE OF THE GOVERNOR FAILURE WAS NOT DETERMINED. THE GOVERNOR WAS REPL ACED AND THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP WAS RETURNED TO OPE RABLE STATUS AFTER BEING TESTED IN ACCORDANCE WITH TECHNICAL SPECIFICATI ON AND IWP REQUIREMENTS.
THE TURBINE GOVERNOR FAILED TO CONTROL THE TURBINE SPEED PROPERLY. THE CAUSE OF THE GOVERNOR FAILURE WAS NOT DETERMINED. THE GOVERNOR WAS REPL ACED AND THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP WAS RETURNED TO OPE RABLE STATUS AFTER BEING TESTED IN ACCORDANCE WITH TECHNICAL SPECIFICATI ON AND IWP REQUIREMENTS.
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MAR 26, 1981                                                                                                           LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 60 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/                                     DOCKET NO./           EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 60 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/
COMP 0HENT SUBCODE/CAUSE CODE / LER NO./                                                 RF. PORT DATE/                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                         CONTKOL NO.           REPORT TYPE                                     CAUSE DESCRIPTION NORTH ANNA-2                                                                                       05000339             011481       DN 1/ 14/81. WITH UNIT 2 AT 100% POWER. THE BREAKER FOR 2-QS-P-1A (QUENCH REACTOR CONTAINMENT SYSTEMS                                                             81-011/03L-0           020481         SPRAY PUMP) WAS RACKED OUT AND THE SUCTION VALVE FOR THE PUMP (MOV-QS-2 VALVES                                                                                     036067             30-DAY       00A) WAS CLOSED AND DE-EHERGIZED IN ORDER TO REPAIR A LEAKING VENT VALVE GATE                                                                                                                 ON THE QUENCE SPRAY PUMP DISCHARGE STRAINER. SINCE THE QUENCH SPRAY PU COMPONENT FAILURE                                                                                                           MP WAS RETURNED TO SERVICE WITHIN THE TIME ALLOTED BY THE APPROPRIATE AC MECHANICA8                                                                                                         TION STATEMENT, AND OHE QUENCH SPRAY SYSTEM REMAINED OPERABLE, THE HEALT VELAM VALVE CORP.                                                                                                           H AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
EVENT DATE/
THE LEAKING VALVE WAS A 1" VELAN CORPORATION VENT VALVE. THE VALVE BONN ET WAS REMOVED, THE INTERNALS INSPECTED AND FOUND TO HAVE A DIRTY SEAT-.
COMP 0HENT SUBCODE/CAUSE CODE / LER NO./
THE VALVE SEAT WAS CLEANED, AND THE VALVE DISC WAS LAPPED IN ORDER TO C LEAN IT. SUBSEQUENT T9 MAINTENANCE. THE VALVE WAS MANUALLY OPERATED AND FOUND TO OPERATE SATISFACTORILY.
RF. PORT DATE/
NORTH ANNA-2                                                                                       05000339             011481       OH JANUARY 14, 1981 DURING MODE 1 OPERATION, THE HYDROGEN RECOMBINER SY CNTNMHT COMBUS GAS CONTROL SYS                                                           81-015/03L-0           020981       STEM WAS REMOVED FROM SERVICE FOR PIPING MODIFICATIONS CONTRARY TO TECHN 01HER COMPONENTS                                                                           036122             30-DAY       ICAL SPECIFICATION 3.6.4.2. SINCE THE REDUNDANT HYDROGEN RF MBINER WAS SUBCOMPONENT NOT APPLICABLE                                                                                           RETURHED TO SERVICE WITHIN 30 DAYS AS REQUIRED BY THE ACTION '. 1EMENT OTHER                                                                                                                       AND THE UNIT 2 HYDROGEN RECOMBINER REMAINED OPERABLE THE HEALTH AhD SAF NOT APPLICABLE                                                                                                     ETY OF THE PUBLIC WERE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUANT ROCKWELL-INTERNATIONAL                                                                                                       TO TECH. SPEC. 6.9.t.9.6.
EVENT DESCRIPTION /
l CAUSE SUBCODE/ MANUFACTURER CONTKOL NO.
REPORT TYPE CAUSE DESCRIPTION NORTH ANNA-2 05000339 011481 DN 1/ 14/81. WITH UNIT 2 AT 100% POWER. THE BREAKER FOR 2-QS-P-1A (QUENCH REACTOR CONTAINMENT SYSTEMS 81-011/03L-0 020481 SPRAY PUMP) WAS RACKED OUT AND THE SUCTION VALVE FOR THE PUMP (MOV-QS-2 VALVES 036067 30-DAY 00A) WAS CLOSED AND DE-EHERGIZED IN ORDER TO REPAIR A LEAKING VENT VALVE GATE ON THE QUENCE SPRAY PUMP DISCHARGE STRAINER. SINCE THE QUENCH SPRAY PU COMPONENT FAILURE MP WAS RETURNED TO SERVICE WITHIN THE TIME ALLOTED BY THE APPROPRIATE AC MECHANICA8 TION STATEMENT, AND OHE QUENCH SPRAY SYSTEM REMAINED OPERABLE, THE HEALT VELAM VALVE CORP.
H AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
THE LEAKING VALVE WAS A 1" VELAN CORPORATION VENT VALVE.
THE VALVE BONN ET WAS REMOVED, THE INTERNALS INSPECTED AND FOUND TO HAVE A DIRTY SEAT-.
THE VALVE SEAT WAS CLEANED, AND THE VALVE DISC WAS LAPPED IN ORDER TO C LEAN IT.
SUBSEQUENT T9 MAINTENANCE. THE VALVE WAS MANUALLY OPERATED AND FOUND TO OPERATE SATISFACTORILY.
NORTH ANNA-2 05000339 011481 OH JANUARY 14, 1981 DURING MODE 1 OPERATION, THE HYDROGEN RECOMBINER SY CNTNMHT COMBUS GAS CONTROL SYS 81-015/03L-0 020981 STEM WAS REMOVED FROM SERVICE FOR PIPING MODIFICATIONS CONTRARY TO TECHN 01HER COMPONENTS 036122 30-DAY ICAL SPECIFICATION 3.6.4.2.
SINCE THE REDUNDANT HYDROGEN RF MBINER WAS SUBCOMPONENT NOT APPLICABLE RETURHED TO SERVICE WITHIN 30 DAYS AS REQUIRED BY THE ACTION '. 1EMENT OTHER AND THE UNIT 2 HYDROGEN RECOMBINER REMAINED OPERABLE THE HEALTH AhD SAF NOT APPLICABLE ETY OF THE PUBLIC WERE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUANT ROCKWELL-INTERNATIONAL TO TECH. SPEC.
6.9.t.9.6.
THE UNIT 1 HYDROGEN RECOMBINER WAS REMOVED FROM SERVICE TO PERFORM A PIP ING MODIFICATION. WNEN COMALETED, THE RECOMBIHER WAS RETURNED TO SERVIC E.
THE UNIT 1 HYDROGEN RECOMBINER WAS REMOVED FROM SERVICE TO PERFORM A PIP ING MODIFICATION. WNEN COMALETED, THE RECOMBIHER WAS RETURNED TO SERVIC E.
NORTH ANNA-2                                                                                       05000339             012181       OH 1/21/31,' l3ITH UNIT II AT ?00% POWER- UGHTAINMENT PRESSURE PROTECTION ENGHRD SAFETY FEATR INSTR SYS                                                           81-012/03L-0           021181       CHANNEL III FAILED LOW. THE CHANNEL WAS PLACED IN TRIP AND DECLARED INO INSTRUMENTATION + CONTROLS                                                                 036120             30-DAY       #7RABLE. SINCE CONTAIHMEPT PRESSURE CHANNELS I,     II, AND IV REMAINED AVA INDICATOR                                                                                                         .;ABLE TO INITIATE CONTAINMENT DEPRESSURIZATION IF REQUIRED, AND CONTAIN COMPONENT FAILURE                                                                                                           aENT PRESSURE CHANNELS I AND II WERE AVAILABLE TO INITIATE AN INTERMEDIA INSTRUMENT                                                                                                         TE HIGH-HIGH OR A HIGH CONTAINMENT PRESSURE SIGNAL IF REQUIRED, THE HEAL WESTINGHOUSE ELECTRIC CORP.                                                                                                   TH AND SAFETY OF THE PU3LIC WERE NOT AFFECTED.
NORTH ANNA-2 05000339 012181 OH 1/21/31,' l3ITH UNIT II AT ?00% POWER-UGHTAINMENT PRESSURE PROTECTION ENGHRD SAFETY FEATR INSTR SYS 81-012/03L-0 021181 CHANNEL III FAILED LOW.
THE EVENT WAS CAUSED BY THE FAILURE OF A POWER SUPPLY CARD TO REACTOR CD NTAINMENT PRESSURE PROTECTION CHANNEL III.         THE FAILED CARD WAS REPLACED WIiH A CALIBRATED CARD, FUNCTIONALLY TESTED AND RESTORED TO A NORMAL CO HDITION.
THE CHANNEL WAS PLACED IN TRIP AND DECLARED INO INSTRUMENTATION + CONTROLS 036120 30-DAY
NORTH ANNA-2                                                                                         05000339             012281     ON JANUARY 22, 1981, WITH THE UNIT AT 100% POWER, WHILE POWER RANGE CHAN REACTOR TRIP SYSTEMS                                                                     81-014/03L-0           021181     NEL 3, N-43       WAS BEING TESTED AND IN THE TRIP MODE, A SPIKE OCCURRED ON INSTRUMENTATION + CONTROLS                                                                 036121             30-DAY     CHANNEL 4. H-44 WHICH GAVE 2/4 COINCIDENCE RESULTING IN AN IHADVERTANT POWER SUPPLY                                                                                                       REACTOR TRIP. SINCE THE PLANT WAS SAFELY SHUT DOWN, THE HEALTH AND SAFET COMPONENT FAILURE                                                                                                           Y OF THE GENERAL PUBLIC WERE NOT AFFECTED. THIS IS CONTRARY TO TECHNICA INSTRUNENT                                                                                                         L SPECIFICATION 3.3.1.1 SINCE THE MINIMUM NUMBER OF OPERATING CHANNELS W WESTINGHOUSE ELECTRIC COF.P.                                                                                                   ERE LESS THAN 1. AND REPORTABLE PURSUANT TO TECH SPEC 6.9.1.9.B.
#7RABLE.
THE CAUSE OF THE SPIKE ON N-44 IS UNKNOWN AT THIS TIME. PRIOR TO STARTI NG UP THE UNIT, N-44 WAS CALIBRATED SUCCESSFULLY. SUBSEQUENT TO THE STA RTUP.; SURVEILLANCE TESTS WERE PERFORMED ON ALL OF 1HE POWER RANGE FLUX C HANNELS AND N-44 WAS AGAIN CALIBRATED. RECORDERS MONITORING.THESE CHANN ELS ARE REVIEWED DAILY AND NO ABNORMAL INDICATIONS HAVE BEEN FOUND.
SINCE CONTAIHMEPT PRESSURE CHANNELS I, II, AND IV REMAINED AVA INDICATOR
  - - - - _ _ - - - - _ _ - _ _ - - - - - - . - - - - - _ - _ - - -                      - - - _ _ - - - - . - - - - - - - - - - - . -      -------_z.__                ~
.;ABLE TO INITIATE CONTAINMENT DEPRESSURIZATION IF REQUIRED, AND CONTAIN COMPONENT FAILURE aENT PRESSURE CHANNELS I AND II WERE AVAILABLE TO INITIATE AN INTERMEDIA INSTRUMENT TE HIGH-HIGH OR A HIGH CONTAINMENT PRESSURE SIGNAL IF REQUIRED, THE HEAL WESTINGHOUSE ELECTRIC CORP.
                                                                                                                                                                              ~m-"                                                 '
TH AND SAFETY OF THE PU3LIC WERE NOT AFFECTED.
a - -"' _ _ _ - _ _ --,---.:----
THE EVENT WAS CAUSED BY THE FAILURE OF A POWER SUPPLY CARD TO REACTOR CD NTAINMENT PRESSURE PROTECTION CHANNEL III.
THE FAILED CARD WAS REPLACED WIiH A CALIBRATED CARD, FUNCTIONALLY TESTED AND RESTORED TO A NORMAL CO HDITION.
NORTH ANNA-2 05000339 012281 ON JANUARY 22, 1981, WITH THE UNIT AT 100% POWER, WHILE POWER RANGE CHAN REACTOR TRIP SYSTEMS 81-014/03L-0 021181 NEL 3, N-43 WAS BEING TESTED AND IN THE TRIP MODE, A SPIKE OCCURRED ON INSTRUMENTATION + CONTROLS 036121 30-DAY CHANNEL 4.
H-44 WHICH GAVE 2/4 COINCIDENCE RESULTING IN AN IHADVERTANT POWER SUPPLY REACTOR TRIP. SINCE THE PLANT WAS SAFELY SHUT DOWN, THE HEALTH AND SAFET COMPONENT FAILURE Y OF THE GENERAL PUBLIC WERE NOT AFFECTED.
THIS IS CONTRARY TO TECHNICA INSTRUNENT L SPECIFICATION 3.3.1.1 SINCE THE MINIMUM NUMBER OF OPERATING CHANNELS W WESTINGHOUSE ELECTRIC COF.P.
ERE LESS THAN 1. AND REPORTABLE PURSUANT TO TECH SPEC 6.9.1.9.B.
THE CAUSE OF THE SPIKE ON N-44 IS UNKNOWN AT THIS TIME.
PRIOR TO STARTI NG UP THE UNIT, N-44 WAS CALIBRATED SUCCESSFULLY. SUBSEQUENT TO THE STA RTUP.; SURVEILLANCE TESTS WERE PERFORMED ON ALL OF 1HE POWER RANGE FLUX C HANNELS AND N-44 WAS AGAIN CALIBRATED. RECORDERS MONITORING.THESE CHANN ELS ARE REVIEWED DAILY AND NO ABNORMAL INDICATIONS HAVE BEEN FOUND.
------- z.
~
~m-"
a


I 4
I 4
MAK 26, 1981                                                                         LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 61 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /       DOCKET NO./                           EVENT DATE/
MAK 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 61 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                       REPORT DATE/                                 EVENT DESCRIPTIDH/
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER           CONTROL NO.                           REPORT TYPE                                   CAUSE DESCRIPTION NORTH ANNA-2                                             05000339                     012681     ON JANUARY 26, 1981, THE CONTAINMENT HI ANU ni-HI CHANNEL III ANNUNCIATO ENGNRD SAFETY FEATR INSTR SYS                   81-013/03L-0                         022581     R BECAME ENERGIZED. AFTER ENSURING THAT A HIGH PRESSURE DID NOT EXIST, INSTRUMENTATION + CONTROLS                                   036242                   30-DAY     THE CHANNEL MAS PLACtD IN THE TRIPPED CONDITION AND DECLARED INDPERABLE.
EVENT DATE/
CONTROLLER                                                                                     CONTAINMENT PRESSURE CHANNELS I,     II AND IV REMAINED OPERATIONAL TO INIT COMPONENT FAILURE                                                                                 IATE A CDA IF REQUIRED, THEREFORE THE HEALTH AND SAFETY OF THE PUBLIC WE ELECTRONIC                                                                                   RE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUANT TO TECH. SPEC. 6.9.1.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
WESTINGHOUSE ELECTRIC CORP.                                                                       .9.B.
REPORT DATE/
EVENT DESCRIPTIDH/
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION NORTH ANNA-2 05000339 012681 ON JANUARY 26, 1981, THE CONTAINMENT HI ANU ni-HI CHANNEL III ANNUNCIATO ENGNRD SAFETY FEATR INSTR SYS 81-013/03L-0 022581 R BECAME ENERGIZED. AFTER ENSURING THAT A HIGH PRESSURE DID NOT EXIST, INSTRUMENTATION + CONTROLS 036242 30-DAY THE CHANNEL MAS PLACtD IN THE TRIPPED CONDITION AND DECLARED INDPERABLE.
CONTROLLER CONTAINMENT PRESSURE CHANNELS I, II AND IV REMAINED OPERATIONAL TO INIT COMPONENT FAILURE IATE A CDA IF REQUIRED, THEREFORE THE HEALTH AND SAFETY OF THE PUBLIC WE ELECTRONIC RE NOT AFFECTED.
THIS EVENT IS REPORTABLE PURSUANT TO TECH. SPEC.
6.9.1.
WESTINGHOUSE ELECTRIC CORP.
.9.B.
THE POWER SUPPLY CARD (S/N 5088) DRIFTED HIGH CAUSING AN INCREASE IN OUT PUT VOLTACE. THE FAULTY CARD WAS REPLACED THE CHANNEL CALIBRATED AND D ECLARED OPERABLE.
THE POWER SUPPLY CARD (S/N 5088) DRIFTED HIGH CAUSING AN INCREASE IN OUT PUT VOLTACE. THE FAULTY CARD WAS REPLACED THE CHANNEL CALIBRATED AND D ECLARED OPERABLE.
NORTH ANNA-2                                             05000339                     020581     ON FEBRUARY 5,   1981, WHILE OPERATING AT 100% POWER, THE TEMPERATURE INDI REACTOR TRIP SYSTEMS                           81-016/03L-0                         021981     CATOR ( T I-412 D ) , ASSOCIATED WITH TAVG PROTECTION FOR LOOP "A", WAS READI INSTRUMENTATION + CONTROLS                                 036243                   30-DAY     NG APPROXIMATELY 5F-15F LOW AND RESPONDING ERRATICALLY AFTER BEING PLACE OTHER                                                                                         D IN SERVICE UPON COMPLETION OF A PERIODIC TEST ON THE CHANNEL.. SINCE T COMPONENT FA?3.URE                                                                               HE AFFECTED CHANNEL WAS PLACED IN THE TRIP CONDITION WITHIN ONE HOUR, TH INSTRUMENT                                                                                   E PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
NORTH ANNA-2 05000339 020581 ON FEBRUARY 5, 1981, WHILE OPERATING AT 100% POWER, THE TEMPERATURE INDI REACTOR TRIP SYSTEMS 81-016/03L-0 021981 CATOR ( T I-412 D ), ASSOCIATED WITH TAVG PROTECTION FOR LOOP "A",
WAS READI INSTRUMENTATION + CONTROLS 036243 30-DAY NG APPROXIMATELY 5F-15F LOW AND RESPONDING ERRATICALLY AFTER BEING PLACE OTHER D IN SERVICE UPON COMPLETION OF A PERIODIC TEST ON THE CHANNEL.. SINCE T COMPONENT FA?3.URE HE AFFECTED CHANNEL WAS PLACED IN THE TRIP CONDITION WITHIN ONE HOUR, TH INSTRUMENT E PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.
WESTINGHOUSE ELECTRIC CORP.
WESTINGHOUSE ELECTRIC CORP.
THE ERRATIC AND LOWER THAN NORMAL READINGS ON THE TEMPERATURE INDICATOR WERE CAUSED BY A FAILED RELAY CARD. THE CARD WAS REPLACED, CALIBRATED A ND RETURNED TO SERVICE.
THE ERRATIC AND LOWER THAN NORMAL READINGS ON THE TEMPERATURE INDICATOR WERE CAUSED BY A FAILED RELAY CARD.
OCONEE-1                                                 05000269                     112480     ON NOVEMBER 24, 1980, THE LEVEL INDICATION WAS LOST TO THE STATION EWST.
THE CARD WAS REPLACED, CALIBRATED A ND RETURNED TO SERVICE.
STATION SERV WATER SYS + CONT                   80-034/03X-1                         021981-     DURING THE TIME OF THE INOPERABILITY, BOTH NORMAL HPSW PUMPS AND THE HP INSTRUf1ENTATION + CONTROLS                                 033363                   UTHER       SU JOCKEY PUMP WERE OPERABLE, THUS ASSURING SAFE OPERATION OF THE PLANT INDICATOR                                                                                     BUT REQUIRING MANUAL START OF TPE PUMPS IF NEEDED.       IN. ADDITION, THE LEV EXTERNAL CAUSE                                                                                   EL IN THE EWST WAS MONITORED EVERY 2 HOURS. IHUS, THIS INCIDENT WAS OF NOT APPLICABLE                                                                               NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND THE HEALTH AND SAFETY OTHER                                                                                             OF THE PUBLIC WERE NOT AFFECTED.
OCONEE-1 05000269 112480 ON NOVEMBER 24, 1980, THE LEVEL INDICATION WAS LOST TO THE STATION EWST.
THIS INCIDENT WAS CAU3ED BY WATER COLLECTING IN THE AIR COMPRESSOR LOCAT ED ON THE MICROWAVE TOWER WHICH PROVIDES INSTRUMENT AIR FOR THE EWST INS TRUMENTATION. IMMEDIATE CORRECTIVE ACTION WAS TO PLACE HPSW PUMPS IN MA NUAL MODE & ESTABLISH AN ALTERNATE MEANS OF INDICATING WATER LEVEL IN EW ST. THE NORMAL INSTRUMENTATION WAS CHECKED, & THE AIR RECEIVER DRAINED.
STATION SERV WATER SYS + CONT 80-034/03X-1 021981-DURING THE TIME OF THE INOPERABILITY, BOTH NORMAL HPSW PUMPS AND THE HP INSTRUf1ENTATION + CONTROLS 033363 UTHER SU JOCKEY PUMP WERE OPERABLE, THUS ASSURING SAFE OPERATION OF THE PLANT INDICATOR BUT REQUIRING MANUAL START OF TPE PUMPS IF NEEDED.
OCONEE-1                                                 05000269                     120980     ON DECEMBER 9,   1980 THE ELEVATED WATER STORAGE TANK (EWST) AND A PORTION STATION SERV WATER SYS + CONT                   80-236/03L-0                         012281       0F THE HIGH PhESSURE SERVICE WATER (HPSW) FIRE PROTECTION YARD LOOP WER       i COMPONENT CODE NOT APPLICABLE                               033722                   33-DAY     E REMOVED FROM SERVICE. A TEMPORARY FLOW PATH WAS ESTABLISHED TO PROVID-SUBCOMPONENT NOT APPLICABLE                                                                   E FIRE PROIECTION TO CT-5. TEMPORARY HOSE RUPTURED. HPSW PUMPS WERE AV DTHER                                                                                             AILABLE FOR MANUAL ACTIVATION IF REQUIRED. A FIRE WATCH WAS MAINTAINED-NOT APPLICABLE                                                                               DURING THE PERIOD WHEN THE TEMPORARY HOSE RUPTURED. THERE WAS NO EFFECT ITEM NOT APPLICABLE                                                                               ON HEALTH AND SArETY OF THE PUBLIC.
IN. ADDITION, THE LEV EXTERNAL CAUSE EL IN THE EWST WAS MONITORED EVERY 2 HOURS.
REMOVAL FROM SERV 1CE OF EUST & PORTION OF HPSW FIRE PROTECTION YARD LOOP WEPC PLANNED. HOSE RUPTURE WAS DUE TO RESULTING FRESSURE SURGE WHEN HP SM PUMPS WERE PUT INTO SERVICE. RUPTURED HOSES WERE EXPEDITIOUSLY REPLA CED WHILE FIRE WATCHES WERE POSTED. EWST WAS RETURNED TO SERVICE AS 500-N AS POSSIBLE.
IHUS, THIS INCIDENT WAS OF NOT APPLICABLE NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND THE HEALTH AND SAFETY OTHER OF THE PUBLIC WERE NOT AFFECTED.
THIS INCIDENT WAS CAU3ED BY WATER COLLECTING IN THE AIR COMPRESSOR LOCAT ED ON THE MICROWAVE TOWER WHICH PROVIDES INSTRUMENT AIR FOR THE EWST INS TRUMENTATION. IMMEDIATE CORRECTIVE ACTION WAS TO PLACE HPSW PUMPS IN MA NUAL MODE & ESTABLISH AN ALTERNATE MEANS OF INDICATING WATER LEVEL IN EW ST.
THE NORMAL INSTRUMENTATION WAS CHECKED, & THE AIR RECEIVER DRAINED.
OCONEE-1 05000269 120980 ON DECEMBER 9, 1980 THE ELEVATED WATER STORAGE TANK (EWST) AND A PORTION STATION SERV WATER SYS + CONT 80-236/03L-0 012281 0F THE HIGH PhESSURE SERVICE WATER (HPSW) FIRE PROTECTION YARD LOOP WER i
COMPONENT CODE NOT APPLICABLE 033722 33-DAY E REMOVED FROM SERVICE. A TEMPORARY FLOW PATH WAS ESTABLISHED TO PROVID-SUBCOMPONENT NOT APPLICABLE E FIRE PROIECTION TO CT-5.
TEMPORARY HOSE RUPTURED. HPSW PUMPS WERE AV DTHER AILABLE FOR MANUAL ACTIVATION IF REQUIRED. A FIRE WATCH WAS MAINTAINED-NOT APPLICABLE DURING THE PERIOD WHEN THE TEMPORARY HOSE RUPTURED. THERE WAS NO EFFECT ITEM NOT APPLICABLE ON HEALTH AND SArETY OF THE PUBLIC.
REMOVAL FROM SERV 1CE OF EUST & PORTION OF HPSW FIRE PROTECTION YARD LOOP WEPC PLANNED.
HOSE RUPTURE WAS DUE TO RESULTING FRESSURE SURGE WHEN HP SM PUMPS WERE PUT INTO SERVICE.
RUPTURED HOSES WERE EXPEDITIOUSLY REPLA CED WHILE FIRE WATCHES WERE POSTED. EWST WAS RETURNED TO SERVICE AS 500-N AS POSSIBLE.


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 62 PROCESSED DURING MARCH, 1981 FOR PGMER REACTORS 4
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 62 PROCESSED DURING MARCH, 1981 FOR PGMER REACTORS 4
FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTICH OCONEE-1                               05000269     011881     UNIT 1 WAS REDUCING POWER FROM 90% WHEN THE D.C. INPUT FUSE IN THE 1DID ONSITE POWER SYSTEM + CONTROL       81-002/03L-0   021781     VITAL INVERTER BLEW, CAUSING THE INVERTER TO LOSE ITS POWER SOURCE.           fMR GENERATORS                             036123     30-DAY     EE VITAL INSTRUMENTATIDH POWER PANELBOARDS WERE STILL IN SERVICE. THESE INVERTER                                                     WOULD HAVE PROVIDED SUFFICIENT A.C. VITAL INSTRUMENTATION TO SAFELY SHU CCMPONENT FAILURE                                             T DOWN THE UNIT IF AN ACCIDENT HAD OCCURRED. THUS. THIS INCIDENT WAS OF ELECTRICAL                                                 NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND THE HEALTH AND SAFETY OTHER                                                           OF THE PUBLIC WERE NOT AFFECTED.
EVENT DATE/
THE BLOWN POWER FUSE WAS POSSIBLY CAUSED BY POORLY MADE CONNECTIONS IN T HE LOGIC CARDS' " EDGE CONNECTORS" AND/OR INTERMITTENT COMPONENT PROBLEMS ON THE LOGIC CARDS. THE DID INVERTER LOAD WAS IMMEDIATELY TRANSFERRED TO THE A.C. REGULATED BUS AND THE FUSES WERE REPLACED. THE LOGIC CARDS AND THEIR' EDGE CONNECTORS WILL BE INSPECTED ON ALL UNITS.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
OCONEE-1                               05000269     012581     ON JANUARY 25, 1981     D.C. INPUT FUSE IN 1DID VITAL INVERTER BLEW, CAUSIN ONSITE POWER SYSTEM + CONTROL       81-003/03L-0   022481     G THE INVERTER TO TRIP 3 LOSE ITS PCWER SOURCE. IN ADDITION, 1DIB INVERT CIRCUIT CLOSERS / INTERRUPTERS         036241     30-DAY     FD TFIPPED WHEN A.C. OUTPUT BREAKER WAS APPARENTLY OPENED WHILE PERSONNE CIRCUIT BREAKER                                             L WERE WORKING OH 1DID INVERTER. A SECOND TRIP OF 1DID INVERTER OCCURRED COMPONENT FAILURE                                               WHEN PERSONNEL MISTAKENLY OPENED A.C. OUTPUT BREAKER WHILE DE-ENERGIZIN-OTHER                                                       G 1DID. ALTHOUGH BOTH 1KVID 4 1KVID WERE DE-ENERGIZED, THEY WERE NOT SIM EXIDE INDUSTRIAL DIV                                         ULTANEOUS. THUS. THE HEALTH & SAFETY OF THE PUBLIC WERE NOT ENDANGERED.
REPORT DATE/
THE FIRST TRIP OF 1DID WAS CAUSED BY BLOWN FUSES. THE CAUSE OF THE 1DIB TRIP IS NOT EXACTLY KNOWN. 1DID TRIPPED AGAIN AS A RESULT OF THE A.C.
EVENT DESCRIPTION /
DUTPUT BREAKER MISTAKENLY BEING OPENED.     FUSES WERE REPLACED, INVERTERS WERE RETURNED TO SERVICE. AND CHANNELS WERE RESET ACCO#DINGLY. GUARDS W ILL BE INSTALLED ON ALL D.C. INPUT AND A.C. DUTPUT 5%EA(ERS.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
OCCHEE-2                               05000270     101180     ON 10/21/80, IT WAS DISCOVERED THAT 4 HOLES HAD BEEN KNOCKED IN THE FIRE-FIRE PROTECTION SYS + CONT         80-022/01X-1   021981       BARRIER BETWEEN UNIT 2 CABLE SPREAD ROOM & TURBINE BUILDING. THIS INCID OTHER COMPONENTS                       032843     OTHER     ENT OCCURRED ON 10/11/80 & AN HOURLY FIRE WATCH HAD HOT BEEN ESTAB. SINC
REPORT TYPE CAUSE DESCRIPTICH OCONEE-1 05000269 011881 UNIT 1 WAS REDUCING POWER FROM 90% WHEN THE D.C.
* SUBCOMPONENT NOT APPLICABLE                                 E BOTH MANUAL HOSE LINES & INSTALLED WATER SPRAY SYS WERE AVAILABLE, FIR DEFECTIVE PROCEDURES                                         E PROTECTION CAPABILITIES OF THIS AREA WERE NOT UNDULY COMPROMISED. THUS NOT APPLICABLE                                             ,  THIS INCIDENT WAS OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION, A ITEM NOT APPLICABLE                                         ND THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
INPUT FUSE IN THE 1DID ONSITE POWER SYSTEM + CONTROL 81-002/03L-0 021781 VITAL INVERTER BLEW, CAUSING THE INVERTER TO LOSE ITS POWER SOURCE.
THIS INCIDENT APPEARS TO BE 1HE RESULT OF THREE RELATED DEFICIENCIES INV OLVING THE FAILURE OF PROPER HOTIFICATION. AFTER DISCOVERY OF THE INCID ENT, AN HOURLY FIRE WATCH WAS ESTABLISHED. THE SLEEVES WERE ENCLOSED WI TH STRUCTURAL GROUT. THE CHANGE IN PROCEDURES AND MAINTENANCE TRAINING ARE ADEQUATE TO PREVENT REOCCURRENCE.
fMR GENERATORS 036123 30-DAY EE VITAL INSTRUMENTATIDH POWER PANELBOARDS WERE STILL IN SERVICE. THESE INVERTER WOULD HAVE PROVIDED SUFFICIENT A.C.
OCONEE-2                               05000270     121780     ON 12/17/80, 2B HPI PUMP WAS DECLARED INOPERABLE. PUMP HAD BEEN REMOVED EMERG CORE COOLING SYS + CONT       80-025/03L-0   013081       FROM SERVICE FOR A MOTOR DIL CHANGE. CN FOUR CONSECUTIVE TEST RUNS AFT MOTORS                                 033723     30-DAY     ER OIL CHANGE, MOTOR INDICATED HIGH UPPER BEARING TEMPERATURES           PUMP WA SUBCOMPONENT NOT APPLICABLE                                 S RETURNED TO SERVICE WELL WITHIN TIME PERMITTED. HPI PUMPS 2A 8 2C WER PERSONNEL ERROR                                               E AVAILABLE AS WELL AS ALL OTHER ECC SYSTEMS. THUS THIS INCIDENT WAS OF MAINTENANCE & REPAIR PERSONNEL                               NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION, & HEALTH 8 SAFETY OF PU OTHER                                                         BLIC WERE NOT AFFECTED.
VITAL INSTRUMENTATION TO SAFELY SHU CCMPONENT FAILURE T DOWN THE UNIT IF AN ACCIDENT HAD OCCURRED. THUS. THIS INCIDENT WAS OF ELECTRICAL NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND THE HEALTH AND SAFETY OTHER OF THE PUBLIC WERE NOT AFFECTED.
CAUSE WAS PERSONNEL BEING CONFUSED & DOING JRONG THINGS.       EXACT CAUSE F0 R HIGH TEMPERATURES IS NOT KNOWN. PERSONNEL HAVE BEEN INSTRUCTED NOT TO PERFORM ACTIONS THAT THEY KNOW ARE NOT CORRECT. FUTURE CORRECTIVE ACTI ONS PLANNED ARE TO HAVE APPRnP. PERSONNEL REVIEW INCIDENT 8 CORRECT PROB LEM WITH THE HIGH BEARING r     ERATURES.
THE BLOWN POWER FUSE WAS POSSIBLY CAUSED BY POORLY MADE CONNECTIONS IN T HE LOGIC CARDS' " EDGE CONNECTORS" AND/OR INTERMITTENT COMPONENT PROBLEMS ON THE LOGIC CARDS.
m ,,                      -    __          _.
THE DID INVERTER LOAD WAS IMMEDIATELY TRANSFERRED TO THE A.C. REGULATED BUS AND THE FUSES WERE REPLACED. THE LOGIC CARDS AND THEIR' EDGE CONNECTORS WILL BE INSPECTED ON ALL UNITS.
OCONEE-1 05000269 012581 ON JANUARY 25, 1981 D.C.
INPUT FUSE IN 1DID VITAL INVERTER BLEW, CAUSIN ONSITE POWER SYSTEM + CONTROL 81-003/03L-0 022481 G THE INVERTER TO TRIP 3 LOSE ITS PCWER SOURCE. IN ADDITION, 1DIB INVERT CIRCUIT CLOSERS / INTERRUPTERS 036241 30-DAY FD TFIPPED WHEN A.C.
OUTPUT BREAKER WAS APPARENTLY OPENED WHILE PERSONNE CIRCUIT BREAKER L WERE WORKING OH 1DID INVERTER. A SECOND TRIP OF 1DID INVERTER OCCURRED COMPONENT FAILURE WHEN PERSONNEL MISTAKENLY OPENED A.C. OUTPUT BREAKER WHILE DE-ENERGIZIN-OTHER G 1DID. ALTHOUGH BOTH 1KVID 4 1KVID WERE DE-ENERGIZED, THEY WERE NOT SIM EXIDE INDUSTRIAL DIV ULTANEOUS. THUS. THE HEALTH & SAFETY OF THE PUBLIC WERE NOT ENDANGERED.
THE FIRST TRIP OF 1DID WAS CAUSED BY BLOWN FUSES.
THE CAUSE OF THE 1DIB TRIP IS NOT EXACTLY KNOWN.
1DID TRIPPED AGAIN AS A RESULT OF THE A.C.
DUTPUT BREAKER MISTAKENLY BEING OPENED.
FUSES WERE REPLACED, INVERTERS WERE RETURNED TO SERVICE. AND CHANNELS WERE RESET ACCO#DINGLY. GUARDS W ILL BE INSTALLED ON ALL D.C.
INPUT AND A.C. DUTPUT 5%EA(ERS.
OCCHEE-2 05000270 101180 ON 10/21/80, IT WAS DISCOVERED THAT 4 HOLES HAD BEEN KNOCKED IN THE FIRE-FIRE PROTECTION SYS + CONT 80-022/01X-1 021981 BARRIER BETWEEN UNIT 2 CABLE SPREAD ROOM & TURBINE BUILDING. THIS INCID OTHER COMPONENTS 032843 OTHER ENT OCCURRED ON 10/11/80 & AN HOURLY FIRE WATCH HAD HOT BEEN ESTAB. SINC SUBCOMPONENT NOT APPLICABLE E BOTH MANUAL HOSE LINES & INSTALLED WATER SPRAY SYS WERE AVAILABLE, FIR DEFECTIVE PROCEDURES E PROTECTION CAPABILITIES OF THIS AREA WERE NOT UNDULY COMPROMISED. THUS NOT APPLICABLE THIS INCIDENT WAS OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION, A ITEM NOT APPLICABLE ND THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
THIS INCIDENT APPEARS TO BE 1HE RESULT OF THREE RELATED DEFICIENCIES INV OLVING THE FAILURE OF PROPER HOTIFICATION. AFTER DISCOVERY OF THE INCID ENT, AN HOURLY FIRE WATCH WAS ESTABLISHED. THE SLEEVES WERE ENCLOSED WI TH STRUCTURAL GROUT.
THE CHANGE IN PROCEDURES AND MAINTENANCE TRAINING ARE ADEQUATE TO PREVENT REOCCURRENCE.
OCONEE-2 05000270 121780 ON 12/17/80, 2B HPI PUMP WAS DECLARED INOPERABLE. PUMP HAD BEEN REMOVED EMERG CORE COOLING SYS + CONT 80-025/03L-0 013081 FROM SERVICE FOR A MOTOR DIL CHANGE.
CN FOUR CONSECUTIVE TEST RUNS AFT MOTORS 033723 30-DAY ER OIL CHANGE, MOTOR INDICATED HIGH UPPER BEARING TEMPERATURES PUMP WA SUBCOMPONENT NOT APPLICABLE S RETURNED TO SERVICE WELL WITHIN TIME PERMITTED. HPI PUMPS 2A 8 2C WER PERSONNEL ERROR E AVAILABLE AS WELL AS ALL OTHER ECC SYSTEMS.
THUS THIS INCIDENT WAS OF MAINTENANCE & REPAIR PERSONNEL NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION, & HEALTH 8 SAFETY OF PU OTHER BLIC WERE NOT AFFECTED.
CAUSE WAS PERSONNEL BEING CONFUSED & DOING JRONG THINGS.
EXACT CAUSE F0 R HIGH TEMPERATURES IS NOT KNOWN.
PERSONNEL HAVE BEEN INSTRUCTED NOT TO PERFORM ACTIONS THAT THEY KNOW ARE NOT CORRECT. FUTURE CORRECTIVE ACTI ONS PLANNED ARE TO HAVE APPRnP. PERSONNEL REVIEW INCIDENT 8 CORRECT PROB LEM WITH THE HIGH BEARING r ERATURES.
m


MAR 26, 1981                                                                               LER MONTHLY REPORT SORTED BY FACILITY                                     PAGE 63 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                       DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 63 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                             REPORT DATE/                               -EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                           CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION OCONEE-2                                                                       05000270     121980   ON 12/19/80, THE CBAST PUMP WAS DECLARED INOPERABLE WHEN IT FAILED TO PU CHEM, VOL CD*1T + LIQ POISH SYS                                           80-026/03L-0   012081   MP FRCM CBAST TO LDST. DURING PERIOD OF INOPERABILITY, EWST WAS AVAILAB PUMPS                                                                         033678       30-DAY   LE. ALSO CBAST PUMP WAS RETURNED TO SERVICE WITHIN TIME PERMITTED. THU DIAPHRAGM S, INCIDENT WAS OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND HE COMPONENT FAILURE                                                                                   ALTH AND SAFETY OF PUBLIC WERE NOT AFFECTED. FAILURE OF CBAST PUMPS IS MECHANICAL                                                                                         A RECURRING PROBLEM AT OCONEE.
EVENT DATE/
OTHER APPARENT CAUSE WAS DUE TO AIR BEING IN HYDRAULIC RESERVOIR. OIL LEVEL W AS FOUND TO BE LOW. OIL WAS ADDED TO RESERVOIR. A STATION MODIFICATION HAS BEEN SUBMITTED REQUESTING THAT CURRENT LAPP PUMPS BE REPLACED WITH A CENTRIFUGAL TYPE PUMP.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
05000270     012081   DN JANUARY 20, 1981, IT WAS DISCOVERED THAT THERE WAS NO FLOW OF LOW PRE OCONEE-2 CNTNMNT HEAT REMOV SYS + CONT                                             51-001/03L-0   021981   SSURE SERVICE WATER (LPSW) TO THE "2A" HPI PUMP. AT THE TIME-IT WAS FOU VALVES                                                                       036160       30-DAY   HD THAT THERE WAS NO FLOW IN THE "2A" BEARING COOLER, PUMPS "2B" AND "2C OTHER                                                                                               " WERE AVAILABLE FOR USE. THEREFORE, THE HPI SYSTEM WAS-NOT IMPAIRED.
REPORT DATE/
OTHER                                                                                                ALSO THE USE OF "2A" WAS QUICKLY REGAINED WHEN FLOW WAS RESTORED. THUS.
-EVENT DESCRIPTION /
NOT APPLICABLE                                                                                        THIS INCIDENT WAS OF HO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND ITEM NOT APPLICABLE                                                                                   THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
THE REASON FOR THE FLOW STOPPAGE IS NOT KNOWN AT THIS TIME. WHEN LACK 0
REPORT TYPE CAUSE DESCRIPTION OCONEE-2 05000270 121980 ON 12/19/80, THE CBAST PUMP WAS DECLARED INOPERABLE WHEN IT FAILED TO PU CHEM, VOL CD*1T + LIQ POISH SYS 80-026/03L-0 012081 MP FRCM CBAST TO LDST.
                                                                                                                                      -F FLOW WAS ENCOUNTERED, VALVE 2/TVC/(RHO) MAS BYPASSED, AND FLOW WAS RES TORED,   FUTURE CORRECTIVE ACTION WILL BE TAKEN AS DEEMED HECESSARY AFTER '
DURING PERIOD OF INOPERABILITY, EWST WAS AVAILAB PUMPS 033678 30-DAY LE.
THE CAUSE FOR THE FLOW STOPPAGE HAS BEEN DETERMINED.
ALSO CBAST PUMP WAS RETURNED TO SERVICE WITHIN TIME PERMITTED. THU DIAPHRAGM S, INCIDENT WAS OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND HE COMPONENT FAILURE ALTH AND SAFETY OF PUBLIC WERE NOT AFFECTED. FAILURE OF CBAST PUMPS IS MECHANICAL A RECURRING PROBLEM AT OCONEE.
OYSTER CREEK-1                                                                 05000219     071180   DN JULY 11, 1980, DURING A PLANT STARTUP, THE HIGH DRYWELL PRESSURE SENS EMERG CORE COOLING SYS + CONT                                             80-029/03L-1   020381   OR RV46B ACTUATED CAUSING THE CORE SPRAY PUMPS AND BOTH DIESEL GENERATOR COMPONENT CODE NOT APPLICABLE                                                 032047       30-DAY   S TO START. AFTER VERIFYING THAT AN ACTUAL HIGH DRYWELL PRESSURE CONDIT SUBCOMPONENT NOT APPLICABLE ION DID NOT EXIST, THE PRIMARY CORE SPRAY PUMPS WERE TURNED OFF. THIS C DESIGN / FABRICATION ERROR                                                                          AUSED THE ALTERNATE PUMPS TO START AND THESE WERE ALSO STOPPED. UNDER T MANUFACTURING                                                                                      HESE CONDITIONS THE AUT0t1ATIC AND REMOTE MANUAL INITIAL FEATURES OF THE ITT-BARTON                                                                                          ALTERNATE CORE SPRAY PUMPS WERE DEFEATED.
OTHER APPARENT CAUSE WAS DUE TO AIR BEING IN HYDRAULIC RESERVOIR. OIL LEVEL W AS FOUND TO BE LOW.
THE INITIATING CAUSE'0F THE OCCURRENCE IS ATTRIBUTED TO INSTRUMENT SETPO INT SHIFT. AFTER THE OPERATOR STOPPED THE PUMPS. THE ALTERNATE PUMPS WO ULD NOT HAVE STARTED AUTOMATICALLY BECAUSE OF THE DESIGN OF THE LOGIC CI RCUIT. THE PLANT WAS SHUTDOWN AND ALL FOUR HIGH DRYWELL PRESSURE SENSOR S WERE RECALIBRATED.
OIL WAS ADDED TO RESERVOIR. A STATION MODIFICATION HAS BEEN SUBMITTED REQUESTING THAT CURRENT LAPP PUMPS BE REPLACED WITH A CENTRIFUGAL TYPE PUMP.
05000219       121780   DURING FUNCTIONAL TESTING, SNUBBERS -19/11 -19/12 8 -19/13 (SERIAL NO.
OCONEE-2 05000270 012081 DN JANUARY 20, 1981, IT WAS DISCOVERED THAT THERE WAS NO FLOW OF LOW PRE CNTNMNT HEAT REMOV SYS + CONT 51-001/03L-0 021981 SSURE SERVICE WATER (LPSW) TO THE "2A" HPI PUMP.
0YSTER CREEK-1                                                                                        470915, 477361 & 477121) LOCATED ON CONTAINMENT SPRAY 8 CORE SPRAY SYSTE EMERG CORE COOLING SYS + CONT                                              80-061/03L-0    011681 HANGERS, SUPPORTS, SHOCK SUPPRSS                                               033679     30-DAY   M COMMON SUCTION HEADER, FAILED TO LOCK UP IN COMPRESSION MODE. PLANS T SNUBBERS                                                                                           D PERFORM A DETAILED COMPUTER ANALYSIS WHICH MODELS EACH SNUBBER BASED 0 COMPONENT FAILURE                                                                                    N ITS MODE OF FAILURE FOR 'sARIOUS MODES OF OPERATION ARE BEING MADE SO T-MECHANICAL                                                                                        HAT SAFETY SIGNIFICANCF AND PIPE STRESS MAGNITUDES CAN ACCURATELY BE REP BERGEN-PATTERSON PIPE SUPPORT                                                                       ORTED IN FORM OF A RFi1SION TO THIS REPORT.
AT THE TIME-IT WAS FOU VALVES 036160 30-DAY HD THAT THERE WAS NO FLOW IN THE "2A" BEARING COOLER, PUMPS "2B" AND "2C OTHER
" WERE AVAILABLE FOR USE.
THEREFORE, THE HPI SYSTEM WAS-NOT IMPAIRED.
ALSO THE USE OF "2A" WAS QUICKLY REGAINED WHEN FLOW WAS RESTORED.
THUS.
OTHER THIS INCIDENT WAS OF HO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND NOT APPLICABLE THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
ITEM NOT APPLICABLE THE REASON FOR THE FLOW STOPPAGE IS NOT KNOWN AT THIS TIME. WHEN LACK 0
-F FLOW WAS ENCOUNTERED, VALVE 2/TVC/(RHO) MAS BYPASSED, AND FLOW WAS RES
: TORED, FUTURE CORRECTIVE ACTION WILL BE TAKEN AS DEEMED HECESSARY AFTER THE CAUSE FOR THE FLOW STOPPAGE HAS BEEN DETERMINED.
OYSTER CREEK-1 05000219 071180 DN JULY 11, 1980, DURING A PLANT STARTUP, THE HIGH DRYWELL PRESSURE SENS EMERG CORE COOLING SYS + CONT 80-029/03L-1 020381 OR RV46B ACTUATED CAUSING THE CORE SPRAY PUMPS AND BOTH DIESEL GENERATOR COMPONENT CODE NOT APPLICABLE 032047 30-DAY S TO START.
AFTER VERIFYING THAT AN ACTUAL HIGH DRYWELL PRESSURE CONDIT SUBCOMPONENT NOT APPLICABLE ION DID NOT EXIST, THE PRIMARY CORE SPRAY PUMPS WERE TURNED OFF.
THIS C AUSED THE ALTERNATE PUMPS TO START AND THESE WERE ALSO STOPPED. UNDER T DESIGN / FABRICATION ERROR HESE CONDITIONS THE AUT0t1ATIC AND REMOTE MANUAL INITIAL FEATURES OF THE MANUFACTURING ALTERNATE CORE SPRAY PUMPS WERE DEFEATED.
ITT-BARTON THE INITIATING CAUSE'0F THE OCCURRENCE IS ATTRIBUTED TO INSTRUMENT SETPO INT SHIFT.
AFTER THE OPERATOR STOPPED THE PUMPS. THE ALTERNATE PUMPS WO ULD NOT HAVE STARTED AUTOMATICALLY BECAUSE OF THE DESIGN OF THE LOGIC CI RCUIT.
THE PLANT WAS SHUTDOWN AND ALL FOUR HIGH DRYWELL PRESSURE SENSOR S WERE RECALIBRATED.
0YSTER CREEK-1 05000219 121780 DURING FUNCTIONAL TESTING, SNUBBERS -19/11
-19/12 8 -19/13 (SERIAL NO.
EMERG CORE COOLING SYS + CONT 80-061/03L-0 011681 470915, 477361 & 477121) LOCATED ON CONTAINMENT SPRAY 8 CORE SPRAY SYSTE HANGERS, SUPPORTS, SHOCK SUPPRSS 033679 30-DAY M COMMON SUCTION HEADER, FAILED TO LOCK UP IN COMPRESSION MODE.
PLANS T SNUBBERS D PERFORM A DETAILED COMPUTER ANALYSIS WHICH MODELS EACH SNUBBER BASED 0 N ITS MODE OF FAILURE FOR 'sARIOUS MODES OF OPERATION ARE BEING MADE SO T-COMPONENT FAILURE HAT SAFETY SIGNIFICANCF AND PIPE STRESS MAGNITUDES CAN ACCURATELY BE REP MECHANICAL BERGEN-PATTERSON PIPE SUPPORT ORTED IN FORM OF A RFi1SION TO THIS REPORT.
CAUSE WAS ATTRIBUTED TO MAIN PISTON SEAL FAILURES. SEAL BREAKDOWN ALLOWE D MATERIAL TO GF7 INTO HYDRAULIC FLUID AND FLUID TO LEAK FROM CYLINDER.
CAUSE WAS ATTRIBUTED TO MAIN PISTON SEAL FAILURES. SEAL BREAKDOWN ALLOWE D MATERIAL TO GF7 INTO HYDRAULIC FLUID AND FLUID TO LEAK FROM CYLINDER.
THREE SNUBBEPS WERE REPLACED WITH OPERABLE SPARES.' DUE TO TOTAL NUf1BER OF SNUBBER FAILURES, ALL REMAINING HYDRAULIC SNUBBERS MUST NOW BE FUNCT IONALLY TESTED.
THREE SNUBBEPS WERE REPLACED WITH OPERABLE SPARES.' DUE TO TOTAL NUf1BER OF SNUBBER FAILURES, ALL REMAINING HYDRAULIC SNUBBERS MUST NOW BE FUNCT IONALLY TESTED.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _            _            _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ - __ _ _ _              -        _.    .  -,      -                    -                  . _      ~_. _
~.


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 64 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 64 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTIDH OVSTER CREEK-1                         05000219     010281     DURING SURVEILLANCE TESTING. THE CCNTAINMENT SPRAY SYSTEM HIGH DRYWELL P CNTHMNT HEAT REMOV SYS + CONT       81-001/03L-0   013081     RESSURE INDICATING SWITCH IP-15C WAS FOUND TO TRIP AT A VALUE GREATER TH INSTRUMENTATION + CONTROLS             036036     30-DAY     AN THE 2.0 PSIG TECHNICAL SPECIFICATIONS LIMITS.     THE "AS FOUND" TRIP P0 SWITCF                                                       INT WAS 2.10 PSIG, S0 ITS ACTUATION WOULD HAVE BEEN DELAYED BY A FRACTIO COMPONENT FAILURE                                             N OF A SECOND. HOWEVER, THE REDUNDANT SWITCH IP-15A WOULD HAVE ACTUATED INSTRUMENT                                                   AT THE DESIRED SETPOINT, SO THE SAFETY SIGNIFICANCE OF THE EVENT IS CON ITT-BARTON                                                   SIDERED MINIMAL.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTIDH OVSTER CREEK-1 05000219 010281 DURING SURVEILLANCE TESTING. THE CCNTAINMENT SPRAY SYSTEM HIGH DRYWELL P CNTHMNT HEAT REMOV SYS + CONT 81-001/03L-0 013081 RESSURE INDICATING SWITCH IP-15C WAS FOUND TO TRIP AT A VALUE GREATER TH INSTRUMENTATION + CONTROLS 036036 30-DAY AN THE 2.0 PSIG TECHNICAL SPECIFICATIONS LIMITS.
THE "AS FOUND" TRIP P0 SWITCF INT WAS 2.10 PSIG, S0 ITS ACTUATION WOULD HAVE BEEN DELAYED BY A FRACTIO COMPONENT FAILURE N OF A SECOND.
HOWEVER, THE REDUNDANT SWITCH IP-15A WOULD HAVE ACTUATED INSTRUMENT AT THE DESIRED SETPOINT, SO THE SAFETY SIGNIFICANCE OF THE EVENT IS CON ITT-BARTON SIDERED MINIMAL.
CAUSE WAS ATTRIBUTED TO INSTRUMENT REPEATABILITY. THE SWITCH WAS RESET TO TRIF UITHIN THE TECHNICAL SPECIFICATIONS LIMIT OF 2.0 PSIG, AND A STU DY IS PRESENTLY BEING DONE EXAMINING POSSIBLE SETPOINT CHANGES TO ACCOUN T FOR THIS REPEATABILITY. THE PORC HAS ALSO RECOMMENDED REPLACEMENT OF THESE SWITCHES WITH A MORE QUALIFIED MODEL.
CAUSE WAS ATTRIBUTED TO INSTRUMENT REPEATABILITY. THE SWITCH WAS RESET TO TRIF UITHIN THE TECHNICAL SPECIFICATIONS LIMIT OF 2.0 PSIG, AND A STU DY IS PRESENTLY BEING DONE EXAMINING POSSIBLE SETPOINT CHANGES TO ACCOUN T FOR THIS REPEATABILITY. THE PORC HAS ALSO RECOMMENDED REPLACEMENT OF THESE SWITCHES WITH A MORE QUALIFIED MODEL.
GYSTER CREEK-1                         05000219     010281     DURING NORMAL PLANT OPERATION, THE STACK GAS ACTIVITY WAS NOT CONTINUGUS PRCSS + EFF RADIOL MONITOR SYS     81-002/03L-0   013081     LY MONITORED AS REQUIRED BY TECH. SPEC. 3.6.A.3 DUE TO A TRIP OF THE STA PUMPS                                 036037     30-DAY     CK GAS SAMPLE PUMP. A REVIEW OF RECORDS FOR OTHER MONITORING SYSTEMS IN VANE TYPE                                                   DICATED THAT GASEOUS RELEASES TO THE STACK WERE NORMAL DURING THIS EVENT COMPONENT FAILURE                                               THERE WERE NO ADVERSE EFFECTS CH PUBLIC HEALTH OR SAFETY.
GYSTER CREEK-1 05000219 010281 DURING NORMAL PLANT OPERATION, THE STACK GAS ACTIVITY WAS NOT CONTINUGUS PRCSS + EFF RADIOL MONITOR SYS 81-002/03L-0 013081 LY MONITORED AS REQUIRED BY TECH. SPEC. 3.6.A.3 DUE TO A TRIP OF THE STA PUMPS 036037 30-DAY CK GAS SAMPLE PUMP.
NATURAL END OF LIFE GAST MANUFACTURING CORPORATION THE CAUSE OF THIS EVENT WAS ATTRIBUTED TG THE SAMPLE PUMP FAILING DUE TO NORMAL WEAR. THE CARBON VANES OF THE PUMP THINNED OUT, BROKE UP INSIDE THE PUMP CAUSING IT TO TRIP DN OVERLOAD DUE T0' BINDING. THE PUMP WAS R EPLACED WITH A SPARE.
A REVIEW OF RECORDS FOR OTHER MONITORING SYSTEMS IN VANE TYPE DICATED THAT GASEOUS RELEASES TO THE STACK WERE NORMAL DURING THIS EVENT COMPONENT FAILURE THERE WERE NO ADVERSE EFFECTS CH PUBLIC HEALTH OR SAFETY.
OVSTER CREEK-1                         05000219     010681     DURING AN OPERABILITY TEST TO CHECK INSTALLED AMMETERS. EMERGENCY SERVIC CNTNMNT HEAT REMOV SYS + CONT       81-005/03L-0   020681     E WATER PUMP 52B WAS FOUND TO DRAW LESS THAN 10 AMPERES CURRENT AND WAS PUMPS                                 036161     30-DAY     FOUND TO HAVE A 0 PSIG DISCHARGE PRESSURE. THE ACCEPTABLE VALUES ARE 53 CENTRIFUGAL                                                 +/- 3.0 AMPERES AND >/: 100 PSIG. THE REDUNDANT PUMP IN SYSTEM-I (52A)
NATURAL END OF LIFE GAST MANUFACTURING CORPORATION THE CAUSE OF THIS EVENT WAS ATTRIBUTED TG THE SAMPLE PUMP FAILING DUE TO NORMAL WEAR.
OTHER                                                         HAD ACCEPTABLE DATA. AND THE SYSTEM II ESW PUMPS (52C AND 52D) WERE ALS NOT APPLICABLE                                             O SHOWN TO BE CPERABLE. DUE TO THE OPERABLE ALTERNATE LOOP AND THE OPER DYRON JACKSON PUMPS. INC.                                     ABLE REDUNDANT PUMP, THE SAFETY SIGNIFICANCE IS MINIMAL.
THE CARBON VANES OF THE PUMP THINNED OUT, BROKE UP INSIDE THE PUMP CAUSING IT TO TRIP DN OVERLOAD DUE T0' BINDING.
THE PUMP WAS R EPLACED WITH A SPARE.
OVSTER CREEK-1 05000219 010681 DURING AN OPERABILITY TEST TO CHECK INSTALLED AMMETERS. EMERGENCY SERVIC CNTNMNT HEAT REMOV SYS + CONT 81-005/03L-0 020681 E WATER PUMP 52B WAS FOUND TO DRAW LESS THAN 10 AMPERES CURRENT AND WAS PUMPS 036161 30-DAY FOUND TO HAVE A 0 PSIG DISCHARGE PRESSURE. THE ACCEPTABLE VALUES ARE 53 CENTRIFUGAL
+/- 3.0 AMPERES AND >/: 100 PSIG.
THE REDUNDANT PUMP IN SYSTEM-I (52A)
OTHER HAD ACCEPTABLE DATA. AND THE SYSTEM II ESW PUMPS (52C AND 52D) WERE ALS NOT APPLICABLE O SHOWN TO BE CPERABLE. DUE TO THE OPERABLE ALTERNATE LOOP AND THE OPER DYRON JACKSON PUMPS. INC.
ABLE REDUNDANT PUMP, THE SAFETY SIGNIFICANCE IS MINIMAL.
THE CAUSE WAS ATTRIBUTED TD A CLOGGED PUMP SUCTIDH STRAINER. THE PUMP S TRAINER WAS CLEARED BY USE OF A SERVICE AIR CONNECTIDH TO THE SUCTION PI PING, AND THE PUMP WAS TESTED AGAIN AND THE NEW DATA WAS ACCEPTABLE. TH E REMAINING ESW PUMPS WERE ALSO TESTED AND SHOWN TO BE OPERABLE AS REQUI RED BY THE TECHNICAL SPECIFICATIONS, FEEAGRAPH 3.4.C.4.
THE CAUSE WAS ATTRIBUTED TD A CLOGGED PUMP SUCTIDH STRAINER. THE PUMP S TRAINER WAS CLEARED BY USE OF A SERVICE AIR CONNECTIDH TO THE SUCTION PI PING, AND THE PUMP WAS TESTED AGAIN AND THE NEW DATA WAS ACCEPTABLE. TH E REMAINING ESW PUMPS WERE ALSO TESTED AND SHOWN TO BE OPERABLE AS REQUI RED BY THE TECHNICAL SPECIFICATIONS, FEEAGRAPH 3.4.C.4.
OYSTER CREEK-1                         05000219     011281     0F JANUARY 12. DURING THE MONTHLY VISUAL INSPECTION OF FIRE HYDRANTS, HY FIRE PROTECTION SYS + CONT         81-003/03L-0   020931     DRANT 82 WAS FOUND TO HAVE WATER' FROZEN IN THE BARREL. RENDERING IT INOP VALVES                                 036124     30-DAY     ERABLE. THE SIGNIFICANCE OF THIS EVENT WOULD HAVE BEEN MINIMAL DUE TO T OTHER                                                       HE CLOSE PROXIMITY OF FIRE HYDRANT #3. PAST EXPERIENCE HAS SHOWN THAT T COMPONENT FAILURE                                             HIS IS THE FIRST OCCURRENCE OF THIS TYPE AT OYSTER CREEK.
OYSTER CREEK-1 05000219 011281 0F JANUARY 12. DURING THE MONTHLY VISUAL INSPECTION OF FIRE HYDRANTS, HY FIRE PROTECTION SYS + CONT 81-003/03L-0 020931 DRANT 82 WAS FOUND TO HAVE WATER' FROZEN IN THE BARREL. RENDERING IT INOP VALVES 036124 30-DAY ERABLE. THE SIGNIFICANCE OF THIS EVENT WOULD HAVE BEEN MINIMAL DUE TO T OTHER HE CLOSE PROXIMITY OF FIRE HYDRANT #3.
PAST EXPERIENCE HAS SHOWN THAT T COMPONENT FAILURE HIS IS THE FIRST OCCURRENCE OF THIS TYPE AT OYSTER CREEK.
MECHANICAL KENNEDf VALVE MFG. CO.
MECHANICAL KENNEDf VALVE MFG. CO.
THE CAUSE OF THE OCCURRENCE WAS DUE TO WATER LEAKING FROM THE HYDRANT VA LVE AND THEN FREEZING IN THE BARREL DURING SEVERE LOW TEMPERATURE CONDIT IONS. FIRE HOSE WAS ROUTED FROM HYDRANT #3 TO HYDRANT #2, AND THE HYDRA NT WAS THAWED OUT AND LATER RETURNED TO SERVICE. THE FUTURE ACTION WILL BE TO REPAIR THE HYDRANT OPERATING VALVE.
THE CAUSE OF THE OCCURRENCE WAS DUE TO WATER LEAKING FROM THE HYDRANT VA LVE AND THEN FREEZING IN THE BARREL DURING SEVERE LOW TEMPERATURE CONDIT IONS.
FIRE HOSE WAS ROUTED FROM HYDRANT #3 TO HYDRANT #2, AND THE HYDRA NT WAS THAWED OUT AND LATER RETURNED TO SERVICE. THE FUTURE ACTION WILL BE TO REPAIR THE HYDRANT OPERATING VALVE.


i MAR 26, 1981                                                   LER MONTHLY REPORT SORTED BY FACILITY                                       PAGE 65 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 65 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                               CAUSE DESCRIPTION OYSTER CREEK-1                                     05000219     011581   DURING SURVEILLANCE TESTING, THE REACTOR TRIPLE LOW WATER LEVEL INDICATO ENONRD SAFETY FEATR INSTR SYS             81-006/03L-0   020981   R SWITCH RE-18B TRIPPED AT A MANOMETER READING HIGHER THAN THE LIMIT OF INSTRUMENTATION + CONTROLS                   036125       30-DAY   216.0"H2O AS GIVEN IN THE TECHNICAL SPECIFICATIONS, TABLE 3.1'.1, ITEM G.
EVENT DATE/
SWITCH                                                           2. THE TRIP POINT VALUE WAS 129.0"H20. THE SAFETY SIGNIFICANCE IS CONS COMPONENT FAILURE                                                     IDERED MINIMAL SINCE THE REDUNDANT TRIP SYSTEM WOULD HAVE INITIATED THE INSTRUMENT                                                     REQUIRED PROTECTIVE ACTIONS WITHIN THE TECHNICAL SPECIFICATION LIMIT.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
ITT-BARTON THE CAUSE OF THE OCCURRENCE WAS INSTRUMENT DRIFT. THE SWITCH WAS RESET TO TRIP WITHIN THE TECHNICAL SPECIFICATION LIMIT OF 121.0"H2O TO 123.0"H
REPORT DATE/
: 20. POSSIBLE SETPOINT CHANGES TO ACCOUNT FOR INSTRUMENT REPEATABILITY A RE CURRENTLY BEING STUDIED.
EVENT DESCRIPTION /
OYSTER CREEK-1                                     05000219     011681   RECENT STUDIES HAVE INDICATED THAT DURING A LOSS OF COOLANT ACCIDENT WIT EMERG GENERATOR SYS + CONTROLS             81-004/01T-0   013081   H A LOSS OF OFF-SITE POWER PLUS A SINGLE BUS FAILURE THE LOAD ON THE EME GENERATORS                                     036038       2-WEEK   RGENCY DIESEL GENERATORS MAY EXCEED THE FULL LOAD RATING OF 2500 KW. THI GENERATOR                                                       S EVENT IS CONSIDERED REPORTABLE PER TECH. SPEC. 6.9.2.A(9). ALTHOUGH TH DESIGN / FABRICATION ERROR                                           E LOAD ON THE DIESEL GENERATOR IS NOT EXPECTED TO EXCEED THE PEAK LOAD R DESIGN                                                           ATING OF 2750 KW THE OPERATORS HAVE BEEN PROVIDED GUIDANCE VIA A STANDIN ELECTRO-MOTIVE DIV.                                                   G ORDER WHICH WILL REDUCE THE LOAD TO LESS THAN THE FULL LOAD RATING.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
'                                                                                                                CAUSE WAS ATTRIBUTED TO USING MORE CONSERVATIVE METHODS OF DETERMINING T HE DIESEL GENERATOR LOAD DURING ACCIDENT CONDITIONS. A STANDING ORDER H AS BEEN ISSUED WHICH HILL REDUCE THE LOAD ON THE DIESEL GENERATOR TO HIT 1                                                                                                               HIN THE CONTINUOUS FULL LOAD RATING. OTHER ANTICIPATED ACTIONS INCLUDE INSTALLING UNDERVOLTAGE DEVICES ON HON-ESSENTIAL LOADS.
REPORT TYPE CAUSE DESCRIPTION OYSTER CREEK-1 05000219 011581 DURING SURVEILLANCE TESTING, THE REACTOR TRIPLE LOW WATER LEVEL INDICATO ENONRD SAFETY FEATR INSTR SYS 81-006/03L-0 020981 R SWITCH RE-18B TRIPPED AT A MANOMETER READING HIGHER THAN THE LIMIT OF INSTRUMENTATION + CONTROLS 036125 30-DAY 216.0"H2O AS GIVEN IN THE TECHNICAL SPECIFICATIONS, TABLE 3.1'.1, ITEM G.
PALISADES-1                                       05000255     010781   DURING ROUTINE TESTING OF SAFETY INJECTION EQUIPMENT, HPSI MOTOR-OPERATE EMERG CORE COOLING SYS + CONT               81-003/03L-0   020581   D VALVE MCV-3011 FAILED TO OPEN UPON INITIATION OF TEST SIGNAL. REDUNDA RELAYS                                         036162       30-DAY   NT EQUIPMENT WAS OPERABLE. VALVE WAS STROKED OPEN AND MAINTAINED OPEN U TIMER, SEQUENCER, T-S CONTROL                                   HTIL REPAIRS WERE COMPLETED. LCO OF TECHNICAL SPECIFICATION 3.3.2E AND
SWITCH 2.
,                                          COMPONENT FAILURE                                                     REPORTING REQUIREMENTS OF TECH. SPEC. 6.9.2.32 APPLY.
THE TRIP POINT VALUE WAS 129.0"H20.
ELECTRICAL                                                                                             -
THE SAFETY SIGNIFICANCE IS CONS COMPONENT FAILURE IDERED MINIMAL SINCE THE REDUNDANT TRIP SYSTEM WOULD HAVE INITIATED THE INSTRUMENT REQUIRED PROTECTIVE ACTIONS WITHIN THE TECHNICAL SPECIFICATION LIMIT.
FANSTEEL, INC.
ITT-BARTON THE CAUSE OF THE OCCURRENCE WAS INSTRUMENT DRIFT.
INVESTIGATION REVEALED DIRTY CONTACTS'IN DBA SEQUENCER (34-3). CONTACTS WERE CLEANED AND PROPER VALVE OPERATION WAS RESTORED.
THE SWITCH WAS RESET TO TRIP WITHIN THE TECHNICAL SPECIFICATION LIMIT OF 121.0"H2O TO 123.0"H 20.
PALISADES-1                                         05000255     011981   DURING PERFORMANCE OF FIRE SPRINKLER SYSTEM TESTING. THE DRAIN VALVE IN FIRE PROTECTION SYS + CONT                 81-006/03L-0   021681   THE SOUTHWEST CABLE PENETRATION ROOM FIRE SPRINKLER SUPPLY LINE FAILED.
POSSIBLE SETPOINT CHANGES TO ACCOUNT FOR INSTRUMENT REPEATABILITY A RE CURRENTLY BEING STUDIED.
036164       30-DAY     THE CONDITION OCCURRED DURING OPENING OF THE VALVE. A CONTINUOUS FIRE VALVES GATE                                                            WATCH WITH FIRE SUPPRESSION EQUIPMENT WAS ESTABLISHED. SPRINKLER SYSTEM COMPONENT FAILURE                                                       WAS INOPERABLE FOR APPROXIMATELY 20 MINUTES. LCO OF TECHNICAL SPECIFIC-ATION 3.22.3 AND REPORTING REQUIREMENT 5 OF TECH SPEC 6.9.2.32 APPLY. EV MECHANICAL POWELL, M. W., CD.                                                     ENT IS NOT REPETITIVE. NO ADVERSE EFFECT ON PUBLIC HEALTH OR SAFETY.
OYSTER CREEK-1 05000219 011681 RECENT STUDIES HAVE INDICATED THAT DURING A LOSS OF COOLANT ACCIDENT WIT EMERG GENERATOR SYS + CONTROLS 81-004/01T-0 013081 H A LOSS OF OFF-SITE POWER PLUS A SINGLE BUS FAILURE THE LOAD ON THE EME GENERATORS 036038 2-WEEK RGENCY DIESEL GENERATORS MAY EXCEED THE FULL LOAD RATING OF 2500 KW. THI GENERATOR S EVENT IS CONSIDERED REPORTABLE PER TECH. SPEC. 6.9.2.A(9). ALTHOUGH TH DESIGN / FABRICATION ERROR E LOAD ON THE DIESEL GENERATOR IS NOT EXPECTED TO EXCEED THE PEAK LOAD R DESIGN ATING OF 2750 KW THE OPERATORS HAVE BEEN PROVIDED GUIDANCE VIA A STANDIN ELECTRO-MOTIVE DIV.
THE VALVE TMV 504 FPS) HAD A PREVIOUS HISTORY OF-LEAKAGE, WHICH HAD-BEEN CONTROLLED BY TIGHTENING OF THE VALVE BONNET. OVERTIGHTENING APPARENTL Y OCCURRED, RESULTING IN WEAKENING OF THE VALVE AND LEADING TO' FAILURE (
G ORDER WHICH WILL REDUCE THE LOAD TO LESS THAN THE FULL LOAD RATING.
BONNET BECAME SEPARATED FROM VALVE BODY). VALVE WAS REPLACED.
CAUSE WAS ATTRIBUTED TO USING MORE CONSERVATIVE METHODS OF DETERMINING T HE DIESEL GENERATOR LOAD DURING ACCIDENT CONDITIONS. A STANDING ORDER H AS BEEN ISSUED WHICH HILL REDUCE THE LOAD ON THE DIESEL GENERATOR TO HIT 1
HIN THE CONTINUOUS FULL LOAD RATING.
OTHER ANTICIPATED ACTIONS INCLUDE INSTALLING UNDERVOLTAGE DEVICES ON HON-ESSENTIAL LOADS.
PALISADES-1 05000255 010781 DURING ROUTINE TESTING OF SAFETY INJECTION EQUIPMENT, HPSI MOTOR-OPERATE EMERG CORE COOLING SYS + CONT 81-003/03L-0 020581 D VALVE MCV-3011 FAILED TO OPEN UPON INITIATION OF TEST SIGNAL.
REDUNDA RELAYS 036162 30-DAY NT EQUIPMENT WAS OPERABLE. VALVE WAS STROKED OPEN AND MAINTAINED OPEN U TIMER, SEQUENCER, T-S CONTROL HTIL REPAIRS WERE COMPLETED. LCO OF TECHNICAL SPECIFICATION 3.3.2E AND COMPONENT FAILURE REPORTING REQUIREMENTS OF TECH. SPEC. 6.9.2.32 APPLY.
ELECTRICAL FANSTEEL, INC.
INVESTIGATION REVEALED DIRTY CONTACTS'IN DBA SEQUENCER (34-3).
CONTACTS WERE CLEANED AND PROPER VALVE OPERATION WAS RESTORED.
PALISADES-1 05000255 011981 DURING PERFORMANCE OF FIRE SPRINKLER SYSTEM TESTING. THE DRAIN VALVE IN FIRE PROTECTION SYS + CONT 81-006/03L-0 021681 THE SOUTHWEST CABLE PENETRATION ROOM FIRE SPRINKLER SUPPLY LINE FAILED.
VALVES 036164 30-DAY THE CONDITION OCCURRED DURING OPENING OF THE VALVE.
A CONTINUOUS FIRE WATCH WITH FIRE SUPPRESSION EQUIPMENT WAS ESTABLISHED. SPRINKLER SYSTEM GATE COMPONENT FAILURE WAS INOPERABLE FOR APPROXIMATELY 20 MINUTES.
LCO OF TECHNICAL SPECIFIC-MECHANICAL ATION 3.22.3 AND REPORTING REQUIREMENT 5 OF TECH SPEC 6.9.2.32 APPLY.
EV POWELL, M.
W.,
CD.
ENT IS NOT REPETITIVE. NO ADVERSE EFFECT ON PUBLIC HEALTH OR SAFETY.
THE VALVE TMV 504 FPS) HAD A PREVIOUS HISTORY OF-LEAKAGE, WHICH HAD-BEEN CONTROLLED BY TIGHTENING OF THE VALVE BONNET.
OVERTIGHTENING APPARENTL Y OCCURRED, RESULTING IN WEAKENING OF THE VALVE AND LEADING TO' FAILURE (
BONNET BECAME SEPARATED FROM VALVE BODY).
VALVE WAS REPLACED.


PAGE 66 MAR 26, 1981                                                          LER MONTHLY REPORT SORTED BY-FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /             DOCKET NO./         EVENT DATE/
PAGE 66 LER MONTHLY REPORT SORTED BY-FACILITY MAR 26, 1981 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
REPORT DATE/                                    EVENT DESCRIPTION /
DOCKET NO./
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                         CAUSE DESCRIPTION CAUSE SUBCODE/ MANUFACTURER                 CONTROL NO.         REPORT TYPE 05000255       012181       DURING NORMAL PLANT OPERATION, COPPER TUBING TO PS-1473 (1-2 DIESEL-GENE PALISADES-1                                                                                                                                  TO MAKE REPAIRS, THE DIE 81-005/01L-0         021681       RATOR SERVICE WATER LOW PRESSURE ALARM) BROKE.
EVENT DATE/
EMERG GENERATOR SYS + CONTROLS                                                      SEL GENERATOR WAS MADE INOPERABLE; AS A RESULT, THE LCD OF-T.S. 3.7.2I W ENGINES, INTERNAL COMBUSTION                            036173        30-DAY AS ENTERED. ENGINE WAS RESTORED TO OPERABLE STATUS WITHIN TIME REQUIRED-SUBCOMPONENT NOT APPLICABLE                                                         BY T.S. 3.7.2I. EVENT NOT REPETITIVE. NO THREAT TO PUBLIC HEALTH OR S COMPONENT FAILURE                                                                   AFETY.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
MECHANICAL ALCO ENGINE DIV., WHITE IND.                                                         A CONTRACTOR WORKMAN ACCIDENTLY BUMPED THE TUBING, CAUSING IT TO BREAK.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION PALISADES-1 05000255 012181 DURING NORMAL PLANT OPERATION, COPPER TUBING TO PS-1473 (1-2 DIESEL-GENE EMERG GENERATOR SYS + CONTROLS 81-005/01L-0 021681 RATOR SERVICE WATER LOW PRESSURE ALARM) BROKE.
TO MAKE REPAIRS, THE DIE ENGINES, INTERNAL COMBUSTION 036173 30-DAY SEL GENERATOR WAS MADE INOPERABLE; AS A RESULT, THE LCD OF-T.S. 3.7.2I W AS ENTERED.
ENGINE WAS RESTORED TO OPERABLE STATUS WITHIN TIME REQUIRED-SUBCOMPONENT NOT APPLICABLE BY T.S.
3.7.2I.
EVENT NOT REPETITIVE. NO THREAT TO PUBLIC HEALTH OR S COMPONENT FAILURE AFETY.
MECHANICAL ALCO ENGINE DIV., WHITE IND.
A CONTRACTOR WORKMAN ACCIDENTLY BUMPED THE TUBING, CAUSING IT TO BREAK.
THE WORKMAN IMMEDIATELY NOTIFIED THE PLANT SHIFT SUPERVISOR. THIS EVEN T HAS BEEN REVIEWED WITH THE CONTRACTOR SITE PROJECT ENGINEER: THE NEED-FOR WORKMEN TO EXERCISE CAUTION WHEN WORKING NEAR SAFETY RELATED EQUIPME NT WAS EMPHASIZED.
THE WORKMAN IMMEDIATELY NOTIFIED THE PLANT SHIFT SUPERVISOR. THIS EVEN T HAS BEEN REVIEWED WITH THE CONTRACTOR SITE PROJECT ENGINEER: THE NEED-FOR WORKMEN TO EXERCISE CAUTION WHEN WORKING NEAR SAFETY RELATED EQUIPME NT WAS EMPHASIZED.
05000255         012881       DURING EVALUATION OF MASONRY WALLS PER IE BULLETIN 80-11, IT WAS DETERMI I          PALISADES-1                                                              021181       NED THAT 28 MALLS DID NOT MEET ACCEPTANCE CRITERIA. A TOTAL OF 64 WALLS OTHER SYSTEMS                                      81-004/01T-0 OTHER COMPONENTS                                         036163         2-WEEK         WERE EVALUATED. THE 60 A 180 DAY RESPONSES TO BULLETIN 80-11 (CPCO LET SUBCOMPONENT NOT APPLICABLE TERS DATED 7/9/80 8 11/6/80) PROVIDE ADDITIONAL INFORMATION. FUTURE REP ORTS CONCERNING THIS f.ER WILL BE PROVIDED IN FOLLOW-UP RESPONSES TO IE B l            DESIGN / FABRICATION ERROR                                                          ULLETIN 80-11     DUE TO ANTICIPATED CHANGES IN ACCEPTANCE CRITERI A, IT IS DESIGN                                                                               EXPECTED THE NUMBER OF DISCREPANT W.4LS WILL'BE REDUCED.
I PALISADES-1 05000255 012881 DURING EVALUATION OF MASONRY WALLS PER IE BULLETIN 80-11, IT WAS DETERMI OTHER SYSTEMS 81-004/01T-0 021181 NED THAT 28 MALLS DID NOT MEET ACCEPTANCE CRITERIA. A TOTAL OF 64 WALLS OTHER COMPONENTS 036163 2-WEEK WERE EVALUATED. THE 60 A 180 DAY RESPONSES TO BULLETIN 80-11 (CPCO LET TERS DATED 7/9/80 8 11/6/80) PROVIDE ADDITIONAL INFORMATION. FUTURE REP SUBCOMPONENT NOT APPLICABLE ORTS CONCERNING THIS f.ER WILL BE PROVIDED IN FOLLOW-UP RESPONSES TO IE B ULLETIN 80-11 DUE TO ANTICIPATED CHANGES IN ACCEPTANCE CRITERI A, IT IS l
BECHTEL CORP.                                                                       THE ORIGINAL DESIGN OF BLOCK WILLS CONFORMED TO INDUSTRY STANDARDS IN EF FECT AT THE-TIME OF CONCTRUCTION AND APPARENTLY DID NOT CONSIDER ALL POS TULATED LOADINGS (EG. SEISMIC, TORNADO). t1ETHODS TO CORRECT DISCREPANCI ES ARE BEING DEVELOPED AND WILL BE IMPLEMENTED WHEN MATERIALS ARE AVAILA BLE AND SCHEDULING CONSIDERATI0HS PERMIT.
DESIGN / FABRICATION ERROR DESIGN EXPECTED THE NUMBER OF DISCREPANT W.4LS WILL'BE REDUCED.
05000277        010381      DURING CONTROL ROD AND RECIRC FLOW ADJUSTMENTS, WITH THE UNIT AT POWER, PEACH BOTTOM-2                                                                       THE APRM FLUX SCRAM TRIP SETTING MAS BETWEEN 2.88 AND 5.60% HIGHER THAN REACTOR TRIP SYSTEMS                              81-0 0 7/ 0 3 L-0    020281                                                          IT WAS OUT OF ADJUSTMENT COMPONENT CODE NOT APPLICABLE                            036040        30-DAY      THE SETTING SPECIFIED IN TECH. SPEC. 2.1.A.1 SUBCOMPONENT NOT APPLICABLE FOR APPROXIMATELY 6 HOURS AND WAS PROMPTLY RESET WHEN DISCOVERED. BASED ON INDICATED CORE MAXIMUM FRACTION OF CRITICAL PCWER DURING THIS PERIOD PERSONNEL ERROR                                                                       ,  AND AS DISCUSSED IN TECH. SP EC. B ASES 2.1. A. NO SAFETY LIMIT WOULD HAV OTHER                                                                               E BEEN EXCEEDED HAD A WORST CASE TRANSIENT OCCURRED.
BECHTEL CORP.
ITEM NOT APPLICABLE                                                                 THE EVENT UAS CAUSED BY AN ENGINEER'S FAILURE TO MAKE NECESSARY ADJUSTME NTS TO THE APRM GAINS. THE GAINS WERE PROMPTLY RESET WHEN THE ERROR WAS DISCOVERED. 4 DISCUSSION WAS HELD BY THE STATION REACTOR ENGINEER WITH f                                                                                                     APPROPRI ATE N JCLEAR ENGINEERING PERSONNEL CONCERNING THE'IMPORTANCE OF MONITORING AND TIMELY ADJUSTMENT OF APRM GAINS.
THE ORIGINAL DESIGN OF BLOCK WILLS CONFORMED TO INDUSTRY STANDARDS IN EF FECT AT THE-TIME OF CONCTRUCTION AND APPARENTLY DID NOT CONSIDER ALL POS TULATED LOADINGS (EG. SEISMIC, TORNADO). t1ETHODS TO CORRECT DISCREPANCI ES ARE BEING DEVELOPED AND WILL BE IMPLEMENTED WHEN MATERIALS ARE AVAILA BLE AND SCHEDULING CONSIDERATI0HS PERMIT.
05000277         011681       DURING POWER OPERATIONS, A GROUP THREE ISOLATION WAS INITIATED. ONE GRO PEACH BOTT0t-2 81-005/03L-0 012981              UP THREE VALVE. TORUS VENT VALVE A0-2514, FAILED TO CLOSE AUTOMATICALLY CNTHMNT ISOLATION SYS + CONT                                                         UPON RECEIPT OF THE ISOLATION SIGNAL AND WOULD HOT CLOSE USING THE REMOT VALVE OPERATORS                                         036039         30-DAY E VALVE CONTR0t % WITCH. IM ACCORDANCE WITH TECH. SPEC. 4.7.D.2 THE OTHE SOLENDID - AC                                                                      R ISOL ATION VALVE IN THE LINE ( AO-2513) WAS VERIFIED CLOSED AND MONITORE COMPONENT FAILURE                                                                   D DAILY TO VERIFY THAT IT REMAINED CLOSED UNTIL REPAIRS WERE COMPLETED 0 MECHANICAL                                                                         N A0-2514.
DURING CONTROL ROD AND RECIRC FLOW ADJUSTMENTS, WITH THE UNIT AT POWER, PEACH BOTTOM-2 05000277 010381 REACTOR TRIP SYSTEMS 81-0 0 7/ 0 3 L-0 020281 THE APRM FLUX SCRAM TRIP SETTING MAS BETWEEN 2.88 AND 5.60% HIGHER THAN THE SETTING SPECIFIED IN TECH. SPEC. 2.1.A.1 IT WAS OUT OF ADJUSTMENT COMPONENT CODE NOT APPLICABLE 036040 30-DAY FOR APPROXIMATELY 6 HOURS AND WAS PROMPTLY RESET WHEN DISCOVERED. BASED SUBCOMPONENT NOT APPLICABLE INDICATED CORE MAXIMUM FRACTION OF CRITICAL PCWER DURING THIS PERIOD ON PERSONNEL ERROR AND AS DISCUSSED IN TECH. SP EC. B ASES 2.1. A. NO SAFETY LIMIT WOULD HAV OTHER E BEEN EXCEEDED HAD A WORST CASE TRANSIENT OCCURRED.
ASCO                                                                                 THE CAUSE OF FAILURE WAS A STICKING SOLENOID VALVE ( ASCO CAT. 38300 D9RF
ITEM NOT APPLICABLE THE EVENT UAS CAUSED BY AN ENGINEER'S FAILURE TO MAKE NECESSARY ADJUSTME NTS TO THE APRM GAINS.
                                                                                                    ). ON JANUARY 16. THE SOLENDID WAS FREED AND THE VALVE SUCCESSFULLY CLO SED. OH JANUARY 21 THE SOLENDID VALVE WAS REPL ACED IN KIND AND TESTED SATISFACTORILY.
THE GAINS WERE PROMPTLY RESET WHEN THE ERROR WAS DISCOVERED. 4 DISCUSSION WAS HELD BY THE STATION REACTOR ENGINEER WITH f
APPROPRI ATE N JCLEAR ENGINEERING PERSONNEL CONCERNING THE'IMPORTANCE OF MONITORING AND TIMELY ADJUSTMENT OF APRM GAINS.
PEACH BOTT0t-2 05000277 011681 DURING POWER OPERATIONS, A GROUP THREE ISOLATION WAS INITIATED. ONE GRO TORUS VENT VALVE A0-2514, FAILED TO CLOSE AUTOMATICALLY UP THREE VALVE.
CNTHMNT ISOLATION SYS + CONT 81-005/03L-0 012981 UPON RECEIPT OF THE ISOLATION SIGNAL AND WOULD HOT CLOSE USING THE REMOT VALVE OPERATORS 036039 30-DAY E VALVE CONTR0t % WITCH.
IM ACCORDANCE WITH TECH. SPEC. 4.7.D.2 THE OTHE R ISOL ATION VALVE IN THE LINE ( AO-2513) WAS VERIFIED CLOSED AND MONITORE SOLENDID - AC COMPONENT FAILURE D DAILY TO VERIFY THAT IT REMAINED CLOSED UNTIL REPAIRS WERE COMPLETED 0 MECHANICAL N A0-2514.
ASCO THE CAUSE OF FAILURE WAS A STICKING SOLENOID VALVE ( ASCO CAT. 38300 D9RF
).
ON JANUARY 16. THE SOLENDID WAS FREED AND THE VALVE SUCCESSFULLY CLO SED.
OH JANUARY 21 THE SOLENDID VALVE WAS REPL ACED IN KIND AND TESTED SATISFACTORILY.


MAR 26, 1981                                                                                                             LER MONTHLY REPORT SDRTED BY FACILITY                                                                                           PAGE 67 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                       DOCKET NO./                                           EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SDRTED BY FACILITY PAGE 67 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER HO./                                                                     REPORT DATE/                                                                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                           CONTROL NO.                                           REPORT TYPE                                                                                   CAUSE DESCRIPTION PEACH BOTTOM-2                                                           05000277                                                   L11781                 WITH THE PLANT AT POWER, THE                         'D' MAIN STEAM LINE (MSL) RAD MONITOR FAILE REACTOR TRIP SYSTEMS                                               81-006/03L-0                                                   021381                 D IN THE TRIPPED CONDITION, AND WAS MAINTAINED TRIPPED PER TECH. SPEC. T INSTRUMENTATION + CONTROLS                                               036165                                                   30-DAY                 ABLE 3.1.1.                     DURING REPAIRS. THE ' A' MONITOR CABLE WAS ERRONEOUSLY DISCO SENSOR /C57ECTOR/ ELEMENT                                                                                                                               NNECTED. A PLANT SHUTDOWN WAS INITIATED PER TECH. SPEC. TABLE 3.1.1, UN TIL THE MONITOR WAS RETURNED TO SERVICE IN APPROXIMATELY 2 HOURS.                                   BECAU PERSONNEL ERROR MAINTENANCE 8 REPAIR PERSONNEL                                                                                                                         SE THE 'D' MONITOR REMAINED TRIPPED DURING THE EVENT, THE REQUIRED PROTE GENERAL ELECTRIC CO.                                                                                                                                     CTIVE ACTION WOULD HAVE BEEN INITIATED ON MSL HIGH RAD LEVELS.
EVENT DATE/
THE CAUSE WAS TECHNICIAN ERROR.                           REPAIR WORK WAS BEING DONE HURRIEDLY DU E TO EXTREMELY HIGH TEMPERATURES IN THE AREA AND IT UAS ASSUMED THE 'D' MONITOR WAS HEXT TO THE 'D' MS LINE.                               PROPER INSTRUMENT IDENTIFICATION T ECHNIQUES UERE REVIEUED WITH THE TECHNICIANS. THE RAD MONITOR CABLES WI LL BE MORE CLEARLY MARKED DURING THE HEXT APPROPRIATE OUTAGE.
COMPONENT SUBCODE/CAUSE CODE / LER HO./
PEACH BOTTOM-3                                                           05000278                                                     121880               DURING SHUTDOUN OF UNIT, OPERATOR OBSERVED THAT RCIC INBOARD STEAM SUPPL REAC COPE ISOL COOL SYS + CONT                                     80-031/03L-0                                                   011381               Y ISOLATION VALVE DID NOT AUTOMATICALLY CLOSE AS REQUIRED. APPLICABLE T VALVE OPERATORS                                                         033680                                                     30-DAY               ECH SPEC IS 3.5.D.1. DUTBOARD STEAM SUPPLY VALVE CLOSED AUTOMATICALLY A OTHER                                                                                                                                                   S REQUIRED. VALVES HORMALLY AUTOMATICALLY CLOSE WHEN MAIN STEAM PRESSUR COMPONENT FAILURE                                                                                                                                         E DECREASES BELOW 105 PSIG. LOW PRESSURE ISOLATION LOGIC WAS TOTALLY OP MECHANICAL                                                                                                                                             ERABLE.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION PEACH BOTTOM-2 05000277 L11781 WITH THE PLANT AT POWER, THE
'D' MAIN STEAM LINE (MSL) RAD MONITOR FAILE REACTOR TRIP SYSTEMS 81-006/03L-0 021381 D IN THE TRIPPED CONDITION, AND WAS MAINTAINED TRIPPED PER TECH. SPEC. T INSTRUMENTATION + CONTROLS 036165 30-DAY ABLE 3.1.1.
DURING REPAIRS. THE ' A' MONITOR CABLE WAS ERRONEOUSLY DISCO SENSOR /C57ECTOR/ ELEMENT NNECTED. A PLANT SHUTDOWN WAS INITIATED PER TECH. SPEC. TABLE 3.1.1, UN PERSONNEL ERROR TIL THE MONITOR WAS RETURNED TO SERVICE IN APPROXIMATELY 2 HOURS.
BECAU MAINTENANCE 8 REPAIR PERSONNEL SE THE
'D' MONITOR REMAINED TRIPPED DURING THE EVENT, THE REQUIRED PROTE GENERAL ELECTRIC CO.
CTIVE ACTION WOULD HAVE BEEN INITIATED ON MSL HIGH RAD LEVELS.
THE CAUSE WAS TECHNICIAN ERROR.
REPAIR WORK WAS BEING DONE HURRIEDLY DU E TO EXTREMELY HIGH TEMPERATURES IN THE AREA AND IT UAS ASSUMED THE
'D' MONITOR WAS HEXT TO THE
'D' MS LINE.
PROPER INSTRUMENT IDENTIFICATION T ECHNIQUES UERE REVIEUED WITH THE TECHNICIANS. THE RAD MONITOR CABLES WI LL BE MORE CLEARLY MARKED DURING THE HEXT APPROPRIATE OUTAGE.
PEACH BOTTOM-3 05000278 121880 DURING SHUTDOUN OF UNIT, OPERATOR OBSERVED THAT RCIC INBOARD STEAM SUPPL REAC COPE ISOL COOL SYS + CONT 80-031/03L-0 011381 Y ISOLATION VALVE DID NOT AUTOMATICALLY CLOSE AS REQUIRED. APPLICABLE T VALVE OPERATORS 033680 30-DAY ECH SPEC IS 3.5.D.1.
DUTBOARD STEAM SUPPLY VALVE CLOSED AUTOMATICALLY A OTHER S REQUIRED. VALVES HORMALLY AUTOMATICALLY CLOSE WHEN MAIN STEAM PRESSUR COMPONENT FAILURE E DECREASES BELOW 105 PSIG.
LOW PRESSURE ISOLATION LOGIC WAS TOTALLY OP MECHANICAL ERABLE.
LIMITORQUE CORP.
LIMITORQUE CORP.
VALVE CLOSING TORQUE SWITCH ON TYPE SMB LIMITORQUE OPERATOR FOR VALVE MD 3-13-15 WAS FOUND OPEN. SWITCH WAS REPLACED. VALVE OPERATION AND RESP 0 NSE TO AN ISOLATION SIGNAL WERE SATISFACTORILY TESTED AND VALVE WAS RETU RNED TO SERVICE ON DECEMBER 19, 1980.                                                                       t PEACH BOTTOM-3                                                           05000278                                                   010981               DURING A ROUTINE SURVEILLANCE TEST WITH THE UNIT AT POWER, IT WAS FOUND EMERG CORE COOLING SYS + CONT                                       81- 0 0 2/ 0 3 L-0                                             020681               THAT A0-5247 (HPCI TURBINE EXHAUST INBOARD DRAIN ISOLATION VALVE) WOULD UALVES                                                                   036126                                                   30-DAY               NOT FULLY STROKE EITHER OPEN OR CLOSED. THE VALVE WAS DECLARED INOPERAB GLOBE                                                                                                                                                   LE AND OUTBOARD ISOLATION VALVE AD-5248 WAS CLOSED. THE VALVES UERE PLA COMPONENT FAILURE                                                                                                                                       CED ON THE INOPERABLE ISOLATION VALVE DAILY LOG. REPAIR WAS COMPLETED 0 MECHANICAL                                                                                                                                             H A0-5247 ON THE SAME DAY (1/9/81). APPLICABLE TECHNICAL SPECIFICATION BLACK-SIVALS-BRYSON                                                                                                                                     IS 37D.
VALVE CLOSING TORQUE SWITCH ON TYPE SMB LIMITORQUE OPERATOR FOR VALVE MD 3-13-15 WAS FOUND OPEN.
THE VALVE PACKING FOLLOWER WAS FOUND TO BE COCKED, WHICH PREVENTED FREE VALVE STEM TRAVEL. THE VALVE IS A SIVALLS AND BRYSON MODEL, 70-271DRTSX GLOBE. THE PACKING FOLLCUER WAS REALIGNED, THE PACKING RE-TENSIONED, A ND 1HE VALVE STROKED SUCCESSFULLY ON JANUARY 9, 1981.
SWITCH WAS REPLACED. VALVE OPERATION AND RESP 0 NSE TO AN ISOLATION SIGNAL WERE SATISFACTORILY TESTED AND VALVE WAS RETU RNED TO SERVICE ON DECEMBER 19, 1980.
PEACH BOTTOM-3                                                           05000278                                                   011381               DURING A SURVEILLANCE TEST, WITH THE UNIT AT FULL POWER, AN OIL LEAK OF CNTHMNT HEAT REMOV SYS + CONT                                       81-003/01T-0                                                   012781               ABOUT 3 TO 5 GPM WAS DISCOVERED ON THE DIL SUPPLY LINE TO THE HPCI TURBI VALVES                                                                   036041                                                   2-WEEK               ME MANUAL /0VERSPEED TRIP MECHANISM. IF HPCI TURBINE HAD STARTED WITH OI NEEDLE                                                                                                                                                 L LEAKING FR0il THE LINE, DIL WOULD STILL HAVE BEEN SUPPLIED TO THE BEARI COMPONENT FAILURE                                                                                                                                       NGS FOR ABOUT 30 MINUTES AT REDUCED PRESSURE. AT THAT POINT A TURBINE B MECHANICAL                                                                                                                                             EARING LOW PRESSURE ALARM WOULD HAVE BEEN RECEIVED. REMAINING ECCS SYST ROBERTSHAW CONTROLS CD.                                                                                                                                 EMS WERE IMMEDIATELY VERIFIED TO BE OPERABLE.
t PEACH BOTTOM-3 05000278 010981 DURING A ROUTINE SURVEILLANCE TEST WITH THE UNIT AT POWER, IT WAS FOUND EMERG CORE COOLING SYS + CONT 81- 0 0 2/ 0 3 L-0 020681 THAT A0-5247 (HPCI TURBINE EXHAUST INBOARD DRAIN ISOLATION VALVE) WOULD UALVES 036126 30-DAY NOT FULLY STROKE EITHER OPEN OR CLOSED. THE VALVE WAS DECLARED INOPERAB GLOBE LE AND OUTBOARD ISOLATION VALVE AD-5248 WAS CLOSED. THE VALVES UERE PLA COMPONENT FAILURE CED ON THE INOPERABLE ISOLATION VALVE DAILY LOG.
THE CAUSE WAS DETERMINED TO BE A RUPTURED DIAPHRAGM ON THE ROBERTSHAW OI L PRESSURE CONTROL VALVE MODEL VC-210. A NEW-DIAPHRAGM WAS INSTALLED IN THE VALVE AND THE SYSTEM SATISFACTORILY TESTED AND RETURNED T0-SERVICE ON JANUARY 13, 1981
REPAIR WAS COMPLETED 0 MECHANICAL H A0-5247 ON THE SAME DAY (1/9/81).
_ . _ _ _ -        .                _ _ _ _ _ _ _ _ _ _ _ - _ . _ - - _ - _ _ _ _ _          . _ _ _ _ _ - _ _ _ - _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ . _ _ _ - - - _            _ _ _ _ _ _ _ _ - _ _        ______ - ___        .- _-. -    - - _ _ - _ _ _ _ - .  -      .~
APPLICABLE TECHNICAL SPECIFICATION BLACK-SIVALS-BRYSON IS 37D.
THE VALVE PACKING FOLLOWER WAS FOUND TO BE COCKED, WHICH PREVENTED FREE VALVE STEM TRAVEL.
THE VALVE IS A SIVALLS AND BRYSON MODEL, 70-271DRTSX GLOBE.
THE PACKING FOLLCUER WAS REALIGNED, THE PACKING RE-TENSIONED, A ND 1HE VALVE STROKED SUCCESSFULLY ON JANUARY 9, 1981.
PEACH BOTTOM-3 05000278 011381 DURING A SURVEILLANCE TEST, WITH THE UNIT AT FULL POWER, AN OIL LEAK OF CNTHMNT HEAT REMOV SYS + CONT 81-003/01T-0 012781 ABOUT 3 TO 5 GPM WAS DISCOVERED ON THE DIL SUPPLY LINE TO THE HPCI TURBI VALVES 036041 2-WEEK ME MANUAL /0VERSPEED TRIP MECHANISM.
IF HPCI TURBINE HAD STARTED WITH OI NEEDLE L LEAKING FR0il THE LINE, DIL WOULD STILL HAVE BEEN SUPPLIED TO THE BEARI COMPONENT FAILURE NGS FOR ABOUT 30 MINUTES AT REDUCED PRESSURE. AT THAT POINT A TURBINE B MECHANICAL EARING LOW PRESSURE ALARM WOULD HAVE BEEN RECEIVED. REMAINING ECCS SYST ROBERTSHAW CONTROLS CD.
EMS WERE IMMEDIATELY VERIFIED TO BE OPERABLE.
THE CAUSE WAS DETERMINED TO BE A RUPTURED DIAPHRAGM ON THE ROBERTSHAW OI L PRESSURE CONTROL VALVE MODEL VC-210.
A NEW-DIAPHRAGM WAS INSTALLED IN THE VALVE AND THE SYSTEM SATISFACTORILY TESTED AND RETURNED T0-SERVICE ON JANUARY 13, 1981
.~


MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY                                                 PAGE 68 PROCESSED DURING 11 ARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /     DOCKET NO./             EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 68 PROCESSED DURING 11 ARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                     REPORT DATE/                                     EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER         CONTROL NO.             REPORT TYPE                                       CAUSE DESCRIPTION PEACH BOTTOM-3                                         05000278   012781           DURING SURVEILLANCE TESTING WHILE AT POWER, THE SETPOINT OF TEMPERATURE EMERG CORE COOLING SYS + CONT           81-005/03L-O             021981           SWITCH TS 5943 B (HPCI STEAM LINE AREA HIGH TEMP. ISOLATION) WAS FOUND T INSTRUMENTATION + CONTROLS                             036166     30-DAY         0EG.
EVENT DATE/
BE GREATER THAN THE TECHNICAL SPECIFICATION TABLE 3.2.B LIMIT OF 200 D SWITCH                                                                                 F. BY 6 DEG. F. THIS IS ONE OF 16 SWITCHES IN FOUR TRIP SYSTEMS THA COMPONENT FAILURE ELECTRONIC                                                                      T PROVIDE HPCI SYSTEM ISOLATION IN THE EVENT OF HIGH TEMPERATURE IN THE OTHER                                                                            VICINITY OF THE HPCI STEAMLINE. THE REMAINING TEMPERATURE SWITCHES WERE OPERABLE.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
THE INSTRUMFMTATION ERROR WAS CAUSED BY SETPOINT DRIFT. THE INSTRUMENT (MODU-FLASH SERIES 600) WAS IMMEDIATELY RECALIBRATED TO WITHIN TECHNICAL SPECIFICATION LIMITS, TESTED, AND RETURNED TO SERVICE.
REPORT DATE/
PILGRIM-1                                             05000293   120980 SYSTEM CODE NOT APPLICABLE                                                        A FIRE WHICH OCCURRED IN THE SECURITY BUILDING'S MECHANICAL ROOM ON 12/9 80-095/03L-0             011981         /80, WAS DETECTED AT APPROXIMATELY 1552 HRS. BY SECURITY PERSONNEL AND E COMPONENT CODE NOT APPLICABLE                         033681     30-DAY         XTINGUISHED WITHIN TEN MINUTES. THE SECURITY PERSONNEL IMMEDIATELY NOTI SUBCOMPONENT NOT APPLICABLE                                                     FIED THE CONTROL ROOM AND THE SENIOR FIRE PROTECTION ENGINEER, HOWEVER, OTHER NOT APPLICABLE                                                                  STATION PROCEDURE NUMBER 5.5.1 WAS NOT FOLLOWED IN THAT THE WATCH ENGINE ER DID NOT SUMMON THE FIRE BRIGADE.
EVENT DESCRIPTION /
ITEM NOT APPLICABLE FIRE DID NOT INVOLVE PROCESS BUILDINGS. THIS KNOWLEDGE INHIBITED STATIO N PERSONNEL FROM SUMMONING FIRE BRIGADE. A MEMO WILL BE ISSUED TO FIRE BRIGADE PERSONMEL CONCERNING NECESSITY TO SUMMON FIRE BRIGADE AS REQUIRE D BY PROCEDURE NUMBER 5.5.1. ADDITIONALLY THE REQUIREMENT WILL BE EMPHA PILGRIM-1                                                                          SIZED DURING THE NEXT FIRE BRIGADE TRAINING.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
05000293   010781         ON JANUARY 7,   1981, AT APFROXIMATELY 0113 AND AGAIN AT 1430 HOURS. THE M PRCSS + EFF RADIOL MONITOR SYS         81-002/03L-0             020681         AIN STACK SAMPLE FLOW ALARM WAS RECEIVED ON PANEL C903 IN THE CONTROL RO PUMPS                                                 036127     30-DAY         OM. INVESTIGATION REVEALED THAT IN THE FORMER CASE, THE SUCTION LINE TO VANE TYPE                                                                         THE STACK GAS SAMPLE PUMP P143 WAS PLUGGED, AND IN THE LATTER CASE, THE COMPONENT FAILURE                                                                   PUMP'S FUSE WAS BLOWN.
REPORT TYPE CAUSE DESCRIPTION PEACH BOTTOM-3 05000278 012781 DURING SURVEILLANCE TESTING WHILE AT POWER, THE SETPOINT OF TEMPERATURE EMERG CORE COOLING SYS + CONT 81-005/03L-O 021981 SWITCH TS 5943 B (HPCI STEAM LINE AREA HIGH TEMP. ISOLATION) WAS FOUND T INSTRUMENTATION + CONTROLS 036166 30-DAY 0 BE GREATER THAN THE TECHNICAL SPECIFICATION TABLE 3.2.B LIMIT OF 200 D SWITCH EG.
ELECTRICAL                                                                                                    ON BOTH OCCASIONS A CONTROLLED SHUTDOWN WAS INI TIATED AS REQUIRED BY TECHMICAL SPECIFICATION 3.8.B.5.
F.
GAST MANUFACTURING CORPORATION ON THE FIRST OCCASION, THE SUCTION LINE WAS FOUND FROZEN. THE BREAKER W HICH ENERGIZES THE HEAT TRACING ON THE SUCTION LINE WAS FOUND "0FF" AND RETURNED TO THE "0N" POSITION. ON THE S3COND OCCURRENCE. THE PUMP'S POW ER SUPPLY FUSE WAS FOUND BL0uH AND REP! ACED. CURRENT PLANT PRACTICES AR POINT BEACH-1                                                                      E ADEQUATE TO DETECT AND RESOLVE PROBLEMS OF THIS NATURE.
BY 6 DEG.
05000~266     121780         AT 1210 HOURS, 12/17/80, DURING TESTING,4D EMERGENCY DIESEL GENERATOR (C EMERG GENERATOR SYS + CONTROLS         80-016/03L-0             011581         OMMON TO UNITS 1 AND 2) FAILED TO CLOSE IN ON BUS. 3D EMERGENCY DIESEL MECHANICAL FUNCTION UNITS                             033632     30-DAY         GENERATOR WAS TESTED TO VERIFY ITS OPERABILITY. 4D EMERGENCY DIESEL GEN SUBCOMPONENT NOT APPLICABLE                                                     ERATOR WAS RETURNED TO SERVICE AT 1530 HOURS.       BECAUSE THE REDUNDANT EME COMPONENT FAILURE                                                               RGENCY DIESEL GENERATOR WAS OPERALLE, THE PUBLIC HEALTH 3 SAFETY WERE NO MECHANICAL GENERAL MOTORS                                                                    T AFFECTED. EVENT LED TO A DEGRADED MODE OF OPERATION PERMITTED BY TECHN ICAL SPECIFICATIONS.
F.
THIS IS ONE OF 16 SWITCHES IN FOUR TRIP SYSTEMS THA COMPONENT FAILURE T PROVIDE HPCI SYSTEM ISOLATION IN THE EVENT OF HIGH TEMPERATURE IN THE ELECTRONIC VICINITY OF THE HPCI STEAMLINE. THE REMAINING TEMPERATURE SWITCHES WERE OTHER OPERABLE.
THE INSTRUMFMTATION ERROR WAS CAUSED BY SETPOINT DRIFT.
THE INSTRUMENT (MODU-FLASH SERIES 600) WAS IMMEDIATELY RECALIBRATED TO WITHIN TECHNICAL SPECIFICATION LIMITS, TESTED, AND RETURNED TO SERVICE.
PILGRIM-1 05000293 120980 A FIRE WHICH OCCURRED IN THE SECURITY BUILDING'S MECHANICAL ROOM ON 12/9 SYSTEM CODE NOT APPLICABLE 80-095/03L-0 011981
/80, WAS DETECTED AT APPROXIMATELY 1552 HRS. BY SECURITY PERSONNEL AND E COMPONENT CODE NOT APPLICABLE 033681 30-DAY XTINGUISHED WITHIN TEN MINUTES.
THE SECURITY PERSONNEL IMMEDIATELY NOTI SUBCOMPONENT NOT APPLICABLE FIED THE CONTROL ROOM AND THE SENIOR FIRE PROTECTION ENGINEER, HOWEVER, OTHER STATION PROCEDURE NUMBER 5.5.1 WAS NOT FOLLOWED IN THAT THE WATCH ENGINE NOT APPLICABLE ER DID NOT SUMMON THE FIRE BRIGADE.
ITEM NOT APPLICABLE FIRE DID NOT INVOLVE PROCESS BUILDINGS. THIS KNOWLEDGE INHIBITED STATIO N PERSONNEL FROM SUMMONING FIRE BRIGADE.
A MEMO WILL BE ISSUED TO FIRE BRIGADE PERSONMEL CONCERNING NECESSITY TO SUMMON FIRE BRIGADE AS REQUIRE D BY PROCEDURE NUMBER 5.5.1.
ADDITIONALLY THE REQUIREMENT WILL BE EMPHA SIZED DURING THE NEXT FIRE BRIGADE TRAINING.
PILGRIM-1 05000293 010781 ON JANUARY 7, 1981, AT APFROXIMATELY 0113 AND AGAIN AT 1430 HOURS. THE M PRCSS + EFF RADIOL MONITOR SYS 81-002/03L-0 020681 AIN STACK SAMPLE FLOW ALARM WAS RECEIVED ON PANEL C903 IN THE CONTROL RO PUMPS 036127 30-DAY OM.
INVESTIGATION REVEALED THAT IN THE FORMER CASE, THE SUCTION LINE TO VANE TYPE THE STACK GAS SAMPLE PUMP P143 WAS PLUGGED, AND IN THE LATTER CASE, THE COMPONENT FAILURE PUMP'S FUSE WAS BLOWN.
ON BOTH OCCASIONS A CONTROLLED SHUTDOWN WAS INI ELECTRICAL TIATED AS REQUIRED BY TECHMICAL SPECIFICATION 3.8.B.5.
GAST MANUFACTURING CORPORATION ON THE FIRST OCCASION, THE SUCTION LINE WAS FOUND FROZEN. THE BREAKER W HICH ENERGIZES THE HEAT TRACING ON THE SUCTION LINE WAS FOUND "0FF" AND RETURNED TO THE "0N" POSITION. ON THE S3COND OCCURRENCE. THE PUMP'S POW ER SUPPLY FUSE WAS FOUND BL0uH AND REP! ACED.
CURRENT PLANT PRACTICES AR E ADEQUATE TO DETECT AND RESOLVE PROBLEMS OF THIS NATURE.
POINT BEACH-1 05000~266 121780 AT 1210 HOURS, 12/17/80, DURING TESTING,4D EMERGENCY DIESEL GENERATOR (C EMERG GENERATOR SYS + CONTROLS 80-016/03L-0 011581 OMMON TO UNITS 1 AND 2) FAILED TO CLOSE IN ON BUS.
3D EMERGENCY DIESEL MECHANICAL FUNCTION UNITS 033632 30-DAY GENERATOR WAS TESTED TO VERIFY ITS OPERABILITY. 4D EMERGENCY DIESEL GEN SUBCOMPONENT NOT APPLICABLE ERATOR WAS RETURNED TO SERVICE AT 1530 HOURS.
BECAUSE THE REDUNDANT EME COMPONENT FAILURE RGENCY DIESEL GENERATOR WAS OPERALLE, THE PUBLIC HEALTH 3 SAFETY WERE NO MECHANICAL T AFFECTED. EVENT LED TO A DEGRADED MODE OF OPERATION PERMITTED BY TECHN GENERAL MOTORS ICAL SPECIFICATIONS.
ADEQUATE ENGINE SPEED WAS NOT SENSED BY BUS BREAKER CLOSING LOGIC DUE TO SLIPPAGE OF A GENERAL MOTORS ELECTROMOTIVE DIVISION FLEXIBLE SHAFT COUP-LING (P.N. 8276102) ON THE SPEED SENSING FREQUENCY GENERATOR DRIVE SHAFT THE COUPLING WAS SECURED.
ADEQUATE ENGINE SPEED WAS NOT SENSED BY BUS BREAKER CLOSING LOGIC DUE TO SLIPPAGE OF A GENERAL MOTORS ELECTROMOTIVE DIVISION FLEXIBLE SHAFT COUP-LING (P.N. 8276102) ON THE SPEED SENSING FREQUENCY GENERATOR DRIVE SHAFT THE COUPLING WAS SECURED.


MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 69 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./     EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 69 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
CPMPONENT SUBCODE/CAUSE CODE / LER NO./           REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION POINT BEACH
EVENT DATE/
* 05900266       0?D281     AT 0139 HOURS ON 01/02/81 THE SUPPLY BREAKER FOR SAFEGUARDS MOTOR CONTR AC ONSITE POWER SYS + CONTROLS         81-001/01T-0     011681     OL CENTER 1B42 TRIPPED WHILE PERFORMING A MONTHLY VENTILATION SYSTEM TES CIRCUIT CLOSERS / INTERRUPTERS           036128       2-WEEK     T. THE UNIT MAS AT ABOUT 70% STEADY STATE POWER AT THE TIME.             THE LOSS CIRCUIT BREAKER                                                 OF 1B42 RESULTED IN A LOSS OF THE 1Y04 INSTRUMENT BUS. THE LOSS OF THE OTHER                                                             1YO4 BUS RESULTED IN A MOMENTARY VIOLATION OF THE MINIMUM DEGREE OF REDU NOT APPLICABLE                                                   NDANCY REQUIRED BY TECHNICAL SPECIFICATIONS AND IS REPORTABLE PER TECH.
CPMPONENT SUBCODE/CAUSE CODE / LER NO./
WESTINGHOUSE ELECTRIC CORP.                                       SPEC. 15.6.9.2.A.2.
REPORT DATE/
THE 1YO4 INSTRUMENT BUS WAS SHIFTED TO ITS ALTERNATE POWER SUPPLY AT 014 0 HOURS AND POWER WAS RESTORED TO 1B42 AT 0141 THE SAME DAY. THE CAUSE OF THE BREAKER TRIP WAS FOUND TO BE DUST IN THE INSTANTANEOUS TRIP VALVE ON THE BREAKER. THE WESTINGHOUSE TYPE DB-50 BREAKER WAS CLEANED, TESTE D, AND RETURNED-TO-SERVICE.
EVENT DESCRIPTION /
POINT BEACH-1                             05000266       011381     ON 01-13-81, DURING NORMAL OPERATION, A POST ACCEPTANCE REVIEW OF THE AN CONT ROOM HABITBLTY SYS + CONT         81-002/03L-0     020481     NUAL TEST RESULTS FROM 04-80. FOR THE CONTROL ROOM EMERGENCY FILTRATION FILTERS                                   036213       30-DAY     SYSTEM, REVEALED THAT THE 1980 ANNUAL TEST WAS NOT COMPLETE PER TECH. SP SUBCOMPONENT NOT APPLICABLE                                     EC. 15.4.11. AT THIS TIME. THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM PERSONNEL ERROR                                                     (COMMON TO BOTH UNITS) WAS DEEMED INOPERABLE BY TECH. SPEC. DEFINITION.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
RADIATION PROTECTIDH PERSONNEL                                   THIS LED TO A DEGRADED MODE OF OPERATION ALLOWED BY TECH. SPECS. THE P ITEM NOT APPLICABLE                                               UBLIC HEALTH & SAFETY WERE NOT AFFECTED AS SYS, IN REALITY, WAS OPER.
REPORT TYPE CAUSE DESCRIPTION POINT BEACH
THE EVENT WAS CAUSED BY HEALTH PHYSICS PERSONNEL FAILING TO DETERMINE, D URING THE ACCEPTANCE REVIEW, THAT THE TEST L ACKED SYSTEM VELOCITY AND FL OW INFORMATION. THE TEST WAS REPEATED AND THE SYSTEM UAS FOUND TO PERF0 RM SATISFACTORILY ON 01-15-81.       THE TESTING PROCEDURES ARE BEIMG MODIFIE D TO ASSURE THAT SYSTEM VELOCITY AND FLOW INFORMATION IS INCLUDED.
* 05900266 0?D281 AT 0139 HOURS ON 01/02/81 THE SUPPLY BREAKER FOR SAFEGUARDS MOTOR CONTR AC ONSITE POWER SYS + CONTROLS 81-001/01T-0 011681 OL CENTER 1B42 TRIPPED WHILE PERFORMING A MONTHLY VENTILATION SYSTEM TES CIRCUIT CLOSERS / INTERRUPTERS 036128 2-WEEK T.
PRAIRIE ISLAND-1                         05000262       122280     DURING SURVEILLANCE TEST, ONE STEAM EXCLUSION ACTUATION BISTABLE TRIPPED AIR COND. HEAT, COOL. VENT SYSTEM     80-038/C3L-0     012181     AT 123F, 3F ABOVE THE 120F LIMIT.       REDUNDANT TRAIN WAS OPERABLE. NO EF INSTRUMENTATION + CONTROLS               033683       30-DAY     FECT ON PUBLIC HEALTH AND SAFETY.       LAST SIMILAR EVENT WAS RO 79-22.
THE UNIT MAS AT ABOUT 70% STEADY STATE POWER AT THE TIME.
SWITCH COMPONENT FAILURE INSTRUMENT FOXBORO CO., THE DRIFT OF A FOXBORD MODEL 63U-CC-OHDR-F BISTABLE. INSPECTED AND CALIBRAT ED. RETEST WAS SATISFACTORY.
THE LOSS CIRCUIT BREAKER OF 1B42 RESULTED IN A LOSS OF THE 1Y04 INSTRUMENT BUS.
PRAIRIE ISLAND-1                         05000282       011281   WHILE PERFORMING PIPING MnDIFICATION WORK IN THE AREA 0F NO. 11 AUXILIAR FEEDWATER SYSTEMS + CONTROLS           81-001/03L-0     021081   Y FEEDAATER PUMP, A WORKMAN ACCIDENTALLY BUMPED THE OVERSPEED TRIP MECHA VALVE OPERATORS                           036129       30-DAY   NISM, TRIPPING THE VALVE AND MAKING THE PUMP INOPERABLE FOR ABOUT 12 MIN MECHANICAL                                                       UTES. THE EVENT WAS ANNUNCIATED IN THE CONTROL ROOM.         RECENT SIMILAR EV PERSONNEL ERROR                                                   ENT WAS RO 80-26. TECHNICAL SPECIFICATION 3.4.A.2.B APPLIES.               NO EFFECT MAINTENANCE & REPAIR PERSONNEL                                     ON PUBLIC HEALTH OR SAFETY. REDUNDANT EQUIPMENT WAS OPERABLE.
THE LOSS OF THE OTHER 1YO4 BUS RESULTED IN A MOMENTARY VIOLATION OF THE MINIMUM DEGREE OF REDU NOT APPLICABLE NDANCY REQUIRED BY TECHNICAL SPECIFICATIONS AND IS REPORTABLE PER TECH.
GIMBEL MACHINE WORKS PERSONNEL ERROR.     THE VALVE OPERATOR WAS RESET.
WESTINGHOUSE ELECTRIC CORP.
SPEC.
15.6.9.2.A.2.
THE 1YO4 INSTRUMENT BUS WAS SHIFTED TO ITS ALTERNATE POWER SUPPLY AT 014 0 HOURS AND POWER WAS RESTORED TO 1B42 AT 0141 THE SAME DAY.
THE CAUSE OF THE BREAKER TRIP WAS FOUND TO BE DUST IN THE INSTANTANEOUS TRIP VALVE ON THE BREAKER.
THE WESTINGHOUSE TYPE DB-50 BREAKER WAS CLEANED, TESTE D, AND RETURNED-TO-SERVICE.
POINT BEACH-1 05000266 011381 ON 01-13-81, DURING NORMAL OPERATION, A POST ACCEPTANCE REVIEW OF THE AN CONT ROOM HABITBLTY SYS + CONT 81-002/03L-0 020481 NUAL TEST RESULTS FROM 04-80. FOR THE CONTROL ROOM EMERGENCY FILTRATION FILTERS 036213 30-DAY SYSTEM, REVEALED THAT THE 1980 ANNUAL TEST WAS NOT COMPLETE PER TECH. SP SUBCOMPONENT NOT APPLICABLE EC.
15.4.11.
AT THIS TIME. THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM PERSONNEL ERROR (COMMON TO BOTH UNITS) WAS DEEMED INOPERABLE BY TECH. SPEC. DEFINITION.
RADIATION PROTECTIDH PERSONNEL THIS LED TO A DEGRADED MODE OF OPERATION ALLOWED BY TECH. SPECS.
THE P ITEM NOT APPLICABLE UBLIC HEALTH & SAFETY WERE NOT AFFECTED AS SYS, IN REALITY, WAS OPER.
THE EVENT WAS CAUSED BY HEALTH PHYSICS PERSONNEL FAILING TO DETERMINE, D URING THE ACCEPTANCE REVIEW, THAT THE TEST L ACKED SYSTEM VELOCITY AND FL OW INFORMATION. THE TEST WAS REPEATED AND THE SYSTEM UAS FOUND TO PERF0 RM SATISFACTORILY ON 01-15-81.
THE TESTING PROCEDURES ARE BEIMG MODIFIE D TO ASSURE THAT SYSTEM VELOCITY AND FLOW INFORMATION IS INCLUDED.
PRAIRIE ISLAND-1 05000262 122280 DURING SURVEILLANCE TEST, ONE STEAM EXCLUSION ACTUATION BISTABLE TRIPPED AIR COND. HEAT, COOL. VENT SYSTEM 80-038/C3L-0 012181 AT 123F, 3F ABOVE THE 120F LIMIT.
REDUNDANT TRAIN WAS OPERABLE. NO EF INSTRUMENTATION + CONTROLS 033683 30-DAY FECT ON PUBLIC HEALTH AND SAFETY.
LAST SIMILAR EVENT WAS RO 79-22.
SWITCH COMPONENT FAILURE INSTRUMENT FOXBORO CO., THE DRIFT OF A FOXBORD MODEL 63U-CC-OHDR-F BISTABLE. INSPECTED AND CALIBRAT ED.
RETEST WAS SATISFACTORY.
PRAIRIE ISLAND-1 05000282 011281 WHILE PERFORMING PIPING MnDIFICATION WORK IN THE AREA 0F NO. 11 AUXILIAR FEEDWATER SYSTEMS + CONTROLS 81-001/03L-0 021081 Y FEEDAATER PUMP, A WORKMAN ACCIDENTALLY BUMPED THE OVERSPEED TRIP MECHA VALVE OPERATORS 036129 30-DAY NISM, TRIPPING THE VALVE AND MAKING THE PUMP INOPERABLE FOR ABOUT 12 MIN MECHANICAL UTES.
THE EVENT WAS ANNUNCIATED IN THE CONTROL ROOM.
RECENT SIMILAR EV PERSONNEL ERROR ENT WAS RO 80-26.
TECHNICAL SPECIFICATION 3.4.A.2.B APPLIES.
NO EFFECT MAINTENANCE & REPAIR PERSONNEL ON PUBLIC HEALTH OR SAFETY.
REDUNDANT EQUIPMENT WAS OPERABLE.
GIMBEL MACHINE WORKS PERSONNEL ERROR.
THE VALVE OPERATOR WAS RESET.


MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 70 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPONEN1/ DOCKET NO./       EVENT DATE/
MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 70 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPONEN1/
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER   CONTROL NO.       REPORT TYPE                                                                       .
EVENT DATE/
CAUSE DESCRIPTION QUAD CITIES-1                         05000254         121780 REACTOR CONTAINMENT SYSTEMS      80-033/03L-0        010681    WHILE PLACING STANDBY CAS TREATMENT IN A NORMAL STANDBY OPERATION. SUCTI CIRCUIT CLOSERS / INTERRUPTERS        033724        30-DAY    ON VALVE MD-1-7503 FAILED TO OPEN FROM THE CONTROL ROOM.     THE MO-1-7503 CONTACTOR                                                      VALVE WAS OPENED MANUALLY THUS ENABLING BOTH "A" AND "B" TRAINS OF STAND COMPONENT FAILURE                                               BY GAS TREATMENT TO BE OPERABLE AND CAPABLE OF NAINTAINING REACTOR BUILD ELECTRICAL                                                     ING NEGATIVE PRESSURE HAD THE NEED ARISEN.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION QUAD CITIES-1 05000254 121780 WHILE PLACING STANDBY CAS TREATMENT IN A NORMAL STANDBY OPERATION. SUCTI REACTOR CONTAINMENT SYSTEMS 80-033/03L-0 010681 ON VALVE MD-1-7503 FAILED TO OPEN FROM THE CONTROL ROOM.
THE MO-1-7503 CIRCUIT CLOSERS / INTERRUPTERS 033724 30-DAY VALVE WAS OPENED MANUALLY THUS ENABLING BOTH "A" AND "B" TRAINS OF STAND CONTACTOR COMPONENT FAILURE BY GAS TREATMENT TO BE OPERABLE AND CAPABLE OF NAINTAINING REACTOR BUILD ELECTRICAL ING NEGATIVE PRESSURE HAD THE NEED ARISEN.
CENERAL ELECTRIC C3.
CENERAL ELECTRIC C3.
INVESTIGATION OF THE VALVE BREAKER fdVEALED THAT THE AUXILIARY CONTACTS WERE DIRTY AND NOT MAKING PROPER CGNTACT. THE AUXILIARY CONTACTS WERE R EMOVED. CLEANED. AND REPLACED. VALVE MD-1-7503 WAS TESTED AND OPERATED SATISFACTORILY FROM THE CONTROL ROOM ON DECEMBER 18. 1980.
INVESTIGATION OF THE VALVE BREAKER fdVEALED THAT THE AUXILIARY CONTACTS WERE DIRTY AND NOT MAKING PROPER CGNTACT.
QUAD CITIES-1                         05000254         010581 REACTOR CONTAINMENT SYSTEMS AT 9: 10 A.M. WHILE PLACING THE "B" STANDBY GAS TREATMENT SYSTEM IN A NOR 81- 0 01/ 0 3 L-0   012081   MAL SHUTDOWN LINE-UP, DISCHARGE VALVE MD-1/2-7507B FAILED TO CLOSE WHEN CIRCUIT CLOSERS / INTERRUPTERS       036130         30-DAY     OPERATED FROM THE CONTROL ROOM.     TPE "A" STANDBY GAS TREATMENT SYSTEM WA CONTACTOR COMPONENT FAILURE                                               S
THE AUXILIARY CONTACTS WERE R EMOVED. CLEANED. AND REPLACED. VALVE MD-1-7503 WAS TESTED AND OPERATED SATISFACTORILY FROM THE CONTROL ROOM ON DECEMBER 18. 1980.
                                                                  .A.DEMONSTRATED OPERABLE IN ACCORDAd'5 WITH TECHNICAL SPECIFICATION 3.7.B ELECTRICAL                                                            AND WAS FULLY CAPABLE OF MAINTAfdTNG A NEGATIVE REACTOR BUILDING DIF GENERAL ELECTRIC CO.                                              FERENTIAL PRESSURE HAD THE NEED ARISEN.
QUAD CITIES-1 05000254 010581 AT 9: 10 A.M. WHILE PLACING THE "B" STANDBY GAS TREATMENT SYSTEM IN A NOR REACTOR CONTAINMENT SYSTEMS 81- 0 01/ 0 3 L-0 012081 MAL SHUTDOWN LINE-UP, DISCHARGE VALVE MD-1/2-7507B FAILED TO CLOSE WHEN CIRCUIT CLOSERS / INTERRUPTERS 036130 30-DAY OPERATED FROM THE CONTROL ROOM.
TPE "A" STANDBY GAS TREATMENT SYSTEM WA CONTACTOR COMPONENT FAILURE S DEMONSTRATED OPERABLE IN ACCORDAd'5 WITH TECHNICAL SPECIFICATION 3.7.B
.A.
AND WAS FULLY CAPABLE OF MAINTAfdTNG A NEGATIVE REACTOR BUILDING DIF ELECTRICAL FERENTIAL PRESSURE HAD THE NEED ARISEN.
GENERAL ELECTRIC CO.
UPON INVESTIGATION IT WAS DISCOVERED THAT THE BREAKER AUXILIARY CONTACTS WERE WORN AND STICKING: THUS PREVENTING VALVE MD-1/2-7507B FROM CLOSING
UPON INVESTIGATION IT WAS DISCOVERED THAT THE BREAKER AUXILIARY CONTACTS WERE WORN AND STICKING: THUS PREVENTING VALVE MD-1/2-7507B FROM CLOSING
                                                                  . THE CONTACTS WERE REPLACED WITH CONTACTOR KIT 500E17 AND THE VALVE WA S TESTED SATISFACTORILY. THE "B" STANDBY GAS TREATMENT SYSTEM WAS RETUR QUAD CITIES-1                        05000254                    NED TO SERVICE AT 1:30 P.M. ON JANUARY 5. 1981.
. THE CONTACTS WERE REPLACED WITH CONTACTOR KIT 500E17 AND THE VALVE WA S TESTED SATISFACTORILY. THE "B" STANDBY GAS TREATMENT SYSTEM WAS RETUR NED TO SERVICE AT 1:30 P.M. ON JANUARY 5.
010781 EMERG GENERATOR SYS + CONTROLS     81-002/03L-0       012081   WHILE DEMOHCTRATING UNIT 1 EMERGENCY DIESEL GENERATOR OPERABILITY AFTER ENGINES. INTERNAL COMBUSTION                                    MONTHLY PREVENTATIVE MAINTENANCE INSPECTION, THE DIESEL C-ENERATOR TRIPPE 036131         30-DAY   D.
1981.
SUBCOMPONENT NOT APPLICABLE                                            ATTEMPTS TO RESTART THE DIESEL GENERATOR FAILED WHEN PROPER SPEED CD COMPONENT FAILURE                                                NTROL COULD NOT DE ACHIEVED. THE DIESEL GENERATOR WAS DECLARED INOPERAT ELECTRICAL IVE AT 0930. ALL REDUNDANT SYSTEMS WERE IMMEDIATELY DEMONSTRATED UPERAB WESTERN ENGINE CO.                                               LE IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.9.E.1 INVESTIGATION SHOWED A LOOSE FUSE IN THE 125 VDC ENGINE STARTING AND FUE L CONTROL CIRCUIT. A SLIGHT MISALIGNMENT OF THE DIESEL GENERATOR'S OUTP UT BREAKER AUXILIARY CONTACTS WAS ALSO FOUND. THE FUSE HOLDER WAS TIGHT ENED AND THE BREAKER AUXILIARY CONTACTS ADJUSTED. THE DIESEL GENERATOR         ,
QUAD CITIES-1 05000254 010781 WHILE DEMOHCTRATING UNIT 1 EMERGENCY DIESEL GENERATOR OPERABILITY AFTER EMERG GENERATOR SYS + CONTROLS 81-002/03L-0 012081 MONTHLY PREVENTATIVE MAINTENANCE INSPECTION, THE DIESEL C-ENERATOR TRIPPE ENGINES. INTERNAL COMBUSTION 036131 30-DAY D.
OUAD CITIES-1                        05000254        011481    WAS DEMONSTRATED UPERABLE AND RETURNED TO SERVICE AT 1705 OH 1/7/81.           -
ATTEMPTS TO RESTART THE DIESEL GENERATOR FAILED WHEN PROPER SPEED CD SUBCOMPONENT NOT APPLICABLE NTROL COULD NOT DE ACHIEVED. THE DIESEL GENERATOR WAS DECLARED INOPERAT COMPONENT FAILURE IVE AT 0930.
ENGNRD SAFETY FEATR INSTR SYS     81-003/03L-0       012181     WHILE PERFORMING THE HIGH DRYWELL PRESSURE ECCS INITIATION CALIBRATION A INSTRUMENTATION + CONTROLS            036132        30-DAY    ND FUNCTIONAL TES
ALL REDUNDANT SYSTEMS WERE IMMEDIATELY DEMONSTRATED UPERAB ELECTRICAL WESTERN ENGINE CO.
LE IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.9.E.1 INVESTIGATION SHOWED A LOOSE FUSE IN THE 125 VDC ENGINE STARTING AND FUE L CONTROL CIRCUIT. A SLIGHT MISALIGNMENT OF THE DIESEL GENERATOR'S OUTP UT BREAKER AUXILIARY CONTACTS WAS ALSO FOUND.
THE FUSE HOLDER WAS TIGHT ENED AND THE BREAKER AUXILIARY CONTACTS ADJUSTED. THE DIESEL GENERATOR WAS DEMONSTRATED UPERABLE AND RETURNED TO SERVICE AT 1705 OH 1/7/81.
OUAD CITIES-1 05000254 011481 WHILE PERFORMING THE HIGH DRYWELL PRESSURE ECCS INITIATION CALIBRATION A ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 012181 ND FUNCTIONAL TES


==T. PROCEDURE==
==T. PROCEDURE==
QIS-7. PRESSURE SWITCH PS-1-1001-90D WAS F SWITCH                                                        OUND TO TRIP AT 2.03 PSIC. THIS WAS HIGHER THAN THE 2.0 PSIG LCO SETPOI-COMPONENT FAILURE                                                HT DEFINED IN TECHNICAL SPECIFICATION TABLE 3.2-2. THE REhAINING PRESSU INSTRUMENT                                                    RE SWITCHES IN THE ONE-0UT-OF-TWO-TWICE LOGIC SCHEME WERE WITHIH THEIR R STATIC-0-RING                                                    EQUIRED D  ARISEN.SETPOINTS AND WOULD HAVE PROVIDED AN ECCS INITIATION HAD THE NEE THE CAUSE OF THIS OCCURRENCE WAS INSTRUMENT SETPOINT DRIFT. PRESSURE SW ITCH PS-1-1001-90D WAS IMMEDI*TELY RECALIBRATED AND FUNCTIONALLY TESTED SATISFACTORILY.
QIS-7. PRESSURE SWITCH PS-1-1001-90D WAS F INSTRUMENTATION + CONTROLS 036132 30-DAY OUND TO TRIP AT 2.03 PSIC.
THIS WAS HIGHER THAN THE 2.0 PSIG LCO SETPOI-SWITCH HT DEFINED IN TECHNICAL SPECIFICATION TABLE 3.2-2.
THE REhAINING PRESSU COMPONENT FAILURE RE SWITCHES IN THE ONE-0UT-OF-TWO-TWICE LOGIC SCHEME WERE WITHIH THEIR R INSTRUMENT EQUIRED SETPOINTS AND WOULD HAVE PROVIDED AN ECCS INITIATION HAD THE NEE STATIC-0-RING D ARISEN.
THE CAUSE OF THIS OCCURRENCE WAS INSTRUMENT SETPOINT DRIFT. PRESSURE SW ITCH PS-1-1001-90D WAS IMMEDI*TELY RECALIBRATED AND FUNCTIONALLY TESTED SATISFACTORILY.


v i
E v
MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FfCILITY                                                     PAGE 71 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /CDMPONENT/ DOCKET NO./     EVENT DATE/
i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FfCILITY PAGE 71 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /CDMPONENT/
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                                           EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER   CONTROL NO. REPORT TYPE                                             CAUSE DESCRIPTION i'                      OUAD CITIES-2                             05000265     121080           A SERIES OF SIX TRIPS DCCURRED OF THE 2A REACTCR RECIRCULATION PUMP MOTO COOLANT RECIRC SYS + CONTROLS       80-038/03L-0 010781               R GENERATOR SET FIELD BREAKER. ON EACH OCCASICH THE RECIRCULATION PUMP' INSTRUMENTATION + CONTROLS             033684       30-DAY           MOTOR GENERATOR SET WAS RESTARTED WITHOUT DIFFICULTY AND THE REQUIREMENT TRANSMITTER                                                         S OF TECH. SPEC. 3.6.H.3 WERE SATISFIED EACM TIME.
EVENT DATE/
COMPONENT FAILURE i                             ELECTRICAL GENERAL ELECTRIC CO.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
AFTER EXTENSIVE TESTING BY COMMONWEALTH EDISCN COMPANY PERSONNEL AND A MANUFACTURER REPRESENTATIVE, IT WAS DETERTIINED THAT TACHCMETER WHICH CO HTROLS PUMP SPEED WAS DEFECTIVE. TACHOMETER WAS REPLACED CN DECEMBER 31
REPORT DATE/
                                                                                                  ,    1980 AND THE RECIRCULATION PUMP MG SET HAS SHOWN SATISFACTORY PERFORM ANCE SINCE THAT TIME.
EVENT DESCRIPTION /
QUAD CITIES-2                             05000265     122880           AFTER PUMPING THE ERYWELL EQUIPMENT DRAIN SUMP, CUTBOARD ISOLATION VALVE CNTHMNT ISOLATI0H SYS + CONT       80-035/03L-0   011681               A0-2-2001-16 REQUIRED APPROXIMATELY 15 MINUTES TO GIVE CLOSED INDICATI0 VALVE OPERATORS                       033725       30-DAY           N.     TECHNICAL SPECIFICATIONS REQUIRE A CLOSURE TIME OF LESS THAN OR EQUA PHEUMATIC/ DIAPHRAGM / CYLINDER                                     L TO 20 SCCONDS. 'THE REDUNDANT ISCLATION VALVE AD-2-2001-15 WAS PLACED COMPONENT FAILURE                                                     IN THE CLOSED POSITION. I5OLATION CAPABILITY OF THE EQUIPMENT DRAIN SUM MECHANICA(                                                         P WAS ALWAYS INTACT.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
CRAME COMPANY THE POSITION INDICATION LIMIT SWITCH AND THE LENGTH OF VALVE STEM TRAVEL 1                                                                                                   WERE OUT OF ADJUSTMENT. THE STROKE OF THE VALVE STEM WAS LENGTHENED, T HE PACKING WAS ADJUSTED, AND THE LIMIT SWITCHES WERE ADJUSTED. THE A0-2
REPORT TYPE CAUSE DESCRIPTION i
                                                                                                  -2001-16 VALVE WAS CYCLED THREE TIMES SATISFACTORILY WITH A CLOSURE TIME OF 4.2 SECONDS.
OUAD CITIES-2 05000265 121080 A SERIES OF SIX TRIPS DCCURRED OF THE 2A REACTCR RECIRCULATION PUMP MOTO COOLANT RECIRC SYS + CONTROLS 80-038/03L-0 010781 R GENERATOR SET FIELD BREAKER. ON EACH OCCASICH THE RECIRCULATION PUMP' INSTRUMENTATION + CONTROLS 033684 30-DAY MOTOR GENERATOR SET WAS RESTARTED WITHOUT DIFFICULTY AND THE REQUIREMENT TRANSMITTER S OF TECH. SPEC. 3.6.H.3 WERE SATISFIED EACM TIME.
QUAD CITIES-2                             05000265     123080           AT 0840 WHILE ATTEMPTING TO TRANSFER WATER FROM THE SUPPRESSION CHAMBER RESIDUAL HEAT REMOV SYS + CONT     80-039/03L-0   012281           TO THE MAIN CONDENSER HOTWELL USING THE "A" RHR LOOP. VALVE MO-2-1001-34 CIRCUIT CLOSERS / INTERRUPTERS         033744       30-DAY ' A FAILED TO OPEN FROM THE CONTROL ROOM. THE "B" LCOP OF RHR WAS DEMONST CONTACTOR                                                         RATED OPERABLE AND SURVEILLANCE WAS STARTED TO DEMONSTRATE ADEOUATE CORE COMPONENT FAILURE                                                       COOLING CAPABILITY IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.5.B. T ELECTRICAL                                                         HE "A" LOOP OF RHR CONTAINMENT COOLING WAS OPERABLE AT 1100 DECEMBER 30,'
COMPONENT FAILURE i
GENERAL ELECTRIC CO.                                                     1980.
ELECTRICAL GENERAL ELECTRIC CO.
THE CAUSE OF MO-2-1001-34A NOT CPENING WAS CORRODED ELECTRICAL CONTACTS ON THE AUXILIARY CONTACTOR IN THE VALVE BREAKER.           THE CONTACTS WERE REPL ACED AND MD-2-1001-3( A WAS OPERATED TH2cE TIMES SATISFACTORILY.
AFTER EXTENSIVE TESTING BY COMMONWEALTH EDISCN COMPANY PERSONNEL AND A MANUFACTURER REPRESENTATIVE, IT WAS DETERTIINED THAT TACHCMETER WHICH CO HTROLS PUMP SPEED WAS DEFECTIVE. TACHOMETER WAS REPLACED CN DECEMBER 31 1980 AND THE RECIRCULATION PUMP MG SET HAS SHOWN SATISFACTORY PERFORM ANCE SINCE THAT TIME.
QUAD CITIES-2                             05000265     011681           WHILE PERFORMING THE HIGH DRYWELL PRESSURE CALIBRATION AND FUNCTIONAL TE REACTOR TRIP SYSTEMS               81-001/03L-0   012181           S
QUAD CITIES-2 05000265 122880 AFTER PUMPING THE ERYWELL EQUIPMENT DRAIN SUMP, CUTBOARD ISOLATION VALVE CNTHMNT ISOLATI0H SYS + CONT 80-035/03L-0 011681 A0-2-2001-16 REQUIRED APPROXIMATELY 15 MINUTES TO GIVE CLOSED INDICATI0 VALVE OPERATORS 033725 30-DAY N.
TECHNICAL SPECIFICATIONS REQUIRE A CLOSURE TIME OF LESS THAN OR EQUA PHEUMATIC/ DIAPHRAGM / CYLINDER L TO 20 SCCONDS. 'THE REDUNDANT ISCLATION VALVE AD-2-2001-15 WAS PLACED COMPONENT FAILURE IN THE CLOSED POSITION. I5OLATION CAPABILITY OF THE EQUIPMENT DRAIN SUM MECHANICA(
P WAS ALWAYS INTACT.
CRAME COMPANY THE POSITION INDICATION LIMIT SWITCH AND THE LENGTH OF VALVE STEM TRAVEL 1
WERE OUT OF ADJUSTMENT. THE STROKE OF THE VALVE STEM WAS LENGTHENED, T HE PACKING WAS ADJUSTED, AND THE LIMIT SWITCHES WERE ADJUSTED. THE A0-2
-2001-16 VALVE WAS CYCLED THREE TIMES SATISFACTORILY WITH A CLOSURE TIME OF 4.2 SECONDS.
QUAD CITIES-2 05000265 123080 AT 0840 WHILE ATTEMPTING TO TRANSFER WATER FROM THE SUPPRESSION CHAMBER RESIDUAL HEAT REMOV SYS + CONT 80-039/03L-0 012281 TO THE MAIN CONDENSER HOTWELL USING THE "A" RHR LOOP. VALVE MO-2-1001-34 CIRCUIT CLOSERS / INTERRUPTERS 033744 30-DAY ' A FAILED TO OPEN FROM THE CONTROL ROOM.
THE "B" LCOP OF RHR WAS DEMONST CONTACTOR RATED OPERABLE AND SURVEILLANCE WAS STARTED TO DEMONSTRATE ADEOUATE CORE COMPONENT FAILURE COOLING CAPABILITY IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.5.B.
T ELECTRICAL HE "A" LOOP OF RHR CONTAINMENT COOLING WAS OPERABLE AT 1100 DECEMBER 30,'
GENERAL ELECTRIC CO.
1980.
THE CAUSE OF MO-2-1001-34A NOT CPENING WAS CORRODED ELECTRICAL CONTACTS ON THE AUXILIARY CONTACTOR IN THE VALVE BREAKER.
THE CONTACTS WERE REPL ACED AND MD-2-1001-3( A WAS OPERATED TH2cE TIMES SATISFACTORILY.
QUAD CITIES-2 05000265 011681 WHILE PERFORMING THE HIGH DRYWELL PRESSURE CALIBRATION AND FUNCTIONAL TE REACTOR TRIP SYSTEMS 81-001/03L-0 012181 S


==T. PROCEDURE==
==T. PROCEDURE==
QIS-6, PRESSURE SWITCH PS-1-1001-88D WAS FOUND TO TRIP AT INSTRUMENTATION + CONTROLS             036133       30-DAY           2.13 PSIG.     THIS WLS HIGHER THAN THE 2.0 PSIG LCD SETPOINT DEFINED IN TE SWITCH                                                             CHNICAL SPECIFICATION TABLE 3.1-1           THE REMAINING THREE PRESSURE SWITCHE COMPONENT FAILURE                                                   S IN THE ONE-0UT-OF-TWD-TWICE LOGIC SCHEME WERE WITHIN THEIR REQUIRED SE INSTRUMENT                                                         TP0INTS AND WOULD HAVE PROVIDED A REACTOR SCRAM IF HIGH DRYWELL PRES 5URE
QIS-6, PRESSURE SWITCH PS-1-1001-88D WAS FOUND TO TRIP AT INSTRUMENTATION + CONTROLS 036133 30-DAY 2.13 PSIG.
                          . STATIC-0-RING                                                           HAD OCCURRED.
THIS WLS HIGHER THAN THE 2.0 PSIG LCD SETPOINT DEFINED IN TE SWITCH CHNICAL SPECIFICATION TABLE 3.1-1 THE REMAINING THREE PRESSURE SWITCHE COMPONENT FAILURE S IN THE ONE-0UT-OF-TWD-TWICE LOGIC SCHEME WERE WITHIN THEIR REQUIRED SE INSTRUMENT TP0INTS AND WOULD HAVE PROVIDED A REACTOR SCRAM IF HIGH DRYWELL PRES 5URE
THE CAUSE OF THIS OCCURRENCE WAS INSTRUMENT SETPOINT DRIFT. PRESSURE SW ITCH PS-1-1001-88D WAS IMMEDIATELY RECALIBRATED AND FUNCTIONALLY TESTED SATISFACTORILY.
. STATIC-0-RING HAD OCCURRED.
THE CAUSE OF THIS OCCURRENCE WAS INSTRUMENT SETPOINT DRIFT.
PRESSURE SW ITCH PS-1-1001-88D WAS IMMEDIATELY RECALIBRATED AND FUNCTIONALLY TESTED SATISFACTORILY.


l MAR 26, 1981                                                 LER MONTHLY REPORT SDRTED BY FACILITY                                                           PAGE 72 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS                                                                     '
l MAR 26, 1981 LER MONTHLY REPORT SDRTED BY FACILITY PAGE 72 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
FACILITY / SYSTEM / COMPONENT /   DOCKET NO./         EVENT DATE/                                                                                                     .
DOCKET NO./
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 REPORT DATE/                                           EVENT DESCRIPTION /                                     {
EVENT DATE/
CAUSE SUBCODE/ MANUFACTURER         CONTROL NO.         REPORT TYPE CAUSE DESCRIPTION 1
COMPONENT SUBCODE/CAUSE CODE / LER NO./
QUAD CITIES-2                                 05000265         011681     WHILE PERFORMING ROUTINE SURVEILLANCE TEST QIS 40-1,-THE PRESSURE CONTRO MAIN STEAM SYSTEMS + CONTROLS           81-002/03L-0           020381     LLER FOR ELECTROMATIC RELIEF VALVE 2-203-3B WAS FOUND TO TRIP AT 1181 PS INSTRUMENTATION + CONTROLS                     036134         30-DAY     I. THIS IS IN EXCESS OF THE 1130 PSI LIMIT SET'BY TECHNICAL SPECIFICATI                         t 7-             SWITCH                                                                   ON 4.6.E. ALL OTHER ELECTROMATIC RELIEF VALVES WOULD HAVE OPENED AT THE                           t COMPONENT FAILURE                                                           REQUIRED PRESSURE HAD THE NEED ARISEN AND ELECTROMATIC RELIEF VALVE 2-2                       l INSTRUMENT                                                             03-3B COULD HAVE BEEN OPENED REMOTELY FROM THE CONTROL RCOM.
REPORT DATE/
DRESSER INDUST. VALVE A INST D                                                                                                                                             I THE CAUSE OF THIS DCCURRENCE IS INSTRUMENT DRIFT.                     THE PRESSURE CONTROLL ER WAS IMMEDIATELY RECALIBRATED AND TESTED SATISFACTORILY. A FAULTY MIC ROSWITCH WITHIN THE CONTROLLER WAS SUSPECTED TO CONTRIBUTE TO THE INSTRU                         .
EVENT DESCRIPTION /
MENT DRIFT. THE MICROSWITCH WAS REPLACED OH 1-31-81 AND THE INSTRUMENT                           !
{
                                                                                      .WAS TESTED SATISFACTORILY. THE PRESSURE CONTROLLER IS MODEL 1539VX.                               '
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
RANCHO SECO-1                                 05000312         010881     TO PROVIDE ADDITIONAL INFORMATION REGARDING ADEQUACY OF STATION ELECTRIC CONT ROOM HABITBLTY SYS + CONT         81-001/02T-0           012081     AL DISTRIBUTION SYSTEM VOLTAGE, DISTRICT CONTRACTED A/E TO PERFORM FIELD-CIRCUIT CLOSERS / INTERRUPTERS                 036016         2-WEEK       TESTS OH VARIOUS 820V AC CONTROL DEVICES. ~ON 1/8/81 A/E NOTIFIED DISTR i             STARTER                                                                 ICT THAT ONE TYPE OF CONTROL DEVICE, SIZE 3 (NEMA) STARTER COILS WOULD N OTHER                                                                     OT OPERATE AT A DEGRADED VOLTAGE OF 214KV IN SWITCHYARD. SAFETY RELATED NOT APPLICABLE                                                             EQUIPMENT AFFECTED IS EMERGENCY CONTROL ROOM AIR CONDITIDHER, U-545.
REPORT TYPE CAUSE DESCRIPTION 1
QUAD CITIES-2 05000265 011681 WHILE PERFORMING ROUTINE SURVEILLANCE TEST QIS 40-1,-THE PRESSURE CONTRO MAIN STEAM SYSTEMS + CONTROLS 81-002/03L-0 020381 LLER FOR ELECTROMATIC RELIEF VALVE 2-203-3B WAS FOUND TO TRIP AT 1181 PS INSTRUMENTATION + CONTROLS 036134 30-DAY I.
THIS IS IN EXCESS OF THE 1130 PSI LIMIT SET'BY TECHNICAL SPECIFICATI t
7-SWITCH ON 4.6.E.
ALL OTHER ELECTROMATIC RELIEF VALVES WOULD HAVE OPENED AT THE t
COMPONENT FAILURE REQUIRED PRESSURE HAD THE NEED ARISEN AND ELECTROMATIC RELIEF VALVE 2-2 l
INSTRUMENT 03-3B COULD HAVE BEEN OPENED REMOTELY FROM THE CONTROL RCOM.
DRESSER INDUST. VALVE A INST D I
THE CAUSE OF THIS DCCURRENCE IS INSTRUMENT DRIFT.
THE PRESSURE CONTROLL ER WAS IMMEDIATELY RECALIBRATED AND TESTED SATISFACTORILY. A FAULTY MIC
{
ROSWITCH WITHIN THE CONTROLLER WAS SUSPECTED TO CONTRIBUTE TO THE INSTRU MENT DRIFT.
THE MICROSWITCH WAS REPLACED OH 1-31-81 AND THE INSTRUMENT
.WAS TESTED SATISFACTORILY. THE PRESSURE CONTROLLER IS MODEL 1539VX.
RANCHO SECO-1 05000312 010881 TO PROVIDE ADDITIONAL INFORMATION REGARDING ADEQUACY OF STATION ELECTRIC CONT ROOM HABITBLTY SYS + CONT 81-001/02T-0 012081 AL DISTRIBUTION SYSTEM VOLTAGE, DISTRICT CONTRACTED A/E TO PERFORM FIELD-CIRCUIT CLOSERS / INTERRUPTERS 036016 2-WEEK TESTS OH VARIOUS 820V AC CONTROL DEVICES. ~ON 1/8/81 A/E NOTIFIED DISTR i
STARTER ICT THAT ONE TYPE OF CONTROL DEVICE, SIZE 3 (NEMA) STARTER COILS WOULD N OTHER OT OPERATE AT A DEGRADED VOLTAGE OF 214KV IN SWITCHYARD. SAFETY RELATED NOT APPLICABLE EQUIPMENT AFFECTED IS EMERGENCY CONTROL ROOM AIR CONDITIDHER, U-545.
GENERAL ELECTRIC CD.
GENERAL ELECTRIC CD.
ACTUAL RECORDED DEGRADED VOLTAGE CONDITION ON GRID IS LOWER THAN ORIGINA LLY ANTICIPATED. DESIGN MODIFICATION WILL BE PERFORMED DURING 2/1/81 RE                           l FUELING DUTAGE. ADMINISTRATIVE CONTROLS IN EFFECT PRECLUDE SAFETY RELAT                           .
ACTUAL RECORDED DEGRADED VOLTAGE CONDITION ON GRID IS LOWER THAN ORIGINA LLY ANTICIPATED. DESIGN MODIFICATION WILL BE PERFORMED DURING 2/1/81 RE l
ED BUSES BEING SUBJECTED TO DEGRADED VOLTAGE CONDITIONS ASSOCIATED WITH                         .;
FUELING DUTAGE. ADMINISTRATIVE CONTROLS IN EFFECT PRECLUDE SAFETY RELAT ED BUSES BEING SUBJECTED TO DEGRADED VOLTAGE CONDITIONS ASSOCIATED WITH 214KV IN SWITCHYARD.
214KV IN SWITCHYARD.                                                                             L RANCHO SECD-1                                 05000312         011281     DN 1-12-81, A CCW SYSTEM SAMPLE SHOWED A TRITIUM LEVEL GREATER THAN MDA.                       .l COOL SYS FOR REAC AUX + CONT           81-002/03L-0 020581                 A BACKUP SAMPLE VERIFIED THAT SOME LOW-LEVEL ACTIVITY WAS. IN FACT, PRE-                       ;
L RANCHO SECD-1 05000312 011281 DN 1-12-81, A CCW SYSTEM SAMPLE SHOWED A TRITIUM LEVEL GREATER THAN MDA.
HEAT EXCHANGERS                                 036135         30-DAY     SENT IN'THE CCW SYSTEM. PER IE BULLETIN 80-10. A SAFETY EVALUATION WAS P                       .!
.l COOL SYS FOR REAC AUX + CONT 81-002/03L-0 020581 A BACKUP SAMPLE VERIFIED THAT SOME LOW-LEVEL ACTIVITY WAS. IN FACT, PRE-HEAT EXCHANGERS 036135 30-DAY SENT IN'THE CCW SYSTEM. PER IE BULLETIN 80-10. A SAFETY EVALUATION WAS P COOLER ERFORMED. SAFETY EVALUATION DETERMINED THAT OPERATION OF SYSTEM DID NOT l
COOLER           .
COMPONENT FAILURE CONSTITUTE AN UNREVIEWED SAFETY QUESTION HOR RERUIRE A TECH. SPEC.-CHANG 1
ERFORMED. SAFETY EVALUATION DETERMINED THAT OPERATION OF SYSTEM DID NOT                           l COMPONENT FAILURE                                                         CONSTITUTE AN UNREVIEWED SAFETY QUESTION HOR RERUIRE A TECH. SPEC.-CHANG                         '
MECHANICAL E. CONTINUED OPERATION WAS IN COMPLIANCE WITH'ALL APPLICABLE REGULATIONS GRAHAM MANUFACTURING COMMITMENTS AND THE TECHNICAL SPECIFICATICNS.
1              MECHANICAL                                                               E. CONTINUED OPERATION WAS IN COMPLIANCE WITH'ALL APPLICABLE REGULATIONS                         ,
A LEAK SEARCH PROGRAM DETERMINED THAT "A" LETDOWN COOLER, E-220A, WAS SO URCE OF CONTAMINATION.
GRAHAM MANUFACTURING                                                     ,  COMMITMENTS AND THE TECHNICAL SPECIFICATICNS.
"A" COOLER WILL BE ISOLATED DURING 7YCLE 5 OPERAT i
A LEAK SEARCH PROGRAM DETERMINED THAT "A" LETDOWN COOLER, E-220A, WAS SO                         '
IONS EXCEPT DURING SPECIFIC PERIODS WHEN INCREASED COOLING CAPACITY IS'R EQUIRED.' OPERATION WILL BE IN COMPLIANCE WITH ALL APPLICABLE REGULATIONS f
URCE OF CONTAMINATION. "A" COOLER WILL BE ISOLATED DURING 7YCLE 5 OPERAT                         i IONS EXCEPT DURING SPECIFIC PERIODS WHEN INCREASED COOLING CAPACITY IS'R                         !
COMMITMENTS AND THE TECHNICAL SPECIFICATIONS.
EQUIRED.' OPERATION WILL BE IN COMPLIANCE WITH ALL APPLICABLE REGULATIONS                         f
RANCHO SECD-1 05000312 012581 A REVIEW OF THE JANUARY 1981 EFFLUENT MONITORING CHARTS INDICATED THAT-r
                                                                                        ,  COMMITMENTS AND THE TECHNICAL SPECIFICATIONS.
}
:            RANCHO SECD-1                                 05000312         012581     A REVIEW OF THE JANUARY 1981 EFFLUENT MONITORING CHARTS INDICATED THAT-                           r
COOL SYS FOR REAC AUX + CONT 81-005/04L-0 021881 THE PLANT LIQUID EFFLUENT PH EXCEEDED THE 8.5 LIMIT ESTABLISHED BY TECHN INSTRUMENTATION + CONTROLS 036244 30-DAY ICAL SPECIFICATIONS, APPENDIX B, SECTION 2.4.
}             COOL SYS FOR REAC AUX + CONT           81-005/04L-0           021881     THE PLANT LIQUID EFFLUENT PH EXCEEDED THE 8.5 LIMIT ESTABLISHED BY TECHN                       '!
OM JANUARY 25,.1981, THE OTHER tH MOMENTARILY INCREASED TO 8.6 FOR APPROXIMATELY 10 MINUTES. A SIMILAR COMPONENT FAILURE OCCURRENCE IN THE LATTER PART OF 1980 WAS REPORTED VIA LER 80-36.
INSTRUMENTATION + CONTROLS                     036244         30-DAY     ICAL SPECIFICATIONS, APPENDIX B, SECTION 2.4.               OM JANUARY 25,.1981, THE OTHER                                                                   tH MOMENTARILY INCREASED TO 8.6 FOR APPROXIMATELY 10 MINUTES. A SIMILAR COMPONENT FAILURE                                                           OCCURRENCE IN THE LATTER PART OF 1980 WAS REPORTED VIA LER 80-36.
0THER -
0THER -
OTHER                                                                                                                                                                       i
OTHER i
;                                                                                      SINCE THERE WERE NO INDICATIONS THAT'AN EFFLUENT DIVERSION TO THE RETENT                         !
SINCE THERE WERE NO INDICATIONS THAT'AN EFFLUENT DIVERSION TO THE RETENT ION BASINS HAD OCCURRED, A CHECK OF THE DIVERSICH SYSTEM SETPOINT WAS MA l
ION BASINS HAD OCCURRED, A CHECK OF THE DIVERSICH SYSTEM SETPOINT WAS MA                         l DE. .THE DIVERSION SETPOINT WAS SLIGHTLY OUT-OF-TOLERANCE (ACTUATED AT-8'                        '
DE..THE DIVERSION SETPOINT WAS SLIGHTLY OUT-OF-TOLERANCE (ACTUATED AT-8'
                                                                                        .55).     TO MINIMIZE RECURRENCE. THE DIVERSION SETPOINT WAS RESET TO 8.4 +                     !
.55).
                                                                                        /   .1 AND THE ALARM SETPOINT WILL BE LOWERED TO 8.3 +/- .1                                       I t
TO MINIMIZE RECURRENCE. THE DIVERSION SETPOINT WAS RESET TO 8.4 +
  ' - . , ,      . -      . _        ._ ._- _ - ,  - - - - - - .      -      .--      _ . . -      . , ~ - - . . . , ~ - + ,     ---,n.,      - , - . < , ,    _    . - -  ,,
/
.1 AND THE ALARM SETPOINT WILL BE LOWERED TO 8.3 +/-
.1 I
t
., ~ - -.
.., ~ - +,
---,n.,


l' I
l' I
l l
l l
l l                                                         MAR 26, 1981                                                                         LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 73 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS l                                                                               FACILITY / SYSTEM / COMPONENT /                 DOCKET NO./   EVENT DATE/
l l
!                                                                              COMPONENT SUBCODE/CAUSE CODE / LER NO./                       REPORT DATE/                               EVENT DESCRIPTION /
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 73 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS l
CAUSE SUBCODE/ MANUFACTURER                     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION ROBERT E. GINNA-1                                                       05000244     010581     DURING MONTHLY SURVEILLANCE, OPERATOR NOTED LEAK ON         "B" DIESEL EMERGENCY EMERG GENERATOR SYS + CONTROLS                                 81-001/03L-0   012881     GENERATOR (EG) iACKET COOLING WATER RETURN LINE TO EXPANSION TANK COMIN PIPES FITTINGS                                                     036104     30-DAY     G FROM A BROKEN BUSHING.     (TECHNICAL SPECIFICATION 3.7.1). "A".EG WAS I LESS THAN 4 INCHES                                                               MMEDIATELY PLACED IN SERVICE.
FACILITY / SYSTEM / COMPONENT /
DOCKET NO./
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ROBERT E. GINNA-1 05000244 010581 DURING MONTHLY SURVEILLANCE, OPERATOR NOTED LEAK ON "B" DIESEL EMERGENCY EMERG GENERATOR SYS + CONTROLS 81-001/03L-0 012881 GENERATOR (EG) iACKET COOLING WATER RETURN LINE TO EXPANSION TANK COMIN PIPES FITTINGS 036104 30-DAY G FROM A BROKEN BUSHING.
(TECHNICAL SPECIFICATION 3.7.1).
"A".EG WAS I LESS THAN 4 INCHES MMEDIATELY PLACED IN SERVICE.
PERSONNEL ERROR CONSTRUCTION PERSONNEL BECHTEL CORP.
PERSONNEL ERROR CONSTRUCTION PERSONNEL BECHTEL CORP.
POSSIBLE LACK OF CONNECTION OF SUPPORT DURING ORIGINAL CONNECTION OR PER SONNEL INVOLVED IN MODIFICATION INSTALLATION IN AREA MAY HAVE BUMPED LIN E. BUSHING IS 3/4" PLASTIC FOR ATMOSPHFRIC PRESSURE SERVICE. REPLACED BUSHING, ADDED COUPLING FOR FUTURE NAINTENANCE EASE.
POSSIBLE LACK OF CONNECTION OF SUPPORT DURING ORIGINAL CONNECTION OR PER SONNEL INVOLVED IN MODIFICATION INSTALLATION IN AREA MAY HAVE BUMPED LIN E.
ROBERT E. GINNA-1                                                       05000244     010981     DURING TEST "C" SI PUMP DID NOT START WITH BUS 16 BREAKER.         (TECHNICAL S EMERG CORE COOLING SYS + CONT                                 81-002/03L-0   013081     PECIFICATION 3.3.1.1C). THE "C" PUMP HAD BEEN PROVEN OPERABLE USING EUS CIRCUIT CLOSERS / INTERRUPTERS                                     036105     30-DAY       14 BREAKER DURING THIS TEST AS MELL AS THE OTHER 2 PUMPS. AFTER EXAMIN.
BUSHING IS 3/4" PLASTIC FOR ATMOSPHFRIC PRESSURE SERVICE. REPLACED BUSHING, ADDED COUPLING FOR FUTURE NAINTENANCE EASE.
CIRCUIT BREAKER                                                                   ING BREAKER FOR POSITION, BREAKER WAS FULLY RACKED OUT, THEN FULLY RACKE COMPONENT FAILURE                                                                         D IN, AND OPERATION PROVED SUCCESSFUL.
ROBERT E. GINNA-1 05000244 010981 DURING TEST "C" SI PUMP DID NOT START WITH BUS 16 BREAKER.
(TECHNICAL S EMERG CORE COOLING SYS + CONT 81-002/03L-0 013081 PECIFICATION 3.3.1.1C).
THE "C" PUMP HAD BEEN PROVEN OPERABLE USING EUS CIRCUIT CLOSERS / INTERRUPTERS 036105 30-DAY 14 BREAKER DURING THIS TEST AS MELL AS THE OTHER 2 PUMPS.
AFTER EXAMIN.
CIRCUIT BREAKER ING BREAKER FOR POSITION, BREAKER WAS FULLY RACKED OUT, THEN FULLY RACKE COMPONENT FAILURE D IN, AND OPERATION PROVED SUCCESSFUL.
ELECTRICAL WESTINGHOUSE ELECTRIC CORP.
ELECTRICAL WESTINGHOUSE ELECTRIC CORP.
BREAKER POSSIBLY IN "0FF-SET" POSITION INDICATED BY POSITIONING DEVICE P IN NOT MOVING FREELY IN POSITIONING STOP BRACKET FULLY-RACKED-IN SLOT.
BREAKER POSSIBLY IN "0FF-SET" POSITION INDICATED BY POSITIONING DEVICE P IN NOT MOVING FREELY IN POSITIONING STOP BRACKET FULLY-RACKED-IN SLOT.
AT NEXT TEST, ELECTRICIANS TO EXAMINE BREAKER BEFORE CLOSING 8 AFTER OPE HING. TRAINING IN PROPER BREAKER ALIGNMENT 8 REPORTING RACK-IN PROBLEMS HILL BE EMPHASIZED. BREAKER IS WESTING 9 DB-50 AIR CIRCUIT BRK. 500-AMP ROBERT E. GINNA-1                                                       05000244     011581     DURING NORMAL REACTOR COOLANT BORATION, OPERATOR OBSERVED ABSENCE OF BOR CHEM, VOL CONT + LIQ POISH SYS                                 81-003/03L-0   021381     IC ACID FLOW FROM "A" BORIC ACID PUMP. HE PUT "B" BORIC ACID PUMP IN 8 D VALVES                                                             036106     30-DAY     ECLARED "A" PUMP INOP. (TECH. SPEC. 3.2.3B). INVESTIGATION SHOMED SUCTIO DIAPHRAGM                                                                         N VALVE PARTLY CLOSED. VALVE WAS IMMEDIATELY REOPENED. IT WAS FOUND THAT PERSONNEL ERROR                                                                           DURING HORMAL SAMPLING. A H.P. TECHNICIAN HAD THROTTLED THE VALVE 8 APP CONTRACT. & CONSULT. PERSONNEL                                                     ARENTLY REOPENED IT. HE NOTED DIAPHRAGM VALVE STEM INDICATION RISER WAS GRINNELL CORP.                                                                           LOOSE, 8 REPORTED THIS.
AT NEXT TEST, ELECTRICIANS TO EXAMINE BREAKER BEFORE CLOSING 8 AFTER OPE HING.
TRAINING IN PROPER BREAKER ALIGNMENT 8 REPORTING RACK-IN PROBLEMS HILL BE EMPHASIZED. BREAKER IS WESTING 9 DB-50 AIR CIRCUIT BRK. 500-AMP ROBERT E. GINNA-1 05000244 011581 DURING NORMAL REACTOR COOLANT BORATION, OPERATOR OBSERVED ABSENCE OF BOR CHEM, VOL CONT + LIQ POISH SYS 81-003/03L-0 021381 IC ACID FLOW FROM "A" BORIC ACID PUMP. HE PUT "B" BORIC ACID PUMP IN 8 D VALVES 036106 30-DAY ECLARED "A" PUMP INOP. (TECH. SPEC. 3.2.3B). INVESTIGATION SHOMED SUCTIO DIAPHRAGM N VALVE PARTLY CLOSED. VALVE WAS IMMEDIATELY REOPENED. IT WAS FOUND THAT PERSONNEL ERROR DURING HORMAL SAMPLING. A H.P.
TECHNICIAN HAD THROTTLED THE VALVE 8 APP CONTRACT. & CONSULT. PERSONNEL ARENTLY REOPENED IT. HE NOTED DIAPHRAGM VALVE STEM INDICATION RISER WAS GRINNELL CORP.
LOOSE, 8 REPORTED THIS.
VALVE APPARENTLY WAS NOT FULL OPEN AFTER SAMPLING, 8 PIPEFITTER SCREWING IN STEM INDICATION RISER CAUSED VALVE TO FURTHER CLOSE. BORIC ACID SYST EM ALIGNMENT 4 TESTING OF "A" PUMP PERFORMED SATISFACTORILY. SUPT. SHALL ISSUE NOTICE STRESSING APPROVED MAIN
VALVE APPARENTLY WAS NOT FULL OPEN AFTER SAMPLING, 8 PIPEFITTER SCREWING IN STEM INDICATION RISER CAUSED VALVE TO FURTHER CLOSE. BORIC ACID SYST EM ALIGNMENT 4 TESTING OF "A" PUMP PERFORMED SATISFACTORILY. SUPT. SHALL ISSUE NOTICE STRESSING APPROVED MAIN


==T. PROCEDURE==
==T. PROCEDURE==
S FOR SAFETY RELATED SY STEMS. BORIC ACID PUMP SUCTION VALVES WILL BE LOCKED OPEN.
S FOR SAFETY RELATED SY STEMS. BORIC ACID PUMP SUCTION VALVES WILL BE LOCKED OPEN.
SALEM-1                                                                 05000272     060180     DURING ROUTINE SURVEILLANCE TESTING OF THE FIRE DETECTION INSTRUMENTION, FIRE PROTECTION SYS + CONT                                     80-030/03X-1   020481     THE FUSIBLE PLUG FOR THE BATTERY ROOM DETECTORS FOR BOTH UNIT 1 AND UNI INSTRUMENTATION + CONTROLS                                       031460     OTHER     T 2 HAD MELTED DURING THE TESTING, RENDERING THEM INOPERABLE. ACTION ST SENSOR / DETECTOR / ELEMENT                                                       ATEMENT 3.3.3.6 WAS ENTERED AT 0700 HOURS.
SALEM-1 05000272 060180 DURING ROUTINE SURVEILLANCE TESTING OF THE FIRE DETECTION INSTRUMENTION, FIRE PROTECTION SYS + CONT 80-030/03X-1 020481 THE FUSIBLE PLUG FOR THE BATTERY ROOM DETECTORS FOR BOTH UNIT 1 AND UNI INSTRUMENTATION + CONTROLS 031460 OTHER T 2 HAD MELTED DURING THE TESTING, RENDERING THEM INOPERABLE. ACTION ST SENSOR / DETECTOR / ELEMENT ATEMENT 3.3.3.6 WAS ENTERED AT 0700 HOURS.
DEFECTIVE PROCEDURES NOT APPLICABLE OTHER A HOT AIR BLOWER WAS USED TO RAISE TEMPERATURE OF THE DETECTOR TO AN ALA RM CONDITION, BUT WAS NOT REMOVED QUICKLY ENCUGH TO PREVENT DETECTOR DAM AGE. DETECTORS WERE REPLACED 8 TESTED SATISFACTORILY, TERMINATING ACTION STATEMENT AT 2106 HOURS ON 6/3/80. DESIGN CHANGES WERE INITIATED ON 9/
DEFECTIVE PROCEDURES NOT APPLICABLE OTHER A HOT AIR BLOWER WAS USED TO RAISE TEMPERATURE OF THE DETECTOR TO AN ALA RM CONDITION, BUT WAS NOT REMOVED QUICKLY ENCUGH TO PREVENT DETECTOR DAM AGE. DETECTORS WERE REPLACED 8 TESTED SATISFACTORILY, TERMINATING ACTION STATEMENT AT 2106 HOURS ON 6/3/80. DESIGN CHANGES WERE INITIATED ON 9/
15/80, WHICH WILL REPLACE EXISTING DETECTORS WITH A NON-EXPENDADLE TYPE.
15/80, WHICH WILL REPLACE EXISTING DETECTORS WITH A NON-EXPENDADLE TYPE.


MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                                 PAGE 74 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./       EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 74 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./           REPORT DATE/                                         EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.       REPORT TYPE                                           CAUSE DESCRIPTION SALEM-1                                     05000272   072580     AT 0030 HOURS ON JULY 25, 1980, ALL OUTSIDE TELEPHONE COMMUNICATION WAS COMMUNICATION SYSTEMS               80-040/01X-1       020481     LOST INCLUDING THE DIRECT DEDICATED LINE BETWEEN SALEM STATION AND THE N ELECTRICAL CONDUCTORS                       031918     OTHER     RC INCIDENT RESPONSE CENTER IN BETHESDA MARYLAND.           '
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 072580 AT 0030 HOURS ON JULY 25, 1980, ALL OUTSIDE TELEPHONE COMMUNICATION WAS COMMUNICATION SYSTEMS 80-040/01X-1 020481 LOST INCLUDING THE DIRECT DEDICATED LINE BETWEEN SALEM STATION AND THE N ELECTRICAL CONDUCTORS 031918 OTHER RC INCIDENT RESPONSE CENTER IN BETHESDA MARYLAND.
SUBCOMPONENT NOT APPLICABLE OTHER NOT APPLICABLE WESTERN ELECTRIC APPARENTLY. A PERSON OR PERSONS UNKNOWN IN AN ACT OF MALICICUS VANDALISM OR DELIBERATE SABOTAGE CUT ALL THE PHONE LINES LEADING TO THE STATION.
SUBCOMPONENT NOT APPLICABLE OTHER NOT APPLICABLE WESTERN ELECTRIC APPARENTLY. A PERSON OR PERSONS UNKNOWN IN AN ACT OF MALICICUS VANDALISM OR DELIBERATE SABOTAGE CUT ALL THE PHONE LINES LEADING TO THE STATION.
EMERGENCY NEASURES WERE TAKEN TO MAINTAIN LIMITED OUTSIDE COMMUNICATION S UNTIL NORMAL PHONE LINES WERE RE-ESTABLISHED ON JULY 26, 1980. THE NE W JERSEY STATE POLICE IS CONTINUING THEIR INVESTIGATION OF THIS EVENT.
EMERGENCY NEASURES WERE TAKEN TO MAINTAIN LIMITED OUTSIDE COMMUNICATION S UNTIL NORMAL PHONE LINES WERE RE-ESTABLISHED ON JULY 26, 1980.
SALEM-1                                     05000272   010581     DURING HORMAL OPERATIONS WITH THE REACTOR AT 89% OF RATED THERMAL POWER.
THE NE W JERSEY STATE POLICE IS CONTINUING THEIR INVESTIGATION OF THIS EVENT.
REACTOR CORE                       81- 0 01/ 0 3 L- 0 013081     THE INDICATED AXIAL FLUX DIFFERENCE IN TWO CHANNELS DRIFTED OUT OF THE COMPONENT CODE NOT APPLICABLE               036068     30-DAY     RZQUIRED TARGET BAND.             ACTION STATEMENT 3.2.1A.2 WAS ENTERED AT 0200 HOU SUBCOMPONENT NOT APPLICABLE                                     RS ON JANUARY 5. 1981               THIS EVENT CONSTITUTES A REPORTABLE INCIDENT PER PERSONNEL ERROR                                                   TECHNICAL SPECIFICATION 6.9.1.9B.
SALEM-1 05000272 010581 DURING HORMAL OPERATIONS WITH THE REACTOR AT 89% OF RATED THERMAL POWER.
LICENSED & SENIOR OPERATCRS ITEM NOT APPLICABLE ANTICIPATED INCREASE IN AXIAL FLUX DIFFERENCE WHILE INCREASING REACTOR P OMER LEVEL WAS CREATER IN MAGNITUDE THAN THAT EXPECTED BY OPERATING STAF F. REACTOR POWER LEVEL WAS REDUCED TO 87% 1 AXIAL FLUX DIFFERENCES RETU RNED TO VALUES WITHIN REQUIRED TARGET BAND. THIS IS THE FIRST ATTEMPT T 0 BRING THIS NEW CORE TO 100% RATED THERMAL POWER.
REACTOR CORE 81- 0 01/ 0 3 L- 0 013081 THE INDICATED AXIAL FLUX DIFFERENCE IN TWO CHANNELS DRIFTED OUT OF THE COMPONENT CODE NOT APPLICABLE 036068 30-DAY RZQUIRED TARGET BAND.
SALEM-1                                     05000272   010881     DURING NORMAL OPERATIONS AT 0530 HOURS ON JANUARY 8, 1981. INDICATION IN STATION SERV WATER SYS + CONT       81-002/03L-0       020581     THE CONTROL ROOM OF SERVICE WATER FLOW TO THE NO. 14 FAN COIL UNIT WAS HEATERS.ELEClRIC                           036069     30-DAY     LOST. ACTION STATEMENT 3.6.2.3 WAS ENTERED AT THIS TIME. THIS EVENT RE SUBCOMPONENT NOT APPLICABLE                                     SULTED IN OPERATION IN A DEGRADED MODE PER TECHNICAL SPECIFICATION 6.9.1 PERSONNEL ERROR                                                   .9.B.
ACTION STATEMENT 3.2.1A.2 WAS ENTERED AT 0200 HOU SUBCOMPONENT NOT APPLICABLE RS ON JANUARY 5.
LICENSED & SENIOR OPERATORS 2 TEM NOT APPLICABLE PORTABLE PROPANE HEATERS INSTALLED IN NORTH PENETRATION SERVICE WATER CD MPARTMENTS HAD RUN OUT OF FUEL. SERVICE WATER IN INSTRUMENT LINES FROZE RESULTING IN NO INDICATION IN CONTROL ROOM. EMPTY FUEL TANKS WERE REPL ACED WITH FULL TANKS. ACTION STATEMENT WAS TERMINATED AT 16 30 HRS. AS OF 1/20/81 ALL PORTABLE PROPANE HEATERS HAVE BEEN REPLACED W/ ELECTRIC.
1981 THIS EVENT CONSTITUTES A REPORTABLE INCIDENT PER PERSONNEL ERROR TECHNICAL SPECIFICATION 6.9.1.9B.
SALEM-1                                     05000272     010981   DURING NORMAL OPERATION AT 0800 HOURS ON 1/9/81 THE #12 CCWHX WAS REMOV STATION SERV WATER SYS + CONT     81-003/03L-0       020581   ED FROM SERVICE TO REPAIR A LEAKING PIPE NIPPLE WHICH CONNECTS THE SERVI PIPES. FITTINGS                           036070     30-DAY   CE WATER DRAIN VALVE 125W124 WITH THE HEAT EXCHANGER TUBE SHEET. ACTION LESS THAN 4 INCHES                                               STATEMENT 3.7.3.1 WAS ENTERED SINCE TWO OPERABLE CCW LOOPS WERE NOT AVA COMPONENT FAILURE                                               ILABLE FOR PLANT SERVICE PER TECHNICAL SPECIFICATION REQUIREMENTS.
LICENSED & SENIOR OPERATCRS ITEM NOT APPLICABLE ANTICIPATED INCREASE IN AXIAL FLUX DIFFERENCE WHILE INCREASING REACTOR P OMER LEVEL WAS CREATER IN MAGNITUDE THAN THAT EXPECTED BY OPERATING STAF F.
REACTOR POWER LEVEL WAS REDUCED TO 87% 1 AXIAL FLUX DIFFERENCES RETU RNED TO VALUES WITHIN REQUIRED TARGET BAND.
THIS IS THE FIRST ATTEMPT T 0 BRING THIS NEW CORE TO 100% RATED THERMAL POWER.
SALEM-1 05000272 010881 DURING NORMAL OPERATIONS AT 0530 HOURS ON JANUARY 8, 1981. INDICATION IN STATION SERV WATER SYS + CONT 81-002/03L-0 020581 THE CONTROL ROOM OF SERVICE WATER FLOW TO THE NO. 14 FAN COIL UNIT WAS HEATERS.ELEClRIC 036069 30-DAY LOST.
ACTION STATEMENT 3.6.2.3 WAS ENTERED AT THIS TIME.
THIS EVENT RE SUBCOMPONENT NOT APPLICABLE SULTED IN OPERATION IN A DEGRADED MODE PER TECHNICAL SPECIFICATION 6.9.1 PERSONNEL ERROR
.9.B.
LICENSED & SENIOR OPERATORS 2 TEM NOT APPLICABLE PORTABLE PROPANE HEATERS INSTALLED IN NORTH PENETRATION SERVICE WATER CD MPARTMENTS HAD RUN OUT OF FUEL.
SERVICE WATER IN INSTRUMENT LINES FROZE RESULTING IN NO INDICATION IN CONTROL ROOM.
EMPTY FUEL TANKS WERE REPL ACED WITH FULL TANKS.
ACTION STATEMENT WAS TERMINATED AT 16 30 HRS.
AS OF 1/20/81 ALL PORTABLE PROPANE HEATERS HAVE BEEN REPLACED W/ ELECTRIC.
SALEM-1 05000272 010981 DURING NORMAL OPERATION AT 0800 HOURS ON 1/9/81 THE #12 CCWHX WAS REMOV STATION SERV WATER SYS + CONT 81-003/03L-0 020581 ED FROM SERVICE TO REPAIR A LEAKING PIPE NIPPLE WHICH CONNECTS THE SERVI PIPES. FITTINGS 036070 30-DAY CE WATER DRAIN VALVE 125W124 WITH THE HEAT EXCHANGER TUBE SHEET.
ACTION LESS THAN 4 INCHES STATEMENT 3.7.3.1 WAS ENTERED SINCE TWO OPERABLE CCW LOOPS WERE NOT AVA COMPONENT FAILURE ILABLE FOR PLANT SERVICE PER TECHNICAL SPECIFICATION REQUIREMENTS.
METALLURGICAL D0YLE, M. J. CO.
METALLURGICAL D0YLE, M. J. CO.
WELD CONNECTING MONEL METAL TUBE SHEEi t THE CARBON STEEL PIPE NIPPLE WA S LEAKING     NIPPLE WAS REPLACED & THE WitDED CONNECTION COMPLETELY REWOR KED. A DESIGN CHANGE HAS BEEN INITIATED .'HICH WILL REPL ACE THE CARBON S TEEL PIPE NIPPLE W/0NE MADE OF MONEL METAL JHICH WILL-ALLOW A BETTER FUS ION OF WELD. ACTION STATEMENT WAS TERMINATED AT 1400 HRS ON 1/11/31
WELD CONNECTING MONEL METAL TUBE SHEEi t THE CARBON STEEL PIPE NIPPLE WA S LEAKING NIPPLE WAS REPLACED & THE WitDED CONNECTION COMPLETELY REWOR KED.
A DESIGN CHANGE HAS BEEN INITIATED.'HICH WILL REPL ACE THE CARBON S TEEL PIPE NIPPLE W/0NE MADE OF MONEL METAL JHICH WILL-ALLOW A BETTER FUS ION OF WELD.
ACTION STATEMENT WAS TERMINATED AT 1400 HRS ON 1/11/31


MAR 26, 1981                                           LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 75 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 75 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS
  . FACILITY / SYSTEM / COMPONENT / DOCKET NO./     EVENT DATE/
. FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./         REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.     REPORT TYPE                               CAUSE DESCRIPTION SALEM-1                                 05000272       011581     DURING NORMAL OPERATIONS AT 0950 HOURS ON 1/15/81 WHILE PERFORMING TEST FIRE PROTECTION SYS + CONT           81-006/03L-0     020981     5 ON THE FIRE ALARM SYSTEM, IT WAS DISCOVERED THAT NO AUDIBLE FIRE ALARM INSTRUMENTATION + CONTROLS               036137       30-DAY     WOULD SOUND. ACTION STATEMENT 3.3.3.6 WAS INITIATED, AN OPERATOR WAS OTHER                                                           STATIONED AT THE FIRE ALARM PANEL IN THE CONTROL ROOM TO CONTINUALLY MON OTHER                                                             ITOR THE P ANEL FOR VISUAL FIRE ALARM SIGNALS.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 011581 DURING NORMAL OPERATIONS AT 0950 HOURS ON 1/15/81 WHILE PERFORMING TEST FIRE PROTECTION SYS + CONT 81-006/03L-0 020981 5 ON THE FIRE ALARM SYSTEM, IT WAS DISCOVERED THAT NO AUDIBLE FIRE ALARM INSTRUMENTATION + CONTROLS 036137 30-DAY WOULD SOUND.
ACTION STATEMENT 3.3.3.6 WAS INITIATED, AN OPERATOR WAS OTHER STATIONED AT THE FIRE ALARM PANEL IN THE CONTROL ROOM TO CONTINUALLY MON OTHER ITOR THE P ANEL FOR VISUAL FIRE ALARM SIGNALS.
NOT APPLICABLE GAI-TROMICS CORP AN IMPEDANCE MISMATCH WAS CREATED BETWEEN TONE GENERATOR OF FIRE ALARM S YSTEM & REMAINDER OF SYS WHEN ADDITIONAL PAGE EXTENSION PHONES & ROTATIN G FIRE ALARM BEACONS WERE ADDED AS ADDITIONAL LOADS TO TONE GEN. VOX-ANU X AMPLIFIER IN TONE GEN. UNIT WAS ADJUSTED TO OBTAIN CURRENT IMPEDANCE M ATCH. ACTION STATEMENT WAS TERMINATED AT 1225 HOURS ON 1/15/81.
NOT APPLICABLE GAI-TROMICS CORP AN IMPEDANCE MISMATCH WAS CREATED BETWEEN TONE GENERATOR OF FIRE ALARM S YSTEM & REMAINDER OF SYS WHEN ADDITIONAL PAGE EXTENSION PHONES & ROTATIN G FIRE ALARM BEACONS WERE ADDED AS ADDITIONAL LOADS TO TONE GEN. VOX-ANU X AMPLIFIER IN TONE GEN. UNIT WAS ADJUSTED TO OBTAIN CURRENT IMPEDANCE M ATCH. ACTION STATEMENT WAS TERMINATED AT 1225 HOURS ON 1/15/81.
SALEM-1                                 05000272       011981     WHILE IN THE HOT STANDBY CONDITION ON 1/19/81, AT 1500 HOURS. THE NRC RE EMERG CORE COOLING SYS + CONT       81-0 0 7/ 01T-0   013081     SIDENT INSPECTOR REQUESTED THAT THE THROTTLE VALVES WHICH BALANCE FLOW T VALVES                                   036071       2-WEEK     HROUGH THE SAFETY INJECTION LOOPS BE INSPECTED TO VERIFY THAT THEY WERE GLOBE ALL IN THEIR REQ" IRED POSITIONS. VALVES 14SJ16, 11SJ138 12SJ138 AND 13S DEFECTIVE PROCEDURES                                             J138 WERE NOT IN THEIR CORRECT POSITIONS. THE INCORRECTLY POSITIONED VA NOT APPLICABLE                                                 LVES MAY HAVE PREVENTED THE FULFILLMENT OF THE FUNCTIONAL REQUIREMENTS 0 ROCKWELL MANUFACTURING CO.                                       F THE SYSTEM TO COPE WITH ACCIDENTS ANALYZED IN THE SAR.
SALEM-1 05000272 011981 WHILE IN THE HOT STANDBY CONDITION ON 1/19/81, AT 1500 HOURS. THE NRC RE EMERG CORE COOLING SYS + CONT 81-0 0 7/ 01T-0 013081 SIDENT INSPECTOR REQUESTED THAT THE THROTTLE VALVES WHICH BALANCE FLOW T VALVES 036071 2-WEEK HROUGH THE SAFETY INJECTION LOOPS BE INSPECTED TO VERIFY THAT THEY WERE GLOBE ALL IN THEIR REQ" IRED POSITIONS. VALVES 14SJ16, 11SJ138 12SJ138 AND 13S DEFECTIVE PROCEDURES J138 WERE NOT IN THEIR CORRECT POSITIONS. THE INCORRECTLY POSITIONED VA NOT APPLICABLE LVES MAY HAVE PREVENTED THE FULFILLMENT OF THE FUNCTIONAL REQUIREMENTS 0 ROCKWELL MANUFACTURING CO.
F THE SYSTEM TO COPE WITH ACCIDENTS ANALYZED IN THE SAR.
EVENT WAS THE RESULT OF PROCEDURE INADEQUACY. TO INSURE THAT ALL THROTT LING VALVES IN THIS SYSTEM ARE RETURNED TO THEIR EXACT REQUIRED POSITION S FOLLOWING ANY EVOLUTION RECUIRING A VALVE LINE-UP,-ON-THE-SPOT CHANGES HAVE BEEN MADE TO APPROPRIAIE PROCEDURES. AN ENGINEERING REVIEW OF EVE NT WILL BE MADE 8 RESULTS WILL BE REPORTED IN A SUPPLEMENTARY REPORT.
EVENT WAS THE RESULT OF PROCEDURE INADEQUACY. TO INSURE THAT ALL THROTT LING VALVES IN THIS SYSTEM ARE RETURNED TO THEIR EXACT REQUIRED POSITION S FOLLOWING ANY EVOLUTION RECUIRING A VALVE LINE-UP,-ON-THE-SPOT CHANGES HAVE BEEN MADE TO APPROPRIAIE PROCEDURES. AN ENGINEERING REVIEW OF EVE NT WILL BE MADE 8 RESULTS WILL BE REPORTED IN A SUPPLEMENTARY REPORT.
SALEM-1                                 05000272       011981     DURING NORMAL OPERATION ON JANUARY 19, 1981. WHILE PERFORMING A DAILY SU CONT ROOM HABITBLTY SYS + CONT     81-004/03L-0     021281     RVEILLANCE TEST ON THE CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM IS OTHER COMPONENTS                       036245       30-DAY     OLATION DAMPERS, DAMPER 1CAA3 FAILED TO CLOSE DURING THE TEST AND WAS DE SUBCOMPONENT NOT APPLICABLE                                     CLARED INOPERABLE, PER TECHNICAL SPECIFICATION REQUIREMENTS, ACTIUN STA EXTERNAL CAUSE                                                   TEMENT 3.7.6.1.D WAS ENTERED AT 0810 HOURS.
SALEM-1 05000272 011981 DURING NORMAL OPERATION ON JANUARY 19, 1981. WHILE PERFORMING A DAILY SU CONT ROOM HABITBLTY SYS + CONT 81-004/03L-0 021281 RVEILLANCE TEST ON THE CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM IS OTHER COMPONENTS 036245 30-DAY OLATION DAMPERS, DAMPER 1CAA3 FAILED TO CLOSE DURING THE TEST AND WAS DE SUBCOMPONENT NOT APPLICABLE CLARED INOPERABLE, PER TECHNICAL SPECIFICATION REQUIREMENTS, ACTIUN STA EXTERNAL CAUSE TEMENT 3.7.6.1.D WAS ENTERED AT 0810 HOURS.
NOT APPLICABLE AEROFIN CORP.
NOT APPLICABLE AEROFIN CORP.
ICE HAD FORMED ON THE LOUVERS OF THE DAMPERS PREVENTING THEIR CLOSING.
ICE HAD FORMED ON THE LOUVERS OF THE DAMPERS PREVENTING THEIR CLOSING.
THE ICE WAS THE RESULT OF UNUSUALLY COLD AMBIENT TEMPERATURES. WHEN MAI HTENANCE PERSONNEL ARRIVED AT THE DAMPER LOCATION, MOST OF THE ICE HAD M ELTED. THE DAMPER WAS TESTED SATISFACTORILY AND DECLARED OPERABLE. THE ACTION STATEMENT WAS TERMINATED AT 1040 HOURS ON JANUARY 19, 1981.
THE ICE WAS THE RESULT OF UNUSUALLY COLD AMBIENT TEMPERATURES. WHEN MAI HTENANCE PERSONNEL ARRIVED AT THE DAMPER LOCATION, MOST OF THE ICE HAD M ELTED.
SALEM-f                                 05000272       012481     DURING NORMAL OPERATION AT 0550 HOURS ON 1/24/81, THE CARRIAGE GUIDE WIR OTHER COOLANT SUBSYS + CONTROL     81-003/03L-0     021281     E OF THE AUXILIARY ANNUNCIATOR TYPEURITER BROKE. THIS RESULTED IN THE L INSTRUMENTATION + CONTROLS             036246       30-DAY     OSS OF THE CONTAINMENT SUMP LEVEL MONITORING SYSTEM. ACTION STATEMENT 3 RECORDER                                                         4.6.1.B WAS ENTERED. A LAMP WAS CONNECTED ACROSS THE CONTAINMENT SUMP COMPONENT FAILURE                                               PUMP BREAKER AND AN OPERATOR WAS STATIONED AT THE BREAKER TO RECORD THE MECHANICAL                                                     OPERATING TIME OF THE PUMP UNTIL REPAIRS TO THE TYPEWRITER WERE COMPLETE IBM CORP                                                         D.
THE DAMPER WAS TESTED SATISFACTORILY AND DECLARED OPERABLE. THE ACTION STATEMENT WAS TERMINATED AT 1040 HOURS ON JANUARY 19, 1981.
THE BROKEN CARRIAGE GUIDE WIRE WAS REPLACED BY AN IBM MAINTENANCE TECHNI CIAN. THE ACTION STATEMENT WAS TERMINATED AT 2106 HOURS ON 1/24/81.
SALEM-f 05000272 012481 DURING NORMAL OPERATION AT 0550 HOURS ON 1/24/81, THE CARRIAGE GUIDE WIR OTHER COOLANT SUBSYS + CONTROL 81-003/03L-0 021281 E OF THE AUXILIARY ANNUNCIATOR TYPEURITER BROKE.
THIS RESULTED IN THE L INSTRUMENTATION + CONTROLS 036246 30-DAY OSS OF THE CONTAINMENT SUMP LEVEL MONITORING SYSTEM.
ACTION STATEMENT 3 RECORDER 4.6.1.B WAS ENTERED.
A LAMP WAS CONNECTED ACROSS THE CONTAINMENT SUMP COMPONENT FAILURE PUMP BREAKER AND AN OPERATOR WAS STATIONED AT THE BREAKER TO RECORD THE MECHANICAL OPERATING TIME OF THE PUMP UNTIL REPAIRS TO THE TYPEWRITER WERE COMPLETE IBM CORP D.
THE BROKEN CARRIAGE GUIDE WIRE WAS REPLACED BY AN IBM MAINTENANCE TECHNI CIAN.
THE ACTION STATEMENT WAS TERMINATED AT 2106 HOURS ON 1/24/81.


MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY                                                                   PAGE 76 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 76 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION SALEM-1                                 05000272     012681 STATION SERV WATER SYS + CONT                                  DURING NORMAL OPERATION ON 1/26/81, #11 CONTAINMENT FAN COIL UNIT WAS DE 81-010/03L-0   021981     CLARED INOPERABLE IN ORDER TO REPLACE A LEAKING SPOOL PIECE IN THE SERVI PIPES. FITTINGS                         036248     30-DAY     CE WATER LINE TO UNIT. ACTION STATEMENT 3.6.2.3 WAS ENTERED AT 1730 HOU to TO 16 INCHES                                             RS. AT 1907 HOURS, REACTOR TRIPPED.
EVENT DATE/
COMPONENT FAILURE                                              E,                                        IN ORDER TO CHANGE OPERATIONAL MOD METALLURGICAL                                                    FAN COIL UNIT HAD TO BE DECLARED OPERATIONAL. SURVEILLANCE TEST SP(0 D0YLE, M. J. CO.                                              ) 4.6.3.2(A) MAS PERFORMED WITH SATISFAC10RY RESULTS AND FAN COIL UNIT W AS DECLARED OPERATIONAL. ACTION STATEMENT WAS TERMINATED AT 2106 HOURS.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 012681 DURING NORMAL OPERATION ON 1/26/81, #11 CONTAINMENT FAN COIL UNIT WAS DE STATION SERV WATER SYS + CONT 81-010/03L-0 021981 CLARED INOPERABLE IN ORDER TO REPLACE A LEAKING SPOOL PIECE IN THE SERVI PIPES. FITTINGS 036248 30-DAY CE WATER LINE TO UNIT.
ACTION STATEMENT 3.6.2.3 WAS ENTERED AT 1730 HOU to TO 16 INCHES RS.
AT 1907 HOURS, REACTOR TRIPPED.
IN ORDER TO CHANGE OPERATIONAL MOD COMPONENT FAILURE E,
FAN COIL UNIT HAD TO BE DECLARED OPERATIONAL. SURVEILLANCE TEST SP(0 METALLURGICAL
) 4.6.3.2(A) MAS PERFORMED WITH SATISFAC10RY RESULTS AND FAN COIL UNIT W D0YLE, M.
J. CO.
AS DECLARED OPERATIONAL. ACTION STATEMENT WAS TERMINATED AT 2106 HOURS.
NO REPAIRS WERE MADE AT THIS TIME.
NO REPAIRS WERE MADE AT THIS TIME.
SALEM-1                                 05000272     012881 REACTOR TRIP SYSTEMS                 81-005/03L-0   021281   DURING NORMAL OPERATION WHILE PERFORMING A ROUTINE FUNCTIONAL TEST ON TH INSTRUMENTATION + CONTROLS E REACTOR PROTECTION SYSTEM (HIGH STEAM FLOW, CHANNEL II FOR SAFETY INJE 036218     30-DAY   CTION) AT 0820 HOURS ON JANUARY 28, 1981, THE SAFETY INJECTION SIGNAL CO OTHER COMPONENT FAILURE                                              ULD NOT BE GENERATED. PER TECH. SPEC. 3.3.2.B NORMAL OPERATION CONTINUE ELECTRONIC                                                  D WITH THE INOPERABLE CHANNEL PLACED IN THE TRIPPED CONDITION. A MORK 0 HAGAN CORPORATION                                              RDER WAS ISSUED TO TROUBLESHOOT AND REPAIR THE CHANNEL.       PREVIOUS SIMILA R EVENTS WERE:     77-42, 78-44, 78-64, 79-34 AND 80-46.
SALEM-1 05000272 012881 DURING NORMAL OPERATION WHILE PERFORMING A ROUTINE FUNCTIONAL TEST ON TH REACTOR TRIP SYSTEMS 81-005/03L-0 021281 E REACTOR PROTECTION SYSTEM (HIGH STEAM FLOW, CHANNEL II FOR SAFETY INJE INSTRUMENTATION + CONTROLS 036218 30-DAY CTION) AT 0820 HOURS ON JANUARY 28, 1981, THE SAFETY INJECTION SIGNAL CO OTHER ULD NOT BE GENERATED. PER TECH. SPEC. 3.3.2.B NORMAL OPERATION CONTINUE COMPONENT FAILURE D WITH THE INOPERABLE CHANNEL PLACED IN THE TRIPPED CONDITION. A MORK 0 ELECTRONIC RDER WAS ISSUED TO TROUBLESHOOT AND REPAIR THE CHANNEL.
UPON TRCUBLESH00 TING THE CHANNEL, IT WAS FOUND THAT THE COMPARATOR UNIT (HAGAN MODEL 4111082-001) HAD FAILED. THE DEFECTIVE MODULE WAS REPLACED WITH A SPARE. THE REPLACEMENT UNIT WAS CALIBRATED AND A SATISFACTORY C HANNEL FUNCTIONAL TEST WAS COMPLETED. THE CHANNEL WAS RETURNED TD GPERA SALEM-1                                                          TION AT 1050 HOURS ON 1/28/81 05000272     012981   DURING NORMAL OPERATIONS ON 1/29/81, IT WAS DISCOVERED THAT THE CCNTAIAN REAC COOL PRES BOUN LEAK DETEC     81-009/01L-0     021281   ENT SUMP HAD 4.3 GPM OF UNIDENTIFIED LEAKAGE. THE EXCESS LEAKAGE WAS MI INSTRUMENTATION + CONTROLS               036247     30-DAY SENSOR / DETECTOR / ELEMENT                                  STAKENLY ASSUMED TO BE COMING FROM THE #12 CONTAINMENT FAN COOLING UNIT COMPONENT FAILURE                                              AND PER HRC IE BULLETIN NO. 80-24. THE NRC UAS NOTIFIED OF A SERVICE MAT MECHANICAL                                                  ER LEAK IN CONTAINMENT. ON 1/30/81, IT WAS DISCOVERED THAT THC #12 SUMP MANGETROL, INC.                                                  PUMP WAS OPERATING ERRATICALLY AND CALCULATIONS.0F ITS DISCHARGE RATE L ED OPERATIONS TO BELIEVE THERE WAS AN UNIDENTIFIED LEAK.
PREVIOUS SIMILA HAGAN CORPORATION R EVENTS WERE:
APPARENTLY, THE FLOAT ON LD7750 IS LOOSE OR CANTED INSIDE ITS RELL.                                 THE DETECTOR HAS BEEN ISOLATED AND WILL BE REPLACED OR REPAIRED DURING THE NEXT MAINTENANCE OUTAGE.     A SUPPLEMENTARY REPORT WILL BE SUBMITTED WHEN REPAIRS ARE COMPLETED.
77-42, 78-44, 78-64, 79-34 AND 80-46.
SALEM-1                                 05000272     020181 EMERG CORE COOLING SYS + CONT DURING NORMAL OPERATION ON 2/1/81, THE #12 CENTRIFUGAL CHARGING PUMP WAS l                                      31-013/03L-0   021981       DECLARED INOPERABLE BECAUSE OF A LEAK IN THE PUMPS OIL COOLER. ACTION HEAT EXCHANGERS                         036250     30-DAY COOLER                                                      STATEMENT 3.5.2.A WAS ENTERED AT 0220 HOURS. SIMILAR OCCURRENCES: 76-2 3, 77-34, 77-72, 79-68, 80-38, 80-41 AND 80-49.
UPON TRCUBLESH00 TING THE CHANNEL, IT WAS FOUND THAT THE COMPARATOR UNIT (HAGAN MODEL 4111082-001) HAD FAILED.
COMPONENT FAILURE MECHANICAL AMERICAN STANDARD INDUSTRIES THE LEAKING DIL COOLER WAS REPLACED IN KIND.       THE ACTION STATEMENT WAS T ERMINATED AT 0440 HOURS.
THE DEFECTIVE MODULE WAS REPLACED WITH A SPARE.
THE REPLACEMENT UNIT WAS CALIBRATED AND A SATISFACTORY C HANNEL FUNCTIONAL TEST WAS COMPLETED. THE CHANNEL WAS RETURNED TD GPERA TION AT 1050 HOURS ON 1/28/81 SALEM-1 05000272 012981 DURING NORMAL OPERATIONS ON 1/29/81, IT WAS DISCOVERED THAT THE CCNTAIAN REAC COOL PRES BOUN LEAK DETEC 81-009/01L-0 021281 ENT SUMP HAD 4.3 GPM OF UNIDENTIFIED LEAKAGE.
THE EXCESS LEAKAGE WAS MI INSTRUMENTATION + CONTROLS 036247 30-DAY STAKENLY ASSUMED TO BE COMING FROM THE #12 CONTAINMENT FAN COOLING UNIT SENSOR / DETECTOR / ELEMENT AND PER HRC IE BULLETIN NO. 80-24. THE NRC UAS NOTIFIED OF A SERVICE MAT COMPONENT FAILURE ER LEAK IN CONTAINMENT. ON 1/30/81, IT WAS DISCOVERED THAT THC #12 SUMP MECHANICAL PUMP WAS OPERATING ERRATICALLY AND CALCULATIONS.0F ITS DISCHARGE RATE L MANGETROL, INC.
ED OPERATIONS TO BELIEVE THERE WAS AN UNIDENTIFIED LEAK.
APPARENTLY, THE FLOAT ON LD7750 IS LOOSE OR CANTED INSIDE ITS RELL.
THE DETECTOR HAS BEEN ISOLATED AND WILL BE REPLACED OR REPAIRED DURING THE NEXT MAINTENANCE OUTAGE.
A SUPPLEMENTARY REPORT WILL BE SUBMITTED WHEN REPAIRS ARE COMPLETED.
SALEM-1 05000272 020181 DURING NORMAL OPERATION ON 2/1/81, THE #12 CENTRIFUGAL CHARGING PUMP WAS EMERG CORE COOLING SYS + CONT 31-013/03L-0 021981 DECLARED INOPERABLE BECAUSE OF A LEAK IN THE PUMPS OIL COOLER. ACTION l
HEAT EXCHANGERS 036250 30-DAY STATEMENT 3.5.2.A WAS ENTERED AT 0220 HOURS.
SIMILAR OCCURRENCES:
76-2 COOLER 3, 77-34, 77-72, 79-68, 80-38, 80-41 AND 80-49.
COMPONENT FAILURE MECHANICAL AMERICAN STANDARD INDUSTRIES THE LEAKING DIL COOLER WAS REPLACED IN KIND.
THE ACTION STATEMENT WAS T ERMINATED AT 0440 HOURS.


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 77 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 77 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE'SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION SALEM-1                               05000272     020181     DURING NORMAL OPERATION ON 2/1/81 THE #12 CENTRIFUGAL CHARGING PUMP WAS EMERG CORE COOLING SYS + CONT       81-014/03L-0   021931     DECLARED INOPERABLE BECAUSE OF OIL LEAKAGE.         ACTION STATEMENT 3.5.2.A W PUMPS                                 036251     30-DAY     AS ENTERED AT 1700 HOURS.     SIMILAR OCCURRENCES: 76-23, 77-34, 77-72, 79 CENTRIFJGAL                                                 ~68, 80-38, 80-41, 80-4 9 AND 81-13.
EVENT DATE/
COMPONENT FAILURE MECHANICAL PACIFIC PUMPS                                                                                                                                                           .
COMPONENT SUBCODE/CAUSE CODE / LER NO./
LOSS OF OIL CAUSED THE THRUST BEARING TO OVERHEAT AND THE MAIN BEARING T 0 PARTIALLY WIPE. THE BEARINGS WERE REPLACED. THE OIL RESERVOIR, ALL B EARING HOUSINGS AND ALL DIL LINES WERE CLEANED AND FLUSHED. A SATISFACT ORY SURVEILLtNCE TEST WAS PERFORMED AND THE ACTION STATEMENT WAS TERMINA TED AT 1400 HOURS ON 2/3/81.
REPORT DATE/
SALEM-1                               05000272     020481     DURING NORMAL OPERATION ON 2/4/81, THE #2 FIRE PUMP IN THE FIRE SUPPRESS FIRE PROTECTION SYS + CONT         81-012/03L-0   021981     ION MATER SYSTEM WAS DECLARED IMOPERABLE IN ORDER TO REPAIR A LEAKING IN PIPES, FITTINGS                       036249     30-DAY     LET COOLING WATER LINE.     ACTION STATEMENT 3.7.10.1CA) WAS ENTERED AT 162 LESS THAN 4 INCHES                                           S HOURS.
EVENT DESCRIPTION /
CAUSE'SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 020181 DURING NORMAL OPERATION ON 2/1/81 THE #12 CENTRIFUGAL CHARGING PUMP WAS EMERG CORE COOLING SYS + CONT 81-014/03L-0 021931 DECLARED INOPERABLE BECAUSE OF OIL LEAKAGE.
ACTION STATEMENT 3.5.2.A W PUMPS 036251 30-DAY AS ENTERED AT 1700 HOURS.
SIMILAR OCCURRENCES:
76-23, 77-34, 77-72, 79 CENTRIFJGAL
~68, 80-38, 80-41, 80-4 9 AND 81-13.
COMPONENT FAILURE MECHANICAL PACIFIC PUMPS LOSS OF OIL CAUSED THE THRUST BEARING TO OVERHEAT AND THE MAIN BEARING T 0 PARTIALLY WIPE.
THE BEARINGS WERE REPLACED.
THE OIL RESERVOIR, ALL B EARING HOUSINGS AND ALL DIL LINES WERE CLEANED AND FLUSHED. A SATISFACT ORY SURVEILLtNCE TEST WAS PERFORMED AND THE ACTION STATEMENT WAS TERMINA TED AT 1400 HOURS ON 2/3/81.
SALEM-1 05000272 020481 DURING NORMAL OPERATION ON 2/4/81, THE #2 FIRE PUMP IN THE FIRE SUPPRESS FIRE PROTECTION SYS + CONT 81-012/03L-0 021981 ION MATER SYSTEM WAS DECLARED IMOPERABLE IN ORDER TO REPAIR A LEAKING IN PIPES, FITTINGS 036249 30-DAY LET COOLING WATER LINE.
ACTION STATEMENT 3.7.10.1CA) WAS ENTERED AT 162 LESS THAN 4 INCHES S HOURS.
COMPONENT FAILURE MECHANICAL
COMPONENT FAILURE MECHANICAL
    -ANACONDA METAL HOSE CO.
-ANACONDA METAL HOSE CO.
A CORRUGATED STAINLESS STEEL HOSE THAT CONNECTS THE COMMON COOLING MATER PIPING SHARED BY THE PUMP AND ITS STARTING DIESEL WAS LEAKING. THE HDS E WAS REPLACED IN KIND. THE ACTION STATEMENT WAS TERMINATED AT 2140 HOU RS.
A CORRUGATED STAINLESS STEEL HOSE THAT CONNECTS THE COMMON COOLING MATER PIPING SHARED BY THE PUMP AND ITS STARTING DIESEL WAS LEAKING.
SALEM-2                               05000311     082080     DURING A COOLDOWN, THREE SPURIOUS SIGNALS WERE RECEIVED THAT RESULTED IN REACTOR TRIP SYSTEMS               80-019/03X-1   021981     THE 2C SEC SAFEGUARDS EQUIPMENT BEING STARTED. TO PRECLUDE UNNECESSARY RELAYS                                 032059     OTHER       OPERATION OF THE-EQUIPr1ENT, THE 2C SEC WAS DE-ENERGIZED AND ACTION STAT SOLID STATE (SCR'S)                                         EMENT 3.3.2.1 WAS ENTERED AT 1418 HPURS.         SIMILAR OCCURRENCES 12.
THE HDS E WAS REPLACED IN KIND.
THE ACTION STATEMENT WAS TERMINATED AT 2140 HOU RS.
SALEM-2 05000311 082080 DURING A COOLDOWN, THREE SPURIOUS SIGNALS WERE RECEIVED THAT RESULTED IN REACTOR TRIP SYSTEMS 80-019/03X-1 021981 THE 2C SEC SAFEGUARDS EQUIPMENT BEING STARTED.
TO PRECLUDE UNNECESSARY RELAYS 032059 OTHER OPERATION OF THE-EQUIPr1ENT, THE 2C SEC WAS DE-ENERGIZED AND ACTION STAT SOLID STATE (SCR'S)
EMENT 3.3.2.1 WAS ENTERED AT 1418 HPURS.
SIMILAR OCCURRENCES 12.
OTHER NOT APPLICABLE WESTINGHOUSE ELECTRIC CORP.
OTHER NOT APPLICABLE WESTINGHOUSE ELECTRIC CORP.
WHEN ENTRY INTO MODE S WAS ACHIEVED AT 2310 HRS ACTION STATEMENT WAS TE                                                         '
WHEN ENTRY INTO MODE S WAS ACHIEVED AT 2310 HRS ACTION STATEMENT WAS TE RMINATED.
RMINATED. LATCHING RELAYS WERE INSTALLED IN PARALLEL WITH XK1 8 XK2 COI LS TO DETECT TRANSIENTS FROM SOLID STATE PROTECTION SYSTEM WHICH COULD C AUSE SEC TO OPERATE.       THESE RELAYS WERE INSTALLED ON 7/28/80 & REMOVED 0 N 9/3/80. DURING THIS TIME, NO TRANSIENTS DCCURRED. NO ACTION PLANNED.
LATCHING RELAYS WERE INSTALLED IN PARALLEL WITH XK1 8 XK2 COI LS TO DETECT TRANSIENTS FROM SOLID STATE PROTECTION SYSTEM WHICH COULD C AUSE SEC TO OPERATE.
SALEM-2                               05000311     123080   WHILE PERFORMING ROUTINE SURVEILLANCE ON 82B DIESEL GENERATOR. IT WAS DI EMERG GENERATOR SYS + CONTROLS     80-031/03L-0   012981   SCOVERED THAT THE COUPLING CONNECTING TWO SECTIONS OF THE CAMSHAFT HAD A ENGINES, INTERNAL COMBUSTION           033726     30-DAY   LL EIGHT OF ITS ATTACHING ~ BOLTS SHEARED. THIS EQUIPMENT FAILURE WAS DIS SUBCOMPONENT NOT APPLICABLE                                 COVERED WITH THE PLANT IN THE COLD SHUTDOWN, BUT THIS EVENT MUST BE REPO COMPONENT FAILURE                                           RTED AS IF THE PLANT HAD BEEN OPERATING IN A DEGRADED MODE IN ACCORDANCE MECHANICAL                                                   WITH TECHNICAL SPECIFICATION 6.9.1.9B.
THESE RELAYS WERE INSTALLED ON 7/28/80 & REMOVED 0 N 9/3/80.
DURING THIS TIME, NO TRANSIENTS DCCURRED. NO ACTION PLANNED.
SALEM-2 05000311 123080 WHILE PERFORMING ROUTINE SURVEILLANCE ON 82B DIESEL GENERATOR. IT WAS DI EMERG GENERATOR SYS + CONTROLS 80-031/03L-0 012981 SCOVERED THAT THE COUPLING CONNECTING TWO SECTIONS OF THE CAMSHAFT HAD A ENGINES, INTERNAL COMBUSTION 033726 30-DAY LL EIGHT OF ITS ATTACHING ~ BOLTS SHEARED. THIS EQUIPMENT FAILURE WAS DIS SUBCOMPONENT NOT APPLICABLE COVERED WITH THE PLANT IN THE COLD SHUTDOWN, BUT THIS EVENT MUST BE REPO COMPONENT FAILURE RTED AS IF THE PLANT HAD BEEN OPERATING IN A DEGRADED MODE IN ACCORDANCE MECHANICAL WITH TECHNICAL SPECIFICATION 6.9.1.9B.
ALCO ENGINE DIV., WHITE IND.
ALCO ENGINE DIV., WHITE IND.
INSPECTION OF THE COUPLING REVEALED THAT ONE OF THE NUTS WAS NOT ATTACHE D TO ITS EOLT.     THIS WOULD INDICATE THAT THE. JOINT MAY NOT HAVE BEEN PRO PERLY LIGHTENED DURING INITIAL ASSEMBLY. TWO NEW CAMSHAFT SECTIONS WITH THEIR ATTACHING BOLTS AND NUTS HAVE BEEN ORDERED. REPAIRS ARE EXPECTED TO BE COMPLETED ON JANUARY 26, 1951
INSPECTION OF THE COUPLING REVEALED THAT ONE OF THE NUTS WAS NOT ATTACHE D TO ITS EOLT.
THIS WOULD INDICATE THAT THE. JOINT MAY NOT HAVE BEEN PRO PERLY LIGHTENED DURING INITIAL ASSEMBLY. TWO NEW CAMSHAFT SECTIONS WITH THEIR ATTACHING BOLTS AND NUTS HAVE BEEN ORDERED. REPAIRS ARE EXPECTED TO BE COMPLETED ON JANUARY 26, 1951


MAR 26, 1981                                             LER MONTHLY REPORT SORTED BY FACILITY                                       PAGE 78 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./     EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 78 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./             REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER       CONTROL NO.     REPORT TYPE                               CAUSE DESCRIPTION SALEM-2                                   05000311         010481   OURING COLD SHUTDOWN. THE DIESEL UNIT TRIP RELAY ON #2A DIESEL GENERATOR EMERG GENERATOR SYS + CONTROLS         81-001/03L-0       020351     TRIPPED. SINCE DIESEL 82B WAS IHOPERABLE AWAITING REPAIRS. THE MINIMUM ENGINES. INTERNAL COMBUSTION               036072         30-DAY     OF TWO OPERABLE DIESEL GENERATORS REQUIRED BY TECHNICAL SPECIFICATIONS SUBCOMPONENT NOT APPLICABLE                                       COULD NOT BE MET. ACTION STATEMENT 3.8.1.2 WAS ENTERED AT 1353 HCURS.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SALEM-2 05000311 010481 OURING COLD SHUTDOWN. THE DIESEL UNIT TRIP RELAY ON #2A DIESEL GENERATOR EMERG GENERATOR SYS + CONTROLS 81-001/03L-0 020351 TRIPPED. SINCE DIESEL 82B WAS IHOPERABLE AWAITING REPAIRS. THE MINIMUM ENGINES. INTERNAL COMBUSTION 036072 30-DAY OF TWO OPERABLE DIESEL GENERATORS REQUIRED BY TECHNICAL SPECIFICATIONS SUBCOMPONENT NOT APPLICABLE COULD NOT BE MET.
ACTION STATEMENT 3.8.1.2 WAS ENTERED AT 1353 HCURS.
OTHER NOT APPLICABLE ALCO ENGINE DIV.. WHITE IND.
OTHER NOT APPLICABLE ALCO ENGINE DIV.. WHITE IND.
THE CAUSE OF THE RELAY TRIP REMAINS UNDETERMINED. THE RELAY WAS RESET A ND THE DIESEL GENERATOR WAS DETERMINED OPERABLE UPON THE SATISFACTORY CD MPLETION OF THE REQUIRED SURVEILLANCE TESTS. THE ACTION STATEMENT-WAS T ERMINATED AT 1556 HOURS.
THE CAUSE OF THE RELAY TRIP REMAINS UNDETERMINED. THE RELAY WAS RESET A ND THE DIESEL GENERATOR WAS DETERMINED OPERABLE UPON THE SATISFACTORY CD MPLETION OF THE REQUIRED SURVEILLANCE TESTS.
SAN ONOFRE-1                             05000206         112280   WITH RCS DRAINED TO MID LOOP & TRANSFERRING A 4KV BUS POWER SUPPLY FROM-AC ONSITE POWER SYS + CONTROLS         80-038/03L-1       020281   AUX. TRANSFORMER C TO AUX. TRANSFORNER A8B. AC POWER TO ALL STATION AUXI CIRCUIT CLOSERS / INTERRUPTERS             033347         30-DAY   LIARIES WAS LOST FOR 15 SECS DUE TO BRKR MISALIGNMENT. IT WAS ALSO NOTED CIRCUIT BREAKER                                                   THAT SOURCE BRKR TO 4KV BUS 1C DID NOT DPEN ON LOSS OF VOLTAGE DUE TO A~
THE ACTION STATEMENT-WAS T ERMINATED AT 1556 HOURS.
PERSONNEL ERROR                                                     H OPEN D.C. SUITCH SUPPLYING POWER TO STATIDH UNDERVOLTAGE SCHEME. THERE LICENSED & SENIOR OPERATORS                                       WAS NO EFFECT UPON PUBLIC HEALTH & SAFETY NOR WAS THERE ANY IMPACT ON PL OTHER                                                               ANT SAF. BOTH EMERG. D/G STARTED AUTO. 8 WERE AVAILABLE FOR LOADING.           !
SAN ONOFRE-1 05000206 112280 WITH RCS DRAINED TO MID LOOP & TRANSFERRING A 4KV BUS POWER SUPPLY FROM-AC ONSITE POWER SYS + CONTROLS 80-038/03L-1 020281 AUX. TRANSFORMER C TO AUX. TRANSFORNER A8B. AC POWER TO ALL STATION AUXI CIRCUIT CLOSERS / INTERRUPTERS 033347 30-DAY LIARIES WAS LOST FOR 15 SECS DUE TO BRKR MISALIGNMENT. IT WAS ALSO NOTED CIRCUIT BREAKER THAT SOURCE BRKR TO 4KV BUS 1C DID NOT DPEN ON LOSS OF VOLTAGE DUE TO A~
A LICENSED GPERATOR INTENDING TO OPEN AUXILIARY TRANSFORMER C BUS SUPPLY       '
PERSONNEL ERROR H OPEN D.C.
BREAKERS INADVERTENTLY CPENED THE AKV SUS TIE BREAKERS. THE D.C. PCWER SUPPLY SWITCH TO STATION UNDERVOLTAGE SCHEME WAS INADVERTENTLY OPENED BY PERSONNEL RACKING OUT A NEARBY BRKR. ADMINISTRATIVE CONTROLS ON SAFETY RELATED D.C. CIRCUITS WILL BE IMPLEMENTED TD PRECLUDE RECURRENCE.
SUITCH SUPPLYING POWER TO STATIDH UNDERVOLTAGE SCHEME. THERE LICENSED & SENIOR OPERATORS WAS NO EFFECT UPON PUBLIC HEALTH & SAFETY NOR WAS THERE ANY IMPACT ON PL OTHER ANT SAF. BOTH EMERG. D/G STARTED AUTO. 8 WERE AVAILABLE FOR LOADING.
SAN DNOFRE-1                             05000206         011681   UNDER A SISLOP CONDITION. IF THE SAFETY INJECTION ACTUATION PARAMETERS 0 EMERG CORE COOLING SYS + CONT         81- 0 01/ 01T-0   011981   SCILLATE ABOUT THEIR SAFETY INJECTIGN SETPOINTS. THE SEQUENCER WILL RESE RELAYS                                     036219         2-WEEK   T AND RE-SEQUENCE THE SAFETY INJECTION LOADS. IF THESE OSCILLATIONS OCC l
A LICENSED GPERATOR INTENDING TO OPEN AUXILIARY TRANSFORMER C BUS SUPPLY BREAKERS INADVERTENTLY CPENED THE AKV SUS TIE BREAKERS. THE D.C. PCWER SUPPLY SWITCH TO STATION UNDERVOLTAGE SCHEME WAS INADVERTENTLY OPENED BY PERSONNEL RACKING OUT A NEARBY BRKR.
TIMER. SEQUENCER, T-S CONTROL                                     UR PRIOR TO THE COMPLETE LOADING OF THE SIS LOADS. SOME LOADS WILL NOT B DESIGN / FABRICATION ERROR                                         E AUTOMATICALLY-LOADED.
ADMINISTRATIVE CONTROLS ON SAFETY RELATED D.C. CIRCUITS WILL BE IMPLEMENTED TD PRECLUDE RECURRENCE.
SAN DNOFRE-1 05000206 011681 UNDER A SISLOP CONDITION. IF THE SAFETY INJECTION ACTUATION PARAMETERS 0 EMERG CORE COOLING SYS + CONT 81- 0 01/ 01T-0 011981 SCILLATE ABOUT THEIR SAFETY INJECTIGN SETPOINTS. THE SEQUENCER WILL RESE RELAYS 036219 2-WEEK T AND RE-SEQUENCE THE SAFETY INJECTION LOADS.
IF THESE OSCILLATIONS OCC l
TIMER. SEQUENCER, T-S CONTROL UR PRIOR TO THE COMPLETE LOADING OF THE SIS LOADS. SOME LOADS WILL NOT B DESIGN / FABRICATION ERROR E AUTOMATICALLY-LOADED.
DESIGN CONSOLIDATED CONTROLS CORP.
DESIGN CONSOLIDATED CONTROLS CORP.
FOLLOWING A SISLOP.0SCILLATION OF THE SAFETY INJECTION PARAMETERS ABOUT THE SETPOINTS COULD CAUSE RE-SEQUENCING OF THE SIS LOADS SUCH THAT SOME L                                                                         LO ADS WOULD NEVER BE LOADED. THE SEQUENCER SYSTEM IS BEING REDESIGNED $
FOLLOWING A SISLOP.0SCILLATION OF THE SAFETY INJECTION PARAMETERS ABOUT THE SETPOINTS COULD CAUSE RE-SEQUENCING OF THE SIS LOADS SUCH THAT SOME L
LO ADS WOULD NEVER BE LOADED.
THE SEQUENCER SYSTEM IS BEING REDESIGNED $
UCH THAT THIS SCENARIO WILL NOT OCCUR.
UCH THAT THIS SCENARIO WILL NOT OCCUR.
SAN ONOFRE-1                             05000206         020281   DURING A FIELD VERIFICATION / INSPECTION IN ACCORDANCE WITH IE BULLETIN 79 FEEDWATER SYSTEMS + CONTROLS         81-002/01T-0       021681   -14   SEVERAL MISSING BOLTS WERE DISCOVERED CH FEECWATER LINE 392-10"-EG.
SAN ONOFRE-1 05000206 020281 DURING A FIELD VERIFICATION / INSPECTION IN ACCORDANCE WITH IE BULLETIN 79 FEEDWATER SYSTEMS + CONTROLS 81-002/01T-0 021681
HANGERS. SUPPORTS. SHOCK SUPPRSS         036138         2-WEEK     SUBSEQUENT CALCULATIONS INDICATED THAT. WITHOUT THE LOLTS. THE STIFFNES SUPPORTS                                                         S CALCULATIONS WOULD BE INVALIDATED AND THE ALLOWABLE PIPING STRESS WOUL COMPONENT FAILURE                                                 D PROBABLY BE EXCEEDED DURING AN EARTHQUAKE AS DEFINED IN THE FSAR. THI MECHANICAL                                                       5 REFORT IS IN CONFORMANCE WITH TECHNICAL SPECIFICATION 6.9.2.A.
-14 SEVERAL MISSING BOLTS WERE DISCOVERED CH FEECWATER LINE 392-10"-EG.
BECHTEL CORP.                                                     THE SUPPORTS (BOLTS) WERE REQUIRED BY DESIGN D1SCLOSURE DOCUMENTS; HOWEV ER. IN THE FIELD. SEVERAL BOLTS WERE DISCOVERED MISSING. THE BOLTS WILL BE REPLACED PRIOR TO RETURN TO SERVICE FROM THE CURRENT GUTAGE TO CONFO RM THE SUPPORTS TO THE SEISMIC ANALYSIS INPUT INFORMATION.
HANGERS. SUPPORTS. SHOCK SUPPRSS 036138 2-WEEK SUBSEQUENT CALCULATIONS INDICATED THAT. WITHOUT THE LOLTS. THE STIFFNES SUPPORTS S CALCULATIONS WOULD BE INVALIDATED AND THE ALLOWABLE PIPING STRESS WOUL COMPONENT FAILURE D PROBABLY BE EXCEEDED DURING AN EARTHQUAKE AS DEFINED IN THE FSAR.
THI MECHANICAL 5 REFORT IS IN CONFORMANCE WITH TECHNICAL SPECIFICATION 6.9.2.A.
BECHTEL CORP.
THE SUPPORTS (BOLTS) WERE REQUIRED BY DESIGN D1SCLOSURE DOCUMENTS; HOWEV ER. IN THE FIELD. SEVERAL BOLTS WERE DISCOVERED MISSING. THE BOLTS WILL BE REPLACED PRIOR TO RETURN TO SERVICE FROM THE CURRENT GUTAGE TO CONFO RM THE SUPPORTS TO THE SEISMIC ANALYSIS INPUT INFORMATION.


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 79 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./ EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 79 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAU3E CODE / LER NO./   . REPORT DATE/                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION SEQUOYAH-1                             05000327     120180   SPECIAL REPORT 80-6.       DURING STEAM GENERATOR MOISTURE CARRYOVER TESTS PE STEAM GEN BLCWDOWN SYS + CONT       80-006/04L-0   123180   RFORMED ON 12/1 3 12/2/80, AN INADVERTENT, UNCONTROLLED DISCHARGE OF THE VALVES                                 033753     30-DAY     RADI0 ACTIVE TRACER (50DIUM-24) OCCURRED. DISCHARGE EVENTUALLY REACHED OTHER                                                       THE TENNESSEE RIVER.       APPROX. 79,400 GALS WERE RELEASED OF CONCENTRATION DEFECTIVE PROCEDURES                                           BETWEEN 6.9E-3 TO 0.37 CI. CAUSE OF EVENT WAS ERROR IN VALVE LINE-UP.
EVENT DATE/
,      NOT APPLICABLE OTHER THE INCIDENT RESULTED DIRECTLY FROM INADECUATE TEST INSTRUCTIONS AND IMP ROPER COMMUNICATIONS BETWEEN THE TEST DIRECTIONS AND LABORATORY PERSONNE L. NO PERSONNEL RECEIVED MEASURABLE EXPOSURE. NO DETECTABLE RADICACTIV
COMPONENT SUBCODE/CAU3E CODE / LER NO./
,                                                                  ITY WAS RELEASED TO THE TENNESSEE RIVER. TEST INSTRUCTIONS HAVE BEEN CL ARIFIED.
. REPORT DATE/
SEQUDYAH-1                             05000327     122580   AT 0631 CST WITH UNIT 1 AT'86% RTP, RWST LEVEL INDICATOR t-LI-63-50 FAIL ENGNRD SAFETY FEATR INSTR SYS       80-206/03L-0 012281     ED HIGH. THE PL ANT ENTERED ACTION STATEMENT 16 0F LCO 3. 3.2.1 AND ACTIO INSTRUMENTATION + CONTROLS             033685     30-DAY   N STATEMENT "A" CF LCD 3.3.3.7 UNTIL THE INSTRUMENT CHANNEL WAS RETURNED TRANSMITTER                                                 TO SERVICE AT 0928 CST. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY OTHER                                                       . f'REVIOUS OCCURRENCES - NONE.
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SEQUOYAH-1 05000327 120180 SPECIAL REPORT 80-6.
DURING STEAM GENERATOR MOISTURE CARRYOVER TESTS PE STEAM GEN BLCWDOWN SYS + CONT 80-006/04L-0 123180 RFORMED ON 12/1 3 12/2/80, AN INADVERTENT, UNCONTROLLED DISCHARGE OF THE VALVES 033753 30-DAY RADI0 ACTIVE TRACER (50DIUM-24) OCCURRED. DISCHARGE EVENTUALLY REACHED OTHER THE TENNESSEE RIVER.
APPROX. 79,400 GALS WERE RELEASED OF CONCENTRATION DEFECTIVE PROCEDURES BETWEEN 6.9E-3 TO 0.37 CI.
CAUSE OF EVENT WAS ERROR IN VALVE LINE-UP.
NOT APPLICABLE OTHER THE INCIDENT RESULTED DIRECTLY FROM INADECUATE TEST INSTRUCTIONS AND IMP ROPER COMMUNICATIONS BETWEEN THE TEST DIRECTIONS AND LABORATORY PERSONNE L.
NO PERSONNEL RECEIVED MEASURABLE EXPOSURE. NO DETECTABLE RADICACTIV ITY WAS RELEASED TO THE TENNESSEE RIVER.
TEST INSTRUCTIONS HAVE BEEN CL ARIFIED.
SEQUDYAH-1 05000327 122580 AT 0631 CST WITH UNIT 1 AT'86% RTP, RWST LEVEL INDICATOR t-LI-63-50 FAIL ENGNRD SAFETY FEATR INSTR SYS 80-206/03L-0 012281 ED HIGH.
THE PL ANT ENTERED ACTION STATEMENT 16 0F LCO 3. 3.2.1 AND ACTIO INSTRUMENTATION + CONTROLS 033685 30-DAY N STATEMENT "A" CF LCD 3.3.3.7 UNTIL THE INSTRUMENT CHANNEL WAS RETURNED TRANSMITTER TO SERVICE AT 0928 CST.
THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY OTHER
. f'REVIOUS OCCURRENCES - NONE.
NOT APPLICABLE BARTON INSTRU CO., DIV 0F ITT INSTRUMENT LINES FOR LEVEL TRANSMITTER WERE FROZEN INSIDE INSULATED CABI NET HOUSING TRANSMITTER. DOOR TO CABINET WAS DISCOVERED TO BE AJAR ALLO WING LINES TO FREEZE. LINES WERE THAWED USING A HEAT GUN AND INSTRUMENT LOOP WAS RETURNED TO SERVICE. CABINET DOOR WAS LOCKED TO PREVENT REOCC URRENCE.
NOT APPLICABLE BARTON INSTRU CO., DIV 0F ITT INSTRUMENT LINES FOR LEVEL TRANSMITTER WERE FROZEN INSIDE INSULATED CABI NET HOUSING TRANSMITTER. DOOR TO CABINET WAS DISCOVERED TO BE AJAR ALLO WING LINES TO FREEZE. LINES WERE THAWED USING A HEAT GUN AND INSTRUMENT LOOP WAS RETURNED TO SERVICE. CABINET DOOR WAS LOCKED TO PREVENT REOCC URRENCE.
SEQUOYAH-1                             05000327     122580   AT 86% RTP, S/G-3 TRAIN     "A" STEAMLINE PRESSURE I FLOW CHANNELS TAILED HI SAFETY RELATED DISPLAY INSTR       80-202/03L-O   012281   GH AT 0441 CST. ACTION STATEMENTS OF LCO 3.3.3.7(A), 3.3.9           M~J. & 3.3.2 INSTRUMENTATION + CONTROLS             033727     30-DAY   .1( 16 ) WERE IN EFFECT UNTIL OPER. WAS RESTORED AT 062' UST. AT 0649 CST TRANSMITTER                                               S/G-te 2, & 4 TRAIN     "B" FECDWATER FLOW CHANNELS FAILE.1 LOW 3 PLANT "NTER DESIGN / FABRICATION ERROR                                   ED ACTION STATEMENT 7 0F LCO 3.3.1.1         WHEN S/G-1 TRAIN "A" FEEDWATEM FLO DESIGN                                                     W CHANNEL SUBSEQ. FAILED LOW AT 0852 CST, PLANT PREPARED FOR SHUTDOWN PE FOXBORO CO.,     THE                                         R LCD 3.0.3 BUT REMAINED AT POWER WHEN OPER. WAS RESTORED AT 0934 CST.
SEQUOYAH-1 05000327 122580 AT 86% RTP, S/G-3 TRAIN "A" STEAMLINE PRESSURE I FLOW CHANNELS TAILED HI SAFETY RELATED DISPLAY INSTR 80-202/03L-O 012281 GH AT 0441 CST. ACTION STATEMENTS OF LCO 3.3.3.7(A), 3.3.9 M~J.
THE INSTRUMENT CHANNELS BECAME INOPERABLE DUE TO FREEZING OF UNPROTECTED SENSE LINES. THE LINES WERE THAWED BY APPLYING TEMPORARY HEAT AND INSU LATION. DESIGN CHANGES HAVE BEEN INITIATED TO HAVE THE REQUIRED HEAT TR ACING AND INSULATION INSTALLED TO PREVENT REOCCURRENCE.
& 3.3.2 INSTRUMENTATION + CONTROLS 033727 30-DAY
SEQUOYAH-1                             05000327     122880   WITH UNIT 1 AT 86% RTP, REMOTE SHUTDOWN MONITORING INDICATORS 1-LI-68-32 OTHR INST SYS REQD FOR SAFETY       80-207/03L-0   012681   5C 8 1-LI-68-326C (PRESSURIZER LEVEL) WERE DECLARED INOPERABLE AT 0435 C INSTRUMENTATION + CONTROLS             033686     30-DAY   ST WHEN INDICATORS WERE OBSERVED TO BE READING TWELVE PERCENT HIGHER THA TRANSMITTER                                                 H INDICATORS IN MAIN CONTROL ROOM. PLANT ENTERED ACTION STATEMENT "A" 0 OTHER                                                       F LCO 3.3.3.5 UNTIL INDICATORS WERE RETURNED TO SERVICE AT 1430 CST ON 1 NOT APPLICABLE                                             /2/81. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY. PREVIOUS OCCURR FOXBORD CO.,     THE                                         ENCES - NDHE.
.1( 16 ) WERE IN EFFECT UNTIL OPER. WAS RESTORED AT 062' UST. AT 0649 CST TRANSMITTER S/G-te 2, & 4 TRAIN "B" FECDWATER FLOW CHANNELS FAILE.1 LOW 3 PLANT "NTER DESIGN / FABRICATION ERROR ED ACTION STATEMENT 7 0F LCO 3.3.1.1 WHEN S/G-1 TRAIN "A" FEEDWATEM FLO DESIGN W CHANNEL SUBSEQ. FAILED LOW AT 0852 CST, PLANT PREPARED FOR SHUTDOWN PE FOXBORO CO.,
THE R LCD 3.0.3 BUT REMAINED AT POWER WHEN OPER. WAS RESTORED AT 0934 CST.
THE INSTRUMENT CHANNELS BECAME INOPERABLE DUE TO FREEZING OF UNPROTECTED SENSE LINES.
THE LINES WERE THAWED BY APPLYING TEMPORARY HEAT AND INSU LATION.
DESIGN CHANGES HAVE BEEN INITIATED TO HAVE THE REQUIRED HEAT TR ACING AND INSULATION INSTALLED TO PREVENT REOCCURRENCE.
SEQUOYAH-1 05000327 122880 WITH UNIT 1 AT 86% RTP, REMOTE SHUTDOWN MONITORING INDICATORS 1-LI-68-32 OTHR INST SYS REQD FOR SAFETY 80-207/03L-0 012681 5C 8 1-LI-68-326C (PRESSURIZER LEVEL) WERE DECLARED INOPERABLE AT 0435 C INSTRUMENTATION + CONTROLS 033686 30-DAY ST WHEN INDICATORS WERE OBSERVED TO BE READING TWELVE PERCENT HIGHER THA TRANSMITTER H INDICATORS IN MAIN CONTROL ROOM.
PLANT ENTERED ACTION STATEMENT "A" 0
OTHER F LCO 3.3.3.5 UNTIL INDICATORS WERE RETURNED TO SERVICE AT 1430 CST ON 1 NOT APPLICABLE
/2/81.
THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY. PREVIOUS OCCURR FOXBORD CO.,
THE ENCES - NDHE.
THE ERRONEDUS INDICATION WAS CAUSED BY A LEAKING VALVE IN A COMMON DRAIN LINE FOR THE TRANSMITTERS. AFTER THE VALVE WAS TIGHTENED DOWN, THE IHS TRUMENT LOOPS WERE RETURNED TO SERVICE AND PROPER OPERATION OF THE. INSTR UMENT LOOPS WERE VERIFIED.
THE ERRONEDUS INDICATION WAS CAUSED BY A LEAKING VALVE IN A COMMON DRAIN LINE FOR THE TRANSMITTERS. AFTER THE VALVE WAS TIGHTENED DOWN, THE IHS TRUMENT LOOPS WERE RETURNED TO SERVICE AND PROPER OPERATION OF THE. INSTR UMENT LOOPS WERE VERIFIED.


j MAR 26, 1981                                                     LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 80 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./               EVENT DATE/
j MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 80 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                   REPORT DATE/                                   EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO.               REPORT TYPE                                     CAUSE DESCRIPTION
EVENT DATE/
                                                                                                                                                                    ?
COMPONENT SUBCODE/CAUSE CODE / LER NO./
SEQUDYAH-1                                           05000327     122980     UNIT IN MODE 1 AT 86% REACTOR PCMER.
REPORT DATE/
CNTNMNT HEAT REMOV SYS + CONT        80-205/03L-0 012681 ON 12-29-80 AND AGAIN ON 1-$-81   T   ;
EVENT DESCRIPTION /
PENETRATIONS.PRIMRY CONTAINMNT                                              WO ICE CONDENSER INTERMEDIATE DECK DOORS BELOW AHU-3A MERE FOUND FROZEN 033728     30-DAY     CLOSED. LCO 3.6.5.3 WAS ENTERED ON BOTH OCCASIONS. THERE WAS N3 EFFECT OTHER                                                                     UPON PUBLIC HEALTH OR SAFETY. PREVIOUS OCCURRENCES - 2 (REFERENCE SQR0 COMPONENT FAILURE                                                           327/80-170 AND 80-203).
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION
?
SEQUDYAH-1 05000327 122980 UNIT IN MODE 1 AT 86% REACTOR PCMER.
ON 12-29-80 AND AGAIN ON 1-$-81 T
CNTNMNT HEAT REMOV SYS + CONT 80-205/03L-0 012681 WO ICE CONDENSER INTERMEDIATE DECK DOORS BELOW AHU-3A MERE FOUND FROZEN PENETRATIONS.PRIMRY CONTAINMNT 033728 30-DAY CLOSED.
LCO 3.6.5.3 WAS ENTERED ON BOTH OCCASIONS. THERE WAS N3 EFFECT OTHER UPON PUBLIC HEALTH OR SAFETY.
PREVIOUS OCCURRENCES - 2 (REFERENCE SQR0 COMPONENT FAILURE 327/80-170 AND 80-203).
MECHANICAL WESTINGHOUSE ELECTRIC CORP.
MECHANICAL WESTINGHOUSE ELECTRIC CORP.
ICE WAS REMOVED FROM DOORS WITHIN 24 HOURS ON BOTH OCCASIONS. WATER FR0 ZEN IN ANU-3A DRAIN LIHE DID NOT ALLOM WATER T3 PASS DURING DEFROST CYCL ES. THE WATER SPILLED OVER FROM DRIP PAN ONTO THE DOORS CAUSING COORS T 0 BECOME FROZEN CLOSED.
ICE WAS REMOVED FROM DOORS WITHIN 24 HOURS ON BOTH OCCASIONS. WATER FR0 ZEN IN ANU-3A DRAIN LIHE DID NOT ALLOM WATER T3 PASS DURING DEFROST CYCL ES.
SEQUOYAH-1                                           050C0327     010281                                                                                       '
THE WATER SPILLED OVER FROM DRIP PAN ONTO THE DOORS CAUSING COORS T 0 BECOME FROZEN CLOSED.
PRCSS + EFF RADIOL MONITOR SYS                                            WITH UNIT 1 AT 90% RTP. CONDENSATE STORAGE TANK LEVEL CHANNEL 0-L-2-230 81-001/03L-0               013081     WAS DECLARED INOPERABLE AT 1330 CST WHEN THE CONTROL ROOM INDICATOR FAIL PIPES, FITTINGS                                     036073     30-DAY     ED LOU.
SEQUOYAH-1 050C0327 010281 WITH UNIT 1 AT 90% RTP. CONDENSATE STORAGE TANK LEVEL CHANNEL 0-L-2-230 PRCSS + EFF RADIOL MONITOR SYS 81-001/03L-0 013081 WAS DECLARED INOPERABLE AT 1330 CST WHEN THE CONTROL ROOM INDICATOR FAIL PIPES, FITTINGS 036073 30-DAY ED LOU.
LESS THAN 4 INCHES                                                                    THE PLANT ENTERED ACTION STATEMENT 34 0F LCO 3.3.3.9 UNTIL THE INSTRUMENT CHANNEL WAS RETURNED TO SERVICE AT 1600 CST. THERE WAS NO EF OTHER FECT ON PUDLIC HEALTH OR SAFETY. NO PREVIOUS OCCURRENCES.
THE PLANT ENTERED ACTION STATEMENT 34 0F LCO 3.3.3.9 UNTIL THE LESS THAN 4 INCHES INSTRUMENT CHANNEL WAS RETURNED TO SERVICE AT 1600 CST.
THERE WAS NO EF OTHER FECT ON PUDLIC HEALTH OR SAFETY. NO PREVIOUS OCCURRENCES.
NOT APPLICABLE OTHER THE APPARENT CAUSE OF THE FAILURE WAS AN IMPROPERLY TIGHTENED COMPRESSIO N FITTING ON THE INSTRUMENT SENSE LINE WHICH DECAME DISCONNECTED. THE S ENSE LINE WAS PROPERLY CONNECTED AND THE LEVEL CHANNEL WAS RETURNED TO S ERVICE.
NOT APPLICABLE OTHER THE APPARENT CAUSE OF THE FAILURE WAS AN IMPROPERLY TIGHTENED COMPRESSIO N FITTING ON THE INSTRUMENT SENSE LINE WHICH DECAME DISCONNECTED. THE S ENSE LINE WAS PROPERLY CONNECTED AND THE LEVEL CHANNEL WAS RETURNED TO S ERVICE.
SEQUDYAH-1                                           05000327     010581     AT 0645 CST ON 1/5/81, WITH UNIT 1 AT 92% RTP. MAIN FEEDWATER FLOW CHANN REACTOR TRIP SYSTEMS                 81-003/03L-0               093081     EL F-3-35B (S/G #3) FAILED LOW.     ON 1/12/81 WITH UNIT 1 AT 100% RTP. FE r
SEQUDYAH-1 05000327 010581 AT 0645 CST ON 1/5/81, WITH UNIT 1 AT 92% RTP. MAIN FEEDWATER FLOW CHANN REACTOR TRIP SYSTEMS 81-003/03L-0 093081 EL F-3-35B (S/G #3) FAILED LOW.
INSTRUMENTA1 ION + CONTROLS                         036220     30-DAY     EDWATER FLOW CHANNEL F-3-35B FAILED AT 0445 CST AND FEEDuaTER FLOW CHANN TRANSMITTER                                                               El F-3-90B (S/G #1) FAILED A' 3615 CST. IN EACH CASE THE PLANT ENTERED DESIGN / FABRICATION ERROR                                                 ACTION STATEMENT 7 0F LCO 3.3.1.1.       THERE WAS NO EFFECT ON PUBLIC HEALTH DESIGN                                                                                                                                                     <
ON 1/12/81 WITH UNIT 1 AT 100% RTP. FE r
FOXBORO CO., THE                                                            OR SAFETY. FOR PREVIOUS DCCURRENCES REFER TO SCRO-50-327/80-202.
INSTRUMENTA1 ION + CONTROLS 036220 30-DAY EDWATER FLOW CHANNEL F-3-35B FAILED AT 0445 CST AND FEEDuaTER FLOW CHANN TRANSMITTER El F-3-90B (S/G #1) FAILED A' 3615 CST.
THE FEEDWATER FLOW CHANNELS FAILED DUE TO FREEZING OF. INADEQUATELY PROTE CTED INSTRUMENT SENSE LINES. THE LINES WERE THAWED USING A HEAT GUN AND RETURNED TO SERVICE. A PLASTIC ENCLOSURE CONTAINING HEATERS.HAS BEEN E RECTED AROUND THE SENSE LINES TO PREVENT RECURRENCE UNTIL DCR-P-999 (PRE VIOUStY INITIATED) CAN BE IMPLEMENTED.
IN EACH CASE THE PLANT ENTERED DESIGN / FABRICATION ERROR ACTION STATEMENT 7 0F LCO 3.3.1.1.
SEQUOYAH-1                                           05000327     010981     UNIT 1 IN MODE 1 AT 90% REACTOR POWER.
THERE WAS NO EFFECT ON PUBLIC HEALTH DESIGN OR SAFETY. FOR PREVIOUS DCCURRENCES REFER TO SCRO-50-327/80-202.
CNTNMNT HEAT REMOV SYS + CONT                                                                                             DURING ROUTINE INSPECTION OF THE 81-002/03L-0 020481                     ICE CONDENSER, TWO INTERMEDIATE DECK DOORS WERE FOUND FROZEN CLOSED.       L PENETRATIONS.PRIMRY CONTAINMNT                       036074     30-DAY     CO 3.6.5.2 utS ENTERED. THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFET
FOXBORO CO., THE THE FEEDWATER FLOW CHANNELS FAILED DUE TO FREEZING OF. INADEQUATELY PROTE CTED INSTRUMENT SENSE LINES.
,      OTHER                                                                     Y. PREVIOUS OCCURRENCES - 3 (REFERENCE SCRO-50-327/80-170. 80-203. AND
THE LINES WERE THAWED USING A HEAT GUN AND RETURNED TO SERVICE. A PLASTIC ENCLOSURE CONTAINING HEATERS.HAS BEEN E RECTED AROUND THE SENSE LINES TO PREVENT RECURRENCE UNTIL DCR-P-999 (PRE VIOUStY INITIATED) CAN BE IMPLEMENTED.
!    . COMPONENT FAILURE                                                         80-205).
SEQUOYAH-1 05000327 010981 UNIT 1 IN MODE 1 AT 90% REACTOR POWER.
DURING ROUTINE INSPECTION OF THE CNTNMNT HEAT REMOV SYS + CONT 81-002/03L-0 020481 ICE CONDENSER, TWO INTERMEDIATE DECK DOORS WERE FOUND FROZEN CLOSED.
L PENETRATIONS.PRIMRY CONTAINMNT 036074 30-DAY CO 3.6.5.2 utS ENTERED. THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFET OTHER Y.
PREVIOUS OCCURRENCES - 3 (REFERENCE SCRO-50-327/80-170. 80-203. AND
. COMPONENT FAILURE 80-205).
METALLURGICAL WESTINGHOUSE ELECTRIC CORP.
METALLURGICAL WESTINGHOUSE ELECTRIC CORP.
ICE WAS REMOVED FROM DOORS WITHIN 24 HRS. WATER WAS LEAKING FROM AHU-3A DEFROST DRAIN LINE FLANGE DUE TO LODSE FLANGE BOLTS. BOLTS WERE RETIGH
ICE WAS REMOVED FROM DOORS WITHIN 24 HRS.
                                                                                  'ENED.
WATER WAS LEAKING FROM AHU-3A DEFROST DRAIN LINE FLANGE DUE TO LODSE FLANGE BOLTS.
T          INVESTIGATION TO DETERMINE CAUSE OF FLANCE BEING LOOSE DID NOT R l                                                                                 EVEAL A CONCLUSIVE OR LOGICAL EXPLANATION. FLANGE IS BEING PERIODICALLY MONITORED IN AN ATTEMPT TO DETERMINE CAUSE & TO PREVENT REOCCURRENCE.
BOLTS WERE RETIGH
'ENED.
INVESTIGATION TO DETERMINE CAUSE OF FLANCE BEING LOOSE DID NOT R T
l EVEAL A CONCLUSIVE OR LOGICAL EXPLANATION. FLANGE IS BEING PERIODICALLY MONITORED IN AN ATTEMPT TO DETERMINE CAUSE & TO PREVENT REOCCURRENCE.
l
l
  --                                  __  _                      _ ,          ._      .  ,    .      - - ._ ___            - ~ _ _ _ ,               . __    _
- ~ _ _ _,


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                         PAGE 81-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/ DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 81-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION SEQUDYAH-1                             05000327     011281     AT 040C CST WITH UNIT 1 AT 100% RTP, RWST LEVEL CHANNEL L-63-53 FAILED, ENGNRD SAFETY FEATR INSTR SYS       81-004/03L-0   020681     PLACING THE PLANT IN ACTION STATEMENT 18 0F LCO 3.3.2.1 AND ACTION STATE INSTRUMENTATION + CONTROLS             036075     30-DAY     MENT "A" 0F LCO 3.3.3.7. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY TRANSMITTER                                                 . ONE PREVIOUS OCCURRENCE: SQRO-50-327/80-206.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SEQUDYAH-1 05000327 011281 AT 040C CST WITH UNIT 1 AT 100% RTP, RWST LEVEL CHANNEL L-63-53 FAILED, ENGNRD SAFETY FEATR INSTR SYS 81-004/03L-0 020681 PLACING THE PLANT IN ACTION STATEMENT 18 0F LCO 3.3.2.1 AND ACTION STATE INSTRUMENTATION + CONTROLS 036075 30-DAY MENT "A" 0F LCO 3.3.3.7.
THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY TRANSMITTER
. ONE PREVIOUS OCCURRENCE:
SQRO-50-327/80-206.
DESIGN / FABRICATION ERROR CONSTRUCTION / INSTALLATION 9ARTON INSTRU CO., DIV 0F ITT THE INSTRUMENT CHANNEL FAILED DUE TO FREEZING OF ITS SENSE LINES INSIDE THE INSULATED CABINET HOUSING THE LEVEL TRANSMITTER. AN INVESTIGATION I DENTIFIED THAT INSUFFICIENT INSULATION HAD BEEN INSTALLED AROUND THE SEN SE LINES 8 ON THE SIDES OF THE CABINET. STRIP HEATERS WILL BE USED TO P REVENT RECURRENCE UNTIL PROPER THICKNESS'0F INSULATION CAN BE INSTALLED.
DESIGN / FABRICATION ERROR CONSTRUCTION / INSTALLATION 9ARTON INSTRU CO., DIV 0F ITT THE INSTRUMENT CHANNEL FAILED DUE TO FREEZING OF ITS SENSE LINES INSIDE THE INSULATED CABINET HOUSING THE LEVEL TRANSMITTER. AN INVESTIGATION I DENTIFIED THAT INSUFFICIENT INSULATION HAD BEEN INSTALLED AROUND THE SEN SE LINES 8 ON THE SIDES OF THE CABINET. STRIP HEATERS WILL BE USED TO P REVENT RECURRENCE UNTIL PROPER THICKNESS'0F INSULATION CAN BE INSTALLED.
SEQUOYAH-1                             05000327     011481     UNIT IN MODE 1 WITH RCS TEMPERATURE 578 DEGREES F AND PRESSURE 2235 PSIG EMERG CORE COOLING SYS + CONT       81-006/03L-0   020281         IT WAS DISCOVERED DURING A REVIEW OF MR'S THAT ON 9/29/80, DURING THE VALVES                                 036076     30-DAY     . PERFORMANCE OF SI-166.10, VALVE 1-FCV-63-38 WAS FOUND TO BE LEAKING APP OTHER                                                       ROXINATELY 3 GPM. AN MR WAS INITIATED TO REPAIR THE VALVE. AFTER COMPL DEFECTIVE PROCEDURES                                         ETION OF MAINTENANCE THE VALVE WAS NOT STROKE TESTED AS REQUIRED BY SURV NOT APPLICABLE                                               EILLANCE REQUIREMENT 4.0.5. THERE WAS NO EFFECT UPON PUBLIC HEALTH OR S OTHER                                                         AFETY. PREVIOUS DCCURRENCES SQRO-50-327/80-190 AND 80-200.
SEQUOYAH-1 05000327 011481 UNIT IN MODE 1 WITH RCS TEMPERATURE 578 DEGREES F AND PRESSURE 2235 PSIG EMERG CORE COOLING SYS + CONT 81-006/03L-0 020281 IT WAS DISCOVERED DURING A REVIEW OF MR'S THAT ON 9/29/80, DURING THE VALVES 036076 30-DAY
. PERFORMANCE OF SI-166.10, VALVE 1-FCV-63-38 WAS FOUND TO BE LEAKING APP OTHER ROXINATELY 3 GPM.
AN MR WAS INITIATED TO REPAIR THE VALVE.
AFTER COMPL DEFECTIVE PROCEDURES ETION OF MAINTENANCE THE VALVE WAS NOT STROKE TESTED AS REQUIRED BY SURV NOT APPLICABLE EILLANCE REQUIREMENT 4.0.5.
THERE WAS NO EFFECT UPON PUBLIC HEALTH OR S OTHER AFETY.
PREVIOUS DCCURRENCES SQRO-50-327/80-190 AND 80-200.
THE FAILURE TO PERFORM THE TESTING AS REQUIRED BY SURVEILLANCE REQUIREME NT IS ATTRIBUTED TO AN INADEQUATE PROCEDURE. THE APPROPRIATE STANDARD P RACTICE IS BEING REVISED TO INSURE SURVEILLANCE INSTRUCTIONS ARE PERFORM ED FOLLOWING MAINTENANCE. THE VALVE WAS SATISFACTORILY TESTED ON 11/20/
THE FAILURE TO PERFORM THE TESTING AS REQUIRED BY SURVEILLANCE REQUIREME NT IS ATTRIBUTED TO AN INADEQUATE PROCEDURE. THE APPROPRIATE STANDARD P RACTICE IS BEING REVISED TO INSURE SURVEILLANCE INSTRUCTIONS ARE PERFORM ED FOLLOWING MAINTENANCE. THE VALVE WAS SATISFACTORILY TESTED ON 11/20/
80.
80.
SEQUOYAH-1                             05000327     011481     AT 1005 (C) ON 1/14/81, VITAL INVERTER 2-II FAILED RENDERING VITAL INSTR ONSITE POWER SYSTEM + CONTROL       81-005/03L-0   020581     UMENT POWER BOARD 2-II INOPERATIVE. THERE WAS NO EFFECT CN PUBLIC HEALT GENERATORS                             036139     30-DAY     H OR SAFETY. PREVIOUS OCCURRENCES TOTAL OCCURRENCES FOR ALL EIGH INVERTER                                                   T INVERTERS.
SEQUOYAH-1 05000327 011481 AT 1005 (C) ON 1/14/81, VITAL INVERTER 2-II FAILED RENDERING VITAL INSTR ONSITE POWER SYSTEM + CONTROL 81-005/03L-0 020581 UMENT POWER BOARD 2-II INOPERATIVE. THERE WAS NO EFFECT CN PUBLIC HEALT GENERATORS 036139 30-DAY H OR SAFETY.
COMPONENT FAILURE ELECTRICAL STATIC FR0 DUCTS THE FOLLOWING TWO COMPONENTS FAILED WHILE IN SERVICE: C1A CAPACITOR IN T-HE A10 POWER SUPPLY AND THE RB-8 CONTROL-CARD. THESE COMPONENTS WERE RF-PLACED AND THE INVERTER WAS RETURNED TO SERVICE AT 1755 (C) ON 1/14/81.
PREVIOUS OCCURRENCES TOTAL OCCURRENCES FOR ALL EIGH INVERTER T INVERTERS.
COMPONENT FAILURE ELECTRICAL STATIC FR0 DUCTS THE FOLLOWING TWO COMPONENTS FAILED WHILE IN SERVICE: C1A CAPACITOR IN T-HE A10 POWER SUPPLY AND THE RB-8 CONTROL-CARD.
THESE COMPONENTS WERE RF-PLACED AND THE INVERTER WAS RETURNED TO SERVICE AT 1755 (C) ON 1/14/81.
PREPARATIONS ARE IN PROGRESS TO REPLACE THIS INVERTER WITH A NEW INVERT ER IDENTICAL TO THOSE INSTALLED ON UNIT 1.
PREPARATIONS ARE IN PROGRESS TO REPLACE THIS INVERTER WITH A NEW INVERT ER IDENTICAL TO THOSE INSTALLED ON UNIT 1.
SEQUDYAH-1                             05000327     011681     AT 1035 CST WITH UNIT 1 AT 50% RTP, THE LEVEL CHANNEL FOR STEAM GENERATO REACTOR TRIP SYSTEMS               81-007/03L-0   020581     R 33 (L-3-97) UAS DECLARED INOPERABLE WHEN THE TRIP BISTABLE (1-LS-3-97F INSTRUMENTATION + CONTROLS             036077     30-DAY     ) FAILED TO DEENERGIZE DURING THE PERFORMANCE OF THE SCHEDULED FUNCTIONA SWITCH                                                       L TEST. THE BISTABLE WAS MANUALLY TRIPPED IN ACCORDANCE WITH ACTION STA COMPONENT FAILURE                                             TEMENT 7 0F LCO 3.3.1.1     THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY-ELECTRONIC                                                 . NO PREVIOUS OCCURRENCES.
SEQUDYAH-1 05000327 011681 AT 1035 CST WITH UNIT 1 AT 50% RTP, THE LEVEL CHANNEL FOR STEAM GENERATO REACTOR TRIP SYSTEMS 81-007/03L-0 020581 R 33 (L-3-97) UAS DECLARED INOPERABLE WHEN THE TRIP BISTABLE (1-LS-3-97F INSTRUMENTATION + CONTROLS 036077 30-DAY
) FAILED TO DEENERGIZE DURING THE PERFORMANCE OF THE SCHEDULED FUNCTIONA SWITCH L TEST.
THE BISTABLE WAS MANUALLY TRIPPED IN ACCORDANCE WITH ACTION STA COMPONENT FAILURE TEMENT 7 0F LCO 3.3.1.1 THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY-ELECTRONIC
. NO PREVIOUS OCCURRENCES.
FOXBORO CO., THE THE LEVEL CHANNEL FAILED BECAUSE'THE BISTABLE WOULD NOT DEENERGIZE. THE MODULE WAS REPLACED, CALIBRATED, AND RETURNED TO SERVICE. SINCE THIS I S THE FIRST OCCURRENCE OF THIS TYPE, THE FAILURE IS NOT CONSIDERED TO BE-A GENERIC PROBLEM.
FOXBORO CO., THE THE LEVEL CHANNEL FAILED BECAUSE'THE BISTABLE WOULD NOT DEENERGIZE. THE MODULE WAS REPLACED, CALIBRATED, AND RETURNED TO SERVICE. SINCE THIS I S THE FIRST OCCURRENCE OF THIS TYPE, THE FAILURE IS NOT CONSIDERED TO BE-A GENERIC PROBLEM.


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  ' MAR 26 1981                                                   LER MONTHLY REPORT SORTED BY FACILITY                                               PAGE 82 PROCESSED DURING MARCH. 1931 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /         DOCKET NO./       EVENT DATE/
' MAR 26 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 82 PROCESSED DURING MARCH. 1931 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                 REPORT DATE/                                     EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO.     REPORT TYPE                                     CAUSE DESCRIPTION SEQUDYAH-1                                     05000327       011681 CNTNMNT HEAT REMOV SYS + CONT              81-008/03L-0      001081      UNIT IN MODE 1 AT 50% REACTOR POWER. DURING ROUTINE INSPECTION OF THE IC PENETRATIONS.PRIMRY CONTAINMNT                  036140                    E CONDENSER. THREE INTERMEDIATE DECK DOORS WERE FOUND FROZEN CLOSED.             TH 30-DAY     E DUORS ARE LOCATED UNDER AIR HANDLING UNITS 6A. 8A. AND 8B. LCO 3.6.5.
EVENT DATE/
,    OTHER                                                                     3 MAS ENTEPED. THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFETY. PREVI COMPONENT FAILURE                                                         005 OCCURRENCES - 4 (REFERENCES SQRO-50-327/80-170 80-203. 80-205. AND ELECTRICAL                                                               81-002).
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION i
SEQUDYAH-1 05000327 011681 UNIT IN MODE 1 AT 50% REACTOR POWER. DURING ROUTINE INSPECTION OF THE IC CNTNMNT HEAT REMOV SYS + CONT 81-008/03L-0 001081 E CONDENSER. THREE INTERMEDIATE DECK DOORS WERE FOUND FROZEN CLOSED.
TH PENETRATIONS.PRIMRY CONTAINMNT 036140 30-DAY E DUORS ARE LOCATED UNDER AIR HANDLING UNITS 6A. 8A. AND 8B.
LCO 3.6.5.
OTHER 3 MAS ENTEPED.
THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFETY.
PREVI COMPONENT FAILURE 005 OCCURRENCES - 4 (REFERENCES SQRO-50-327/80-170 80-203. 80-205. AND ELECTRICAL 81-002).
WESTINGHOUSE ELECTRIC CORP.
WESTINGHOUSE ELECTRIC CORP.
WATER FR02E IN THE AIR HANDLING UNITS DEFROST DRAIN LINES CAUSING THE DR AIN LINES TO RUPTURE. THE WATER FROZE IN THE DRAIN LINES DUE TO A FUSE FAILURE IN THE CONTROLLER FOR ONE SECTION OF HEAT TAPE. DURING SUBSEQUE NT DEFROST CYCLES WATER SPILLED FROM DRAIN LINES AND FROZE ON DOORS.             IC SEQUDYAM-1 E WAS REMOVED FROM DOORS WITHIN 24 HOURS.
WATER FR02E IN THE AIR HANDLING UNITS DEFROST DRAIN LINES CAUSING THE DR AIN LINES TO RUPTURE.
05000327       012781     WITH UNIT 1 IN MODE 3 AND RCS AT 360 F AND 1500 PSIG. CONTAINMEhT SUMP L ENGNRD SAFETY FEATR INSTR SYS               81-009/03L-0       022481     EVEL LOOP L-63-177 WAS DECL ARED INOPERABLE AFTER A CHANNEL CHECK MAS PER INSTRUMENTATION + CONTROLS                     036252         30-DAY     FORMED.
THE WATER FROZE IN THE DRAIN LINES DUE TO A FUSE FAILURE IN THE CONTROLLER FOR ONE SECTION OF HEAT TAPE.
TRANSMITTER                                                                          THE ASSOCIATED BISTABLE WAS PLACED IN THE BYPASS MODE IN ACCORD CCMPONENT FAILURE ANCE WITH ACTION STATEMENT 18 0F LCO 3.3.2.1. THERE WAS NO EFFECT ON PU INSTRUMENT                                                                BLIC NEALTH OR SAFETY. NO PREVIOUS OCCURRENCES.
DURING SUBSEQUE NT DEFROST CYCLES WATER SPILLED FROM DRAIN LINES AND FROZE ON DOORS.
BARTON INSTRU CD.. DIV 0F ITT THE CAUSE FOR THE CALIBRATION DRIFT WAS DIAGNOSED AS A PROBLEM WITH THE LEVEL TRANSMITTER. THE LEVEL TRANSMITTER HAS BEEN REPLACED AND IS BEING TESTED. FINAL TESTING AND ADDITIONAL REPAIR WORK. IF NEEDED. ARE SCHED ULED TO BE COMPLETED DURING THE UNIT DUTtGE NOW IN PROGRESS.
IC E WAS REMOVED FROM DOORS WITHIN 24 HOURS.
2EQUOYAH-t                                     05000327         012881     AT 1515 (C) ON 1/28/81, MODE 1 NOTIFICATION WAS RECEIVED THAT DURING TH COOL SYS FOR REAC AUX + CONT               81-010/ 0 3 L-0   021381 HANGERS. SUPPORTS. SHOCK SUPPRSS                036141        30-DAY E IEB 79-14 REVIEW A WEIGHT DISCREPANCY (180 LB. LIGHT) WAS DISCOVERED W SUPPORTS HICH ALTERED SUPPORT DESIGN REQUIREMENTS. TRAIN "A" 0F COMPONENT C00LIN DESIGN / FABRICATION ERROR                                                G WATER WAS DECLARED INOPERABLE THUS ENTERING LCO 3.7.3.1 ACTION STATENE HT. THERE WAS NO EFFECT TO PUBLIC HEALTH OR SAFETY. PREVIOUS OCCURRENC DESIGN                                                                   ES - HONE.
SEQUDYAM-1 05000327 012781 WITH UNIT 1 IN MODE 3 AND RCS AT 360 F AND 1500 PSIG. CONTAINMEhT SUMP L ENGNRD SAFETY FEATR INSTR SYS 81-009/03L-0 022481 EVEL LOOP L-63-177 WAS DECL ARED INOPERABLE AFTER A CHANNEL CHECK MAS PER INSTRUMENTATION + CONTROLS 036252 30-DAY FORMED.
TENNESSEE VALLEY AUTHORITY INCORRECT WEIGHTS WERE USED IN THE COMPUTER ANALYSIS WHICH COULD LEAD TO A LINE BREAK DOWN STREAN OF VALVE PCV-70-90 CURING DESIGN BASE EARTHQUA KE. TWO SUPPORTS WERE MODIFIED FOR INTERIM USE UNTIL THE FIRST REFUELIN G OUTAGE WHEN REDESIGNED SUPPORTS WILL BE INSTALLED. TRAIN "A" 0F COMPO ST. LUCIE-1                                                                  NENT COOLING WATER DECLARED OPERABLE AT 0811 (C) ON 1/30/81.
THE ASSOCIATED BISTABLE WAS PLACED IN THE BYPASS MODE IN ACCORD TRANSMITTER ANCE WITH ACTION STATEMENT 18 0F LCO 3.3.2.1.
05000335         022280     AT FULL POWER "B" DIESEL GENERATOR FAILED TO REACH RATED SPEED DURING OP EMERG GENERATOR SYS + 00NTROLS             80-012/03X-1       011481     ERATIONAL CHECK.. ENGINES WERE TRIPPED 1 FOUND ENGINE INJECTOR LINKAGES S ENGINES, INTERNAL COMBU2 TION                   030829-       OTHER       TICKY. INJECTOR CONTROL LEVERS-MANUALLY EXERCISED AND ENGINES RETESTED SUBCOMPONENT NOT APPLICABLE                                             ' SATISFACTORILY. NO ADDITIONAL PROBLEMS NOTED.             PREVIOUS ENGINE STARTING COMPONENT FAILURE                                                           FAILURES REPORTED IN LER'S 76-21 76-44. 77-3, 77-15. AND 79-28. -HOWEV METALLURGICAL                                                             ER'LER 77-3 IS THE ONLY RELATED FAILURE.
THERE WAS NO EFFECT ON PU CCMPONENT FAILURE BLIC NEALTH OR SAFETY. NO PREVIOUS OCCURRENCES.
GENERAL MOTORS PROBLEM WAS FIRST REPORTED 10 BE STICKING INJECTOR LINKAGES 8 SOLUTION W AS TO BE A MAINTENANCE ITEM TO PERIODICALLY LUBRICATE THEM. DETAILED EV ALUATION HAS SHOUN, HOWEVER. THAT ALL CRITICAL LINKAGE BEARINGS ALREADY RECEIVE ADEQUATE LUBRICATION 1 ITEM WAS DELETED. CAUSE OF ORIGINAL EVEN T IS AS YET UNIDENTIFIED. BUT EVENT HAS NOT REPEATED.
INSTRUMENT BARTON INSTRU CD.. DIV 0F ITT THE CAUSE FOR THE CALIBRATION DRIFT WAS DIAGNOSED AS A PROBLEM WITH THE LEVEL TRANSMITTER. THE LEVEL TRANSMITTER HAS BEEN REPLACED AND IS BEING TESTED.
FINAL TESTING AND ADDITIONAL REPAIR WORK. IF NEEDED. ARE SCHED ULED TO BE COMPLETED DURING THE UNIT DUTtGE NOW IN PROGRESS.
2EQUOYAH-t 05000327 012881 AT 1515 (C) ON 1/28/81, MODE 1 NOTIFICATION WAS RECEIVED THAT DURING TH COOL SYS FOR REAC AUX + CONT 81-010/ 0 3 L-0 021381 E IEB 79-14 REVIEW A WEIGHT DISCREPANCY (180 LB. LIGHT) WAS DISCOVERED W HANGERS. SUPPORTS. SHOCK SUPPRSS 036141 30-DAY HICH ALTERED SUPPORT DESIGN REQUIREMENTS. TRAIN "A" 0F COMPONENT C00LIN SUPPORTS G WATER WAS DECLARED INOPERABLE THUS ENTERING LCO 3.7.3.1 ACTION STATENE DESIGN / FABRICATION ERROR HT.
THERE WAS NO EFFECT TO PUBLIC HEALTH OR SAFETY.
PREVIOUS OCCURRENC DESIGN ES - HONE.
TENNESSEE VALLEY AUTHORITY INCORRECT WEIGHTS WERE USED IN THE COMPUTER ANALYSIS WHICH COULD LEAD TO A LINE BREAK DOWN STREAN OF VALVE PCV-70-90 CURING DESIGN BASE EARTHQUA KE.
TWO SUPPORTS WERE MODIFIED FOR INTERIM USE UNTIL THE FIRST REFUELIN G OUTAGE WHEN REDESIGNED SUPPORTS WILL BE INSTALLED. TRAIN "A" 0F COMPO NENT COOLING WATER DECLARED OPERABLE AT 0811 (C) ON 1/30/81.
ST. LUCIE-1 05000335 022280 AT FULL POWER "B" DIESEL GENERATOR FAILED TO REACH RATED SPEED DURING OP EMERG GENERATOR SYS + 00NTROLS 80-012/03X-1 011481 ERATIONAL CHECK.. ENGINES WERE TRIPPED 1 FOUND ENGINE INJECTOR LINKAGES S ENGINES, INTERNAL COMBU2 TION 030829-OTHER TICKY.
INJECTOR CONTROL LEVERS-MANUALLY EXERCISED AND ENGINES RETESTED SUBCOMPONENT NOT APPLICABLE
' SATISFACTORILY. NO ADDITIONAL PROBLEMS NOTED.
PREVIOUS ENGINE STARTING COMPONENT FAILURE FAILURES REPORTED IN LER'S 76-21 76-44. 77-3, 77-15. AND 79-28. -HOWEV METALLURGICAL ER'LER 77-3 IS THE ONLY RELATED FAILURE.
GENERAL MOTORS PROBLEM WAS FIRST REPORTED 10 BE STICKING INJECTOR LINKAGES 8 SOLUTION W AS TO BE A MAINTENANCE ITEM TO PERIODICALLY LUBRICATE THEM.
DETAILED EV ALUATION HAS SHOUN, HOWEVER. THAT ALL CRITICAL LINKAGE BEARINGS ALREADY RECEIVE ADEQUATE LUBRICATION 1 ITEM WAS DELETED. CAUSE OF ORIGINAL EVEN T IS AS YET UNIDENTIFIED. BUT EVENT HAS NOT REPEATED.


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 83 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 83 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SbBCODE/CAUSE CODE / LER NO./       REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                                 CAUSE DESCRIPTION S?. LUCIE-1                             05000335     113080     DURING NORMAL FULL POWER OPERATION IT WAS DISCOVERED THAT SOME REACTOR T REACTOR TRIP SYSTEMS                 80-067/01X-1   011681     RIP BREAKERS WOULD NOT TRIP ON UNDERVOLTAGE (UV) AS EXPECTED. THE TRIP CIRCUIT CLOSERS / INTERRUPTERS         033466     OTHER     BREAKERS HAVE REDUNDANT UV AND SHUNT TRIP DEVICES. ONE DEVICE WOULD NOT CIRCUIT BREAKER                                                 TRIP AND TWO OTHERS TRIPPED SLUGGISHLY. THE ABILITY OF THE REACTOR TO COMPONENT FAILURE                                             TRIP EITHER MANUALLY OR UPON RPS SIGNAL WAS NOT COMPROMISED AS SHOWN BY ELECTRICAL                                                   AN UNRELATED PLANT TRIP WHICH OCCURRED DURING THIS INVESTIGATION. THIS GENERAL ELECTRIC CO.                                           IS BEING REPORTED PER T.S. 6.9.1.8.I. THIS IS THE IST LER OF THIS TYPE.
EVENT DATE/
THE IHOPERABLE UV DEVICE ARMATURE WAS REALIGNED AND ALL 7 OTHER UV DEVIC ES WERE MANUALLY EXERCISED, LUBRICATED, AND TESTFD SATISFACTORILY. THE UV AND SHUNT TRIP DEVICES WERE PREVIOUSLY TESTED SIMULTANEOUSLY EVERY MO NIH. A NEW PREVENTATIVE MAINTENANCE PROGRAM HAS BEEN INITIATED TO CHECK THE UV COILS INDEPENDENTLY MONTHLY. THE BREAKERS ARE GE TYPE AK-2A.
COMPONENT SbBCODE/CAUSE CODE / LER NO./
ST. LUCIE-1                             05000335     120180     AT FULL POWER IT BECAME NECESSARY TO ISOLATE "B" CCW HEAT EXCHANGER TO R COOL SYS FOR REAC AUX + CONT         80-066/03L-0   123180     EPAIR A LEAK IN ICW DISCHARGE PIPING FROM "B" CCW HEAT EXCHANGER. LEAKI PIPES. FITTINGS                         033730     30-DAY     NG ELBOW REPAIRED AND TWO INDEPENDENT CCW LOOPS REESTABLISHED IN 48 HOUR 16 INCHES AND LARGER                                         S (WITHIH 72 HOURS ALLOWED BY T.S. 3.7 3.1.). HEAT REMOVAL CAPABILITY 0 COMPONENT FAILURE                                             F HEAT EXCHANGER NEVER IMPAIRED. TWO INDEPENDENT LOOPS COULD HAVE BEEN.
REPORT DATE/
NATURAL END OF LIFE                                           ESTABLISHED AT ANY TIME.
EVENT DESCRIPTION /
ITEM NOT APPLICABLE THE ICW PIPING SHOWED NORMAL SIGNS OF WEAR AND CORROSIVE ATTACK AT THE E LBOW. IT WAS DETERMINED PRUDENT TO ISOLATE THE HEAT EXCHANGER AND REPAI R THE LEAK.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
ST. LUCIE-1                             05000335     120380     AT NORMAL FULL POWER CONTAINMENT RADIATION CHANNEL MD FAILED HIGH. CHAN ENGNRD SAFETY FEATR INSTR SYS       80-068/03L-0   123180     NEL MD IMMEDIATELY BYPASSED AND TROUBLESHOOTING COMMENCED. WHEN IT MAS           ,
REPORT TYPE CAUSE DESCRIPTION S?. LUCIE-1 05000335 113080 DURING NORMAL FULL POWER OPERATION IT WAS DISCOVERED THAT SOME REACTOR T REACTOR TRIP SYSTEMS 80-067/01X-1 011681 RIP BREAKERS WOULD NOT TRIP ON UNDERVOLTAGE (UV) AS EXPECTED. THE TRIP CIRCUIT CLOSERS / INTERRUPTERS 033466 OTHER BREAKERS HAVE REDUNDANT UV AND SHUNT TRIP DEVICES. ONE DEVICE WOULD NOT CIRCUIT BREAKER TRIP AND TWO OTHERS TRIPPED SLUGGISHLY. THE ABILITY OF THE REACTOR TO COMPONENT FAILURE TRIP EITHER MANUALLY OR UPON RPS SIGNAL WAS NOT COMPROMISED AS SHOWN BY ELECTRICAL AN UNRELATED PLANT TRIP WHICH OCCURRED DURING THIS INVESTIGATION. THIS GENERAL ELECTRIC CO.
INSTRUMENTATION + CONTROLS             033731     30-DAY     DETERMINED DETECTOR HAD FAILED, CHANNEL MD RADIATION WAS TRIPPED PER T.S         #
IS BEING REPORTED PER T.S.
SENSOR / DETECTOR / ELEMENT                                   . 3.3.2.1     THIS OCCURRED LESS THAN 10 HOURS AFTER CHANNEL HAD FAILED.
6.9.1.8.I.
COMPONENT FAILURE                                             NO SAFETY LIMITS WERE EXCEEDED. PREVIOUS LER'S OF THIS NATURE ARE 80-37 INSTRUMENT                                                   ,  78-04 AND 76-05.
THIS IS THE IST LER OF THIS TYPE.
THE IHOPERABLE UV DEVICE ARMATURE WAS REALIGNED AND ALL 7 OTHER UV DEVIC ES WERE MANUALLY EXERCISED, LUBRICATED, AND TESTFD SATISFACTORILY. THE UV AND SHUNT TRIP DEVICES WERE PREVIOUSLY TESTED SIMULTANEOUSLY EVERY MO NIH.
A NEW PREVENTATIVE MAINTENANCE PROGRAM HAS BEEN INITIATED TO CHECK THE UV COILS INDEPENDENTLY MONTHLY. THE BREAKERS ARE GE TYPE AK-2A.
ST. LUCIE-1 05000335 120180 AT FULL POWER IT BECAME NECESSARY TO ISOLATE "B" CCW HEAT EXCHANGER TO R COOL SYS FOR REAC AUX + CONT 80-066/03L-0 123180 EPAIR A LEAK IN ICW DISCHARGE PIPING FROM "B" CCW HEAT EXCHANGER.
LEAKI PIPES. FITTINGS 033730 30-DAY NG ELBOW REPAIRED AND TWO INDEPENDENT CCW LOOPS REESTABLISHED IN 48 HOUR 16 INCHES AND LARGER S (WITHIH 72 HOURS ALLOWED BY T.S.
3.7 3.1.).
HEAT REMOVAL CAPABILITY 0 COMPONENT FAILURE F HEAT EXCHANGER NEVER IMPAIRED. TWO INDEPENDENT LOOPS COULD HAVE BEEN.
NATURAL END OF LIFE ESTABLISHED AT ANY TIME.
ITEM NOT APPLICABLE THE ICW PIPING SHOWED NORMAL SIGNS OF WEAR AND CORROSIVE ATTACK AT THE E LBOW.
IT WAS DETERMINED PRUDENT TO ISOLATE THE HEAT EXCHANGER AND REPAI R THE LEAK.
ST. LUCIE-1 05000335 120380 AT NORMAL FULL POWER CONTAINMENT RADIATION CHANNEL MD FAILED HIGH.
CHAN ENGNRD SAFETY FEATR INSTR SYS 80-068/03L-0 123180 NEL MD IMMEDIATELY BYPASSED AND TROUBLESHOOTING COMMENCED. WHEN IT MAS INSTRUMENTATION + CONTROLS 033731 30-DAY DETERMINED DETECTOR HAD FAILED, CHANNEL MD RADIATION WAS TRIPPED PER T.S SENSOR / DETECTOR / ELEMENT
. 3.3.2.1 THIS OCCURRED LESS THAN 10 HOURS AFTER CHANNEL HAD FAILED.
COMPONENT FAILURE NO SAFETY LIMITS WERE EXCEEDED. PREVIOUS LER'S OF THIS NATURE ARE 80-37 INSTRUMENT 78-04 AND 76-05.
VICTOREEN INSTRUMENT DIV.
VICTOREEN INSTRUMENT DIV.
RADIATION DETECTOR IS IN A HIGH RADIATION FIELD DURING NORMAL PLANT OPER ATION AND CANNOT BE REPLACED WITHOUT A PLANT OUTAGE.       DETECTOR WILL BE R EPLACED DURING AN UPCOMING PLANT OUTAGE.       REPLACEMENT DETECTOR OBTAINED AND CALIBRATED. CHANNEL MD CIS RADIATION WILL BE MAINTAINED IN ACCORDAN CE WITH T.S. 3.3.2.1 UNTIL DETECTOR REPLACED.
RADIATION DETECTOR IS IN A HIGH RADIATION FIELD DURING NORMAL PLANT OPER ATION AND CANNOT BE REPLACED WITHOUT A PLANT OUTAGE.
ST. LUCIE-1                             05000335     121880     DURING NORMAL OPERATION. A LEAK TEST SURVEILLANCE ON CONTAINMENT PERSONN REACTOR CONTAINMENT SYSTEMS         A0-062/03L-0   011681     EL AIR LOCK OUTER DOOR INTERSPACE WAS MISSED WHILE AUTOMATIC TESTER FOR PENETRATIONS.PRIMRY CONTAINMNT         033729     30-DAY       REPAIR. CONTAINMENT ENTRY WAS MADE BUT TEST NOT PERFORMED UNTIL ENTRY PERSONNEL ACCESS                                             PERSONNEL EXITED CONTAINMENT CONTRARY TO T/S 4.6.1.3. CONTAINMENT INTEG PERSONNEL ER"ao                                               RITY MAINTAINED. HINTH OCCURRENCE OF MISSED SURVEILLANCE, SECOND THIS T LICENSED & if JIOR OPERATORS                                 YPE.
DETECTOR WILL BE R EPLACED DURING AN UPCOMING PLANT OUTAGE.
REPLACEMENT DETECTOR OBTAINED AND CALIBRATED. CHANNEL MD CIS RADIATION WILL BE MAINTAINED IN ACCORDAN CE WITH T.S.
3.3.2.1 UNTIL DETECTOR REPLACED.
ST. LUCIE-1 05000335 121880 DURING NORMAL OPERATION. A LEAK TEST SURVEILLANCE ON CONTAINMENT PERSONN REACTOR CONTAINMENT SYSTEMS A0-062/03L-0 011681 EL AIR LOCK OUTER DOOR INTERSPACE WAS MISSED WHILE AUTOMATIC TESTER FOR PENETRATIONS.PRIMRY CONTAINMNT 033729 30-DAY REPAIR.
CONTAINMENT ENTRY WAS MADE BUT TEST NOT PERFORMED UNTIL ENTRY PERSONNEL ACCESS PERSONNEL EXITED CONTAINMENT CONTRARY TO T/S 4.6.1.3.
CONTAINMENT INTEG PERSONNEL ER"ao RITY MAINTAINED. HINTH OCCURRENCE OF MISSED SURVEILLANCE, SECOND THIS T LICENSED & if JIOR OPERATORS YPE.
ITEI1 NOT APPLICABLE LEAK TESTS BEING PERFORMED MANUALLY WITH A PORTABLE TESTER BUT ENTRY PER SONNEL NOT AWARE MANUAL TEST NECESSARY. TEST PERFORMED SATISFACTORILY W-ITHIN 1 1/2 HOURS OF ENTRY AND CLEARANCE TAG PLACED ON OUTER DOOR TO PRE VENT A REOCCURRENCE. AUTOMATIC TESTER REPAIRED AND FUNCTIONAL.
ITEI1 NOT APPLICABLE LEAK TESTS BEING PERFORMED MANUALLY WITH A PORTABLE TESTER BUT ENTRY PER SONNEL NOT AWARE MANUAL TEST NECESSARY. TEST PERFORMED SATISFACTORILY W-ITHIN 1 1/2 HOURS OF ENTRY AND CLEARANCE TAG PLACED ON OUTER DOOR TO PRE VENT A REOCCURRENCE. AUTOMATIC TESTER REPAIRED AND FUNCTIONAL.


MAR 26, 1981                                                                                                                                               LER MONTHLY REPORT SORTED BY FACILITY                                                                                               'PAGE 84 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                                                         DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                                                 REPORT DATE/                                                     EVENT DESCRIPTION /
'PAGE 84 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
CAUSE SUBCODE/ MANUFACTURER                                                                                               CONTROL NO. REPORT TYPE                                                     CAUSE DESCRIPTION ST. LUCIE-1                                                                                                                                   05000335     122680       DG?ING NORMAL FULL POWER OPERATION, A 10% STEAM BYPASS VALVE (PCV-8005).
DOCKET NO./
TURBINE BYPASS SYS + CONT                                                                                                                 80-069/03L-0   012681         FAltED OPEN CAUSING REACTOR POWER TO INCREASE TO 101.5%, 103.5% AS MEAS INSTRUMENTATION + CONTROLS                                                                                                                   033732     30-DAY       URED FY NUCLEAR, DELTA T, & CALORIMETRIC POWER RESPECTIVELY. TURBINE LO OTHER COMPONENT FAILURE AD WAS DECREASED 1 THE VALVE WAS CLOSED LOCALLY BY FAILING THE POSITIONE R.       THIS CAUSED TC TO MOMENTARILY RISE TO 542.2 DEG. F. WHICH IS ABOVE T INSTRUMENT                                                                                                                                                     HE TECH. SPEC. 3.2.5 LIMIT OF 542 DEG. F. THIS IS THE FIRST OCCURRENCE-ROCHESTER INSTRU. SYSTEMS INC.                                                                                                                                         OF THIS TYPE, AND THE SEVENTH INVOLVING TC GREATER THAN 542 DEG. F.
EVENT DATE/
THE VALVE OPENED DUE TO THE FAILURE OF A VOLTAGE TO CURRENT CONVERTER IN THE STEAM BYPASS CONTROLLER CABINET.                             THE VALVE WAS ISOLATED AND THE PL ANT WAS STABILIZED WITH NO FURTHER PROBLEMS. THE CONVERT 0R WAS REPLACED AND TESTED. THE VALVE WAS THEN RETURNED TO SERVICE.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
ST. LUC 1E-1                                                                                                                                   05000335     123180       DURING NORMAL OPERATION, AT 100% POWER. THE V0tUME CONTROL TANK (VCT) WA CHEM, VOL CONT + LIQ POISN SYS                                                                                                             80-071/03L-0   012931       S INADVERTENTLY DILUTED, LEADING TO REACTOR COOLANT SYSTEM DILUTION.
REPORT DATE/
VALVES                                                                                                                                                                                                                                                                                                 IN 033747     30-DAY       DICATED REACTOR POWER INCREASED OVER ABOUT 15 MINUTES, PEAKING AT 102%.
EVENT DESCRIPTION /
OTHER                                                                                                                                                           TC ALSO INCREASED DURING THE TRANSIENT REACHING 542.5 DEG. F. (THE STEA COMPONENT FAILURE                                                                                                                                                     DY STATE LIMIT IS 542 DEG.                       F.). ACTION PER TECH. SPEC. 3.2.5 WAS TAKEN MECHANICAL                                                                                                                                                       AND PCWER AND TC WERE REDUCED. THIS IS THE FIRST EVENT OF THIS TYPE.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION ST. LUCIE-1 05000335 122680 DG?ING NORMAL FULL POWER OPERATION, A 10% STEAM BYPASS VALVE (PCV-8005).
TURBINE BYPASS SYS + CONT 80-069/03L-0 012681 FAltED OPEN CAUSING REACTOR POWER TO INCREASE TO 101.5%, 103.5% AS MEAS INSTRUMENTATION + CONTROLS 033732 30-DAY URED FY NUCLEAR, DELTA T,
& CALORIMETRIC POWER RESPECTIVELY. TURBINE LO OTHER AD WAS DECREASED 1 THE VALVE WAS CLOSED LOCALLY BY FAILING THE POSITIONE COMPONENT FAILURE R.
THIS CAUSED TC TO MOMENTARILY RISE TO 542.2 DEG. F.
WHICH IS ABOVE T INSTRUMENT HE TECH. SPEC. 3.2.5 LIMIT OF 542 DEG. F.
THIS IS THE FIRST OCCURRENCE-ROCHESTER INSTRU. SYSTEMS INC.
OF THIS TYPE, AND THE SEVENTH INVOLVING TC GREATER THAN 542 DEG.
F.
THE VALVE OPENED DUE TO THE FAILURE OF A VOLTAGE TO CURRENT CONVERTER IN THE STEAM BYPASS CONTROLLER CABINET.
THE VALVE WAS ISOLATED AND THE PL ANT WAS STABILIZED WITH NO FURTHER PROBLEMS. THE CONVERT 0R WAS REPLACED AND TESTED. THE VALVE WAS THEN RETURNED TO SERVICE.
ST. LUC 1E-1 05000335 123180 DURING NORMAL OPERATION, AT 100% POWER. THE V0tUME CONTROL TANK (VCT) WA CHEM, VOL CONT + LIQ POISN SYS 80-071/03L-0 012931 S INADVERTENTLY DILUTED, LEADING TO REACTOR COOLANT SYSTEM DILUTION.
IN VALVES 033747 30-DAY DICATED REACTOR POWER INCREASED OVER ABOUT 15 MINUTES, PEAKING AT 102%.
OTHER TC ALSO INCREASED DURING THE TRANSIENT REACHING 542.5 DEG. F.
(THE STEA COMPONENT FAILURE DY STATE LIMIT IS 542 DEG.
F.).
ACTION PER TECH. SPEC. 3.2.5 WAS TAKEN MECHANICAL AND PCWER AND TC WERE REDUCED. THIS IS THE FIRST EVENT OF THIS TYPE.
CROSBY VALVE & GAGE CO.
CROSBY VALVE & GAGE CO.
WHILE ADDING MAKEUP AND ADJUSTING BORON CONCENTRATION IN THE VCT, A RELI EF VALVE (V2173, CROSBY, STYLE JR-WR-5) ON THE ACID PUMP DISCHARGE FAILE D. RETURNING BORIC ACID TO THE SOURCE TANK. FLOW INDICATION, UPSTREAM F ROM THE RELIEF, WAS NORMAL.                       THE RELIEF VALVE WAS EXERCISED AND LATER RE PAIRED.
WHILE ADDING MAKEUP AND ADJUSTING BORON CONCENTRATION IN THE VCT, A RELI EF VALVE (V2173, CROSBY, STYLE JR-WR-5) ON THE ACID PUMP DISCHARGE FAILE D. RETURNING BORIC ACID TO THE SOURCE TANK.
ST. LUCIE-1                                                                                                                                   05000335     012381       DURING NORMAL FULL POWER OPERATION, OUR RE-EVALUATION OF PLANT MASONRY W SYSTEM CODE NOT APPLICABLE                                                                                                                 81-003/01T-0   020681       ALLS SHOWED THAT SEVERAL MALLS DID HOT MEET THE CRITERIA 0F IE BULLETIN COMPONENT CODE NOT APPLICABLE                                                                                                                 036142     2-WEEK       80-11,         14 WALLS WERE MISSING THE CLIP ANGLES REQUIRED BY THE DESIGN, 3 SUBCOMPONENT NOT APPLICABLE                                                                                                                                     WALLS REQUIRED CLIP ANGLE REINFORCEMENT, 3 WALLS REQUIRED REINFORCEMENT, DESIGN / FABRICATION ERROR                                                                                                                                             AND ONE WALL REQUIRED ADDING CLIP ANGLES THAT WERE NOT INCLUDED IN THE CONSTRUCTION / INSTALLATION                                                                                                                                     ORIGINAL DESIGN. CONSIDERING IE BULLETIN 79-14, THIS IS THE SECOND EVEN ITEM NOT APPLICABLE                                                                                                                                                   T OF THIS TYPE.
FLOW INDICATION, UPSTREAM F ROM THE RELIEF, WAS NORMAL.
EVALUATIONS WERE PERFORMED TO JUSTIFY OPERATIONS, PRIORITIES WERE ASSIGN ED AND ALL IMMEDIATELY REQUIRED MODIFICATIONS WERE COMPLETED BY 2/5/81 ALL WALLS, THE FAILURE OF WHICH UNDER POSTULATED LOADS AND LOAD COMBINA TION COULD AFFECT SAFETY RELATED SYS, WERE REPAIRED. DETAILS ON FINDINGS 8 CORRECTIVE ACTION WILL BE INCLUDED IN OUR FINAL REPORT BULLETIN 80-11 ST. LUCIE-1                                                                                                                                   05006335     012781       DURING NORMAL FULL POWER OPERATION, NOTIFICATION WAS RECEIVED FROM GE (S OTHR INST SYS REQD FOR SAFETY                                                                                                             81-005/09T-0   020381       ERVICE ADVISORY BULLETIN S.A. 721-PSL-152.2) THAT THEIR TYPE HFA RELAY C CIRCUIT CLOSERS / INTERRUPTERS                                                                                                               036143     2-WEEK       OIL SPOOLS COULD CRACK 8 FAIL IN SUCH A MANNER AS TO PREVENT RELAY OPER.
THE RELIEF VALVE WAS EXERCISED AND LATER RE PAIRED.
CONTACTOR                                                                                                                                                       SINCE THESE RELAYS ARE UTILIZED IN SOME SAFEGUARD SYS THIS DEFECT IS BE
ST. LUCIE-1 05000335 012381 DURING NORMAL FULL POWER OPERATION, OUR RE-EVALUATION OF PLANT MASONRY W SYSTEM CODE NOT APPLICABLE 81-003/01T-0 020681 ALLS SHOWED THAT SEVERAL MALLS DID HOT MEET THE CRITERIA 0F IE BULLETIN COMPONENT CODE NOT APPLICABLE 036142 2-WEEK 80-11, 14 WALLS WERE MISSING THE CLIP ANGLES REQUIRED BY THE DESIGN, 3 SUBCOMPONENT NOT APPLICABLE WALLS REQUIRED CLIP ANGLE REINFORCEMENT, 3 WALLS REQUIRED REINFORCEMENT, DESIGN / FABRICATION ERROR AND ONE WALL REQUIRED ADDING CLIP ANGLES THAT WERE NOT INCLUDED IN THE CONSTRUCTION / INSTALLATION ORIGINAL DESIGN.
. DESIGN / FABRICATION ERROR                                                                                                                                             ING REPORTED PER 10 CFR 21 8 TS 6.9.1.8.I. AN INSPECTION OF ALL TYPE HFA                                                           ,
CONSIDERING IE BULLETIN 79-14, THIS IS THE SECOND EVEN ITEM NOT APPLICABLE T OF THIS TYPE.
MANUFACTURING GENERAL ELECTRIC CD.                                                                                                                                                    RELAY COIL SPOOLS IN PLANT HAS REVEALED NO OBSERVABLE CRACKS OF TYPE ID ENIIFIED BY GE AS BEING POTENTIALLY HAZARDOUS, FIRST RELAY LER.
EVALUATIONS WERE PERFORMED TO JUSTIFY OPERATIONS, PRIORITIES WERE ASSIGN ED AND ALL IMMEDIATELY REQUIRED MODIFICATIONS WERE COMPLETED BY 2/5/81 ALL WALLS, THE FAILURE OF WHICH UNDER POSTULATED LOADS AND LOAD COMBINA TION COULD AFFECT SAFETY RELATED SYS, WERE REPAIRED. DETAILS ON FINDINGS 8 CORRECTIVE ACTION WILL BE INCLUDED IN OUR FINAL REPORT BULLETIN 80-11 ST. LUCIE-1 05006335 012781 DURING NORMAL FULL POWER OPERATION, NOTIFICATION WAS RECEIVED FROM GE (S OTHR INST SYS REQD FOR SAFETY 81-005/09T-0 020381 ERVICE ADVISORY BULLETIN S.A. 721-PSL-152.2) THAT THEIR TYPE HFA RELAY C CIRCUIT CLOSERS / INTERRUPTERS 036143 2-WEEK OIL SPOOLS COULD CRACK 8 FAIL IN SUCH A MANNER AS TO PREVENT RELAY OPER.
SINCE THE MECHANISMS FOR THE CREATION AND GROWTH OF THE CRACKS ARE UNKND WN, ALL OF THE REL AYS WILL BE REPLACED AS RECOMMENDED BY GE.                                                           IN THE INT ERIM UNTIL ALL RELAYS CAN BE REPLACED, ALL SAFETY RELATED HFA RELAYS WIL L BE INSPECTED ON A QUARTERLY BASIS. ANY RELAY SPOOLS SHOWING HEW OR.GR                                                           ^
CONTACTOR SINCE THESE RELAYS ARE UTILIZED IN SOME SAFEGUARD SYS THIS DEFECT IS BE
. DESIGN / FABRICATION ERROR ING REPORTED PER 10 CFR 21 8 TS 6.9.1.8.I.
AN INSPECTION OF ALL TYPE HFA MANUFACTURING RELAY COIL SPOOLS IN PLANT HAS REVEALED NO OBSERVABLE CRACKS OF TYPE ID GENERAL ELECTRIC CD.
ENIIFIED BY GE AS BEING POTENTIALLY HAZARDOUS, FIRST RELAY LER.
SINCE THE MECHANISMS FOR THE CREATION AND GROWTH OF THE CRACKS ARE UNKND WN, ALL OF THE REL AYS WILL BE REPLACED AS RECOMMENDED BY GE.
IN THE INT ERIM UNTIL ALL RELAYS CAN BE REPLACED, ALL SAFETY RELATED HFA RELAYS WIL L BE INSPECTED ON A QUARTERLY BASIS.
ANY RELAY SPOOLS SHOWING HEW OR.GR
^
OWING CRACKS CHARACTERISTIC OF IMPENDING FAILURE WILL BE REPLACED.
OWING CRACKS CHARACTERISTIC OF IMPENDING FAILURE WILL BE REPLACED.


i MAR 26, 1981                                                   LER MONTHLY REPORT SORTED BY FACILITY                                       PAGE 85 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /             DOCKET NO./   EVENT DATE/
i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 85 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                     REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                 CONTROL NO. REPORT TYPE                               CAUSE DESCRIPTION SURRY-1                                             05000280   012281     DURING THE PERIORMANCE OF PT-26.1. RADIATION MONITORING EQUIPMENT TEST, PRCSS + EFF RADIOL MONITOR SYS                 81-002/03L-0   021981     WITH THE UNIT DEFUELED. THE RADIATIOM ALARM SETPOINT FOR THE COMPONENT C INSTRUMENTATION + CONTROLS                           036221     30-DAY     00 LING SYSTEM WA5 FOUND TO BE GREATER THAN TWICE BACKGROUND AS LISTED IN COMPUTATION MODULE                                                         TECH. SPEC. 3.7. TABLE 3.7-5. THIS IS REPORTABLE IN ACCORDANCE WITH TE OTHER                                                                     CH. SPEC. 6.6.2.B(4). SINCE THE ACTIVITY LEVELS WERE WITHIN ALLOWABLE L NOT APPLICABLE                                                           IMITS, THE HEALTH AND SAFETY OF THE PUBt.IC WERE NOT AFFECTED.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION SURRY-1 05000280 012281 DURING THE PERIORMANCE OF PT-26.1. RADIATION MONITORING EQUIPMENT TEST, PRCSS + EFF RADIOL MONITOR SYS 81-002/03L-0 021981 WITH THE UNIT DEFUELED. THE RADIATIOM ALARM SETPOINT FOR THE COMPONENT C INSTRUMENTATION + CONTROLS 036221 30-DAY 00 LING SYSTEM WA5 FOUND TO BE GREATER THAN TWICE BACKGROUND AS LISTED IN COMPUTATION MODULE TECH. SPEC.
3.7.
TABLE 3.7-5.
THIS IS REPORTABLE IN ACCORDANCE WITH TE OTHER CH. SPEC. 6.6.2.B(4).
SINCE THE ACTIVITY LEVELS WERE WITHIN ALLOWABLE L NOT APPLICABLE IMITS, THE HEALTH AND SAFETY OF THE PUBt.IC WERE NOT AFFECTED.
VICTOREEN INSTRUMENT DIV.
VICTOREEN INSTRUMENT DIV.
THE IMPROPER SETPOINT WAS ATTRIBUTED TO REDUCED BACKGROUND DUE TO PLANT BEING SHUTDOWN AND DEFUELED. THE ACTIVITY LEVELS IN THE CC SYSTEM WERE VERIFIED TO BE WITHIN ALLOWABLE LIMITS AND THE SETPOINT FOR t10NITOR. RM-CC-105, WAS RESET.
THE IMPROPER SETPOINT WAS ATTRIBUTED TO REDUCED BACKGROUND DUE TO PLANT BEING SHUTDOWN AND DEFUELED. THE ACTIVITY LEVELS IN THE CC SYSTEM WERE VERIFIED TO BE WITHIN ALLOWABLE LIMITS AND THE SETPOINT FOR t10NITOR. RM-CC-105, WAS RESET.
SURRY-1                                             05000280   012981     DURING THE PERFORMANCE OF PT-26.1, RADIATION MONITORIN6 EQUIPMENT TEST, PRCFS + EFF RADIOL MONI'OR SYS                 81-003/03L-0   021981     WITH THE UNIT I DEFUELED AND UNIT 2 AT 100% POWER. THE RADIATION ALARM S INSTRUMENTATION + CONTROLS                           036222     30-DAY     ETPOINT FOR THE COMPONENT COOLING SYSTEM WAS FOUND TG BE GREATER THAN TW COMPdTATION NODULE                                                       ICE BACKGROUND AS LISTED IN TECH. SPEC. 3.7, TABLE 3.7-5. THIS IS REPOR OTHER                                                                     TABLE IN ACCORDANCE WITH TECH. SPEC. 6.6.2.B.(4). SINCE THE ACTIVITY LE NOT APPLICABLE                                                           VELS WERE WITHIN ALLOWABLE LIMITS, THE HEALTH AND SAFETY OF THE PUBLIC W VICTOREEN INSTRUMENT DIV.                                                 ERE NOT AFFECTED.
SURRY-1 05000280 012981 DURING THE PERFORMANCE OF PT-26.1, RADIATION MONITORIN6 EQUIPMENT TEST, PRCFS + EFF RADIOL MONI'OR SYS 81-003/03L-0 021981 WITH THE UNIT I DEFUELED AND UNIT 2 AT 100% POWER. THE RADIATION ALARM S INSTRUMENTATION + CONTROLS 036222 30-DAY ETPOINT FOR THE COMPONENT COOLING SYSTEM WAS FOUND TG BE GREATER THAN TW COMPdTATION NODULE ICE BACKGROUND AS LISTED IN TECH. SPEC.
3.7, TABLE 3.7-5.
THIS IS REPOR OTHER TABLE IN ACCORDANCE WITH TECH. SPEC. 6.6.2.B.(4).
SINCE THE ACTIVITY LE NOT APPLICABLE VELS WERE WITHIN ALLOWABLE LIMITS, THE HEALTH AND SAFETY OF THE PUBLIC W VICTOREEN INSTRUMENT DIV.
ERE NOT AFFECTED.
THE IMPROPER SETPOINT WAS ATTRIBUTED TO A DECREASE IN BACKGROUND RADIATI ON LEVELS. THE ACTIVITY LEVELS IN THE CC SYSTEM WERE VERIFIED TO BE WIT HIN ALLOWABLE LIMITS AND THE SETPOINT FOR MONITOR, RM-CC-105 AND 106 WER E PESET.
THE IMPROPER SETPOINT WAS ATTRIBUTED TO A DECREASE IN BACKGROUND RADIATI ON LEVELS. THE ACTIVITY LEVELS IN THE CC SYSTEM WERE VERIFIED TO BE WIT HIN ALLOWABLE LIMITS AND THE SETPOINT FOR MONITOR, RM-CC-105 AND 106 WER E PESET.
SURRY-7                                             05000281   122080     DURING THE PERIOD FROM 1600 TO 1700 DN 12/20/80, THE CONDENSER'S COOLING ULTIM TE HEAT SINK FACILITIES                   80-000/04X-0   010581     WATER OUTLET TEMP EXCEEDED THE MAXIMUM AVERAGE RATE OF CHANGE OF 3F/HR HEAT EXCHANGERS                                     033754     OTHER     PERMITTED BY TECHNICAL SPECIFICATION 4.14.A.3. AVG. RATE OF CHANGE WAS CONDENSER                                                                 8F/HR. HOWEVER, THE DURATION OF EACH STEP WAS ONLY 15 MIN. 50 THE MAX.
SURRY-7 05000281 122080 DURING THE PERIOD FROM 1600 TO 1700 DN 12/20/80, THE CONDENSER'S COOLING ULTIM TE HEAT SINK FACILITIES 80-000/04X-0 010581 WATER OUTLET TEMP EXCEEDED THE MAXIMUM AVERAGE RATE OF CHANGE OF 3F/HR HEAT EXCHANGERS 033754 OTHER PERMITTED BY TECHNICAL SPECIFICATION 4.14.A.3.
DESIGM/ FABRICATION ERROR                                                 CHANGE IN COOLING WATER TEMP. WAS CHLY 5F.
AVG. RATE OF CHANGE WAS CONDENSER 8F/HR.
DESILM OTHER WATERBOX OUTLET VALVES WERE THROTTLED DUE TO STATION VACUUM PRIMING PROB LEMS. OPERATION AT REDUCED STATION DISCHARGE COOLING MATER FLOWS AND CO LD RIVER WATER MAGNIFY THE EFFECT OF WATERBOX VALVE OPERATION. NO DETRI MENTAL EFFECT ON RIVER WATER ENVIRONMENT.
HOWEVER, THE DURATION OF EACH STEP WAS ONLY 15 MIN. 50 THE MAX.
SURRY-2                                             05000281   123180     ELECTRICAL PENETRATION E-4 THROUGH THE FIRE WALL BETWEEN 03 EQUIPMENT RO FIRE PROTECTION SYS + CONT                     80-049/03L-0   012981     OM AND 02 TURBINE BASEMENT HAD BEEN FOUND OPENED AND THERE WAS NO FIRE W COMPONENT CODE NOT APPLICABLE                       033687     30-DAY     ATCH ON EITHER SIDE OF THE WALL. THIS IS CONTRARY TO TECH SPECS 3.21-G, SUBCOMPONENT NOT APPLICABLE                                               AND REPORTABLE AS PER TECH SPEC 6.6.2.b(3)
DESIGM/ FABRICATION ERROR CHANGE IN COOLING WATER TEMP. WAS CHLY 5F.
PERSONNEL ERROR CONSTRUCTION PERSONNEL ITEM NOT APPLICABLE FIRE STOP WAS REMOVED TO RUN A WELDING LEAD'THROUGH THE ELECTRICAL PENET RATION. AFTER DETECTION, A FIRE WATCH WAS POSTED AND THE FIRE MARSHALL NOTIFIED. MAINTENANCE ORDER MAS SUBMITTED TO REPAIR THE FIRE STOP.     HEA LTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
DESILM OTHER WATERBOX OUTLET VALVES WERE THROTTLED DUE TO STATION VACUUM PRIMING PROB LEMS.
_ - _ - - - _ _ _ _ _ _ - _ - - _ _ _ _ - - _ _ _ _ . -                            _ . _ _ _ _ _ _ _ . _                                  - ,-                    -    c
OPERATION AT REDUCED STATION DISCHARGE COOLING MATER FLOWS AND CO LD RIVER WATER MAGNIFY THE EFFECT OF WATERBOX VALVE OPERATION. NO DETRI MENTAL EFFECT ON RIVER WATER ENVIRONMENT.
SURRY-2 05000281 123180 ELECTRICAL PENETRATION E-4 THROUGH THE FIRE WALL BETWEEN 03 EQUIPMENT RO FIRE PROTECTION SYS + CONT 80-049/03L-0 012981 OM AND 02 TURBINE BASEMENT HAD BEEN FOUND OPENED AND THERE WAS NO FIRE W COMPONENT CODE NOT APPLICABLE 033687 30-DAY ATCH ON EITHER SIDE OF THE WALL.
THIS IS CONTRARY TO TECH SPECS 3.21-G, SUBCOMPONENT NOT APPLICABLE AND REPORTABLE AS PER TECH SPEC 6.6.2.b(3)
PERSONNEL ERROR CONSTRUCTION PERSONNEL ITEM NOT APPLICABLE FIRE STOP WAS REMOVED TO RUN A WELDING LEAD'THROUGH THE ELECTRICAL PENET RATION.
AFTER DETECTION, A FIRE WATCH WAS POSTED AND THE FIRE MARSHALL NOTIFIED. MAINTENANCE ORDER MAS SUBMITTED TO REPAIR THE FIRE STOP.
HEA LTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
c


i f
i f
MAR 26, 1981                                                                         LER MONTHLY REPORT SORTED BY FACILITY                                                         PAGE 86 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/                                   DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 86 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/
COMPONENT SLBCODE/CAUSE CODE / LER NO./                                       REPORT DATE/                                 EVENT DES.RIPTION/
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                     CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION l
EVENT DATE/
SURRY-2                                                               05000281       011481   WITH THE UNIT AT FULL POWER, "C" SAFETY INJECTION ACCUMULATOR WAS FOUND EMERG CORE COOLING SYS + CONT                                       81-006/03L-0     021381   TO HAVE A BORON CONCENTRATION OF 1943 PPM, 7 PPM BELOW THE REQUIRED LIMI UALVES                                                                 036144       30-DAY   T OF 1950 PPM.
COMPONENT SLBCODE/CAUSE CODE / LER NO./
CHECK                                                                                                            THIS IS CONTRARY TO T.S.-3.3.A.2 AND IS REPORTABLE PER T ECHNICAL SPECIFICATION -6.6.2.B(2). SINCE "C" ACCUMULATOR BORON CONCENT COMPONENT FAILURE                                                                             RATION WAS INCREASED ABOVE 1950 PPM WITHIN THE 4 HOUR TECHNICAL SPECIFIC 1
REPORT DATE/
MECHANICAL                                                                                   ATION LIMITATION (55 MIN.), THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT ROCKWELL-INTERNATIONAL                                                                         AFFECTED.
EVENT DES.RIPTION/
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION l
SURRY-2 05000281 011481 WITH THE UNIT AT FULL POWER, "C" SAFETY INJECTION ACCUMULATOR WAS FOUND EMERG CORE COOLING SYS + CONT 81-006/03L-0 021381 TO HAVE A BORON CONCENTRATION OF 1943 PPM, 7 PPM BELOW THE REQUIRED LIMI UALVES 036144 30-DAY T OF 1950 PPM.
THIS IS CONTRARY TO T.S.-3.3.A.2 AND IS REPORTABLE PER T CHECK ECHNICAL SPECIFICATION -6.6.2.B(2).
SINCE "C" ACCUMULATOR BORON CONCENT COMPONENT FAILURE RATION WAS INCREASED ABOVE 1950 PPM WITHIN THE 4 HOUR TECHNICAL SPECIFIC 1
MECHANICAL ATION LIMITATION (55 MIN.), THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT ROCKWELL-INTERNATIONAL AFFECTED.
THE CAUSE OF THE REDUCED CONCENTRATION WAS LEAKAGE THROUGH CHECK VALVE 1
THE CAUSE OF THE REDUCED CONCENTRATION WAS LEAKAGE THROUGH CHECK VALVE 1
                                                                                                        -SI-144. THE CORRECTIVE ACTION WAS TO ISOLATE THIS VALVE WITH FUTURE PL ANS TO REPAIR THE VALVE DURING AN OUTAGE OF SUFFICIENT DURATION.
-SI-144.
SURRY-2                                                               05000281       011481   WITH UNIT NO. 2 AT 100% POWER, PT-27 (HEAT TRACING) REVEALED THAT AMP RE OTHER ENGNRD SAFETY FEATR SYS                                       81-007/03L-0     021381   ADINGS FOR PANELS 8 AND 9, CIRCUITS 20C, WERE BELOW THE ACCEPTANCE CRITE HEATERS ELECTRIC                                                       036145       30-DAY   RIA STIPULATED IN THE PT, THEREFORE. THE DIT RECIRC WERE DECLARED INOPER SUBCOMPONENT NOT APPLICABLE                                                                 ATIVE. THIS EVENT IS CONTRARY TO TECHNICAL SPECIFICATION 3.3.A.3 BUT PE COMPONENT FAILURE                                                                             RMITTED BY TECH. SPEC. 3.3.B.10. THIS EVENT IS REPORTABLE PER TECH. SPE ELECTRICAL                                                                                   C. 6.6.6.2.B(2).
THE CORRECTIVE ACTION WAS TO ISOLATE THIS VALVE WITH FUTURE PL ANS TO REPAIR THE VALVE DURING AN OUTAGE OF SUFFICIENT DURATION.
THERMON MFG.                                                                                                        THE HEALTH AND 3AFETY OF THE PUBLIC WERE NOT AFFECTED.
SURRY-2 05000281 011481 WITH UNIT NO. 2 AT 100% POWER, PT-27 (HEAT TRACING) REVEALED THAT AMP RE OTHER ENGNRD SAFETY FEATR SYS 81-007/03L-0 021381 ADINGS FOR PANELS 8 AND 9, CIRCUITS 20C, WERE BELOW THE ACCEPTANCE CRITE HEATERS ELECTRIC 036145 30-DAY RIA STIPULATED IN THE PT, THEREFORE. THE DIT RECIRC WERE DECLARED INOPER SUBCOMPONENT NOT APPLICABLE ATIVE.
THE LOSS OF HEAT TRACING WAS DUE TO EXCESSIVE TEMPERATURES BREAKING DOWN THE INSULATION. THE DEFECTIVE HEAT TRACING WAS REPLACED AND TESTED WIT HIN 2 HRS.     A DESIGN CHANGE HAS BEEN INITIATED TO CHANGE THE MANNER BY W HICH THESE BORATED LINES ARE HEAT TRACED.
THIS EVENT IS CONTRARY TO TECHNICAL SPECIFICATION 3.3.A.3 BUT PE COMPONENT FAILURE RMITTED BY TECH. SPEC. 3.3.B.10.
SURRY-2                                                               05000281       011881   WITH UNIT 2 AT 100 PERCENT POWER, ONE OF TWO REQUIRED FLOW PATHS TO THE FEEDWATER SYSTEMS + CONTROLS                                       81-012/03L-0     021781   CORE BECAME UNAVAILABLE AND BIT RECIRC WAS TERMINATED DUE TO THE LOSS OF PUMPS                                                                 036147       30-DAY     BORIC ACID TRANSFER PUMP .1-CH-P-2D. THIS IS CONTRARY TO TECHNICAL SPEC CENTRIFUGAL                                                                                   IFICATION 3.2.B.4 AND 3.3.A.3, AND IS REPORTABLE PER TECH. SPEC. 6.6.2.B COMPONENT FAILURE                                                                             .(2).
THIS EVENT IS REPORTABLE PER TECH. SPE ELECTRICAL C. 6.6.6.2.B(2).
MECHANICAL                                                                                              THE REDUNDANT TRANSFER PUMP WAS PLACED IN SERVICE WITHIN 6 MINUTE S; THEREFORE, THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
THE HEALTH AND 3AFETY OF THE PUBLIC WERE NOT AFFECTED.
THERMON MFG.
THE LOSS OF HEAT TRACING WAS DUE TO EXCESSIVE TEMPERATURES BREAKING DOWN THE INSULATION. THE DEFECTIVE HEAT TRACING WAS REPLACED AND TESTED WIT HIN 2 HRS.
A DESIGN CHANGE HAS BEEN INITIATED TO CHANGE THE MANNER BY W HICH THESE BORATED LINES ARE HEAT TRACED.
SURRY-2 05000281 011881 WITH UNIT 2 AT 100 PERCENT POWER, ONE OF TWO REQUIRED FLOW PATHS TO THE FEEDWATER SYSTEMS + CONTROLS 81-012/03L-0 021781 CORE BECAME UNAVAILABLE AND BIT RECIRC WAS TERMINATED DUE TO THE LOSS OF PUMPS 036147 30-DAY BORIC ACID TRANSFER PUMP.1-CH-P-2D.
THIS IS CONTRARY TO TECHNICAL SPEC CENTRIFUGAL IFICATION 3.2.B.4 AND 3.3.A.3, AND IS REPORTABLE PER TECH. SPEC. 6.6.2.B COMPONENT FAILURE
.(2).
THE REDUNDANT TRANSFER PUMP WAS PLACED IN SERVICE WITHIN 6 MINUTE MECHANICAL S; THEREFORE, THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.
GOULDS PUMPS INC.
GOULDS PUMPS INC.
PUMP'S OIL SEAL FAILED, THEREBY CAUSING BEARING FAILURE AND SUBSEQUENT L OSS OF PUMP.     TRANSFER PUMP 1-CH-P-2C WAS PLACED IN SERVICE. TRANSFER P UMP 1-CH-P-2D WAS REPAIRED, TESTED, AND RE1URNED TO SERVICE.
PUMP'S OIL SEAL FAILED, THEREBY CAUSING BEARING FAILURE AND SUBSEQUENT L OSS OF PUMP.
SURRY-2                                                               05000281       011981 FIRE PROTECTION SYS + CONT                                          81-011/03L-0    021381 A FIRE NATCH HAD BEEN ESTAR WHEN FUEL OIL PUMP HOUSE CO2 SYS WAS MADE IN COMPONENT CODE NOT APPLICABLE                                          036146                  OPER FOR DESIGN CHANGE MODIF. AT 0700 IT WAS DISCOVERED THAT A FIRE WATC 30-DAY   H WAS NOT BEING MAINTAINED. OPERATIONS PERSONNEL HAD MADE PERIODIC INSPE SUBCOMPONENT NOT APPLICABLE                                                                   CTIONS OF THE AREA. THE POSITION MAS UNMANNED FOR ONLY 1 1/2 HRS. MANUA PERSONNEL ERROR MAINTENANCE & REPAIR PERSONNEL                                                                L FIRE SUPPRESSION WAS AVAILABLE. A FIRE WATCH WAS IMMED RE-ESTABLISHED.
TRANSFER PUMP 1-CH-P-2C WAS PLACED IN SERVICE. TRANSFER P UMP 1-CH-P-2D WAS REPAIRED, TESTED, AND RE1URNED TO SERVICE.
THEREFORE, HEALTH & SAFETY OF PUBLIC WERE NOT AFFECTED.                       THIS EVENT IS ITEM NOT APPLICABLE                                                                         , CONTRARY TO T.S. 3.21.D.3.A 8 IS REPORTABLE PER T.S. 6.6.2.B.(2).
SURRY-2 05000281 011981 A FIRE NATCH HAD BEEN ESTAR WHEN FUEL OIL PUMP HOUSE CO2 SYS WAS MADE IN FIRE PROTECTION SYS + CONT 81-011/03L-0 021381 OPER FOR DESIGN CHANGE MODIF. AT 0700 IT WAS DISCOVERED THAT A FIRE WATC COMPONENT CODE NOT APPLICABLE 036146 30-DAY H WAS NOT BEING MAINTAINED. OPERATIONS PERSONNEL HAD MADE PERIODIC INSPE SUBCOMPONENT NOT APPLICABLE CTIONS OF THE AREA.
Q THE ASSIGNED FIRE WATCM HAD LEFT THEIR POST WITHOUT BEING PROPERLY RELIE VED. A FIRE WATCH WAS IMMEDIATELY RE-ESTABLISHED, AND APPROPRIATE DISCI PLINARY ACTION WAS TAKEN AGAINST THE MISSING FIRE WATCH.
THE POSITION MAS UNMANNED FOR ONLY 1 1/2 HRS. MANUA PERSONNEL ERROR L FIRE SUPPRESSION WAS AVAILABLE. A FIRE WATCH WAS IMMED RE-ESTABLISHED.
MAINTENANCE & REPAIR PERSONNEL THEREFORE, HEALTH & SAFETY OF PUBLIC WERE NOT AFFECTED.
THIS EVENT IS ITEM NOT APPLICABLE
, CONTRARY TO T.S. 3.21.D.3.A 8 IS REPORTABLE PER T.S. 6.6.2.B.(2).
Q THE ASSIGNED FIRE WATCM HAD LEFT THEIR POST WITHOUT BEING PROPERLY RELIE VED.
A FIRE WATCH WAS IMMEDIATELY RE-ESTABLISHED, AND APPROPRIATE DISCI PLINARY ACTION WAS TAKEN AGAINST THE MISSING FIRE WATCH.


e MAR 26, 1981                                               LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 87 PROCESSED DURING MARCH, 198t FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /         DOCKET NO./   CVENT DATE/
e MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 87 PROCESSED DURING MARCH, 198t FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./               REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION SURRY-2                                       0S000281     011981     WITH UNIT TWO OPERATING STEADY-STATE AT 100% POWER, AN IMPROPERLY SEALED FIRE PR0stCTION SYS + CON'                 81-013/03L-0   021381       FIRE BARRIER PENETRATION WAS DISCOVERED DURING A Q.C. DEPARTMENT WALKD0 COMPONENT CODE NOT APPLIfABLE                 036148     30-DAY     WN OF THE PLANT. THIS IS CONTRARY TO TECHNICAL SPECIFICATI0M 3.21.G.1 A SUBCOMPOW"NT NOT APPLICABLE                                         ND IS REPORTABLE AS PER TECH. SPEC. 6.6.2.B.(3). ALL OTHER FIRE PROTECT PERSONNEL ERROR                                                       ION SYSTEMS REMAINED OPERABLE, THEREFORE, THE HEALTH AND SAFETY OF THE P CONSTRUCTION PERSONNEL                                           . UBLIC WERE NOT AFFECTED.
CVENT DATE/
ITEM NOT APPLICABLE
COMPONENT SUBCODE/CAUSE CODE / LER NO./
* THE FIRE BARRIER PENETRATION HAD BEEN PACKED WITH IMPROPER MATERIAL. A FIRE WATCH WAS ESTABLISHED UNTIL THE PENETRATION COULD BE PROPERLY SEALE D.
REPORT DATE/
SURRY-2                                       0S000281     011981     ON JAMUARY 19, 1981. WITH UNIT NO. 2 AT 100% POWER, A POSITIVE PRESSURE CONT ROOM HABITBLTY SY3 + CONT             81-016/03L-0   021881     0F GREATER THAN 0.0S INCHES 9F WATER, COULD NOT BE MAINTAINED IN THE CON OTHER COMPONENTS                               036223     30-DAY     TROL ROOM. THIS IS CONTRARY TO TECH. SPEC. -3.19.A AND IS REPORTABLE PE SUBCOMPONENT NOT APPLICABLE                                         R T.S.-6.6.2.B(2).     THE CONTROL ROOM EMERGENCY VENTILATION SYSTEM MAS OP COMPONENT FAILURE                                                     ERABLE, THEREFORE, THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED MECHANICAL OTHER THE SEALS ON THE DOORS TO THE CONTROL ROOM COMPLEX WERE DETERIORATED, T HE DEFECTIVE DOORS WERE REPAIRED.
EVENT DESCRIPTION /
VHREE MILE ISLAND-1                           0S000289     011781     WHILE IN THE LONG-TERM COLD SHUTDOWN CONDIriON, DURING A LIMITED PLANT H REAC COOL CLEANUP SYS + CONT               81-001/03L-0   021881     EATUP, 2 LEAKS WERE FOUND IN THE     1" BYPASS AROUND MU-V17. THIS EVENT'IS PIPES. FITTINGS                               036253     30-DAY       REPORTABLE PER 6.9.2.B(4). THE LEAKAGE WAS REDUCED WHEN THE SYSTEM PRE LESS THAN 4 INCHES                                                 SSURE WAS RETURNED TO ATMOSPHERIC PRESSURE.
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
COMPONENT FAILURE CORROSION                                                                                                                                             j OTHER                                                                                                                                                 l THE LEAK ON THE FLOW INSTRUMENT IS THOUGHT TO BE DUE TO A LOCALIZED PITT         '
REPORT TYPE CAUSE DESCRIPTION SURRY-2 0S000281 011981 WITH UNIT TWO OPERATING STEADY-STATE AT 100% POWER, AN IMPROPERLY SEALED FIRE PR0stCTION SYS + CON' 81-013/03L-0 021381 FIRE BARRIER PENETRATION WAS DISCOVERED DURING A Q.C. DEPARTMENT WALKD0 COMPONENT CODE NOT APPLIfABLE 036148 30-DAY WN OF THE PLANT.
ING ATTACK. THE LEAK ON THE SOCKET WELD IS DUE TO AN INITIAL ROOT WELD DEFECT WHICH APPEARS TO HAVE PROPAGATED DUE TO CYCLIC FATIGUE. THE DAMA GED COMPONENTS WERE REMOVED FROM THE SYSTEM AND ARE BEING REPLACED. AF OLLOWUP LER WILL BE ISSUED.
THIS IS CONTRARY TO TECHNICAL SPECIFICATI0M 3.21.G.1 A SUBCOMPOW"NT NOT APPLICABLE ND IS REPORTABLE AS PER TECH. SPEC. 6.6.2.B.(3).
l THREC MILE ISLAND-2                           0S000320     121780     ON 12/17/80 DURING PERFORMANCF OF SURVEILLANCE PROCEDURE 4303-M10, AIR I OTHR INST SYS PEQD FOR SAFETY               80-OS7/03L-0 011681       NTAKE TUNNEL CHLORINE MONITOR WAS FOUND TO BE INOPERABLE IN THAT WHEN PR l                                   INSTRUMENTATION + CONTROLS                     333688     30-DAY     OBE WAS EXPOSED TO CHLORINE VAPORS MONITOR DID NOT RESPOND. THIS IS NOT
ALL OTHER FIRE PROTECT PERSONNEL ERROR ION SYSTEMS REMAINED OPERABLE, THEREFORE, THE HEALTH AND SAFETY OF THE P CONSTRUCTION PERSONNEL
;                                    SENSOR / DETECTOR / ELEMENT                                           A VIOL ATION OF TECH. SPECS. THIS REPORT IS SUBMITTED UNDER SECTION 6.9 t
. UBLIC WERE NOT AFFECTED.
COMPCNENT FAILURE                                                     .1.9(B) BECAUSE ACTION STATEMENT OF SECTION 3.3.3.7 WAS ENTERED INADVERT OTHER                                                               ENTLY. THIS EVENT HAD NO EFFECT ON PLANT, ITS OPERATION, OR HEALTH AND FISCHER 8 PORTER CO.                                                 SAFETY OF THE PUBLIC.
ITEM NOT APPLICABLE THE FIRE BARRIER PENETRATION HAD BEEN PACKED WITH IMPROPER MATERIAL. A FIRE WATCH WAS ESTABLISHED UNTIL THE PENETRATION COULD BE PROPERLY SEALE D.
CAUSE OF EVENT WAS THAT PROBE HAD BECOME DIRTY. THIS REDUCED ITS SENSIT-IVITY TO DETErT CHLORINE AT REQUIRED LEVEL. PROBE WAS REMOVED FROM SERV ICE, CLEANED, AND THEN RETURNED TO SERVICE. SURVEILLANCE PROCEDURE IS B EING MODIFIED TO INCREASE CLEANING FREQUENCY OF PROBE TO ONCE PER 31 DAY S.
SURRY-2 0S000281 011981 ON JAMUARY 19, 1981. WITH UNIT NO. 2 AT 100% POWER, A POSITIVE PRESSURE CONT ROOM HABITBLTY SY3 + CONT 81-016/03L-0 021881 0F GREATER THAN 0.0S INCHES 9F WATER, COULD NOT BE MAINTAINED IN THE CON OTHER COMPONENTS 036223 30-DAY TROL ROOM.
THIS IS CONTRARY TO TECH. SPEC. -3.19.A AND IS REPORTABLE PE SUBCOMPONENT NOT APPLICABLE R T.S.-6.6.2.B(2).
THE CONTROL ROOM EMERGENCY VENTILATION SYSTEM MAS OP COMPONENT FAILURE ERABLE, THEREFORE, THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED MECHANICAL OTHER THE SEALS ON THE DOORS TO THE CONTROL ROOM COMPLEX WERE DETERIORATED, T HE DEFECTIVE DOORS WERE REPAIRED.
VHREE MILE ISLAND-1 0S000289 011781 WHILE IN THE LONG-TERM COLD SHUTDOWN CONDIriON, DURING A LIMITED PLANT H REAC COOL CLEANUP SYS + CONT 81-001/03L-0 021881 EATUP, 2 LEAKS WERE FOUND IN THE 1" BYPASS AROUND MU-V17.
THIS EVENT'IS PIPES. FITTINGS 036253 30-DAY REPORTABLE PER 6.9.2.B(4).
THE LEAKAGE WAS REDUCED WHEN THE SYSTEM PRE LESS THAN 4 INCHES SSURE WAS RETURNED TO ATMOSPHERIC PRESSURE.
COMPONENT FAILURE CORROSION j
OTHER l
THE LEAK ON THE FLOW INSTRUMENT IS THOUGHT TO BE DUE TO A LOCALIZED PITT ING ATTACK.
THE LEAK ON THE SOCKET WELD IS DUE TO AN INITIAL ROOT WELD DEFECT WHICH APPEARS TO HAVE PROPAGATED DUE TO CYCLIC FATIGUE.
THE DAMA GED COMPONENTS WERE REMOVED FROM THE SYSTEM AND ARE BEING REPLACED. AF OLLOWUP LER WILL BE ISSUED.
l THREC MILE ISLAND-2 0S000320 121780 ON 12/17/80 DURING PERFORMANCF OF SURVEILLANCE PROCEDURE 4303-M10, AIR I OTHR INST SYS PEQD FOR SAFETY 80-OS7/03L-0 011681 NTAKE TUNNEL CHLORINE MONITOR WAS FOUND TO BE INOPERABLE IN THAT WHEN PR l
INSTRUMENTATION + CONTROLS 333688 30-DAY OBE WAS EXPOSED TO CHLORINE VAPORS MONITOR DID NOT RESPOND. THIS IS NOT SENSOR / DETECTOR / ELEMENT A VIOL ATION OF TECH. SPECS.
THIS REPORT IS SUBMITTED UNDER SECTION 6.9 t
COMPCNENT FAILURE
.1.9(B) BECAUSE ACTION STATEMENT OF SECTION 3.3.3.7 WAS ENTERED INADVERT OTHER ENTLY.
THIS EVENT HAD NO EFFECT ON PLANT, ITS OPERATION, OR HEALTH AND FISCHER 8 PORTER CO.
SAFETY OF THE PUBLIC.
CAUSE OF EVENT WAS THAT PROBE HAD BECOME DIRTY.
THIS REDUCED ITS SENSIT-IVITY TO DETErT CHLORINE AT REQUIRED LEVEL.
PROBE WAS REMOVED FROM SERV ICE, CLEANED, AND THEN RETURNED TO SERVICE. SURVEILLANCE PROCEDURE IS B EING MODIFIED TO INCREASE CLEANING FREQUENCY OF PROBE TO ONCE PER 31 DAY S.
1
1


MAR 26, 1981                                       LER MONTHLY REPORT SORTED BY FACIIITY                                       PAGE 88 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACIIITY PAGE 88 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./       REPORT DATE/                               EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYPE                               CAUSE DESCRIPTION THREE MILE ISLAND-2                   0$000320     122680     AT 1320 HRS ON 12/26/80,   "A" EMERGENCY DIESEL GEN.(EDG) DF-X-1A WAS STAR EMERG GENERATOR SYS + C0NTROLS     80-059/03L-0 012681       TED DURING A TRAINING EXERCISE. EDG STARTED BUT TRIPPED AFTER APPROX. 9 RELAYS                                   033733     30-DAY       SEC. THIS EVENT WAS NOT A VIOL. OF ANY T/S. THIS EVENT IS REPORTABLE TIME DELAY, PNEt!MATIC                                       UNDER T/S 6.9.1.9(B) DUE TO ENTRY INTO ACTION STATEMENT OF SPEC. 3.8.1.1 COMPONENT FAILURE                                               BY EQUIP. FAILURE. THIS EVENT IS SIMILAR TO S.R. 80-003,   LER'S 80-09 I     ELECTRICAL                                                   AND 80-028. TH.S EVENT HAD NO EFFECT ON PLANT, ITS OPERATION, OR HEALTH I-T-E CIRCUIT BREAKER                                           AND SAFETY OF THE PUBLIC.
EVENT DATE/
COMPONENT SUBCODE/CAUSE CODE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION THREE MILE ISLAND-2 0$000320 122680 AT 1320 HRS ON 12/26/80, "A" EMERGENCY DIESEL GEN.(EDG) DF-X-1A WAS STAR EMERG GENERATOR SYS + C0NTROLS 80-059/03L-0 012681 TED DURING A TRAINING EXERCISE. EDG STARTED BUT TRIPPED AFTER APPROX. 9 RELAYS 033733 30-DAY SEC.
THIS EVENT WAS NOT A VIOL. OF ANY T/S.
THIS EVENT IS REPORTABLE TIME DELAY, PNEt!MATIC UNDER T/S 6.9.1.9(B) DUE TO ENTRY INTO ACTION STATEMENT OF SPEC. 3.8.1.1 COMPONENT FAILURE BY EQUIP. FAILURE. THIS EVENT IS SIMILAR TO S.R. 80-003, LER'S 80-09 I
ELECTRICAL AND 80-028.
TH.S EVENT HAD NO EFFECT ON PLANT, ITS OPERATION, OR HEALTH I-T-E CIRCUIT BREAKER AND SAFETY OF THE PUBLIC.
UPON FURTHER INVESTIGATION IT WAS DETERMINED THAT CAUSE OF EDG TRIP WAS RESULT OF A FAILURE IN ALARM DELAY RELAY, T3B-LOW LUBE DIL PRESSURE, IN EDG STARTING CIRCUITRY. RELAY AND COIL WERE REPLACED. COMPONENT MANUFA CTURER WILL BE CONTACTED TO DETERMINE IF THERE IS A HISTORY OF TP*S TYPE OF FAILURE.
UPON FURTHER INVESTIGATION IT WAS DETERMINED THAT CAUSE OF EDG TRIP WAS RESULT OF A FAILURE IN ALARM DELAY RELAY, T3B-LOW LUBE DIL PRESSURE, IN EDG STARTING CIRCUITRY. RELAY AND COIL WERE REPLACED. COMPONENT MANUFA CTURER WILL BE CONTACTED TO DETERMINE IF THERE IS A HISTORY OF TP*S TYPE OF FAILURE.
TROJAN-1                               05000344     101680     SPECIAL REPORT. A LIMITING CONDITION FOR OPERATION (LCO) 0F THE TROJAN FIRE PROTECTION SYS + CONT         80-000/13X-0   101680     TECHhICAL $?ECIFICATIONS REQUIRES A SPECIAL REPORT BE SUBMITTED IN THE E PUMPS                                   033756     OTHER     VENT OF IHOPERABILITY OF THE FIRE SUPPRESSION SYSTEM. SYSTEM OPERABILIT OTHER                                                       Y WILL NOT BE MET DURING A PLANNED FIAINTENANCE OVERHAUL OF THE DIESEL-DR COMPONENT FAILURE                                             IVEN FIRE PUMP. PUMP OUTAGE IS EXPECTED TO LAST FROM 10/20/80 TO 11/12/
TROJAN-1 05000344 101680 SPECIAL REPORT.
MECHANICAL                                                   80.
A LIMITING CONDITION FOR OPERATION (LCO) 0F THE TROJAN FIRE PROTECTION SYS + CONT 80-000/13X-0 101680 TECHhICAL $?ECIFICATIONS REQUIRES A SPECIAL REPORT BE SUBMITTED IN THE E PUMPS 033756 OTHER VENT OF IHOPERABILITY OF THE FIRE SUPPRESSION SYSTEM. SYSTEM OPERABILIT OTHER Y WILL NOT BE MET DURING A PLANNED FIAINTENANCE OVERHAUL OF THE DIESEL-DR COMPONENT FAILURE IVEN FIRE PUMP.
OTHER PREVENTIVE taINTENANCE OF DIESEL ENGINE AS WELL AS THE PUMP. IN ADDITIO N. THE PUMP WILL ALSO BE COATED WITH A CORROSION ?NHIBITOR. THE LOCAL F IRE DEPARTMENT WlLL PROVIDE A PUMPER TRUCK AT THE SITE WHILE THE DIESEL DRIVEN PCMP IS OUT OF SERVICE.
PUMP OUTAGE IS EXPECTED TO LAST FROM 10/20/80 TO 11/12/
TROJAN-1                               05000344     121280     DURING HORMAL OPERATION, A BLOWN FUSE WAS FOUND IN THE BREAKER CONTROL P AIR COND. HEAT. COOL VENT SYSTEM   31-001/C3L-O   010981     OWLR CIRCUIT FOR THE VENT SUPPLY FAN TO THE TURBINE-DRIVEN AUXILIARY FEE BLOWERS                                 036224     30-DAY     DWATER PUMP ROOM. THE TURBINE-DRIVEN PUMP WOULD HAVE OPERATED NORMALLY SUBCOMPONENT N01 APPLICABLE                                 UPON RECEIVING AN AUTO-START SIGNAL AND BACKUP VENTILATION COULD HAVE BE COMPONENT FAILURE                                             EN SUP* LIED BY OPENING THE PUMP RJ0M DOOR UNTIL IHE FAN WAS RETURNED TO ELECTRICAL                                                   SERVICE. THE REDUNDANT DIESEL-DRIVEN PUMP WAS OPERAb.E AND AVAILABLE FO OTHER                                                         R USE.
MECHANICAL 80.
THERE WAS NO APPARENT CAUSE FOR THE BLOWN FUSE. ELECTRICAL FAULT CHECKS WERE PERFORMED ON THE BREAKER CONTROL CIRCUIT WITH NO DEFICIENCIES FOUN D. A REPLACEMENT FUSE WAS INSTALLED AND THE FAN OPERATIONALLY TESTED SA TISFACTORILY. NO FURTHER CORRECTIVE ACTION IS REQUIRED.
OTHER PREVENTIVE taINTENANCE OF DIESEL ENGINE AS WELL AS THE PUMP.
TROJAN-1                               05000'344     123180   NC. 80-282 WHILE RETURNING THE "B" SERVICE WATER BOOSTER PUMP TO SERVICE AC ONSITE POWER SYS + CONTROLS     80-028/03L-0   012 f r> 1 ,  A MIN 3R FIRE OCCURRED IN 480 VAC ESF MCC B22. THIS RENDERED CERTAIN C CIRCUIT CLOSERS / INTERRUPTERS           033734     30-DAY     ONTAINMENT ISOLATION VALVES IHOPERABLE PER TECH. SPEC. 3.6.3.1, CERTAIN CIRCUIT BREAKER                                             SPRAY VALVES INOPERABLE PER TECH. SPEC. 3.6.2.1 AND THREE OF EIGHT CONT COMPONENT FAILURE                                             AINMENT AIR COOLERS INOPERABLE PER TECH. SPEC. 3.6.2.3. REDUNDANT CONTA ELECTRICAL                                                   INMENT ISOLATION VALVES, SPRAY SYSTEM, AND AIR COOLERS WERE AVAILABLE.
IN ADDITIO N.
ITE IMPERIAL CORPORATION REPEATED' CYCLING OF PUMP ONTO BUS COUPLED WITH INADEQUATE STAB TO BUS BA R CONTACT AND DUST IN THE MCC CABINET CAUSED A FIRE. OPERATORS WERE REM INDED OF UNDESIRABILITY OF REPEATED CYCLING OF LOAD BREAKER. AN ENGINEE RING STUDY TO DETERMINE IF THE BREAKERS ARE ADEQUATELY SIZED WILL BE !!AD E.
THE PUMP WILL ALSO BE COATED WITH A CORROSION ?NHIBITOR. THE LOCAL F IRE DEPARTMENT WlLL PROVIDE A PUMPER TRUCK AT THE SITE WHILE THE DIESEL DRIVEN PCMP IS OUT OF SERVICE.
TROJAN-1 05000344 121280 DURING HORMAL OPERATION, A BLOWN FUSE WAS FOUND IN THE BREAKER CONTROL P AIR COND. HEAT. COOL VENT SYSTEM 31-001/C3L-O 010981 OWLR CIRCUIT FOR THE VENT SUPPLY FAN TO THE TURBINE-DRIVEN AUXILIARY FEE BLOWERS 036224 30-DAY DWATER PUMP ROOM.
THE TURBINE-DRIVEN PUMP WOULD HAVE OPERATED NORMALLY SUBCOMPONENT N01 APPLICABLE UPON RECEIVING AN AUTO-START SIGNAL AND BACKUP VENTILATION COULD HAVE BE COMPONENT FAILURE EN SUP* LIED BY OPENING THE PUMP RJ0M DOOR UNTIL IHE FAN WAS RETURNED TO ELECTRICAL SERVICE. THE REDUNDANT DIESEL-DRIVEN PUMP WAS OPERAb.E AND AVAILABLE FO OTHER R USE.
THERE WAS NO APPARENT CAUSE FOR THE BLOWN FUSE.
ELECTRICAL FAULT CHECKS WERE PERFORMED ON THE BREAKER CONTROL CIRCUIT WITH NO DEFICIENCIES FOUN D.
A REPLACEMENT FUSE WAS INSTALLED AND THE FAN OPERATIONALLY TESTED SA TISFACTORILY. NO FURTHER CORRECTIVE ACTION IS REQUIRED.
TROJAN-1 05000'344 123180 NC. 80-282 WHILE RETURNING THE "B" SERVICE WATER BOOSTER PUMP TO SERVICE AC ONSITE POWER SYS + CONTROLS 80-028/03L-0 012 f r> 1 A MIN 3R FIRE OCCURRED IN 480 VAC ESF MCC B22.
THIS RENDERED CERTAIN C CIRCUIT CLOSERS / INTERRUPTERS 033734 30-DAY ONTAINMENT ISOLATION VALVES IHOPERABLE PER TECH. SPEC.
3.6.3.1, CERTAIN CIRCUIT BREAKER SPRAY VALVES INOPERABLE PER TECH. SPEC. 3.6.2.1 AND THREE OF EIGHT CONT COMPONENT FAILURE AINMENT AIR COOLERS INOPERABLE PER TECH. SPEC.
3.6.2.3.
REDUNDANT CONTA ELECTRICAL INMENT ISOLATION VALVES, SPRAY SYSTEM, AND AIR COOLERS WERE AVAILABLE.
ITE IMPERIAL CORPORATION REPEATED' CYCLING OF PUMP ONTO BUS COUPLED WITH INADEQUATE STAB TO BUS BA R CONTACT AND DUST IN THE MCC CABINET CAUSED A FIRE.
OPERATORS WERE REM INDED OF UNDESIRABILITY OF REPEATED CYCLING OF LOAD BREAKER. AN ENGINEE RING STUDY TO DETERMINE IF THE BREAKERS ARE ADEQUATELY SIZED WILL BE !!AD E.


MAR 26, 1981                                                                                                 LER MONTHLY REPORT SORTED BY FACILITY                                                                                                 PAGE 89 PROCESSED DURING MARCH, 19.1 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /                                                   DOCKET NO./           EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 89 PROCESSED DURING MARCH, 19.1 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./                                                                 REPORT DATE/                                                         EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER                                                       CONTROL NO.           REPORT TYPE                                                         CAUSE DESCRIPTION TROJAN-1                                                                                       05000344       123180             CONTROL VALVES CONNECTING THE REFUELING WATER STORAGE TANK AND THE SPENT EMERG CORE COOLING SYS + CONT                                                           80-029/03L-0         012931               FUEL PURIFICATION SYSTEM WERE FOUND TO HAVE A DEFICIENCY WHICH COULD PR INSTRUMENTATION + CONTROLS                                                                         033735     30-DAY             EVENT THEIR SHUTTING. A FAILURE OF.THIS TYPE DURING A SEISflIC EVENT AND OTHER .                                                                                                                         SAFETY INJECTION COULD CAUSE AN UNACCEPTABLE LOSS OF WATER FROM THE RMS EXTERNAL CAUSE                                                                                                                   T.
EVENT DATE/
NOT APPLICABLE ASCO THE CAUSE OF THIS EVENT IS ATTRIBUTED TO CONSTRUCTION / INSTALLATION ERROR S. AN AC SOLENDID HOUSING WITH A DC SLUG AND CCI! WERE INSTALLED IN A D C CONTROL CIPCUIT.                                                                                                       .g TROJAN-1                                                                                       05000344       010781             NO. 81-02: REPORTED IN ACCORDANCE WITH 3.6.3.1 - AFTER NORMAL SAMPLING 0 OTHER COOLANT SUBSYS + CONTROL                                                         81-002/03L-0         020381             F THE REACTOR COOLANT SYSTEtt, THE COMMON SAMPLE CONTAINMENT ISOLATION VA UALVES                                                                                             036149     30-DAY             LVE FAILED TO CLOSE FR0t1 THE CONTROL ROOM. AFTER SEVERAL ATTEMPTS, THE PLUG                                                                                                                             VALVE CLOSED. THERE WAS NO EFFECT ON PLANT OR PUBLIC SAFETY SINCE THE S                                                     ,
COMPONENT SUBCODE/CAUSE CODE / LER NO./
OTHER                                                                                                                             AMPLE ISOLATION VALVES INSIDE CONTAINMENT WERE OPERAFLE.                                                                   '
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION TROJAN-1 05000344 123180 CONTROL VALVES CONNECTING THE REFUELING WATER STORAGE TANK AND THE SPENT EMERG CORE COOLING SYS + CONT 80-029/03L-0 012931 FUEL PURIFICATION SYSTEM WERE FOUND TO HAVE A DEFICIENCY WHICH COULD PR INSTRUMENTATION + CONTROLS 033735 30-DAY EVENT THEIR SHUTTING. A FAILURE OF.THIS TYPE DURING A SEISflIC EVENT AND OTHER.
SAFETY INJECTION COULD CAUSE AN UNACCEPTABLE LOSS OF WATER FROM THE RMS EXTERNAL CAUSE T.
NOT APPLICABLE ASCO THE CAUSE OF THIS EVENT IS ATTRIBUTED TO CONSTRUCTION / INSTALLATION ERROR S.
AN AC SOLENDID HOUSING WITH A DC SLUG AND CCI! WERE INSTALLED IN A D C CONTROL CIPCUIT.
.g TROJAN-1 05000344 010781 NO. 81-02: REPORTED IN ACCORDANCE WITH 3.6.3.1 - AFTER NORMAL SAMPLING 0 OTHER COOLANT SUBSYS + CONTROL 81-002/03L-0 020381 F THE REACTOR COOLANT SYSTEtt, THE COMMON SAMPLE CONTAINMENT ISOLATION VA UALVES 036149 30-DAY LVE FAILED TO CLOSE FR0t1 THE CONTROL ROOM.
AFTER SEVERAL ATTEMPTS, THE PLUG VALVE CLOSED.
THERE WAS NO EFFECT ON PLANT OR PUBLIC SAFETY SINCE THE S OTHER AMPLE ISOLATION VALVES INSIDE CONTAINMENT WERE OPERAFLE.
HOT APP 8.ICABLE ROCKWELL MANUFACTURING CO.
HOT APP 8.ICABLE ROCKWELL MANUFACTURING CO.
THE Ct9SE OF THE OCCURRENCE WAS INADEQUATE LUBRICATION OF THE VALVE STEM
THE Ct9SE OF THE OCCURRENCE WAS INADEQUATE LUBRICATION OF THE VALVE STEM
                                                                                                                                                                                . THE VALVE STEM WAS CLEANED, LUBRICATED.AND TESTED SATISFACTORILY.
. THE VALVE STEM WAS CLEANED, LUBRICATED.AND TESTED SATISFACTORILY.
TROJAN-1                                                                                       05000344       011281             NO. 81-04:                   DURING A PERIODIC OPERATING TEST OF THE "B" CONTAINMENT SPRA AIR COND, HEAT, COOL, VENT SYSTEM                                                       81-004/03L-0         021881             Y PUMP, THE FAN COOLING UNIT FOR THE. PUMP DID NOT AUTOMATICALLY-START.
TROJAN-1 05000344 011281 NO. 81-04:
CIRCUIT CLOSERS / INTERRUPTERS                                                                     036254     30-DAY             NORMAL BUILDING VENTILATION WAS AVAILABLE FOR COOLING AND THE PUMP COULD CIRCUIT BREAKER                                                                                                                   HAVE OPERATED FOR AN EXTENDED PERIOD CL TIME.                     FSAR 9.4.2 STATES THAT L COMPONENT FAILURE OCAL COOLING FANS BACK-UP BUILDINA VENTILATION.
DURING A PERIODIC OPERATING TEST OF THE "B" CONTAINMENT SPRA AIR COND, HEAT, COOL, VENT SYSTEM 81-004/03L-0 021881 Y PUMP, THE FAN COOLING UNIT FOR THE. PUMP DID NOT AUTOMATICALLY-START.
CIRCUIT CLOSERS / INTERRUPTERS 036254 30-DAY NORMAL BUILDING VENTILATION WAS AVAILABLE FOR COOLING AND THE PUMP COULD CIRCUIT BREAKER HAVE OPERATED FOR AN EXTENDED PERIOD CL TIME.
FSAR 9.4.2 STATES THAT L COMPONENT FAILURE OCAL COOLING FANS BACK-UP BUILDINA VENTILATION.
ELECTRICAL ITE IMPERIAL CORPORATION THERMAL OVERLOADS ON THE FAN UNIT SUPPLY BREAKER (B-2415) WERE TRIPPED.
ELECTRICAL ITE IMPERIAL CORPORATION THERMAL OVERLOADS ON THE FAN UNIT SUPPLY BREAKER (B-2415) WERE TRIPPED.
OVERLOADS WERE RESET AND FANS STARTED. MAINTENANCE INVESTIGATION OF'TH E BREAKER REVEALED NO EXCESSIVE CURRENT FLOWS.
OVERLOADS WERE RESET AND FANS STARTED. MAINTENANCE INVESTIGATION OF'TH E BREAKER REVEALED NO EXCESSIVE CURRENT FLOWS.
VURKEY POINT-3                                                                                 05000250       111980             DURING POWER OPERATION. A REACTOR TRIP OCCURRED DUE TO STEAM FLOW /FEECWA CONDNSATE + FEEDWTR SYS + CONT                                                         80-024/03L-0         121930'             TER FLOW MISMATCH CONCURRENT WITH tou STEAM GENERATOR WATER LEVEL IN 'A' UALVES                                                                                           033757     30-DAY               STEAM GENERATOR. SUESEQUENT TO REPAIR OF THE APPARENT PROBLEli, FEEDUAT GLOBE                                                                                                                           ER CONTROL PROBLEMS RESULTED IN TWO ADDITIONAL' REACTOR SHUTDOUNS. REPORT C0t1PONENT FAILURE                                                                                                               ABLE PER T.S. 6.9.2.B. PUBLIC HEALTH & SAFETY NOT AFFECTED. AUX FEEDWATE.
VURKEY POINT-3 05000250 111980 DURING POWER OPERATION. A REACTOR TRIP OCCURRED DUE TO STEAM FLOW /FEECWA CONDNSATE + FEEDWTR SYS + CONT 80-024/03L-0 121930' TER FLOW MISMATCH CONCURRENT WITH tou STEAM GENERATOR WATER LEVEL IN 'A' UALVES 033757 30-DAY STEAM GENERATOR. SUESEQUENT TO REPAIR OF THE APPARENT PROBLEli, FEEDUAT GLOBE ER CONTROL PROBLEMS RESULTED IN TWO ADDITIONAL' REACTOR SHUTDOUNS. REPORT C0t1PONENT FAILURE ABLE PER T.S.
MECHANICAL                                                                                                                       R SYS WAS OPER DUAiau OCCURRENCES. USNRC WAS NOTIFIED IN ACCORDANCE WITH COPES-VULCAN, INC.                                                                                                                 10 CFR 50.72 REQUIREMENTS.
6.9.2.B. PUBLIC HEALTH & SAFETY NOT AFFECTED. AUX FEEDWATE.
THE ROOT CAUSE OF THE SERIES OF EVENTS WAS A BROKEN VALVE STEM IN FCV                                                                                                                                                                                 478. STEAM GENERATOR 'A' FEEDWATFA FLOW CONTROL VALVE.                     THE APPARENT CAU SE OF THE STEtt FAILURE WAS . If1 PROPER LOAD DISTRIBUTION BETWEEN THE STEM A HD PLUG DUE TO THE TAPER ON THE VALVE STET 1.                   THE VALVE STEMS ON ALL THRE E VALVES OF BOTH UNIT NO. 3 AND UNIT NO. 4 HAVE BEEN REPLACED.
MECHANICAL R SYS WAS OPER DUAiau OCCURRENCES. USNRC WAS NOTIFIED IN ACCORDANCE WITH COPES-VULCAN, INC.
10 CFR 50.72 REQUIREMENTS.
THE ROOT CAUSE OF THE SERIES OF EVENTS WAS A BROKEN VALVE STEM IN FCV 478. STEAM GENERATOR
'A' FEEDWATFA FLOW CONTROL VALVE.
THE APPARENT CAU SE OF THE STEtt FAILURE WAS. If1 PROPER LOAD DISTRIBUTION BETWEEN THE STEM A HD PLUG DUE TO THE TAPER ON THE VALVE STET 1.
THE VALVE STEMS ON ALL THRE E VALVES OF BOTH UNIT NO. 3 AND UNIT NO. 4 HAVE BEEN REPLACED.


MAR 26. 1981                                     LER MONTHLY REPORT SORTED BY FACILITY                                           PAGE 90 PROCESSED DUkiNG MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT / 9DCKET NO./   EVENT DATE/
MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 90 PROCESSED DUkiNG MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCSD7/CAU3E COLE / LER NO./       REPORT DATE/                                 EVENT DESCRIPTION /
9DCKET NO./
CAUSE SUBCODE/ MANUFACTURER     CONTROL NO. REPORT TYP.                                 CAUSE DESCRIPTION TURKEY POINT-3                       05000250     122980   DURING POWER OPERATION. A DC GROUND WAS EXPERIENCED ON 3B BATTERY BUS.
EVENT DATE/
OTHER ELEC POWER SYS + CONTROL     80-023/03L-0   012881     ?NVESTIGATION SHOWED A PROBLEM MITH CONTROL POWER TO 4160 V BREAKER 3AB1 CIRCUIT CLOSERS / INTERRUPTERS       033689     30-DAY     U. FOR 3B HEATER DRAIN PUMP. WHICH PREVENTED BREAKER FROM BEING REMOTELY CIRCUIT BREAKER                                               TRIPPED. THIS IS REPOR1ABLE PURSUANT TO TECH. SPEC. 6.9.2.B IN THAT THI COMPONENT FAILURS                                           S BREAKER WOULD NOT HAVE TRIPPED TO CLEAR 3B 4160 V BUS IN RESPONSE TO A       i ELECTRICAL                                                   BUS ! TRIPPING SIGNAL. BREAKER WAS TRIPPED MANUALLY.                         '
COMPONENT SUBCSD7/CAU3E COLE / LER NO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYP.
CAUSE DESCRIPTION TURKEY POINT-3 05000250 122980 DURING POWER OPERATION. A DC GROUND WAS EXPERIENCED ON 3B BATTERY BUS.
OTHER ELEC POWER SYS + CONTROL 80-023/03L-0 012881
?NVESTIGATION SHOWED A PROBLEM MITH CONTROL POWER TO 4160 V BREAKER 3AB1 CIRCUIT CLOSERS / INTERRUPTERS 033689 30-DAY U.
FOR 3B HEATER DRAIN PUMP. WHICH PREVENTED BREAKER FROM BEING REMOTELY CIRCUIT BREAKER TRIPPED. THIS IS REPOR1ABLE PURSUANT TO TECH. SPEC. 6.9.2.B IN THAT THI COMPONENT FAILURS S BREAKER WOULD NOT HAVE TRIPPED TO CLEAR 3B 4160 V BUS IN RESPONSE TO A i
ELECTRICAL BUS ! TRIPPING SIGNAL.
BREAKER WAS TRIPPED MANUALLY.
GENERAL ELECTRIC CO.
GENERAL ELECTRIC CO.
INVESTIGATION SHOWED SHORTED CONTROL CIRCUIT WIRING BETWEEN 3AB10 AND IT       !
INVESTIGATION SHOWED SHORTED CONTROL CIRCUIT WIRING BETWEEN 3AB10 AND IT S LOCAL START STATION.
S LOCAL START STATION. FAILURE WAS CAUSED BY STEAM ENTERING ELECTRICAL BOX AND SHORTING OUT CIRCUIT. THIS RESULTED IN BURNING OUT TRIP COIL OF FREAKER. CIRCUIT AND CONDUIT HAVE BEEN #EROUTED AND BREAKER WAS REPLAC FJ WITH A SPARE.
FAILURE WAS CAUSED BY STEAM ENTERING ELECTRICAL BOX AND SHORTING OUT CIRCUIT.
TURKEY POINT-3                       05000250     123080   JURING POWER OPERATION. THE 3A BORIC ACID TRANSFER (BAT) PUMP WAS FOUND CHEM. VOL CONT + LIQ POISN sis     80-029/03L-0   012981     TO BE LEAKING WATER 8 WAS REMOVED FROM SERVICE. OPERATION CONTIP"ED PUR PUMPS                                 t13736     30-DAY     SUANT TO T.S. 3.6.D.2 FOR APPROXIMATELY 20 HOURS BEFORE THE TWO PUMP REQ CENTRIFUDAL                                                 UIREMENT OF T.S. 3.6.B.2 COULD BE MET. AN ALTERNATE DORATION PATH WAS A COMPONENT FAILURE                                           VAILABLE VIA THE 4A BAT PUMP WHICH WAS OPERABLE. BAT PUMP OUTAGES WERE MECHANICAL                                                 PREVIOUSLY REPORTED AS LERS 251-77-2, 251-79-1, 251-79-15. 251-79-16.
THIS RESULTED IN BURNING OUT TRIP COIL OF FREAKER.
CHEMPUMP CORP THE CAUSE OF THE FAILURE WAS FLUID LEAKAGE INTO THE SEALED STATOR ASSEMB LY. THE PUMP WAS REPAIRED AND RETURNED TO SERVICE WITHIN 20 HOURS.
CIRCUIT AND CONDUIT HAVE BEEN #EROUTED AND BREAKER WAS REPLAC FJ WITH A SPARE.
TURKEY POINT-3                       05000250     010181     WHILE PERFORMING THE SURVEILLANCE ON "B" EMERGENCY DIESEL GENERATOR (EDG EMERG GENERATOR SYS + CONTROLS     81-001/03L-0   012981     ) TO IMPLEMENT T/S 4.8.1.A. A LOSS OF VOLTAGE CONTROL WAS EXPERIENCED.
TURKEY POINT-3 05000250 123080 JURING POWER OPERATION. THE 3A BORIC ACID TRANSFER (BAT) PUMP WAS FOUND CHEM. VOL CONT + LIQ POISN sis 80-029/03L-0 012981 TO BE LEAKING WATER 8 WAS REMOVED FROM SERVICE. OPERATION CONTIP"ED PUR PUMPS t13736 30-DAY SUANT TO T.S.
ENGINES. INTERNAL COMBUSTION         036150     30-DAY     THE EDG WAS MANUALLY SHUT DOWN. AN INVESTIGATION REVEALED 4AT TWO FUSES SUBCOMPONENT NOT APPLICABLE                                   ASSOCIATED WITH THE 120 VAC SUPPLY AND VOLTAGE REGULATOR 1RANSFORMER HA-COMPONENT FAILURE                                           D FAILED OPEN.     THE FUSES WERE REPLACED. AND THE EDG TESTED AND RETURNED ELECTRICAL                                                   TO SERVICE WITHIN 12 HOURS. THE REDUNDANT "A" EDG WAS AVAILABLE TO SUP SCHOONMAKER. A.G.                                           PLY ESF EQUIPMENT AS DISCUSSED IN FSAR SECTION 8.
3.6.D.2 FOR APPROXIMATELY 20 HOURS BEFORE THE TWO PUMP REQ CENTRIFUDAL UIREMENT OF T.S.
THE CAUSE OF THE FUSE FAILURE COULD NOT BE DETERMINED. HOWEVER. THE CONT ACT BANDS UERE FOUND TO BE LOOSE ON THE FUSE BODY. THE 2-SIX AMPERE FUS ES WERE REPLACED.     THE ANNUAL SURVEILLANCE ASSOCIATED WITH T/S 4.8.1.C W ILL BE EXPANDED TO INCLUDE CHECKING FUSES ASSOCIATED WITH THE EDGS.
3.6.B.2 COULD BE MET.
TURKEY POINT-3                       05000250     010381   WHILE PERFORMING A PLANNED UNIT SHUTDOWN. THE BORIC ACID FLOMPATH FROM T CHEM. VOL CONT + LIQ POISN SYS     81-002/01T-0   011631     HE BORIC ACID TANKS AS DESCRIBED IN T/S 3.6.B.4 WAS FOUND TO BE OBSTRUCT ELECTRICAL CONDUCTORS                 036131     2-WEEK     ED. THE FLOW PATH WAS RE-ESTABLISHED IN 1 HR. 33 MIN       PU3LIC HEALTH AN SUBCOMPONENT NOT APPLICABLE                                 D SAFETY WAS NOT AFFECTED. THE ALTERNATE FLOW PATH FROM THE REFUELING W COMPONENT FAILURE                                           ATER STORAGE TANK WAS OPERABLE THROUGHOUT THIS PERIOD. REFERENCE FSAR S ELECTRICAL                                                 EC. 9.2.2. SIMILAR OCCURRENCES WERE REPORTED AS A0 251-74-C8. AND LERS CHROMALOX                                                   251-77-11, 251-77-12. AND 251-79-1.
AN ALTERNATE DORATION PATH WAS A COMPONENT FAILURE VAILABLE VIA THE 4A BAT PUMP WHICH WAS OPERABLE. BAT PUMP OUTAGES WERE MECHANICAL PREVIOUSLY REPORTED AS LERS 251-77-2, 251-79-1, 251-79-15. 251-79-16.
THE APPARENT CAUSE OF THE OBSTRUCTION WAS REDUCED TEMPERATURE RESULTING FROM FAILURE OF ONE CHANNEL OF HEAT TRACING CIRCUIT NO. 21         THE CIRCUIT WAS FOUND TO HAVE 4 OPEN SECTIONS AND A PARTIAL GROUND. THE ROOT CAUSE COULD NOT BE DETERMINED. THE TEMPERATURE SETPOINT ON THE REMAINING CHA NNEL WAS INCREASED TO RE-ESTABLISH FLOW. DAT1 AGED CHANNEL WAS REPAIRED.
CHEMPUMP CORP THE CAUSE OF THE FAILURE WAS FLUID LEAKAGE INTO THE SEALED STATOR ASSEMB LY.
THE PUMP WAS REPAIRED AND RETURNED TO SERVICE WITHIN 20 HOURS.
TURKEY POINT-3 05000250 010181 WHILE PERFORMING THE SURVEILLANCE ON "B" EMERGENCY DIESEL GENERATOR (EDG EMERG GENERATOR SYS + CONTROLS 81-001/03L-0 012981
) TO IMPLEMENT T/S 4.8.1.A.
A LOSS OF VOLTAGE CONTROL WAS EXPERIENCED.
ENGINES. INTERNAL COMBUSTION 036150 30-DAY THE EDG WAS MANUALLY SHUT DOWN. AN INVESTIGATION REVEALED 4AT TWO FUSES SUBCOMPONENT NOT APPLICABLE ASSOCIATED WITH THE 120 VAC SUPPLY AND VOLTAGE REGULATOR 1RANSFORMER HA-COMPONENT FAILURE D FAILED OPEN.
THE FUSES WERE REPLACED. AND THE EDG TESTED AND RETURNED ELECTRICAL TO SERVICE WITHIN 12 HOURS.
THE REDUNDANT "A" EDG WAS AVAILABLE TO SUP SCHOONMAKER. A.G.
PLY ESF EQUIPMENT AS DISCUSSED IN FSAR SECTION 8.
THE CAUSE OF THE FUSE FAILURE COULD NOT BE DETERMINED. HOWEVER. THE CONT ACT BANDS UERE FOUND TO BE LOOSE ON THE FUSE BODY.
THE 2-SIX AMPERE FUS ES WERE REPLACED.
THE ANNUAL SURVEILLANCE ASSOCIATED WITH T/S 4.8.1.C W ILL BE EXPANDED TO INCLUDE CHECKING FUSES ASSOCIATED WITH THE EDGS.
TURKEY POINT-3 05000250 010381 WHILE PERFORMING A PLANNED UNIT SHUTDOWN. THE BORIC ACID FLOMPATH FROM T CHEM. VOL CONT + LIQ POISN SYS 81-002/01T-0 011631 HE BORIC ACID TANKS AS DESCRIBED IN T/S 3.6.B.4 WAS FOUND TO BE OBSTRUCT ELECTRICAL CONDUCTORS 036131 2-WEEK ED.
THE FLOW PATH WAS RE-ESTABLISHED IN 1 HR. 33 MIN PU3LIC HEALTH AN SUBCOMPONENT NOT APPLICABLE D SAFETY WAS NOT AFFECTED.
THE ALTERNATE FLOW PATH FROM THE REFUELING W COMPONENT FAILURE ATER STORAGE TANK WAS OPERABLE THROUGHOUT THIS PERIOD.
REFERENCE FSAR S ELECTRICAL EC.
9.2.2.
SIMILAR OCCURRENCES WERE REPORTED AS A0 251-74-C8. AND LERS CHROMALOX 251-77-11, 251-77-12. AND 251-79-1.
THE APPARENT CAUSE OF THE OBSTRUCTION WAS REDUCED TEMPERATURE RESULTING FROM FAILURE OF ONE CHANNEL OF HEAT TRACING CIRCUIT NO. 21 THE CIRCUIT WAS FOUND TO HAVE 4 OPEN SECTIONS AND A PARTIAL GROUND.
THE ROOT CAUSE COULD NOT BE DETERMINED. THE TEMPERATURE SETPOINT ON THE REMAINING CHA NNEL WAS INCREASED TO RE-ESTABLISH FLOW.
DAT1 AGED CHANNEL WAS REPAIRED.


MAR 26, 1981                                               LER MONTHLY REPORT SORTED BY FACILITY                                             PAGE 91 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /         DOCKET NO./   EVENT DATE/
MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 91 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
COMPONENT SUBCODE/CAUSE CODE / LER NO./               REPORT DATE/                                 EVENT DESCRIPTION /
DOCKET NO./
CAUSE SUBCODE/ MANUFACTURER             CONTROL NO. REPORT TYPE                                   CAUSE DESCRIPTION TURKEY POINT-3                                 05000250     010581     IN THE COURSE OF IAVESTIGATING POTENTIAL CRACKS DESERVED IN THE LEXAN CO OTHER ENGNRD SAFETY FEATR SYS               81-003/01T-0   0119G1     IL SPOOLS OF GENERAL ELECTRIC CO. TYPE HFA RELAYS, A NEW CGIL ASSEMBLY I RELAYS                                         036152     2-WEEK     N SPARE PARTS STORAGE WAS CONFIRMED TO HAVE A CRACK IN THE SPOOL END PLA CONTROL, GENERAL PURPOSE                                           TE. THE CONCERN IS THAT A CRACKED SPOOL COULD RESULT IN A BROKEN PIECE DESIGN / FABRICATION ERROR                                           WHICH COULD PREVENT DESIRED CONTACT ACTION.       A COIL INSPECTION PROGRAM W MANUFACTURING                                                       AS ESTABLISHED AND IMPLEMENTED. AN EVALUATION PURSUANT TO 10CFR21 REQMT GENERAL ELECTRIC CO.                                                 5 IS IN FROGRESS. A SIMILAR HFA RELAY PROBLEM WAS REP. AS AD 251-75-8.             i NO OPERATICMAL FAILURE OF THIS TYPE RELAY DUE TO COIL SPOOL CRACKS HAS B           l EEN EXPERIENCED. ONE COIL IN SERVICE WAS FOUND CRACKED AND WAS REPLACED
EVENT DATE/
                                                                      . INSPECTION RESULTS REVEALED POSSIBLE INDICATIONS CN 39 0F THE 184 REL AYS. A PERIODIC INSPECTION WILL BE IMPLEMENTED PENDING RECEIPT OF NEW C OILS AND/OR RELAYS.
COMPONENT SUBCODE/CAUSE CODE / LER NO./
VERMONT YANKEE-1                               05000271     122080     WHILE PERFORMING THE TYPE C LEAK RATE TESTING, RCIC -15 WAS FOUND TO HAV REAC CORE ISOL COOL SYS + CONT             80-043/03L-0   011681     E SEAT LEAKAGE OF 1.531 LBM/HR WHICH IS IN EXCESS OF TECHNICAL SPECIFICA VALVES                                         033690     30-DAY     TION, SECTICH 4.7.A.4.       SINCE A SECOND VALVE IN THE LINE PROVIDED CUNTAI CATE                                                               NMENT ISOLATION, THERE WERE NO ADVERSE CONSEQUENCES TO THE HEALTH AND SA COMPONENT FAILURE                                                     FETY OF THE PUBLIC. THERE HAS BEEN NO SIMILAR OCCURRENCE REPORTED TO TH MECHANICAL                                                         E COMMISSION ON THIS VALVE.
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUBCODE/ MANUFACTURER CONTROL NO.
REPORT TYPE CAUSE DESCRIPTION TURKEY POINT-3 05000250 010581 IN THE COURSE OF IAVESTIGATING POTENTIAL CRACKS DESERVED IN THE LEXAN CO OTHER ENGNRD SAFETY FEATR SYS 81-003/01T-0 0119G1 IL SPOOLS OF GENERAL ELECTRIC CO. TYPE HFA RELAYS, A NEW CGIL ASSEMBLY I RELAYS 036152 2-WEEK N SPARE PARTS STORAGE WAS CONFIRMED TO HAVE A CRACK IN THE SPOOL END PLA CONTROL, GENERAL PURPOSE TE.
THE CONCERN IS THAT A CRACKED SPOOL COULD RESULT IN A BROKEN PIECE DESIGN / FABRICATION ERROR WHICH COULD PREVENT DESIRED CONTACT ACTION.
A COIL INSPECTION PROGRAM W MANUFACTURING AS ESTABLISHED AND IMPLEMENTED. AN EVALUATION PURSUANT TO 10CFR21 REQMT GENERAL ELECTRIC CO.
5 IS IN FROGRESS. A SIMILAR HFA RELAY PROBLEM WAS REP. AS AD 251-75-8.
i NO OPERATICMAL FAILURE OF THIS TYPE RELAY DUE TO COIL SPOOL CRACKS HAS B l
EEN EXPERIENCED. ONE COIL IN SERVICE WAS FOUND CRACKED AND WAS REPLACED
. INSPECTION RESULTS REVEALED POSSIBLE INDICATIONS CN 39 0F THE 184 REL AYS.
A PERIODIC INSPECTION WILL BE IMPLEMENTED PENDING RECEIPT OF NEW C OILS AND/OR RELAYS.
VERMONT YANKEE-1 05000271 122080 WHILE PERFORMING THE TYPE C LEAK RATE TESTING, RCIC -15 WAS FOUND TO HAV REAC CORE ISOL COOL SYS + CONT 80-043/03L-0 011681 E SEAT LEAKAGE OF 1.531 LBM/HR WHICH IS IN EXCESS OF TECHNICAL SPECIFICA VALVES 033690 30-DAY TION, SECTICH 4.7.A.4.
SINCE A SECOND VALVE IN THE LINE PROVIDED CUNTAI CATE NMENT ISOLATION, THERE WERE NO ADVERSE CONSEQUENCES TO THE HEALTH AND SA COMPONENT FAILURE FETY OF THE PUBLIC.
THERE HAS BEEN NO SIMILAR OCCURRENCE REPORTED TO TH MECHANICAL E COMMISSION ON THIS VALVE.
WALWORTH CO.
WALWORTH CO.
THE VALVE SEATING SURFACES WERE LAPPED AND THE VALVE WAS SATISFACTORILY RETESTED PRIOR TO PLANT STARTUP PER TECHNICAL SPECIFICATION, SECTION 3.7
THE VALVE SEATING SURFACES WERE LAPPED AND THE VALVE WAS SATISFACTORILY RETESTED PRIOR TO PLANT STARTUP PER TECHNICAL SPECIFICATION, SECTION 3.7
                                                                      .A.4. THE VALVE FAILURE WILL ALSO BE REPORTED IN ACCORDANCE WITH APPEND IX J,   10 CFR 50, V.B.3.
.A.4.
VERMONT YANKEE-1                               05000271     122930   DURING STARTUP AT 24 PERCENT POWER, ROUTINE OPERATOR SURVEILLANCE DISCOV REAC COOL CLEANUP SYS + CONT               80-041/03L-0   012881     ERED WATER LEAKAGE FROM THE 4 INCH. REACTOR WATER CLEANUP LINE 3. UPON PIPES, FITTINGS                               033737     30-DAY   CLOSE INSPECTION, TWO AREAS OF WATER WEEPAGE WERE FOUND.         THERE WERE NO 4 TO 6 INCHES                                                     CONSEQUENCES TO THE PUBLIC HEALTH AND SAFETY AS A RESULT OF THIS EVENT.
THE VALVE FAILURE WILL ALSO BE REPORTED IN ACCORDANCE WITH APPEND IX J, 10 CFR 50, V.B.3.
COMPONENT FAILURE                                                     SIMILAR OCCURRENCES WERE REPORTED TO THE COMMISSION AS LER 80-37 8 79-0 CORROSION                                                           1.
VERMONT YANKEE-1 05000271 122930 DURING STARTUP AT 24 PERCENT POWER, ROUTINE OPERATOR SURVEILLANCE DISCOV REAC COOL CLEANUP SYS + CONT 80-041/03L-0 012881 ERED WATER LEAKAGE FROM THE 4 INCH. REACTOR WATER CLEANUP LINE 3.
UNITED STATES STEEL CORP, REACTOR CLEANUP LINE WAS ISOLATED 8 AFFECTED PORTION OF PIPE WAS REPLACE D WITH A LOW CARBON STAINLESS STEEL PIPE. PIPE MATERIAL FROM REGENERATI VE TO HONREGENERATIVE HEAT EXCHANGER WAS ASTM-A-312, TYPE 304.           A SAMPLE OF THIS PIPE WILL BE SENT TO A LABORATORY FOR ANALYSIS OF THE FAILURE M ODE, AND THE RESULTS PROVIDED IN A SUBSEQUENT REPORT.
UPON PIPES, FITTINGS 033737 30-DAY CLOSE INSPECTION, TWO AREAS OF WATER WEEPAGE WERE FOUND.
VERMONT YANKEE-1                               05000271     010681   DURING THE WEEKLY REVIEW OF SURVEILLANCE TESTING DATA, IT WAS DISCOVERED SYSTEM CODE NOT APPLICABLE                 81-002/03L-0   020581     THAT QUARTERLY STACK PARTICULATE COMPOSITE AS REQUIRED BY T.S. 4.8.C.3.
THERE WERE NO 4 TO 6 INCHES CONSEQUENCES TO THE PUBLIC HEALTH AND SAFETY AS A RESULT OF THIS EVENT.
COMFONENT CODE NOT APPLICABLE                 036153     30-DAY   D COULD NOT BE COMPLETED BECAUSE STACK SAMPLE FILTERS FOR THE MONTH OF 0 SUBCOMPONENT NOT APPLICABLE                                         CTOBER WERE MISPLACED. SIHCE PLANT WAS SHUTDOWN AT THAT TIME AND AN ANA PERSONNEL ERROR                                                     LYSIS OF DATA FROM REMAINING 1.ACK SAMPLE FILTERS INDICATED NO UNUSUAL A RADIATION PROTECTION PERSONNEL                                     CTIVITY, Il IS CONCLUDED " ARF WERE NO CONSEQUENCES TO HEALTH AND SAFETY ITEM NOT APPLICABLE                                                   OF PUBLIC. 'HFRE WERF a0 PR' JICUS OCCURRENCES OF THIS TYPE.
COMPONENT FAILURE SIMILAR OCCURRENCES WERE REPORTED TO THE COMMISSION AS LER 80-37 8 79-0 CORROSION 1.
THE STACK SAMPLE rititRS FOR CCTOBER WERE MISPLACED. APPLICABLE PERSONN EL HAVE BEEN WEINSTRUCTED AS TO THE LOCAIION AND PROPER STORAGE OF THE S TACK SAMPLE FILTERS AFTER THE MONTHLY ANALYSIS IS PERFORMED.
UNITED STATES STEEL CORP, REACTOR CLEANUP LINE WAS ISOLATED 8 AFFECTED PORTION OF PIPE WAS REPLACE D WITH A LOW CARBON STAINLESS STEEL PIPE.
PIPE MATERIAL FROM REGENERATI VE TO HONREGENERATIVE HEAT EXCHANGER WAS ASTM-A-312, TYPE 304.
A SAMPLE OF THIS PIPE WILL BE SENT TO A LABORATORY FOR ANALYSIS OF THE FAILURE M ODE, AND THE RESULTS PROVIDED IN A SUBSEQUENT REPORT.
VERMONT YANKEE-1 05000271 010681 DURING THE WEEKLY REVIEW OF SURVEILLANCE TESTING DATA, IT WAS DISCOVERED SYSTEM CODE NOT APPLICABLE 81-002/03L-0 020581 THAT QUARTERLY STACK PARTICULATE COMPOSITE AS REQUIRED BY T.S. 4.8.C.3.
COMFONENT CODE NOT APPLICABLE 036153 30-DAY D COULD NOT BE COMPLETED BECAUSE STACK SAMPLE FILTERS FOR THE MONTH OF 0 SUBCOMPONENT NOT APPLICABLE CTOBER WERE MISPLACED. SIHCE PLANT WAS SHUTDOWN AT THAT TIME AND AN ANA PERSONNEL ERROR LYSIS OF DATA FROM REMAINING 1.ACK SAMPLE FILTERS INDICATED NO UNUSUAL A RADIATION PROTECTION PERSONNEL CTIVITY, Il IS CONCLUDED " ARF WERE NO CONSEQUENCES TO HEALTH AND SAFETY ITEM NOT APPLICABLE OF PUBLIC.
'HFRE WERF a0 PR' JICUS OCCURRENCES OF THIS TYPE.
THE STACK SAMPLE rititRS FOR CCTOBER WERE MISPLACED.
APPLICABLE PERSONN EL HAVE BEEN WEINSTRUCTED AS TO THE LOCAIION AND PROPER STORAGE OF THE S TACK SAMPLE FILTERS AFTER THE MONTHLY ANALYSIS IS PERFORMED.
f.
f.
                                                                                                ~*
~*


LER MONTHLY REPORT SORTED BY FACILITY                                                       PAGE 92 MAR 26, 1981 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /   DOCKET NO./   EVENT DATE/                                                                                               -
LER MONTHLY REPORT SORTED BY FACILITY PAGE 92 MAR 26, 1981 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /
                                    ;/ LER NO./       REPORT DATE/                                           EVENT DESCRIPTIDH/
DOCKET NO./
COMPONENT SUBCODE/CAUSE C'                                                                              CAUSE DESCRIPTION CAUSE SUBCODE/MANUFACTUk t         CONTROL NO. REPORT TYPE' 05000271     010681         DURING THE WEEKLY REVIEW OF SURVEILLANCE TESTING DATA, IT WAS DISCOVERED VERMONT YANKEE-1 SYSTEM CODE NOT APPLICABLE             81-003/03L-0   020681           THAT THE SURVEILLANCE FREQUENCY FOR THE MONTHLY DIESEL FUEL OIL QUALITY 036154     30-DAY           ANALYSIS WAS EXCEEDED.       SINCE-THE ANALYSIS WAS IMMEDIATELY AND SUCCESSF COMPONENT CODE NOT APPLICABLE SUBCOMPONENT NOT APPLICABLE                                         ULLY DONE AND EACH DELIVERY OF FUEL OIL IS ANALYZED PRIOR TO STORAGE IN PERSONNEL ERROR                                                      THE PLANT TANK. IT IS CONCLUDED THAT THERE WERE NO CONSEQUENCES TO THE H RADIATION PROTECTION PERSONNEL                                     EALTH AMD SAFETY OF THE PUBLIC. OTHER OCCURRENCES WERE REPORTED AS RO 8 ITEM NOT APPLICABLE                                                  0-34/3L. RO 80-05/3L AND RO 79-12/3L.
EVENT DATE/
THE ANALYSIS WAS NOT PERFORMED AS SCHEDULED DUE TO PERSONNEL OVERSIGHT.
COMPONENT SUBCODE/CAUSE C'
;/ LER NO./
REPORT DATE/
EVENT DESCRIPTIDH/
CAUSE SUBCODE/MANUFACTUk t CONTROL NO.
REPORT TYPE' CAUSE DESCRIPTION VERMONT YANKEE-1 05000271 010681 DURING THE WEEKLY REVIEW OF SURVEILLANCE TESTING DATA, IT WAS DISCOVERED SYSTEM CODE NOT APPLICABLE 81-003/03L-0 020681 THAT THE SURVEILLANCE FREQUENCY FOR THE MONTHLY DIESEL FUEL OIL QUALITY COMPONENT CODE NOT APPLICABLE 036154 30-DAY ANALYSIS WAS EXCEEDED.
SINCE-THE ANALYSIS WAS IMMEDIATELY AND SUCCESSF SUBCOMPONENT NOT APPLICABLE ULLY DONE AND EACH DELIVERY OF FUEL OIL IS ANALYZED PRIOR TO STORAGE IN THE PLANT TANK. IT IS CONCLUDED THAT THERE WERE NO CONSEQUENCES TO THE H PERSONNEL ERROR RADIATION PROTECTION PERSONNEL EALTH AMD SAFETY OF THE PUBLIC.
OTHER OCCURRENCES WERE REPORTED AS RO 8 0-34/3L. RO 80-05/3L AND RO 79-12/3L.
ITEM NOT APPLICABLE THE ANALYSIS WAS NOT PERFORMED AS SCHEDULED DUE TO PERSONNEL OVERSIGHT.
THE ANALYSIS WAS IMMEDIATELY PERFORMED WITH SATISFACTORY RESULTS. APPL ICABLE PERSONNEL HAVE BEEN REINSTRUCTED IN THE REQUIREMENTS OF THE SURVE ILLANLE TESTING PROGRAM.
THE ANALYSIS WAS IMMEDIATELY PERFORMED WITH SATISFACTORY RESULTS. APPL ICABLE PERSONNEL HAVE BEEN REINSTRUCTED IN THE REQUIREMENTS OF THE SURVE ILLANLE TESTING PROGRAM.
YANKEE ROWE                                 05000029     012281         DURING NORMAL OPERATION IN MODE 1. WHILE PERFORMING MONTHLY SURVEILLANCE REACTOR TRIP SYSTEMS                   81-00t/03L-0   022081           0F LOW MAIN COOLANT FLOM SYSTEM "B". UNDERCURRENT RELAYS 2A AND 4C FAIL-INSTRUMENTATION
YANKEE ROWE 05000029 012281 DURING NORMAL OPERATION IN MODE
* CONTROLS                 036155     50-DAY         ED TO DROP OUT WHEN DEENERGIZED. THE SYSTEMS ARE REQUIRED TO BE OPERATI SENSOR / DETECTOR / ELEMENT                                         OMAL PER TECHNICAL SPECIFICATION TABLE 3.3-1. THIS IS THE FIRST EVENT 0 COMPONENT FAILURE                                                     F THIS NATURE. THE REDUNDANT SYSTEM "A" WAS OPERATIONAL AND WOULD HAVE MECHANICAL                                                         PERFORMED AS REQUIRED. THEREFORE THERE WERE NO ADVERSE EFFECTS TO THE P WESTINGHOUSE ELECTRIC CORP.                                           UCLIC HEALTH OR SAFETY.
: 1. WHILE PERFORMING MONTHLY SURVEILLANCE REACTOR TRIP SYSTEMS 81-00t/03L-0 022081 0F LOW MAIN COOLANT FLOM SYSTEM "B".
THE ROOT CAUSE OF THIS EVENT WAS DUE TO A RESIDUE LUILDUP               DN THE RELAY A CTIVATION PLUNGER. ALL RELAY PLUNGERS IN SYSTEM "B" WERE INSPECTED 1 CL EANED AS NECESSARY. ALL RELAYS IN SYSTEM                 "A" WERE INSPECTED & CLEANING WAS MOT REQUIRED. RELAYS ARE UESTINGHOUSE TYPE SC-1 NO. 1876-072. NO F URTHER ACTIONS ARE DEEMED NECEESSARY AT THIS TIME.
UNDERCURRENT RELAYS 2A AND 4C FAIL-INSTRUMENTATION
ZION-l                                     05000295     121680       DURING NORMAL OPERATION. THE GAS DECAY TANK RAD MONITOR ORT-PR02B WAS TA PRCSS + EFF RADIOL MONITOR SYS         80-055/03L-0 011581           KEN OUT OF SERVICE FOR MAINTENANCE. THE SalFT OPERATING PERSONNEL WERE INSTRUMENTATION + CONTROLS                 033691     30-DAY         IMMEDIATELY NOTIFIED. HOWEVER. SHIFTLY GRAB SAMPLES WERE NOT TAKEN FOR TWO SHIFTS AS REQUIRED BY TECHNICAL SPECIFICATION 3.14,1.C. hJ RELEASES OTHER PERSONNEL ERROR                                                        OCCURRED DURING THIS TIME AND THE HEALTH AND SAFETY OF THE PUBLIC WERE LICENSED 8 SENIOR OPERATORS                                         NOT AFFECTED.
* CONTROLS 036155 50-DAY ED TO DROP OUT WHEN DEENERGIZED. THE SYSTEMS ARE REQUIRED TO BE OPERATI SENSOR / DETECTOR / ELEMENT OMAL PER TECHNICAL SPECIFICATION TABLE 3.3-1.
OTHER A FAILED EQUIPMENT SURVEILLANCE WAS NOT STARTED DUE TO AN OVERSIGHT BY T HE SHIFT OPERATING PERSONNEL.                 THE PERSONNEL INVOLVED HAVE BEEN RE-INSTR UCTED ON THE NECESSITY OF PERFORMING THE REQUIRED SURVEILLANCE ON FAILED EQUIPMENT. NO FURTHER ACTION IS NECESSARY.
THIS IS THE FIRST EVENT 0 COMPONENT FAILURE F THIS NATURE.
05000295     122680         DURING NORMAL OPERATION, THE GAS DECAY TAKr CUBICLE RAD MONITOR ORT-PR02 ZION-1 GAS RADI0ACT WSTE MANAGMNT SYS         80-056/03L-0   012381         B FAILED TO RESPOND TO ITS INTERNAL CHECK SUURCES OR TO AN EXTERNAL SOUR INSTRUMENTATION + CONTROLS                 033692     30-DAY         CE. THE MONITOR WAS TAKEN OUT OF SERVICE AND SHIFTLY GRAB SAMPLES WERE COMPUTATION MODULE                                                  TAKEN AS REQUIRED BY TECHNICAL SPECIFIC & TION 3.14.1.C. THERE WERC NO SA OTHER                                                                FETY IMPLICATIONS AND THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE N NOT APPLICABLE                                                     OT AFFECTED.
THE REDUNDANT SYSTEM "A" WAS OPERATIONAL AND WOULD HAVE MECHANICAL PERFORMED AS REQUIRED. THEREFORE THERE WERE NO ADVERSE EFFECTS TO THE P WESTINGHOUSE ELECTRIC CORP.
UCLIC HEALTH OR SAFETY.
THE ROOT CAUSE OF THIS EVENT WAS DUE TO A RESIDUE LUILDUP DN THE RELAY A CTIVATION PLUNGER.
ALL RELAY PLUNGERS IN SYSTEM "B" WERE INSPECTED 1 CL EANED AS NECESSARY.
ALL RELAYS IN SYSTEM "A" WERE INSPECTED & CLEANING WAS MOT REQUIRED. RELAYS ARE UESTINGHOUSE TYPE SC-1 NO. 1876-072.
NO F URTHER ACTIONS ARE DEEMED NECEESSARY AT THIS TIME.
ZION-l 05000295 121680 DURING NORMAL OPERATION. THE GAS DECAY TANK RAD MONITOR ORT-PR02B WAS TA PRCSS + EFF RADIOL MONITOR SYS 80-055/03L-0 011581 KEN OUT OF SERVICE FOR MAINTENANCE. THE SalFT OPERATING PERSONNEL WERE INSTRUMENTATION + CONTROLS 033691 30-DAY IMMEDIATELY NOTIFIED. HOWEVER. SHIFTLY GRAB SAMPLES WERE NOT TAKEN FOR TWO SHIFTS AS REQUIRED BY TECHNICAL SPECIFICATION 3.14,1.C.
hJ RELEASES OTHER OCCURRED DURING THIS TIME AND THE HEALTH AND SAFETY OF THE PUBLIC WERE PERSONNEL ERROR LICENSED 8 SENIOR OPERATORS NOT AFFECTED.
OTHER A FAILED EQUIPMENT SURVEILLANCE WAS NOT STARTED DUE TO AN OVERSIGHT BY T HE SHIFT OPERATING PERSONNEL.
THE PERSONNEL INVOLVED HAVE BEEN RE-INSTR UCTED ON THE NECESSITY OF PERFORMING THE REQUIRED SURVEILLANCE ON FAILED EQUIPMENT. NO FURTHER ACTION IS NECESSARY.
ZION-1 05000295 122680 DURING NORMAL OPERATION, THE GAS DECAY TAKr CUBICLE RAD MONITOR ORT-PR02 GAS RADI0ACT WSTE MANAGMNT SYS 80-056/03L-0 012381 B FAILED TO RESPOND TO ITS INTERNAL CHECK SUURCES OR TO AN EXTERNAL SOUR INSTRUMENTATION + CONTROLS 033692 30-DAY CE.
THE MONITOR WAS TAKEN OUT OF SERVICE AND SHIFTLY GRAB SAMPLES WERE TAKEN AS REQUIRED BY TECHNICAL SPECIFIC & TION 3.14.1.C.
THERE WERC NO SA COMPUTATION MODULE IMPLICATIONS AND THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE N FETY OTHER NOT APPLICABLE OT AFFECTED.
NUCLEAR MEASUREMENTS CORP.
NUCLEAR MEASUREMENTS CORP.
THE FAILURE WAS DUE TO BAD ELECTRICAL CONTACTS ON THE PRINTED CIRCUIT B0 ARD (NMC P/N CRM 70). THESE CONTACTS WERE REPAIRED. THE MONITCR WAS TH EN FUNCTIONALLY TESTED AND RETURNED TO SERVICE. THIS IS THE FIRST OCCUR RENCE OF THIS TYPE FOR THE MONITOR AND NO FURTHER CORRECTIVE ACTION IS N ECESSARY.
THE FAILURE WAS DUE TO BAD ELECTRICAL CONTACTS ON THE PRINTED CIRCUIT B0 ARD (NMC P/N CRM 70).
_ __ . - . , ~ _ . _ , , . .
THESE CONTACTS WERE REPAIRED.
THE MONITCR WAS TH EN FUNCTIONALLY TESTED AND RETURNED TO SERVICE. THIS IS THE FIRST OCCUR RENCE OF THIS TYPE FOR THE MONITOR AND NO FURTHER CORRECTIVE ACTION IS N ECESSARY.
_ __. -., ~ _. _,,.


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Latest revision as of 18:37, 12 December 2024

Forwards Computer List Providing Info Re LERs Entered Into Data Base for Mar 1981
ML20126H548
Person / Time
Issue date: 03/27/1981
From: Boyle E
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
References
NUDOCS 8104150440
Download: ML20126H548 (93)
v • d • e


Text

g[en aic,"h o

UNITE D 'i T ATES 3

g NUCLEAR REGULATORY COMMISSION

j WASHINGTON, D. C. 20555 c

/

t.lah 3 7 rM LER MONTHLY REPORT The enclosed computer listing, as identified on the attached sheet, provides information concerning Licensee Event Reports (LERs) entered into the data base during the month of March.

If you desire additional information or special searches, please feel free to contact me on 301/492 4834.

Sincerely,

/

o c

Eugen a L. Boyle Data Management Unit Office for Analysis and Evaluation of Operational Data

Enclosure:

As stated I

I i

j l

clo41sotyjo

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 1 PROCESSED DURING MARCH, 1931 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION ARKANSAS-1 05000313 011381 DURING REFUELING SHUTDOWN, WHILE INSTALLING A SIX INCH CONDUIT PENETRATI FIRE PROTECTION SYS + CONT 81-003/03L-0 020981 NG THE FLOOR OF THE COMPRESSOR ROOM (FIRE ZONE 76-W) BETWEEN THE NORTH W COMPONENT CODE NOT APPLICABLE 036078 30-DAY ALL AND COMPRESSOR C2B, THE PENETRATION FIRE BARRIER WAS REMOVED AND A C SUBCOMPONENT NOT APPLICABLE ONTINUOUS FIRE WATCH WAS NOT ESTABLISHED AS REQUIRED BY TECH. SPEC. 3.21 PERSONNEL ERROR

.2.

THERE HAVE BEEN NO SIMILAR OCCURRENCES ON UNIT 1.

REPORTABLE PER T MAINTENANCE

  • REPAIR PERSONNEL ECH. SPEC. 6.12.3.2.B.

ITEM NOT APPLICABLE A FIRE WATCH WAS ESTABLISHED UPON DISCOVERY AND MAINTAINED UNTIL THE FIR E BARRIER WAS INSTALLED. OCCURRENCE CAUSED BY INADEQUATE INSTRUCTIONS T 0 CONTRACTOR PERSONNEL.

THE CONTRACTOR HAS BEEN INSTRUCTED TO MAINTAIN A FIREWATCH WHENEVER PENETRATIONS ARE OPENED AND TO SEAL PENETRATIONS AS QUICKLY AS POSSIBLE. CONTRACTAR PROCEDURES HAVE BEEN MODIFIED.

ARKANSAS-2 05000368 070380 DURING MODE 1 OPERATION, WHILE MAKING A ROUTINE CHECK OF THE PLANT RADIA AREA MONITORING SYSTEMS 80-047/03X-1 020681 TION MONITORING SYSTEM (RMS), THE CONTAINMENT ATMOSPHERE RADIATION MONIT INSTRUMENTATION + CONTROLS 032093 OTHER OR, 2RITS-8271, WAS FOUND TO BE IHOPERABLE. THE CONTAINMENT SUMP LEVEL TRANSMITTER AND CONTAINMENT BUILDING AREA MONITORS REMAINED OPERABLE. NO SIMILAR OC DESIGN / FABRICATION ERROR CURRENCES. OTHER RMS OCCURRENCES WERE LER'S 50-368/79-057,79-067, 80-0 CONSTRUCTION / INSTALLATION 43 AND 80-046.

REPORTABLE PER T.S. 6.9.1.9.B.

WESTINGHOUSE ELECTRIC CORP.

MONITOR'S VACUUM PUMP THERMAL DVERLOAD TRIPPED DUE TO HIGH AMBIENT TEMPE RATURE IN NORTH PIPING PENETRATION ROOM (MONITOR LOCATION). OVERLOAD RE SET 2 MONITOR DECLARED OPERABLE. PIPE INSULATION, PACKING LEAK HEAT LOA DS 2 POOR COOLING AIR FLOW WERE CAUSES. VENTILATION SYSTEM AIR DUCTS WE RE RELOCATED.

ARKANSAS-2 05000363 072780 IN MODE I, CORE OPERATING LIMITS SUPERVISORY SYSTEM WAS DECLARED IN0PERA OTHR INST SYS NOT REQD FR SFTY 80-059/03X-1 011981 BLE ON TWO OCCASIONS. ON 7/27/80 COLSS PLANT COMPUTER PROGRAM INDICATED INSTRUMENTATION + CONTROLS 032202 OTHER A POWER MARGIN OF -80?. RATHER THAN EXPECTED 0% AT RATED POWER.

ON 12/31 COMPUTATION MODULE

/80 COLSS PROGRAM OUTPUT DATA WOULD NOT UPDATE. ACTION INITIATED TO RED COMPONENT FAILURE UCE POWER TO BRING CPC INDICATED LPD & DNBR VALUES WITHIN LIMITS OF TECH ELECTRONIC NICAL SPECIFICATION 3.2.4 4 FIG 3.2-3.

SIMILAR TO LER 50-368/80-032.

SYSTEMS ENGINEER. LABS., INC.

ON 7/27/80 INTEGRATED DETECTOR FLUX ARRAY (TPHI) BECAME ALTERED, AFFECTI NG COLSS CORE POWER DISTRIBUTION CALCULATORS. ON 12/31/80, A DISC INPUT

/0UTPUT FAILURE OCCURRED ON FIXED HEAD DISK SOFTWARE. DIAGNOSTICS DID H t

OT REVEAL CAUSE.

INTERMITTENT HARDWARE FAILURE SUSPECTED. FAILURES COR RECTED BY RELOADING APPROPRIATE SOFTWARE.

ARKANSAS-2 05000368 112980 HIGH PRESSURE SAFETY INJECTION VALVE 2CV-5056 FAILED TO CLOSE-ON 11/29/8 EMERG CORE COOLING SYS + CONT 80-087/03X-1 012081 O WHILE PERFORMING ROUTINE LEVEL ADJUSTMENTS OF SAFETY INJECTION TANK 2T CIRCUIT CLOSERS / INTERRUPTERS 033375 OTHER

-2C IN MODE 1 8 ON 12/21/80 WHILE PERFORMING SURVEILLANCE STROKE TEST M0 CIRCUIT BREAKER DE 2.

HPSI VALVE WAS PLACED IN OPEN POSITION, BUT CONSIDERED INOPERABLE COMPONENT FAILURE AS VALVE REQUIRED TO BE THROTTLED TO MEET TECH. SPEC. 4.5.2.H.

LOOP 1 ELECTRICAL HPSI SYSTEM. REMAINED OPERABLE.

ITEM NOT APPLICABLE INVESTIGATION REVEALED A BLOWN CONTROL POWER FUSE.

CAUSE OF FUSE FAILUR E WAS NOT IDENTIFIED.. NO ABNORMALITIES WERE IDENTIFIED DURING CHECKOUT.

FUSE WAS REPLACED, VALVE WAS STROKE TESTED AND DECLARED OPERABLE. CAU SE OF THE FUSE FAILURE WILL BE INVESTIGATED FURTHER.

=

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 2 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DEstRIPTION/

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION ARKANSAS-2 05000368 010281 DURING MODE 1 OPERATION, A LEAK WAS IDENTIFIED AT A VENT LINE bcLD ON CH CHEM, VOL CDNT + LIQ POISH SYS 81-0G1/03L-0 012781 ARGING PUMP SUCTION STABILIZER, 2M115C.

THE LEAK WAS IS7 LATED RENDERING PIPES, FITTINGS 036017 30-DAY CHARGING PUMP, 2P36C, INOPERABLE. THE REDUNDANT CHARGING PUMPS AND THE LESS THAN 4 INCHES THREE HIGH PRESSURE INJECTION PUMPS REMAINED AVAILABLE FOR BORATION PAT COMPONENT FAILURE HS.

N3 SIMILAR OCCURRENCES; HOWEVER. THIS OCCURRENCE IS RELATED TO LER METALLURGICAL 50-368/80-090.

REPORTABLE PER TECHNICAL SPECIFICATION 6.9.t.9.D.

OTHER THE SUBJECT WELD WAS MADE DURING PIPF SPDDL PIECE REPLACEMENT DUE YO A C HARGING PUNP SUCTICH HEADER LEAK (SEE LER 50-368/80-4401.

THE PINH9LE L EAK WAS CAUSED bY f. DISSOLYING SLAG INCLUSION. THE MELD WAS REPAIRED AN D THE CHARGING PUMP, 2P36C, DECLARED OPERABLE.

ARKANSAS 2 05000368 010681 DURING A REVIEN OF BLOCK WALLS, PURSUANT TO I.E. BULLETIN 80-11, IT WAS AIR COND. HEAT COOL, VENT SYSTEM 81-002/03L-0 020281 IDENTIFIED THAT A POSTULATED FAILURE DF MASONRY WALL, 24-B-217/218 NOUL OTHER COMPONENTS 036018 30-DAY D RESULT IN LOSS OF CABLES 2BS3L1 AND 2BS3L2, WHICH FEED CONTAINMENT C00 SUBCOMPONENT NOT APPLICABLE LING FANS 2VSF-1A/B.

BOTH CONTAINMENT SPRAY LOOFS WOULD REMAIM GPERABL DESIGN / FABRICATION ERROR E. AS WILL THE REDUNDANT CONTAINMENT COOLING UNIT GR9GP.

NO SIMILAR OCC DESIGN URRENCES. REPORTABLE PER TECHNICAL SPECIFICATION 6 < *.1.9'.B.

IT EM NOT APPLICABLE DESIGN CRITERIA SPECIFIED IN I.E. BULIETIN 80-11 NAS MORE RESTRICTIVE TH AN THAT USED IN THE DRIGINAL DESIGN. WHEN MASONRY WALL WAS RE-AHALYZED UNDER THE NEW CRITERIA. TFE POSSIBLE WALL FAILURE WAS IDENTIFIED. THE W ALL MAS BRACED IN ACCDRDAHCE WITH THE NEW DESIGN CRITERIA WITHIN THE TIM E REQUIREMENT OF ACTION STATEMENT D.

OF TECH. SPEC. 3.6.2.3.

.QRKANSAS-2 05000368 011381 DURING MODE 1 OPERATION, THE PLANT COMPUTER FAILED AND WOULD NOT RESTART O'HR INST SYS NOT REQD FR SFTY 81-003/03L-0 020381 RENDERING THE CORE OPERATING LIMITS SUPERVISORY SYSTEM (COLSS) IN0PERA Ib3YRUMENTATION + CONTROLS 036079 30-DAY BLE.

ACTION WAS TAKEN TO REDUCE POWER TO BRING THE CORE PROTECTION CALC ODMPUTATION MODULE ULATOR (CPC) INDICATED LPD A DNBR VALUES WITHIH THE LIMITS OF TECH. SPEC CtMPONENT FAILURE

. 3.2.4 AND TECH. SPEC. FIGURE 3.2-3.

SIMILAR TO LER'S 50-368/80-082, 8 INSTRUMENT 0-041, AND 80-032.

REPORTABLE PER TECH. SPEC.

6.9.1.9.B.

SYSTEMS ENGINEER. LABS., INC.

THE COMPUTER HAD A PARITY ERROR CAUSED BY A CAPACITOR IN THE FLOATING PO INT POWER SUPPLY, GENERATING NOISE DUF TO A SHORT.

THE CAPACITOR WAS RE PLACED, POWER SUPPLY ADJUSTED FOR PROPER OPERATION, AND COMPUTER DIAGNOS TICS SUCCESSFULLY RUN WITH NO ERRORS DETECTED. COLSS WAS RETURNED TO OP ERABLE STATUS AND NORMAL POWER OPERATION WAS CONTINUED.

r BEAVER VALLEY-1 05000334 060879 IN JUNE, 1979. TWO POWER CABLES ORIGINATJMG AT THE 1B LOW HEAD SAFETY IN EMERG CCRE COOLING SYS + COMT 79-016/03X-2.

012881 JECTION PUMP HEADER ISOLATION VALVE AND THE FUMP SUCTION VALVE WERE FOUN ELECTRICAL CONDUCTORS 026480 OTHER D INCORRECTLY ROUTED THROUGH TWO HON-COLOR-CDDED CABLE TRAYS, AS A RESU SUBCOMPONENT NOT APPL'ICABLE LT OF THESE FINDINGS, A CABLE SAMPLING PROGRAM WAS INITIATED WHERE AN AD PERSONNEL ERROR DITIONAL 26 CABLES WFRE INSPECTED. NO ROUTING VIOLATIONS WERE DISCOVERE CONSTRUCTION PERSONNEL D.

DURING THE 1980 REFUELING OUTAGE. 10 ADDITIOP^L CABLE ROUTING PROBLE OTHER MS WERE FOUND DURING DESIGN WORK CHANGES.

ORIGINAL TWO CABLES WERE REROUTED IN 1979.

10 CABLE ROUTING PROBLEMS DI SCOVERED IN 1980 HAVE BEEN REROUTED A VERIFIED AS CORRECT UNDER DESIGN C HANGE PACKAGE (DCP3 253.

BECAUSE OF THESE DEFICIENCIES. STATION HAS INI TIATED DCP 393 WHICH CALLS FOR A SECOND CABLE VERIFICATION PROGRAM. ONS ITE ENGINEERING GROUP IS CURRENTLY SETTING UP THIS PROGRAM.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 3 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / (ER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SEAVER VALLEY-1 05000334 092080 THE MOTOR-DRIVEN FIRE PUMP WAS RETURNED FROM WESTINGHOUSE AFTER BEING RE FIRE PROTECTION SYS + CONT 80-069/01X-2 013081 BUILT FOR THE THIRD TIME.

DURING THE PERFORMANCE OF A SURVEILLANCE TEST MOTORS 032599 OTHER ON 1/25/81, MOTOR BEARING PROBLEMS WERE AGAIN OBSERVED. TWO TEMPORARY SUBCOMPONENT NOT APPLICABLE FIRE PUMPS REMAIN AVAILABLE ALONG WITH THE INSTALLED ENGINE-DRIVEN FIRE COMPONENT FAILURE PUMP.

I OTHER OTHER THE CAUSE FOR THIS FAILURE IS BEING INVESTIGATED FURTHER. THE MOTOR HAS BEEN SENT OFF-SITE TO BE REBUILT AGAIN AND THE PUMP WILL BE REMOVED FOR FURTHER INVESTIGATION.

BEAVER VALLEY-1 05000334 111780 AT 1403 HOURS, THE STATION OPERATING SUPERVISOR (505) WAS NOTIFIED OF A EMERG CORE COOLING SYS + CONT 80-394/99X-0 021381 STEAM LINE LOW PRES 5URE BISTABLE IBS-MS-4853 INTERMITTENTLY TRIPPING 8 R INSTRUMENTATION + CONTROLS 033745 DTHER ESETTING. WHEN SOS ACCOMPANIED OPERATOR TO THE PPOCESS-RACKS TO TRIP BI INDICATOR STABLE. THEY OPERATED THE WRONG CHANNEL [BS-MS-4843, IN VIOLATION OF TEC PERSONNEL ERROR H.

SPECS. 3.5.2 8 3.5.3. ECCS SYSTEMS.

THE PUBLIC HEALTH & SAFETY WERE i

LICENSED & SENIOR OPERATORS NOT JEOPARDIZED SINCE ALL ACTIONS OCCURRED IN THE MOST CONSERVATIVE MANN i

OTHER ER.

SAFETY INJECTIONS TO DATE: 15 OPERATIONAL AND 2 PRE-OPERATIONAL.

THIS INCIDENT OCCURRED BECAUSE THE SOS DID NOT LOOK AT THE STATUS PANtl HIMSELF, BUT TOCK THE WORD OF ANOTHER PERSON INVOLVED IN PLANT OPERATION S.

THE REQUIPED READING INCIDENT REPORT DISTRIBUTION IS BEING USED TO I NDICATE THE NEED TO RECHECK IMPORTANT EVOLUTIONS SUCH AS TRIPPING BISTAB LES.

BEAVER VALLEY-1 05000335 120680 CCRING PERFORhANCE OF MAINTENANCE SURVEILLANCE PROCEDURE MSP 46.03B, FOR CNTHMNT COMBUS GAS CONTROL -SYS 80-108/03X-1 021881 CALIBRATION OF HYDROGEN ANALYZER H2-HY-100B, A FAILED FUNCTION CIRCUIT INSTRUMENTATION + CONTROLS 033490 OTHER CARD WAS FOUND.

THE ANALYZER WAS DECLARED INOPERABLE AT 1025 HOURS PER OTHER TECHNICAL SPECIFI' CATION 3.6.4.1.

THE HEALTH AND SAFETY OF THE PUBLIC WA' COMPONENT FAILURE S NOT JEOPARDIZED SINCE THE 9EDUNDANT ANALYZER WAS AVAILABLE FOR SERVICE ELECTRONIC IF NEEDED, AND THE ANALYZER WAS REPAIRED AND RETURNED TO SERVICE WITHI BENDIX CORP., THE N A SHORT PERIOD OF TIME.

THE FAILURE WAS AN ELECTRONIC CIRCUIT CARD FAILURE. THE FUNCTION CARD W AS REPLACED WITH A NEW ONE FROM STOCK AND THEN MSP 46.03B WAS SUCCESSFUL LY COMPLETED. THE ANALYZER WAS RETURNED TO SERVICE AT 1524 HOURS.

BEAVER VALLEY-1 05000334 123080 ON 12/30/80, WHILE PERFORMING THE SURVEILLANCE TEST ON THE CHLORINE DETE CONT ROOM HABITBLTY SYS + CONT 30-115/03L-0 012681 CTION SYSTEM, IT WAS DISCOVERED THAT THE 101A, 101B AND 101C DETECTORS' INSTRUMENTATION + CONTROLS 033738 30-DAY ELECTROLYTE WAS NOT DRIPPING. PRIOR TO INCREASING REACTOR COOLANT SYSTE SENSOR / DETECTOR / ELEMENT M TEMPERATURE TO ABOVE 200F, THE DETECTORS WERE DECLARED OUT OF SERVICE DESIGN / FABRICATION ERROR AND THE 101A DETECTOR WAS TRIPPCD. OPERATION CONTINUED IN ACCORDANCE WI

[

MANUFACTURING TH TECHNICAL SPECIFICATION 3.3.3.7.

THIS WAS THE TENTH FAILURE OF THIS l

WALLACE & TIERNAN, INC.

TYPE AT BVPS.

THE WICKS AND GLASS ORIFICES WERE CLOGGED. THE WICKS WERE REPLACED AND THE ORIFICES CLEANED.

ENGINEERING HAS BEEN REQUESTED TO EVALUATE THIS S YSTEM DUE TO THE REPEATED FAILURES.

{

l l

MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 4 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPO..ENT/

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCPIPTION DEAVER VALLEY-1 05000334 010281 AT 0630 HOURS WHILE IN HOT STANDBY. THE CLMTAINMENT DUTER AIRLOCK DOOR F REACTOR CONTAIMMENT SYSTEMS 81-003/03L-0 020281 AILED ITS SEAL LEAKAGE SURVEILLANCE TEST.

THE AIRLOCK WAS DECLARED IHOP PENETRATIONS.PRIMRY CONTAINMNT 036042 30-DAY ERABLE IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.6.1.3.

THE HEALTH A PERSONNEL ACCESS ND SAFETY OF THE PUBLIC WERE NOT JEOPARDIZED SINCE LEAKAGE THROUGH THE A DESIGN / FABRICATION ERROR IRLOCK WAS PREVENTED BY THE INNER DOOR WHICH RC"AINED SEALED.

DESIGN OTHER PREPARATIONS WERE BEING MADE TO RETURN THE PLANT TO PCWER FOLLOWING AN U NPLANNED OUTAGE TO REPAIR THE PRESSURIZER SAFETY VALVES.

AT 2230 HOURS, WHILE STILL IN. HOT STANDBY. THE AIRLOCK WAS RETURNED TO SERVICE AFTER C LEANING, GREASING AND REALIGNING THE SEALS.

BEAVER VALLEY-1 05000334 010681 DURING THE PERFORMANCE OF A SURVEILLANCE TEST ON THE CONTROL ROOM EMERGE CONT ROOM HABITBLTY SYS + COHT 81-004/03L-0 020481 NCY SUPPLY FANS. THE AIR FiOW CALCULATIONS INDICATED FLOW RATES OF 464 A VALVES 036043 30-DAY ND 473 CFM.

TECHNICAL SPECIFICATION 4.7.7.1 REQUIRES A SYSTEM FLOW RATE PROPORTIONING LOUVER OF 400 CFM +/- 10% DURING SYSTEM OPERATION. THE HEALTH AND SAFETY OF T DESIGN / FABRICATION ERROR HE GENERAL PUBLIC AND SITE PERSONNEL WERE NOT JEOPARDIZED.

DESIGN OTHER AFTER AN ADJUSTMENT WAS MADE TO THE SUPPLY FANS INLET DAMPER. THE FLOW R ATE WAS VERIFIED TO BE WITHIN ACCEPlABLE LIMITS.

THE SURVEILLANCE TEST WAS COMPLETED SATISFACTORILY AT 1400 HOURS ON JANUARY 6, 1981.

BEAVER VALLEY-1 05000334 010681 ON 1/6/81 THE DUQUESHE LIGHT COMPANY ENGINEERING DEPARTMENT REPORTED TH MAIN STEAM SYSTEMS + CCHTROLS 81-001/01T-0 012081 AT 32" SHP-1. 2. 3-601-Q2 SUPPORTS H-162. H-164 AMD H-166 HAD MOT BEEN M HANGERS. SUPPORTS. SHOCK SUPPRSS 036179 2-WEEK ODIFIED AS ORIGINALLY REPORTED IN THE 8/14/80 IE BULLETIN 79-14 LETTER.

SUPPORTS THIS IS A VIOLATION OF TECHNICAL SPECIFICATION 6.9.1.8.I.

ANALYSIS OF DESIGN / FABRICATION ERROR STRUCTURES. THE CONSEQUENCES OF SUPPORT FAILURE DUE TO PIPE WHIP IS POS DESIGN TULATED TO BE FAILURE OF THE MAIN STEAM VALVE HOUSE WALL. RESULTING IN F OTHER AILURE OF THE OTHER TWO STEAM LINES.DUE TO FALLING DEBRIS.

CAUSE OF PROBLEM IS THAT ILLEGIBLE CRAWINGS WERE TRANSf11TTED TO CONSTRUC TION DEPARTMENT FOR USE.

MHEN DRAWINGS WERE SENT BACK FOR BETTER COFIES THE DRAWING PERTAINING TO SUPPORTS H-162, H-164 A H-166 WAS LOST.

WOR K ON H-162. 164 & 166 WAS C0f1PLETED ON 1/7/81 & A LETTER FROM QUALITY AS SURANCE DEPT. WAS RECEIVED. VERIFYING THAT ALL OTHER ITEMS ARE COMPLETED-BEAVER VALLEY-1 05000334 010781 ON 1/7/81 WHILE PERFORMING ThE SURVEILLANCE TEST ON THE CHLORINE DETECT CONT ROOM HABITBLTY SYS + CONT 81-005/03L-0 012681 ION SYSTEM. IT WAS DISCOVERED THAT THE 101A AND 101B DETECTORS' ELECTROL 1NSTRUMENTATION & CONTROLS 036044 30-DAY YTE WAS NOT DRIPPING. THESE DETECTORS WERE DECLARED OUT OF SERVICE AND SENSOR / DETECTOR / ELEMENT THE 101A DETECTOR WAS TRIPPED. OPERATION CONTINUED IN ACCORDANCE WITH T DESIGN / FABRICATION ERROR ECHNICAL SPECIFICATI0H 3.3.3.7.

THIS WAS THE ELEVENTH FAILURE OF THIS T MANUFACTURING YPE AT BVPS.

WALLACE & TIERNAN, INC.

THE WICKS WERE REPLACED AND THE URIFICES CLEANED.

EUGINEERING HAS BEEN REQUESTED TO EVALUATE THIS SYSTEM DUE TO THE REPEATED FAILURES.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 5 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BEAVER VALLEY-1 05000334 010781 WITH THE REACTOR SHUTDOWN. AN OPERATOR WAS PERFORMING A MANIPULATION OF COOLANT RECIRC SYS + CONTROLS 81-002/01T-0 012131 THE SEAL LEAK-OFF VALVES AT 1105 HOURS WHEN THE SEAL FLOW DROFPED BELCW PUMPS 036080 2-WEEK THE MINIMUM ON THE 1C REACTOR COOLANT PUMP. THE ONLY RCP RUNNING. THE P CENTRIFUGAL UMP WAS MANUALLY TRIPPED, AS REQUIRED. HOWEVER. TECH. SPEC. 3.4.1.1 REQU DESIGN / FABRICATION ERROP IRES AT LEAST ONE PUMP RUNNING. PUMP WAS RESTARTED WITHIN 20 MIN. THERE DESIGN WAS A MINIMUM OF DECAY HEAT IN CORE 8 SUBC00 LED CONDITIONS WERE MAINTAIN DTHER ED.

HEALTH & SAFETY OF THE PUBLIC 8 SITE PERSONNEL WAS NOT JEOPADIZED.

THE CAUSE OF THE UNSTABLE SEAL FLOW OCCURRED DURING THE VALVING ATTEMPT TO TRANSFER THE RCP SEAL LEAK-OFF FLOW PATH.

THE VALVING INVOLVED IS SE NSITIVE ENDUGH TO CAUSE THIS INSTABILITY. THE PLANT ENGINEERING GROUP I S INVESTIGATING A PROPOSED WESTINGHOUSE SOLUTION TO THIS PROBLEM.

i BEAVER VALLEY-1 05000334 010881 WITH A REACTOR START-UP IN PROGRESS, A CURVEILLANCE TEST WAS BEING PERF0 EMERG CORE COOLING SYS + CONT 81-0 06 / 0 3L-0 020681 RMED ON THE LOW HEAD SAFETY INJECTION PUMPS WHEN THE WATER IN THE COMMON ELECTRICAL CONDUCTORS 036045 30-DAY RECIRCULATION LINE ON THE REFUELING WATER STORAGE TANK WAS FOUND FROZEN SUBCOMPONENT NOT APPLICABLE

. IN ACCORDANCE WIin T.S.

3.5.3, BOTH PUMPS WERE DECLARED INOPERABLE AT DEFECTIVE PROCEDURES 1850 HOURS.

THE EFFRGENCY CORE COOLING FLOW PATH WAS UNAFFECTED BY THI NOT APPLICABLE S BLOCKAGE AND THE HIGH HEAD SAFETY INJECTION PUMPS WERE AVAILABLE. THE OTHER HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE i?OT JEOPARDIZED.

THE HEAT TRACE CIRCUIT (HERMOSTAT FOR THE FROZEN LINE WAS FOUND IN THE O FF POSITION. THE THERM 05 TATS WERE SET IMMEDIATELY AND THE LINE THAWED.

AT 1048 HOURS ON 1/9/81, THE PUMPS WERE DECLARED OPERABLE. AN INVESTIG ATIOC OF OTHER SAFETY-RELATED HEAT TRACING WAS INITIATED AND THEIR OPERA BILITY VERIFIED.

BEAVER VALLEY-1 05000334 011281 AT 1130 HOURS WITH THE PLANT AT 50 PERCENT POWER. A LOW PRESSURE ALARM W EMERG CORE COOLING SYS + CONT 81-0C8/03L-0 021181 AS RECEIVED ON THE 1C SAFETY INJECTION ACCUMULATOR ISI-TK-1C).

PLANT OP VALVES 036081 30-DAY ERATION CONTINUED AS PER TECH. SPEC.

3.5.1.

THE HEALTH AND SAFETY OF TH GLOBE E PUBLIC WERE NOT JEOPARDIZED SINCE ONLY TWO ACCUMULATORS ARE REQUIRED F COMPONENT FAILURE OR ADEQUATE CORE COOLING IN THE EVENT OF A LOSS OF COOLANT ACCIDENT. TH MECHANICAL E REMAINING TWO ACCUMULATORS WERE CAPABLE OF FULFILLING THIS FUNCTION.

VELAN VALVE CORP.

THE PRESSURE IN ISI-TK-1C) WAS RESTORED ABOVE THE TECH. SPEC. LIMIT OF 6 05 PSIG AT 1203 HOURS.

THE SUSPECTED CAUSE FOR THE LOW PRESSURE IS A LE AKING DRAIN VALVE.

AN INVESTIGATION TO FIND THE LEAKIhG VALVE OR VALVES WILL BE MADE DURING THE NEXT GUTAGE AND THEY WILL BE REPAIRED OR REPLAC ED AS REQUIRED.

BEAVER VALLEY-1 05000334 011481 ON 1/14/81 AT 95 PERCENT POWER, WHILE PEPFORMING THE SURVEILLANCE TEST CONT ROOM HABITBLTY SYS + CONT 81-007/03L-0 012681 ON THE CHLORINE DETECTION SYSTEM, IT WAS DISCOVERED THAT THE 101A AND to INSTRUMENTATION + CONTROLS 036046 30-DAY 1B DETECTORS' ELECTROLYTE WAS NOT DRIPPING. THESE DETECTORS WERE DECLAR SENSOR / DETECTOR / ELEMENT ED OUT OF SERVICE AND THE 101B DETECTOR WAS TRIPPED. OPERATION CONTINUE DESIGN / FABRICATION ERROR D IN ACCORDANCE WITH TECHNICAL SPECIFICATIGN 3.3.3.7.

THIS WAS THE TWEL MANUFACTURING FTH FAILURE OF THIS TYPE AT BVPS.

WALLACE 8 TIERNAN. INC.

THE WICKS WERE REPLACED AND THE ORIFICES CLEANED. ENGINEERING HAS BEEN REQUESTED TO EVALUATE THIS SYSTEM DUE TO THE REPEATED FAILURES.

i i

i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 6 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS F ACIL ITY/SYST E. /COMPON ENT/

DCCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

i CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BEAVER VALLEY-1 05000334 011781 OH 1/17/81 A SURVEILLANCE TEST MAS PERFORMED TO VERIFY THE OPERABILITY EMERG CORE COOLING SYS + CONT 81-009/03L-C 021381 0F VARIOUS CONTAINMENT ISOLATICN VALVES.

[MOV-SI-864B) WAS STROKED SHUT VALVES 036082 30-DAY BUT THEN FAILED TO RE-OPEN, ISOLATING ONE OF THE TWO LOW HEAD SAFETY IN OTHER JECTION TRAINS FOR A PERIOD OF 11 MINUTES. PLANT OPERATION CONTINUED AS OTHER PER TECH. SPEC.

3.S.2.

THE DEGRADATION TO PLANT AND PUBLIC SAFETY WAS NOT APPLICJBLE MINIMAL SINCE ONE LOW HEAD TRAIN REMAINED OPERATIONAL AND WAS CAPABLE OF OTHER PROVIDING EMERGENCY COOLING IF REQUIRED.

AFTER DISPATCHING AN OPERATOR TO THE VALVE, IT WAS MANUALLY OPENED SEVER AL TURNS OF THE HANDWHEEL AND THEN FULLY RE-OPENED ELECTRICALLY IN 11 MI NUTES TIME.

THE INITIAL FAILURE TO RE-OPEN WAS CAUSED BY THE VALVE'S OP EN TORQUE CUTOUT SWITCH BEING OUT OF ADJUSTMENT. THE SWITCH WAS ADJUSTE D AND THE VALVE RETURNED TO SERVICE AT 1015 HOURS ON t/18/81 GEAVER VALLEY-1 05000334 012181 ON 1/21/81 REACTOR COOLANT SYSTEM LOOP t LOW FLOW ANNUNCIATOR BEGAN INT

,t REACTOR TRIP SYSTEMS 81-010/03L-0 022081 ERMITTENTLY FLASHING IN ALARM.

AT 1239 HOURS. FLOW CHANNEL 414 WAS REMD INSTRUMENTATION + CONTROLS 036225 30-DAY VED FROM SERVICE AND ITS ASSOCIATED BISTABLE TRIPPED WHEN IT WAS FOUND R TRANSMITTER EADING THE LOWEST OF THE THREE LOOP 1 FLOW CHANNELS. POWER OPERATION CO COMPONENT FAILURE NTINUED AS PER TECHNICAL SPECIFICATION 3.3.1.1.

THE PUBLIC HEALTH AND S INSTRUMENT AFETY WERE NOT JEOPARDIZED %INCE THE CHANNEL FAILURE WAS IN THE CONSERVA WESTINGHOUSE ELECTRIC CORP.

TIVE DIRECTION.

DURING THE INITIAL INVESTIGATION, A LOW VOLTAGE INPUT TO THE TRANSMITTER WAS DISCOVERED. AFTER MAKING AN ADJUSTMENT. THE CHANNEL WAS RETURNED T 0 SERVICE ON 1/23/81.

CONTINUING PROBLEMS WITH THIS CHANNEL HAVE DEVELO PED AND ARE NOW UNDER INVESTIGATION. THEY HAVE BEEN ATTRIBUTED TO EITHE R TRANSMITTER DRIFT OR A SMALL LEAK THROUGH TRANSMITTER BYPASS VALVE.

BEAVER VALLEY-1 05000334 012181 WHILE PERFORMING A SURVEILLANCE TEST ON THE CONTROL ROOM CHLORINE DETECT CONT ROOM HABITBLTY SYS + CONT 81-011/03L-0 022081 ION SYSTEM AT 1840 HOURS, IT WAS DISCOVERED THAT THE 101A AND 101B DETEC INSTRUMENTATION + CONTROLS 036226 30-DAY TOR'S ELECTROLYTE WAS NOT DRIPPING AND THE 10lc DETECTOR HAD A SLOW DRIP SENSOR / DETECTOR / ELEMENT RATE.

THE DETECTORS WERE DECLARED INOPERABLE AND THE OPERATION OF THE DESIGN / FABRICATION ERROR SYSTEM CONTINUED IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.3.3.7.

TH MANUFACTURING IS IS THE THIRTEENTH REPORTED EVENT INVOLVING THE CHLORINE DETECTORS.

WALLICE & TIERNAN, INC.

AT 1914 HOURS. THE if:C DETECTOR WAS ADJUSTED AND DECLARED OPERABLE. TH E 101A AND 101B DEfEL. ORS WERE REPAIRED AND DECLARED OPERABLE ON 1/29/81

. THE CAUSE OF THE REPEATED FAILURES OF THE DETECTOPS TO FUNCTION PROPE RLY HAS NOT BEEN SATISFACTORILY IDENTIFIED. THE PROBLEM IS BEING INVEST IGATED TO DETERMINE THE CORRECTIVE ACTIONS.

QEAVER VALLEY-1 05000334 012181 AT 1535 HOURS ON t/21/81. THE 1A MAIN FILTER BANK WAS DECLARED INOPERABL CNTNMNT AIR PURI + CLEANUP SYS 81-013/03L-0 022081 E AS A RESULT OF A ROUTINE LAB ANALYSIS DONE ON THE BANK'S CHARCOAL BED.

FILTERS 036227 30-DAY THE ANALYSIS-SHOWED THAT THE METHYL IODIDE REMOVAL EFFICIENCY FOR THE B SUBCOMPONENT NOT APPLICABLE ED HAD FALLEN BELOW 90 PERCENT. POWER OPERATION CONTINUED IN ACCORDANCE COMPONENT FAILURE WITH TECHNICAL SPECIFICATION 3.7.8.1.

THE EFFECT TO THE HEALTH AND SAF-NATURAL END OF LIFE ETY OF THE PUBLIC WAS MINIMAL SINCE THE BED EFFICIENCY AT THE TIME OF DI BARNEBEY-CHENEY SCOVERY HAD ONLY DROPPED TO 86.6 PERCENT.

THE-CHARCOAL BED HAD REACHED THE END OF ITS HORMAL LIFE EXPECTANCY. THE FILTER BANK WAS RE-PACKED WITH NEW CHARCOAL AND RETURNED TO SERVICE ON 1/26/81.

A DESIGN CHANGE HAS BEEN INITIATED TO INSTALL AN ADDITIONAL 30 CHARCOAL CELLS PER BANK.

THIS WILL GREATLY EXTEND THE CHARCOAL SERVICE LIFE BY REDUCING THE AIR VELOCITY THROUGH EACH INDIVIDUAL CELL.

. ~

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY

'PAGE 7 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILTTY/ SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUSCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION DIG ROCK POINT 05000155 020180 FOLLOWING OBSERVATION OF MINOR TEMPERATURE 2 PRESSURE CHANGES IN REACTOR' COOL SYS FCR REAC AUX + CONT 80-004/01X-1 021781 COOLING WATER AUXILIARY SYSTEMS. INVESTIGATION BY OPERATIONS PERSONNEL PENETRATIONS,PRIMRY CONTAINMNT 030127 OTHER GN 1/31/80 REVEALED A BROKEN AIR TUBING LINE TO CONTROL VALVE CV4029.

T INSTRUMENT LINE HE LINE WAS TEMPORARILY REPAIRED AT 0110 HRS ON 1/31/80.

FOLLOWING REVI OTPER EW BY TECHNICAL PERSONNEL ON 2/1/30. THE LINE. WHICH REPRESENIS A CONTAI NLT APPLICABLE NMENT BOUNDARY. WAS REPAIRED 4 TESTED ON 2/1/30. NO HAZARD TO PUBLIC OCC ITEM NOT APPLICABLE URRED.

NOT REPETITIVE. REPORTABILITY BASED ON TECH. SPEC. 6.9.2.A.(3).

CONTRACTOR WORKERS MAY HAVE UNKNOWINGLY BROKEN THE TUBING WHILE DOING M0 DIFICATION WORK IN THE AREA ABOUT'2200 HRS ON 1/30/80.

OTHER CONTAINMEN T PENETRATION TUBING IN THE AREA WAS INSPECTED 8 A TEMPORARY CAUTION SIG N WAS POSITIONED NEARBY.

DURING A REFUELING OUTAGE. THE CONTROL AIR TUB i

ING PENETRATIONS FOR THREE VALVES WERE ELIMINATED BY A MODIFICATION.

BIG ROCK POINT 0500015S 091980 DURING ROUTINE ANNUAL LEAK RATE AND OPERABILITY CHECKS (PER TECH SPEC 3.

CNTNMNT ISOLATION SYS + CONT 80-030/03X-1 021781 7 (B)) 0F CONTAINMENT ISOLATION VALVE CV027 IN THE REACTOR AND FUEL PIT UALVES 032697 OTHER DRAIN LINE, MINOR THROUGH SEAT LEAKAGE IN EXCESS OF TECH SPEC LIMITS WAS GLOBE OBSERVED. THE BACK-UP VALVE CV4117 IN SERIES WAS FOUND TO BE ACCEPTABL OTHER E AND WAS TAGGED AND DISABLED IN THE CLOSED CONDITION UNTIL REPAIRS COUL NOT APPLICABLE D BE MADE DURING A PLANT SHUTDCWN. NO HAZARD TO THE PUBLIC OCCURRED. R QLACK-SIVALS-BRYSON EPORTABILITY BASED ON TECHNICAL SPECIFICATION 6.9.2.B(2).

INVESTIGATION DURING A REFUELING OUTAGE REVEALED THAT THE SPRING THAT PR i

0VIDES THE SEATING FORCE WAS NOT PROPERLY TENSIONED. THIS APPEARS TO BE' THE PRIME CAUSE FOR EVENT R0-79-23 ALSO.

THE EXACT CAUSE OF THE SPRING DEFECT IS NOT KNOWN.

THE VALVE OPERATOR WAS ADJUSTED AND THE SEAT WAS REPLACED FER THE COMMITMENT IN R0-79-23.

BIG ROCK POINT 05000155 123080 ROUTINE CALIBRATION OF THE CONTAINMENT BUILDINC LEVEL TRANSMITTER INDICA' EMERG CORE COOLING SYS + CONT 80-049/03L-0 012881 TED AN OUTPUT CORRESPONDING TO 587 1/2' LEVEL WHEN THE ACTUAL LEVEL SHOU INSTRUMENTATION + CONTROLS 033693 30-DAY LD HAVE BEEN 590'.

THE 590' LEVEL IS AN OPERATOR ACTION POINT FOR TERMI TRANSMITTER NATION OF INJECTION WATER TO PROTECT CORE SPRAY SYSTEM VALVE CONTROLS AN OTHER D THUS THE ERROR IS NOT CONSERVATIVE. A SECOND LEVEL SYSTEM PROVIDES PA NOT APPLICABLE RTIAL REDUNDANCY. THE TRANSMITTER WAS RECALIBRATED ON 12/30/80. REPORT

'BARTON INSTRU CO., DIV 0F ITT ABILITY BASED ON T/S 6.9.2.B(1). NO HAZARD TO THE PUBLIC OCCURRED.

AN EXACT CAUSE OF THE DEFICIENCY IN THE BARTON MODEL 386 TRANSMITTER WAS NOT DETERMINED. NO ABNORMAL DRIFT HAS BEEN NOTED PREVIOUSLY. THE INST RUMENT ACCURACY HAS BEEN CHECKED ON TWO OCCASIONS SUBSEQUENT TO 12/30/80 AND WAS FOUND ACCEP1ABLE. THE UNIT WILL BE TESTED AGAIN PRIOR TO OR DU RING THE NEXT REFUELING OUTAGE.

BROWNS FERRY-1 05000259 100680 DURING NORMAL OPERATION, AN OPERATOR DISCOVERED LOSS OF VALVE POSITION I-REAC CORE ISOL COOL SYS + CONT 80-075/03X-1 012981 NDICATION FOR RCIC STEAM SUPPLY VALVE FCV-71-3.

THE VALVE WOULD HAVE CL OTHER COMPONENTS 032897 OTHER OSED FROM AN AUTO CLOSE SIGNAL 1.UT THE OPERATOR WOULD NOT HAVE BEEN AWAR SUBCOMPONENT NOT APPLICABLE E OF THE POSITION. REFERENCE TECHNICAL SPECIFICATION 3.7.D.1 1 2 AND 3.

COMPONENT FAILURE 5.F.2.

HPCI WAS AVAILABLE. iHERE WERE NO SIGNIFICANT RESULTING EVENTS.

CORROSION THERE WAS NO DANGER To HEALTH OR SAFETY OF PUBLIC. NO PREVIOUS DCCURR GENERAL ELECTRIC CO.

ENCES.

CAUSE WAS CORROSION ON GE.

'2 POINT. 600V. 30 AMP. MODEL 6422482612 TERM INAL BLOCK. INSIDE JUNCT. BOX 1681. CORRODED TERT 1. MERE BYPASSED TEMP BY REMOVING 8 SPLICING TOGETHEP ASSOC WIRING. IERM BLOCK WILL BE REPLACED DURING NEXT EXTENDED OUTAGE. UNIT 2 & 3 JUNCT BOXES HAVE BEEN INSPECTED 4 WERE FOUND TO BE WELL-SEALED 8 TERM BLOCKS FREE OF CORROSION.

l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 8 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-1 05000259 121780 DURING NORMAL OPERATION, WHILE PERFORMING SI 4.7.H.

DRYWELL HYDROGEN MON ENGNRD SAFETY FEATR INSTR SYS 80-091/03X-1 021381 ITOR, 1-HC2)M-76-39. WOULD NOT CALIBRATE PROPERLY TO CALIBRATION GAS (TE INSTRUMENTATION + CONTROLS 033550 OTHER CH. SPEC. 3.7.H-3).

REDUNDANT 1-H(2)M-76-37 WAS OPERABLE. THERE WAS NO SENSOR / DETECTOR / ELEMENT EFFECT ON THE PUBLIC HEALTH OR SAFETY. PREVIOUS EVENTS: 296/80-37 AND COMPONENT FAILURE 260/80-36.

INSTRUMENT GENERAL ELECTRIC CD.

THE GE MODEL 47E226428G2 SENSOR FAILED. ALTERNATE SENSOR 1-HC2)E-76-39A WAS CONNECTED TO THE HYDROGEN MONITOR AND SI 4.7.H COMFLETED SATISFACTO RILY.

THIS SYSTEM WILL BE REPLACED WITH A HAYES-REPUBLIC SYSTEM AT THE NEXT REFUELING OUTAGE.

BROWNS FERRY-1 05000259 010581 DURING NORMAL OPERATION, WHILE PERFORMIFG SI 4.2.B-24. CORE SPRAY SPARGE ENGNRD SAFETY FEATR INSTR SYS 81-001/03L-0 012881 R TO RPV D/P SWITCH t-PDIS-75-28 WAS FOUND SET AT 1.4 PSID.

TECHNICAL 5 INSTRUMENTATION + CONTROLS 036019 30-DAY PECIFICATION 3.2.B LIMIT IS 2 +/- 0.4 PSID.

REDUNDANT SWITCH 1-PDIS SWITCH 56 WAS OPERABLE.

THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF THE PUB COMPONENT FAILURE LIC.

PREVIOUS EVENT:

259/80-87.

INSTRUMENT DARTON INSTRU CO., DIV 0F ITT THE BARTON MODEL 288 SETPOINT HAD DRIFTED. THE SWITCH WAS RECALIBRATED AND FUNCTIONALLY TESTED FOR REPEATABILITY. THE SWITCH WAS REPLACED WITH A NEW SWITCH ON JANUARY 15, 1981 NO FURTHER ACTION IS PLANNED.

BROWNS FERRY-1 05000259 011481 DURING NORMAL OPERATION, A SMOKE DETECTOR IN RELAY ROOM ALARMED AND WOUL FIRE PROTECTION SYS + CONT 81-002/03L-0 020581 D NOT CLEAR.

THE ALARM WOULD HAVE MASKED SIGNALS FROM DETECTORS REQUIRE INSTRUMENTATION + CONTROLS 036170 30-DAY D TO BE OPERATIONAL BY TECHNICAL SPECIFICATION 3.11.C.1 THERE WERE NO SENSOR / DETECTOR / ELEMENT SIGNIFICANT RESULTING EVENTS.

THERE WERE NO EFFECTS ON PUBLIC HEALTH OR COMPONENT FAILURE SAFETY.

THERE ARE NO REDUNDANT SYSTEMS. PREVIOUS OCCURRENCE:

BFRO-50 NATURAL END OF LIFE

-259/80-41.

KIODE, WALTER & CO INCREASED DETECTOR SENSITIVITY DUE TO NORMAL, NATURAL AGING CAUSED THE E VENT.

DETECTOR WAS REPLACED AND SUCCESSFULLY TESTED PER SI 4.11.C.1 AND 5.

KIDDE IONIZATION DETECTOR, MODEL FT-200.

NO RECURRENCE CONTROL PEQ UIRED.

BROWNS FERRY-1 05000259 012481 DURING NORMAL OPERATION, THE PLANT RECEIVED NOTIFICATION FROM TVA'S DIVI REACTIVITY CONTROL SYSTEMS 81-003/01T-0 020481 SION OF ENGINEERING DESIGN THAT THE ONE-INCH VENT LINE ON UNIT 1 SCRAM D COMPONENT CODE NOT APPLICABLE 036083 2-WEEK ISCHARGE VOLUME WAS NOT SEISMICALLY QUALIFIED BASED ON ANALYSIS RESULTIN SUBCOMPONENT NOT APPLICABLE G FROM NRC IE BULLETIN 79-14 INSPECTION DATA.

REFERENCE FSAR CHAPTER 12 DESIGN / FABRICATION ERROR

. NO SIGNIFICANT RESULTING EVENTS.

NO DANGER TO HEALTH OR SAFETY OF TH CONSTRUCTION / INSTALLATION E PUBLIC. NO PREVIOUS OCCURRENCES.

ITEM NOT APPLICABLE THE AS-CONSTRUCTED PIPING CONFIGURATION DID NOT CONFORM TO DESIGN REQUIR EMENTS.

SEISMIC RESTRAINTS WERE INSTALLED ON THE ONE INCH VENT LINE.

T HIS PUT THE SYSTEM IN A " MINIMUM POTENTIAL FOR PRESSURE BOUNDARY FAILURE

" CATEGORY.

MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 9 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-1 05000259 012581 DURING NORMAL OPERATION AN OPERATOR OBSERVED THAT SBGT TRAIN "C" RELATIV SYS REQRD FOR SAFE SHUTDOWN 81-004/03L-0 020981 E HUMIDITY HEATERS DID NOT FUNCTION PROPERLY 3 SBGT TRAIN "C" DECLARED-IN INSTRUMENTATION + CONTROLS 036180 30-DAY OPERABLE AT 1400.

(TECH SPEC 3.7.B.1)

THIS SYSTEM IS COMMON TO UNIT 1.-

SWITCH 2.

AND 3.

THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC.

COMPONENT FAILURE SBGT TRAINS "A" AND "B" WERE OPERABLE. PREVIOUS EVEHTS: NONE..

INSTRUMENT DUST SUPPRESSION SYSTEMS A DWYER PHOT 0 HELIC PRESSURE SWITCH / GAGE CIRCUIT HH AND AN ITE IMPERIAL R j

ELAY CONTACT BLOCK MALFUNCTIONED. SI 4.7.C WAS PERFORMED M!THIH 2 HOURS AND THE MALFUNCTIONING COMPONENTS WERE REPAIRED. SBGT TPAEH "C" WAS RE TURNED TO SERVICE AT 0645 ON JANUARY 26, 1981.

NO RECURRENCE CONTROL AC TION IS PLANNED.

l BROWNS FERRY-1 05000259 012981 DURING POWER INCREASES. THE TECHNICAL SPECIFICATION LIMIl 0F 13.33'KW/FT REACTOR CORE 81-0 0 7/ 0 3L-0 021381 FOR LINEAR HEAT GENERATION RATE WAS EXCEEDED IN ONE N3DE.

(T.S. 3.5.J)

FUEL ELEMENTS 036182 30-DAY

. THE NODE REACHED 13.77 KW/FT.

PREVIOUS EVENTS:

50-259/80-53. 50-259 SUBCOMPONENT NOT APPLICABLE

/80-56. AND 50-259/80-78.

THERE WAS NO EFFECT ON THE PUBLIC HEALTH OR S PERSONNEL ERROR AFETY AND HO RESULTIUG SIGNIFICANT CHAIN OF EVENTS.

LICENSED 3 SENIOR OPERATORS ITEM NOT APPLICABLE UNANTICTVAYED RAPID POWER DENSITY INCREASE DUE TO A XENON TkANSIENT WHIC H RESULTED FROM INCREASED CORE POWER FOLLOWING A LOAD DECREASE. LOAD WA S DECREASED 25 MWE.

LARGER MARGIN TO LIMITS WILL BE MAINTAINED DURING X ENON TRANSIENTS.

BROWNS FERRY-1 05000259 013181 DURING STEADY STATE OPERATION, PH OF THE RESERVOIR NEAR THE PL ANT WAS F0 CHEM. VOL CONT + LIQ POISH SYS 81-005/04L-0 020981 UND TO BE IN EXCESS OF THE ALLOWABLE DISCHARGE LIMIT OF 9.e PH.

MONITOR COMPONENT CODE NOT APPLICABLE 036181 30-DAY ING WAS IN PROGRESS TO SUPPORT THE ROUTINE RELEASE OF SPEFt DEMINERALIZE SUBCOMPONENT NOT APPLICABLE D REGENERANTS. TECHNICAL SPECIFICATION: ETS 2 2.1..THERE MAS NO DANGER OTHER TO THE PUBLIC. NO PREVIOUS OCCURRENCES.

NOT APPLICABLE ITEM NOT APPLICABLE THE CAUSE OF THE EXCESS PH VALUE IS UNKNOWN.

HOWEVER. IT APPEARS TO BE CAUSED BY AN UPSTREAM SOURCE.

THE DISCHARGE OF SPENT REGE5ERANTS WAS ST OPPED. A TEMPORARY PROGRAM WAS ESTABLISHED TO MONITOR THE RESERVOIR PH.

HD RECURRENCE CONTROL REQUIRED.

-B20WNS FERRY-2 05000260 011980 DURING NORMAL OPERATION. CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY REACTOR CORE 81-005/03L-0 020681 EXCEEDED LIMIT BY 0.002 FOR ONE NODE IN CORE.

DISCOVERY WAS MADE BY-RE COMPONENT CODE NOT APPLICABLE 036085 30-DAY VIEW OF N00N COMPUTER EDIT AT APPROXIMATELY 1430.

NO REDUNDANT SYSTEM.

SUBCOMPONENT NOT APPLICABLE POWER WAS REDUCED APPROXIMATELY 10 MWE.

THERE WAS NO DANGER TO THE HEA OTHER LTH OR SAFETY OF THE PUBLIC.

NO PREVIOUS OCCURRENCES.

NOT APPLICABLE ITEM NOT APPLICABLE CAUSE OF EVENT WAS OPERATION CLOSE TO A LIMIT IN CONJUNCTION WITH MINOR (NORMAL) PERTURBATION IN MONITORED PARAMETERS SUCH AS RECIRC. FLOW.

POW ER WAS SLIGHTLY REDUCED SHORTLY AFTER DISCOVERY TO PREVENT SHORT TERM RE CURRENCE.

A PROPOSED TECHNICAL SPECIFICATION REVISION IS BEING PREPARED TO REMOVE POWER SPIKING PENALTY ON 8 X 8 FUEL.

s MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE'to PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/

DOCKET NO./

EVENT DATE/

i CCMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION QROWNS FERRY-2 05000260 091630 WITH THE UNIT IN COLD SHUTDOWN AND REFUELING. DRYWELL CONTROL AIR VALVE CNTNMNT ISOLATION SYS + CONT 80-039/03L-1 022081 2-FCV-32-62 COULD NOT BE CLOSED BY OPERATING ITS HANDSWITCH IN THE CONTR VALVE OPERATORS 032704 30-DAY OL ROOM.

2-FCV-32-63 UAS OPERABLE. THERE WAS NO EFFECT ON THE HEALTH 0 GTHER R SAFETY OF THE PUBLIC.

THESE VALVES SHOULD BE INCLUDED IN TECH. SPEC.

COMPONENT FAILURE 3.7.D.2 BUT ARE NOT.

THIS FAILURE 15. THEREFORE. VIOLATION OF INTENT OF MECHANICAL TECHNICAL SPECIFICATIONS.

ITEM HOT APPLICABLE IT APPEARS THE CONTROL AIR SOLENCID WAS STICKING. THIS COULD NOT BE SUB ST ANTI ATED BEC AUSE THE PROBLEM COULD NOT BE REPRODUCED. THE VALVE HAS C YCL ED FROM CONTROL ROOM AND LOCAL HAND SWITCHES. NO FURTHER PROBLEMS WE RE FOUND.

CHANGES TO INCLUDE THESE VALVES IN TECHNICAL %PECIFICATION HA VE BEEN INITIATED.

BROWNS FERRY-2 05000260 112180 DURING HEATUP AFTER A REFUELING OUTAGE WHILE PERFORMING SI 4.2.B-1. REAC REACTOR TRIP SYSTEMS 80-051/03X-1 012988 TOR WATER LEVEL SWITCH 2-LIS-3-58C 5 WITCH 4 (LPCI INITIATION) UAS FOUND INSTRUMENTATION + CONTROLS 0335t4 OTHER NOT TO OPERATE AT THE PROPFR SETPOINT. (TECHNICAL SPECIFICATION 3.2.B).

OTHER REDUNDANT SUITCHES WERE OPERABLE.

THERE WAS NO EFFECT ON THE HEALTH OR COMPONENT FAILURE SAFETY OF THE PUBLIC. PREVIOUS EVENTS: 260/80-5. 260/80-1

  • 259/74-37 MECHANICAL YARWAY CORP.

THE YARWAY CATALOG NUMBER 4418C HAD DIRTY SWITCH CONTACTS. THE CONTACTS WERE CLEANED AND FUNCTIONALLY CHECKED SEVERAL TIMES AT THE PROPER SETP0 INT.

THESE SWITCHES WILL BE REPLACED WITH AN ANALOG TRIP SYSTEM BY DCR 1398.

QROWNS FERRY-2 05000260 123080 DURING HORMAL OPERATION. 1HE UNIT OPERATOR OBSERVED FR-77-16 DOWNSCALE W SAFETY RELATED DISPLAY INSTR 80-059/03L-0 012681 HILE THE DRYMELL EQUIPMENT DRAIN SUMP PUMP WAS OPERATING. FLOW SYSTEM D' INSTRUMENTATION + CONTROLS 033694 30-DAY ECLARED INOPERABLE AT 0001 (TECHNICAL SPECIFICATION 3.6.C.2).

THERE ARE TRANSMITTER NO REDUNDANT SYSTEMS.

THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OF T COMPONENT FAILURE HE PUBLIC. PREVIOUS EVENTS:

296/80-19.

INSTRUMENT GENERAL ELECTRIC CD.

A MODEL 555 GE TRANSMITTER FT77-16 ZERO ADJUSTMENT HAD SHIFTED. THE TRA NSMITTER WAS RECALIBRATED. FUNCTIONALLY TESTED AND RETURNED TO SERVICE A T 1030 ON 12/30/80. HD RECURRENCE CONTROL ACTION IS REQUIRED.

BROWNS FERRY-2 05000260 010281 DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A-8.

SCRAM DISCHARGE INS ENGNRD SAFETY FEATR INSTR SYS 81-002/03L-0 012981 TRUMENT VOLUME ROD-BLOCK LEVEL SUITCH (25 OAL) 2-LS-85-45E WAS FOUND SET INSTRUMENTATION + CONTROLS 036020 30-DAY AT 27 GALLONS.

IN ADDITION, 2-LS-85-45F (3 CAL) ALARM SWITCH REMAINS I e

SWITCH NOPERABLE AS REPORTED ON 260/80-58.

THERE ARE NO REDUNDANT SYSTEMS.

TH COMPONENT FAILURE ERE WAS NO.EFFECT ON THE HEALTH OR SAFETY OF THE PUBLIC. PREVIOUS EVENT INSTRUMENT 5:

260/80-52. 260/80-58. AND 260/81-01 THIS ITEM REPORTED UNDER NRCB ROBERTSHAW CONTROLS CO.

80-t4.

THE ROBERT SHAM MODEL SL-305-EI-X SETPOINT HAD DRIFTED. THE SWITCH WAS RECALIBRATED. FUNCTIONALLY TESTED AND RETURNED TO SERVICE. THIS SWITCH WILL BE REPLACED AS PART OF CRD IMPROVEMENT DCR 2203.

i,

,_a,,.~._

.a

MAR 26, 1981 LER MONTHLY REPO*T SORTED BY FACILITY PAGE 11 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

l COMPONENT SUBCODE/CAUSE CODE / LER HO./

REPORT DATE/

EVEdT DESCRIPTION /

l CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-2 05000260 011281 DURING NORMAL OPERATION, WHILE PERFORMING SI 4.2.B-21, CORE SPRAY PUMP D ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 020481 ISCHARGE PRESSURE SWITCH 2-PS-75-16, WHICH DEFERS ADS ACTUATION, WAS FOU INSTRUMENTATION + CONTROLS 036084 30-DAY ND 2.8% OUT OF TECH. SPEC. 3.2.B LIMITS. REDUNDANT SWITCHES 2-PS-75-7, SWITCH

-35 AND -44 WERE OPERABLE.

THERE WAS NO EFFECT ON THE HEALTH OR SAFETY OTHER OF THE PUBLIC. PREVIOUS EVENTS:

260/80-55, 259/80-46, 259/78-3, 259/73.

NOT APPLICABLE

-37.

MERCOID CORP MERCOID MODEL DA-7004-804 HAD DRIFTED OUT OF TOLERANCE. THE SWITCH WAS INSPECTED, RECALIBRATED AND SI 4.2.B-21 SUCCESSFULLY COMPLETED. THE SWI TCH WAS REPLACED WITH A NEW SWITCH ON JANUARY 21e 1981.

NO FURTHER ACTI ON IS PLANNED.

BROWNS FERRY-2 05000260 011981 DURING NORMAL OPERATION WHILE PERFORMING SI-4.1.A-7, REACTOR WATER LEVEL REACTOR TRIP SYSTEMS 81-004/01T-0 012881 SWITCHES LIS-3-203A SWITCH 1 LIS-3-A, B, C, AND D SWITCHES 2 WERE FOUN INSTRUMENTATION + CONTROLS 036021 2-WEEK D OUTSIDE TECHNICAL SPEC 1FICATION 3.1.A AND 3.E.B LIMITS BY 2.3%; 0.6%;

SWITCH 2.1%, AND 3.6% RESPECTIVELY. REDUNDANT SUITCHES LIS-3-203 B, C, AND D S COMPONENT FAILURE WITCHES UERE OPERATING WITHIN LIMITS.

THERE WAS NO EFFECT ON THE HEALTH INSTRUMENT OR SAFE 7Y OF THE PUBLIC. PREVIOUS EVENTS:

260/80-29.

BARTON INSTRU CO., DIV 0F ITT THE BARTON MODEL 288 SWITCHES DRIFTED DUE TO AIR IMPACT DRILLING NEXT TO THE PANEL ON WHICH THEY WERE. MOUNTED. THIS DRILLING WAS NECESSARY TO I NSTALL PANEL STANCHION GUARDS.

EACH SWITCH WAS INSPECTED, RECALIBRATED, FUNCTIONALLY TESTED AND RETURNED TO SERVICE. NO RECURRENCE CONTROL CAN.

BE IDENTIFIED AT THIS-TIME.

BROWNS FERRY-2 05000260 012181 DURING NORMAL OPERATION, CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY REACTOR CORE 31-006/03L-0 920681 LIMIT WAS EXCEEDED FOLLOWING A 10 MUE INCREASE VIA RECIRCULATION FLOU.

COMPONENT CODE NOT APPLICABLE 036086

>0-DAY PROBLEM WAS NOT IMMEDIATELY DISCOVERED EECAUSE THE PROCESS COMPUTER WAS SUBCOMPONENT NOT APPLICABLE INOPERABLE FOR APPROXIMATELY 10 HOURS.

POWER WAS REDUCED.

THERE WAS H OTHER 0 DANGER TO HEALTH OR SAFETY OF PUBLIC. PREVIOUS OCCURRENCE:

BFRO-50-2 NOT APPLICABLE 60/81-005.

REFERENCE TECH. SPEC. 3.5.J.

l ITEM NOT APPLICABLE EVENT CAUSED BY POWER INCREASE IN CONJUNCTION WITH INOPERABLE PROCESS CD MPUTER.

POWER IMMEDIATELY REDUCED UPON DISCOVERY AND A NOTE POSTED IN C R TO REMIND OPERATOR HOT TO INCREASE POWER.

THERE WAS A CONTROL ROD PAT TERN ADJUSTMENT MADE JANUARY 23, 1981 FOR RECURRENCE CONTROL.

BROWNS FERRY-3 05000296 040280 WITH UNIT AT 100 PERCENT STEADY STATE POWER, THE 3B DIESEL GENERATOR GOV AC ONSITE POWER SYS + CONTROLS 80-008/03X-1 012681 ERNOR ACTUATOR WOULD NOT RESPOND PROPERLY DURING OPERABLILITY SURVEILLAN-MECHANICAL FUNCTION UNITS 030885 OTHER CE INSTRUCTION 4.9.A.1, SUPPLEMENT A.

REDUNDANT SYSTEMS WERE OPERABLE.

SUBCOMPONENT NOT APPLICABLE THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC, AND NO SIGNI OTHER-FICANT RESULTING CHAIN OF FVENTS. PREVIOUS SIMILAR OCCURRENCE REPORTED NOT APPLICABLE ON LER BFRO-050-259/76-23.

WOODWARD GOVERNOR CO.

UNKNOWN; SUSPECTED OIL CONTAMINATION. THE SUMP WAS FLUSHED AND REFILLED WITH NEW OIL, AND SURVEILLANCE INSTRUCTION 4.9.A.I SUPPLEMENT A WAS SUC CESSFULLY RUN.

WOODUARD GOVERNOR. TYPE EGB, MODEL 10-C.

OIL WILL BE SA MPLED AND CHANGED ANNUALLY.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ = _-~

l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 12 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS 1

FACILITY /SYSTEP/ COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 051280 UPON COMPLETION OF THE FLOW TEST ON 3B RHR PUMP SEAL HEAT EXCHANGER. IT RESIDUAL HEAT REMOV SYS + CONT 80-015/03X-1 012688 WAS DETERMINED THAT THE COOLING WATER FLOW WAS INADEQUATE PER T.S.

3.5.B COMPONENT CODE NOT APPLICABLE 033739 OTHER 1(2) AND 3.5.B.5.

REDUNDANT SYSTEMS WERE OPERABLE PER TECH. SPEC.

THE SUBCOMPONENT NOT APPLICABLE RE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. NO RESULTING SIG OTHER HIFICANT CHAIN OF EVENTS, AND NO PREVIOUS SIMILAR OCCURRENCES.

l I

NOT APPLICABLE ITEM NOT APPLICABLE APPARENT RESTRICTION IN THE COOLING WATER PIPING UPSTREAM AND/OR DOWNSTR EAM FROM THE HEAT EXCHANGER. THE HEAT EXCHANGER WAS REMOVED. THE C00LIN C WATER LINES FLUSHED, AND THE UNIT PERFORMED NORMALLY. A SYSTEM FLUSHI NG EVALUATION IS BEING PERFORMED.

BROWHS FERRY-3 05000290 051380 UPON COMPLETION OF THE FLOW TEST ON 3D DIESEL GENERATOR HEAT EXCHANGER.

EMERG GENERATOR SYS + CONTROLS 80-016/03X-1 011981 IT WAS DETERMINED THAT THE COOLING WATER FLCW WAS INADEQUATE PER TECHNIC ENGINES. INTERNAL COMBUSTION 033695 OTHER Al SPECIFICATION 3.9.B.2.

REDUNDANT SYSTEMS 3A. 3B. AND 3C DIESEL GENER SUBCOMPONENT NOT APPLICABLE ATORS WERE OPERABLE.

THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE OTHER PUBLIC. NO RESULTING SIGNIFICANT CHAIN OF EVENTS.

PREVIOUS SIMILAR OCC NOT APPLICABLE URRENCES ON BFR0 50-296/80-15.

ITEM NOT APPLICABLE APPARENT RESTRICTION IN THE COOLING WATER PIPING UPSTREAM AND/OR DOWNSTR I

EAM FROM THE HEAT EXCHANGER.

THE HEAT EXCHANGER WAS REMOVED. THE C00LIN G WATER LINES FLUSHED. AND UNIT PERFORMED NORMALLY. A SYSTEM FLUSHING E VALUATION IS BEING PERFORMED.

BROWNS FERRY-3 05000296 071480 DURING NORMAL OPERATION WHILE PERFORMING SI 4.5.B.1.D.

3D RHR PUMP MOTOR RESIDUAL HEAT REMOV SYS + CONT 80-027/03X-1 012981 TRIPPED ON INSTANTANEOUS OVERCURRENT ON "A" PHASE WHEN STARTED. REFERE COMPONENT CODE NOT APPLICABLE 032025 OTHER NCE TECHNICAL SPECIFICATION 3.5.B.3.

REMAINING RHR PUMPS. CSS AND DIESE SUSCOMPONENT NOT APPLICABLE L GENERATORS OPERABLE. THERE WAS NO DANGER TO HEALTH CR SAFETY OF PUBLI OTHER C.

NO PREVIOUS OCCURRENCES.

NOT APPLICABLE ITEM NOT APPLICABLE RHR PUMP MOTOR TRIPPED ON INSTANTANEOUS OVERCURRENT. MOTOR WAS MEGGERED

. HI POTTED AND BRIDGED. RELAY SETTING CHECKED IN TOLERANCE. TRACES OF STARTING CURRENT SHOW DC OFFSET CAUSED BY SATURATION OF CT TO BE HIGHER THAN ANTICIPATED. INCREASING CURRENT MONITORED BY RELAY.

SETTINGS FOR RHR RELAYS ASSOCIATED WITH THIS LER HAVE BEEN REVISED.

BROWNS FERRY-3 05000296 080980 DURING THE PERFORMANCE OF MRI 303 IT WAS DISCOVERED THAT THE EECW FLOW W RESIDUAL HEAT REMOV SYS + CONT 80-031/03L-1 012781 AS BELOW THE MINIMUM ALLOWED FLOW ON 3B RHR PUMP SEAL HEAT EXCHANGER. T HEAT EXCHANGERS 032363 30-DAY HERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPE OTHER CIFICATION 3.5.B.

PREVIOUS SIMILAR OCCURRENCES WERE REPORTED ON LER/R0 OTHER NUMBERS BFRO-50-296/80-015 AND BFRO-50-296/80-006.

NOT APPLICABLE ITEM NOT APPLICABLE IT WAS DISCOVERED THAT MUD AND SHELLS WERE RESTRICTING THE FLOW IN THE E ECW PIPING INLET TO THE RHR PUMP SEAL HEAT EXCHANGER.

THE PIPING WAS DI SASSEMBLED AND CLEANED. PERIODIC TESTING WILL CONTROL RECURRENCE.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 13 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION l

BROWNS FERRY-3 05000296 081380 DURING NORMAL OPERATION WHILE PERFORMING SI 4.1.A.14, PRESSURE SWITCHES REACTOR TRIP SYSTEMS 80-030/03X-1 011981 PS-1-81A AND PS-1-91A, TURBINE FIRST STAGE PRESSURE, SETPOINTS HAD DRIFT INSTRUMENTATION + CONTROLS 032261 DTHER ED ABOVE TECH. SPEC. LIMITS.

(REF. T.S.

TABLE 3.1.A).

SETPOINTS WERE F i

l SWITCH CUND TO BE 7 PSIG 8 2 PSI, RESPECTIVELY, ABOVE T.S.

LIMIT OF 154 PSI. RE COMPONENT FAILURE DUNDANT SWITCHES PS-1-81B 8 PS-1-91B WERE OPERABLE. THERE WAS NO EFFECT INSTRUMENT ON PUBLIC HEALTH / SAFETY. PREVIOUS EVENTS:

259/80-58, 259/79-08, 259/78-1 BARKSDALE COMPANY 16, 260/80-22, 260/79-16, 296/80-22, 296/79-12, 8 296/79-07.

j PRESSURE EUITCHES, MODEL B2T-A12SS, SETPOINTS HAD DRIFTED. THE SWITCHES l

UERE INSPECTED, RECALIBRATED AND FUNCTIONALLY TESTED FOR REPEATABILITY.

OTHER UNITS WILL BE CHECKED BY THE NORMAL SI SCHEDULE. THESE SWITCHES WILL BE REPLACED BY AN ANALOG SYSTEM.

BROWNS FERRY-3 05000296. 090780 WITH UNIT AT 63.6 PERCENT STEADY STATE POWER, MAIN STEAM ISOLATION VALVE.

MAIN STEAM ISOL SYS + CONTROLS 80-038/03X-1 012781 3-FCV-1-26 CLOSED TOO FAST UHILE RUNNING SURVEILLANCE INSTRUCTION 4.7.D VALVE OPERATORS 032657 OTHER

.1.B.2.

THERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC. THE PNEUMATIC / DIAPHRAGM / CYLINDER VALVE WAS C" 0 SED AND POWER WAS REDUCED FOR 144 HOURS AS A RESULT.

"A",

COMPONENT FAILURE "C"

AND "D" MAIN STEAM LINES WERE OPERAELE. SEE TECHNICAL SPECIFICATI0 l

OTHER H 3.7.D.1.

PREVIOUS SINILAR OCCURRENCES WERE REPORTED ON LER BFRO-50-29 ATWOOD 8 MORRILL CO.,

INC.

6/78-014.

THE DIL LEVEL IN THE HYDRAULIC CYLINDER WAS LOW.

NO LEAKAGE WAS FOUND.

ONE GALLON OF OIL WAS ADDED AND THE FLOW CONTROL VALVE ADJUSTED TO OBTAI N CORRECT SPEED SETTING.

NO FUTURE CORRECTIVE ACTION IS NEEDED DUE TO L OW OCCURRENCE RATE.

ATWOOD AND MORRILL, 26 INCH C.S.,

WYE PATTERN, 1250 LB.

BROWNS FERRY-3 05000296 091580 WITH UNIT AT 99 PERCENT STEADY STATE POWER, SURVEILLANCE INSTRUCTION 4.9 EMERG GENERATOR SYS + CONTROLS 80-036/03X-1 012081

.A.1.A. WAS BEING RUN FOLLOWING A SPECIAL ELECTRICAL NAINTENANCE INSTRUC MECHANICAL FUNCTION UNITS 032543 OTHER TION 18 TEST WHEN DIESEL GENERATOR 3A WOULD NOT TRIP TO IDLE SPEED FROM SUBCOMPONENT NOT APPLICABLE A LOADED CONDITION. DIESEL GENERATORS 3B, 3C, AND 3D WERE OPERABLE.

TH COMPONENT FAILURE ERE WAS NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC, NO SIGNIFICANT-MECHANICAL RESULTING CHAIN OF EVENTS, AND THERE HAVE BEEN NO PREVIOUS SIMILAR OCCUR WOODWARD GOVERNOR CO.

RENCES.

SEE TECHNICAL SPECIFICATION 3.9.B.2.

THE PIN ON THE PINION GEAR TO THE INTERMEDIATE SHAFT GEAR USED FOR SPEED-ADJUSTING ON THE WOODWARD GOVERNOR WAS SHEARED. THE GOVERNOR WAS REPLAC ED WITH A REBUILT ONE OF THE SAME TYPE.

WOODWARD TYPE EGB10-C.

RECURRE HCE COHTROL NOT REQUIRED BECAUSE FAILURE IS RANDOM IN NATURE.

BROWNS FERRY-3 05000296 121080 DURING REFUELING, WHILE PERFORMING SI 4.8.B.4.3, A BAD ELECTRONIC CARD W AIRBORNE RADIDACT MONITOR SYS 80-055/03L-0 010881 AS IDENTIFIED AND CAM 3-RM-90-250 WAS DECLARED INOPERABLE AT 1710 HOURS INSTRUMENTATION + CONTROLS 033746 30-DAY (TECH. SPEC. 3.8.B.6 8 TECH. SPEC. 3.8.B.8).

CHEMICAL LABORATORY SAMPLI-OTHER NG PROGRAM WAS INITIATED.

THERE WAS NO EFFECT ON THE HEALTH GR SAFETY 0 COMPONENT FAILURE F THE PUBLIC.

THERE ARE NO REDUNDANT SYSTEMS. PREVIUUS EVENTS:

NONE.

ELECTRONIC NUCLEAR MEASUREMENTS CORP.

THE WINDOW CARD IN NMC CAM MODEL AO-331F(BF) MALFUNCTIONED. THE ITEM WA S REPAIRED, CAM FUNCTIONALLY TESTED AND RETURNED TO SERVICE. NO RECURRE NCE CONTROL ACTION IS PLANNED, DUE TG LOW FAILURE HISTORY.

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ - _ _ _ _ _ _ - - _ -

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 14 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 123080 DURING REFUELING OPERATIONS, WHILE PERFORMING SI 4.4.A.2 IT WAS FOUND TH EMERG CORE COOLING SYS + CONT 80-061/03L-0 012681 AT 3B SLC PUMP DISCHARGE RELIEF VALVE WOULD HOT RELIEVE AT 1425 +/- 75 P VALVES 033697 30-DAY SIG. REFERENCE TECHNICAL SPECIFICATION 4.4.A.2.

3A PUMP WAS DEMONSTRATE OTHER D OPERABLE. THERE WERE NO SIGNIFICANT RESULTING EVENTS.

THERE WAS NO D COMPONENT FAILURE ANGER TO HEALTH OR SAFETY-OF PUBLIC. PREVIOUS EVENT BFRO-50-259/79-002.

MECHANICAL CROSBY VALVE 3 GAGE CO.

SUSPECT VALVE DISC GALLED OR BINDING WITH VALVE GUIDE.

VALVE WAS REPLAC ED AND VERIFIED OPERABLE. THE DAMAGED VALVE, CROSBY, SIZE 1 X 2. TYPE J MWK, 1600 PSI RELIEF VALVE, WILL BE SENT TO MANUFACTURER FOR REBUILD AND TESTING. NO RECURRENCE CONTROL REQUIRED.

BROWNS FERRY-3 0500J296 123180 DURING REFUELING OPERATIONS, IT WAS FOUND THAT MAIN STEAM ISOLATION VALV MAIN STEAM SYSTEMS + CONTROLS 80-059/03L-0 012781 ES 1-14, 1-15.

1-26, 1-27, 1-37, 1-38, 1-51 CAUSED TOTAL "AS FOUND" PRIM VALVES 033664 30-DAY ARY CONTAINMENT LEAK RATE TO EXCEED 60 PERCENT LA LEAK RATE OF 655.9 SCF GLOBE H.

LEAK RATE UAS 3941.1027 SCFH.

MAIN STEAM ISOLATION VALVE LEA % AGE CO COMPONENT FAILURE NTRIBUTED 97 PERCENT OF LEAKAGE. NO SIGNIFICANT RESULTING EVENTS. NO D CORROSION ANGER TO HEALTH OR SAFETY OF PUBLIC. REFERENCE TECH. SPEC.

3.7.A.

PREV ATWOOD 8 MORRILL CO., INC.

IOUS EVENT BFRO-50-260/80-049.

CAUSE OF EVENT WAS DETERIORATION OF VALVE SEATING SURFACES DURING POWER l

DPERATION DUE TO STEAM EROSION. ATWOOD MORRILL, 26 IN. GLOBE, MODEL 208 51H, RATING 125D PSIG AT 575 DEG. F.

EFFECT MAINTENANCE AND RETEST UNTI' L PRIMARY CONTAINMENT LEAK RATE IS ACCEPTABLE. RECURRENCE CONTROL INVES TIGATION CONTINUING.

GROWHS FERRY-3 05000296 123180 DURING REFUELING OPERATIONS WHILE PERFORMING MAINTENANCE INSTRUCTION FOR REACTIVITY CONTROL SYSTEMS 80-060/03L-C 012781 SCRAM ACCUMULATOR LEVEL SWITCHES, IT WAS FOUND THAT SEVENTEEN LEVEL SWI INSTRUMENTATION + CONTROLS 033696 30-DAY TCHES WOULD NOT OPERATE DUE TO DIRTY FLOATS AND ONE OTHER SWITCH NEEDED SWITCH TO BE REPLACED.

REFERENCE:

TECHNICAL SPECIFICATION 4.3.A.2.D.

THERE W COMPONENT FAILURE AS NO DANGER TO HEALTH OR SAFETY OF PUBLIC. NO REDUNDANT SYSTEM. PREVI INSTRUMENT OUS OCCURRENCE:

BFRO-50-260/80-43.

GEMS, INC.

SOME GUMMY SUBSTANCE WAS OBSERVED ON SOME SWITCHES BETWEEN FLOAT BOTTCM AND TOP OF SPOOL BOTTOM WHICH MIGHT HAVE CAUSED A FLOAT TO STICK. THESE SWITCHES WERE CLEANE'D AND TESTED.

ONE WAS REPLACED. GEtts INC., TYPE L' IQUID LEVEL, SIZE T1AX. RESIST. LOAD 10.0 VA DWG. 117C1434 F001 EFFORTS TO IDENTIFY AND REMOVE SUBSTANCE FROM SYSTEM ARE IN PROGRESS.

BROWNS FERRY-3 05000296 010681 DURING REFUELING OPERATIONS BOTH SMOKE DETECTORS IN A REACTOR BUILDING F FIRE PROTECTION SYS + CONT 81- 0 01/ 0 3 L- 0 012881 IXED SPRAY ZONE WERE INOPERABLE. CHLY ONE DETECTOR IS ALLOWED TO BE IHO COMPONENT CODE NOT APPLICABLE 036022 30-DAY PERABLE BY TECHNICAL SPECIFICATION 3.11.C.1.

THERE WERE NO SIGNIFICANT SUBCOMPONENT NOT APPLICABLE RESULTING EVENTS.

NO EFFECT ON PUBLIC HEALTH OR SAFETY. NO PREVIOUS EV OTHER ENTS.

NOT APPLICABLE ITEM NOT APPLICABLE A SCREW CAME LOOSE FROM A TERMINAL BLOCK AND THIS INTERRUPTED POWER TO B OTH SMOKE DETECTORS IN A FIXED SPRAY ZONE.

ACTUAL CAUSE OF SCREW COMING LOOSE IS UNKNOUN. REPLACED SCREW IN BLOCK AND CHECKED OTHER TERMINAL B LOCKS IN PANEL; NO OTHER LOOSE SCREWS FOUND.

FURTHER RECURRENCE CONTROL NOT PLANNED.

n y

-iv

- - - = ~ - -

r-_g_m---,

~

____,,_-__,.__m.,

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 15 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM. COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BROWNS FERRY-3 05000296 011081 DURING REFUELING OPERATIONS, DIESEL GENERATOR 3A AND BREAKER 1836 TRIPPE EMERG GENERATOR SYS + CONTROLS 81-004/03L-0 020381 D FROM DIESEL GENERATOR OVERSPEED DURING DIESEL GENERATOR EMERGENCY LOAD INSTRUMENTATION - CONTROLS 036087 30-DAY ACCEPTANCE TEST.

THERE WERE NO SIGNIFICANT RESULTING EVENTS. THERE WA CONTROLLER S NO DANGER TO THE HEALTH OR SAFETY OF THE PUBLIC.

NO PREVIOUS EVENTS.

COMPONENT FAILURE REFERENCE TECHNICAL SPECIFICATION 3.9.C.1.

OTHER ELECTRO - MOTIVE DIV. OF G. M.

VS RELAY ON SPEED SENSING PANEL 2 ENERGIZED AT LESS THAN 870 RPM AND RES ULTED IN DIESEL GENERATOR TRIP.

POTENTI0 METERS FOR VS RELAYS ON SSP 1 AN D SSP 2 WERE CALIBRATED AND VERIFIED OPERABLE. SI 4.9.A.1.D WILL BE REVI SED TO VERIFY OPERABILITY OF VS RELAYS. EMD PART NO. 8409614.

BRUNSWICK-1 05000325 110580 DURING NORMAL OPERATION, WHILE VERIFYING CONTROL ROD POSITIONS, CONTROL SAFETY RELATED DISPLAY INSTR 80-087/03L-0 120180 ROD 50-27 HAD NO " FULL OU1" INDICATION ON THE ROD STATUS DISPLAY AND CON INSTRUMENTATION + CONTROLS 033698 30-DAY TROL ROD 38-23 LACKED POSITIDH INDICATION ON THE ROD STATUS DISPLAY AND SWITCH ON THE COMPUTER PRINTOUT MHILE AT POSITION "02".

SIMILAR EVENTS INVOLVI COMPONENT FAILURE NG CONTROL ROD POSITION INDICATIONS WERE REPORTED IN LER'S 1-80-25, 1-80 ELECTRICAL

-62, AND 1-80-78.

THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE GENERAL ELECTRIC CO.

PUCLIC.

TECHNICAL SPECIFICATIONS 3.1.3.7, 6.9.1.9B.

THE INDICATION PROBLEMS EXPERIENCED WITH THESE TWO RODS ARE BELIEVED TO HAVE RESULTED FROM DEFECTIVE ROD POSITION INDICATION REED SWITCHES. CDR RECTIVE MAINTENANCE FOR THESE RODS WILL BE COMPLETED DURING THE NEXT GUT AGE OF SUFFICIEllT LENGTH THAT ALLOWS ACCESS TO THE PRIMARY CONTAINMENT.

BRUNSWICK-1 05000325 121180 DURING NORMAL SURVEILLANCE ROD BLOCK MONITOR "B" WAS OBSERVED INDICATING REACTGR TRIP SYSTEFS 80-091/03L-0 010881 DOWNSCALE. THE MONITOR WAS THEN DECLARED INOPERABLE AS REQUIRED BY TEC INSTRUMENTATION + CONTROLS 033665 30-DAY HNICAL SPECIFICATIONS. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY 0 OTHER F THE PUBLIC.

TECHNICAL SPECIFICATIONS 3.1.4.3, 6.9.1.9B.

COMPONENT FAILURE ELECTRICAL GENERAL ELECTRIC CO.

MONITOR INDICATED DOWNSCALE DUE TO A FAILED POWER SUPPLY CAUSED BY A DEF ECTIVE POWER SUPPLY REGULATOR & ZENER DIODE IN POWER SUPPLY REGULATOR CI RCUIT.

REGULATOR & DIODE WERE REPLACED & MONITOR RETURNED TO NORMAL OPE R.

THIS IS FIRST EVENT INVOLVING A FAILURE OF THESE COMPONENTS & IS CON SIDERED AN ISOLATED EVENT WITH NO FURTHER CORRECTIVt ACTION REQUIRED.

BRUNSWICK-1 05000325 122880 MHILE PERFORMING A NORMAL SHUTDOWN FROM POWER OPERATION, THE ROD WORTH M REACTIVITY CONVROL SYSTEMS 80-093/03L-0 012181 INIMIZER (RWM) INITIATED AN INSERT / WITHDRAWAL ROD BLOCK AT ROD GROUP 56.

INSTRUMENTATION

  • CONTROLS 033699 30-DAY A COMPUTER VERIFICATION SHOUED ALL RODS WERE IN THE CORRECT POSITIONS.

COMPUTATION MGDULE THE RWM MAS THEN BYPASSED AND A SECOND OPERATOR WAS UTILIZED TO VERIFY DESIGN / FABRICATION ERROR COMPLIANCE WITH 1HE PRESCRIBED ROD PATTERN AND THE RW:1 WAS DECLARED INOP DESIGN ERABLE AS REQUIRED BY TECHNICAL SPECIFICATIONS 3.1.4.1, 6.9.1.9B.

GENERAL ELECTRIC CD.

SEVERAL COMPUTER RWM SOFTWEAR PROBLEMS WERE DISCOVERED WHICH ARE BELIEVE D TO HAVE CAUSED THIS EVENT..

THESE PROBLEMS WERE CORRECTED AND THE RMM SYSTEM WAS PETURNED TO NORMAL OPERATION. THE UNIT NO. 2 RUM SOFTWEAR WA S ALSO CHANGED TO THE SAME CONFIGURATION AS THAT ON UNIT NO. I IN ORDER TO AVOID ANY SIMILAR EVENTS WITH THE RWM SYSTEM IN THE FUTURE.

4 MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 16 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

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REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION i

BRUNSWICK-1 05000325 010181 DURING NORMAL SURVEILLANCE IT WAS DISCOVERED THAT THE SECONDARY CONTAINM REACTOR CONTAINMENT SYSTEMS 81-005/03L-0 012781 ENT 20' ELEVATION INNER AIR LOCK DOOR HAD A MISSING SECTION OF GASKET SE PENETRATIONS,PRIMRY CONTAINMNT 036024 30-DAY ALING MATERIAL MAKING THE DOOR INOPERABLE. THIS EVENT DID NOT AFFECT TH PERSONNEL ACCESS E HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 3.6.5.1, 6.9 COMPONENT FAILURE

.1.9B.

NATURAL END OF LIFE OTHER HIGH PERSONNEL TRAFFIC THROUGH THE DOOR CAUSED AN APPROXIMATE 6" SECTION i

0F THE GASKET TO BECOME EXCESSIVELY WORN AND DETACHED FROM THE DOOR STR UCTURE.

THE MISSING GASKET SECTION WAS REPLACED AND THE GASKETS ON THE DOORS OF BOTH UNITS WERE INSPECTED TO ENSURE PROPER SEALING. A PROCEDUR E IS PRESENTLY BEING DEVELOPED TO INSPECT THESE DOORS ON A REGULAR BASIS BRUNSWICK-1 05000325 010181 WHILE PERFORMING A CALIBRATION CHECK ON THE CONTAINMENT ATMOSPHERIC MONI CNTHMNT COMBUS GAS CONTROL SYS 81-006/03L-0 012781 TOR, 1-CAC-ATH-1259-2. IT WAS DETERMINED THAT THIS INSTRUMENT WAS-0UT OF INSTRUMENTATION + CONTROLS 036025 30-DAY CALIBRATION. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUB COMPUTATION MODULE LIC.

TECHNICAL SPECIFICATION 3.3.5.3, 6.9.1.9B.

COMPONENT FAILURE INSTRUMENT BECKMAN INSTRUMENTS, INC.

1 THE INSTRUMENT WAS OUT OF CALIBRATION DUE TO INSTRUMENT DRIFT.

THE MONI TOR WAS RECALIBRATED AND RETURNED TO SERVICE. DUE TO A HISTORY OF PROBL EMS INVOLVING THESE MONITORS, THEY WILL BE REPLACED WITH 0THERS OF A MOR E RELIABLE DESIGN DURING A FUTURE SCHEDULED OUTAGE.

B2UNSWICK-1 05000325 010381 DURING A NORMAL REACTOR SlARTUP, CONTROL ROD 26-35 HAD "Ft"it IH" POSITIO ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 012081 N INDICATION LIGHTS LIT REGARDLESS OF THE ACTUAL ROD POSITION. FOLLOWING

' INSTRUMENTATION + CONTROLS 036023 30-DAY THE REACTOR STARTUP WHILE MOVING CONTROL RODS DURING LOAD CHANGES, ON J SENSOR / DETECTOR / ELEMENT ANUARY 13, 1981, ROD 18-51 DID NOT HAVE POSITION INDICATION AT POSITION COMPONENT FAILURE "48," AND ON JANUARY 14, 1981 ROD 38-31 DID NOT HAVE POSITION INDICATIO NATURAL END OF LIFE N AT POSITION "05" WHILE ROD 22-15 DID NOT HAVE " FULL IN" POSITION INDIC GENERAL ELECTRIC CD.

ATION AT POSITION "00."

TECHNICAL SPECIFICATION 3.1.3.7, 6.9.1.9B.

LOGIC CHIP G-33 0F THE ROD 26-35 BUFFER CARD FAILED.

THE BUFFER CARD WA S REPLACED AND NORMAL INDICATION FOR ROD 26-35 WAS RESTORED. RODS 18-51 38-31, AND 22-15 ARE BELIEVED TO HAVE DEFECTIVE REED SWITCHES LOCATED IN THE PIP PROBE.

THESE SWITCHES'WILL BE REPAIRED DURING THE NEXT DUTAG E OF SUFFICIENT LENGTH TO ALLOW WORK IN THE DRYWELL.

BRUNSWICT-1 05000325 010681 WHILE PERFORMING PRIMARY CONTAINMENT LEAK RATE TESTING OF PERSONNEL AIRL REACTOR CONTAINMENT SYSTEMS 81 - 0 0 8.'0 3 L - 0 020381 OCK INTERIOR AND EXTERIOR DOORS, PT 2.6.5P, IT WAS DISCOVERED THAT DRYWE PENETRATIONS.PRIMRY CONTAINMNT 036183 30-DAY LL EXTERIOR AIRLOCK DOOR LEAKAGE RATE EXCEEDED THE SPECIFIED < 5 SCFH.

PERSONNEL ACCESS THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECH. SPE OTHER CS.

3.6.1.3, 6.9.1.9B.

NOT APPLICABLE i

OTHER A TUBING FITTING BECAME LODGED IN THE DOOR SEALING AREA WHICH DENTED IT AND CUT THE DOOR GASKET.

THE FITTING UAS REMOVED. THE DENTED SEALING AR EA RESURFACED AND A NEW DOOR GASKET WAS INSTALLED. THE PT WAS THEN SATI SFACTORILY PERFORMED WITH AN EXTERIOR DOOR LEAKAGE RATE OF 4.5 SCFH.

TH IS IS CONSIDERED AN ISCLATED EVENT WITH NO FURTHER ACTION REQUIRED.

I i

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MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 17 -

PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-1 05000325 011281 DURING THE PERFORMANCE OF CONTAINMENT ATMOSPHERE CONTROL (CAC). DRYWELL CNTNMHf COMBUS GAS CONTROL SYS 81-023/03L-0 021181 HYDROGEN AND OXYGEN CHANNEL CALIBRATION, P.T. 55.4PC, CAC MONITOR. 1-CAC INSTRUMENTATION + CONTROLS 036089 30-DAY

-ATH-1259. INDICATED UPSCALE REGARDLESS OF THE SAMPLE POINT SELECTED. T SENSOR / DETECTOR / ELEMENT HIS MONITOR HAS A HISTORY OF SIMILAR EVENTS INVOLVING UPSCALE INDICATION COMPONENT FAlltfRE

. THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNI ELECTRICAL CAL SPECIFICATION 3.3.5.3, 6.9.1.9B BECKMAN INSTRUMENTS, INC.

A FAILED MP51eun MAGNETIC ANALYZER SAMPLE CELL OCCURRED DUE TO EXCESSIVE MOISTURE EUILD-UP IN THE MONITOR SAMPLE LINES.

THE SAMPLE LINES WERE B LOWN DOWN TO REM 9VE THE MOISTURE AND THE MAGNETIC ANALYZER WAS REPLACED.

THE MONITOR WAS THEN CALIBRATED AND RETURNED TO SATISFACTORY OPERATION.

BRUNSWICK-1 05000325 011481 DURING THE PERFORMAPCE OF MAIN STEAM LINE ISOLATION. VALVE CLOSURE FUNCTI MAIN SiEAM ISOL SYS + CONTROLS 81-002/03L-0 021281 DNAL TEST, P.T.

1.3.1P, RPS LOGIC RELAYS, C71-K3D & K3E, DID NOT DE-ENGE INSTRUMENTATION + CONTROLS 036047 30-DAY RGIZE AS REQUIRED WHEN MSIV-1-B21-F028B WAS CLOSED. "A" RPS CHANNEL WAS SWITCH THEN PLACED IN THE " TRIPPED" POSITION AS REQUIRED BY TECHNICAL SPECIFICA OTHER TIONS.

THIS EVENT OCCURRED AGAIN ON FEBRUARY 12, 1981, AND A SIMILAR PA NOT APPLICABLE ST EVENT WAS REPORTED IN LER 1-80-75.

THIS EVENT DID HOT AFFECT-THE HEA NAMCO CONTROLS LTH OR SAFETY OF THE PUBLIC.

TECHNI \\L SPECIFICATIONS 3.3.1, 6.9.1.9B.

A STICKING VALVE POSITION LIMIT SUI' ACTUATOR ART 1 CAM, OF LIMIT SUITCH MODEL NO. EA740-80100, PREVENTED LC.. RELAYS FROM DE-ENERGIZING. ACTUA TOR ARM & ARM CAM UERE MECH EXERCISED 3 LUB TO ENSURE FREE MOVEMENT AFTE R 1-14-81 EVENT. AFTER EVENT ON 2-12-81, LIMIT SUITCH UAS REPLACED & INS TR RETURNED TO NORMAL OPER. NO HISTORY OF FAILURE WITH SIMILAR' SWITCHES.

BRUNSWICK-1 05000325 011581 DURING THE PERFORMANCE OF THE RCIC SYSTEM COMPONENT OPERABILITY TEST, P.

REAC CORE ISOL COOL SYS + CONT 81-009/03L-0 020581 T.

10.2, THE SYSTEM OIL COOLER INLET ISOLATION VALVE, 1-E51-F046, WOULD INSTRUMENTATION + CONTROLS 036088 30-DAY NOT OPEN FROM THE RTGB THEREBY MAKING THE RCIC SYSTEM INOPERABLE. THIS SWITCH EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPEC OTHER IFICATIONS 3.7.4, 6.9.1.9B.

NOT APPLICABLE OTHER THE VALVE MOTOR CONTROL CENTER LOCAL-NORMAL KEY LOCK SWITCH WAS NOT FULL Y TURNED TO THE " NORMAL" POSITION WHICH PREVENTED AN OPEN SIGNAL TO THE VALVE FROM THE RTGB CONTROL SWITCH. KEY LOCK SWITCH WAS POSITIONED TO "N ORMAL" 1 VALVE OPERATED SATISFACTORILY. A CHECK OF THE OTHER MOTOR CONT ROL CENTER KEY LOCK SWITCHES ON BOTH UNITS DID NOT REVEAL ANY PROBLEM.

BRUNSWICK-1 05000325 012081 UPON AN AUTO INITIATION FOLLOUING A REACTOR SCRAM. THE RCIC TURBINE FAIL REAC CORE ISOL COOL SYS + CONT 81-010/03L-0 021881 ED TO ACCELERATE TO GREATER THAN ITS DESIGNED IDLE SPEED, f1AKING THE RCI CIRCUIT CLOSERS / INTERRUPTERS 036228 30-DAY C SYSTEM INOPERABLE. THE HPCI SYSTEM UAS THEN UTILIZED TO RESTORE AND M SWITCH (OTHER THAN SENSOR)

AINTAIN REACTOR LEVEL IMMEDIATELY FOLLOUING THE SCRAM.

THIS EVENT DID N COMPONENT FAILURE OT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS ELECTRICAL 3.7.4, 6.9.1.9B.

LIMITORQUE CORP.

DIRTY HIGH RESISTIVE CONTACTS IN TURBINE STEAM INLET SUPPLY VALVE, 1-E51

-F045, POSITION LIMIT SWITCH PREVENTED TURBINE RAMP GENERATOR FROM ACCEL ERATING TURBINE BEYOND ITS DESIGNED IDLE SPEED DUE TO HIGHER THAN NORMAL VOLTAGE DROP ACROSS THESE CONTACTS. CONTACTS WERE CLEANED 1 RCIC TURBIN E WAS SUCCESSFULLY OPERATED. OTHER CONTACTS CHECKED ON BOTH UNIT #1 & 2.

MAR 26, 1981 LER MONTHL.Y REPORT SORTED BY FACILITY PAGE 18 PROCESSED DURING MARCU, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

CCMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-1 05000325 012181 DURING ROUTINE SHUTDOWN OPERATIONS IT WAS DISCOVERED THAT REACTOR RECIRC PROCESS SAMPLING SYSTEMS 81-011/03L-0 021881 ULATION SAMPLE INBOARD ISOLATION VALVE, 1-B32-F019. MODEL NO. T36D-1B, H VALVES 036229 30-DAY AD SEAT LEAKAGE OF APPROXIMATELY.25 GPM.

THE RECIRCULATION SAMFLE CUTB GLOBE OARD ISOLATICH VALVE, 1-B32-F020, WAS THEN CLOSED AND DEACTIVATED AS REQ UIRED BY TECHNICil SPECIFICATIONS. THIS EVENT DID NOT AFFECT THE HEALTH OTHER NOT APPLICABLE OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 3.1.3, 6.9.1.9B.

UELAN VALVE CORP.

THE CAUSE OF THE VALVE SEAT LEAKAGE IS PRESENTLY UNKNOWN.

THIS VALVE WI LL BE INSPECTED AND REPAIRED DURING THE NEXT PLANNED OUTAGE OF SUFFICIEN T LENGTH AS TO ALLOW PERSONNEL ACCESS TO THE PRIMARY CONTAINMENT.

BRUNSWICK-2 05000324 101980 DURING THE PERFORMANCE OF CONTAINMENT ATMOSPHERE MONITORING SYSTEM COMPO CNTHMNT ISOLATION SYS + CONT 80-080/03X-1 012081 NENT TEST PT 24.2, THE REACTOR INSTRUMENT PENETRATION (RIP) ISCLATION VA CIRCUIT CLOSERS / INTERRUPTERS 032999 OTHER LVE X76-B, WOULD NOT REOPEN WHICH MADE THE CONTAINMENT ATMOSPHERIC CONTR SWITCH (OTHER THAN SENSOR)

DL (CAC) MONITORS 1259, 1260, AND 1261 INOPERABLE DUE TO LOSS OF SAMPLE i

COMPONENT FAILURE FLOW THROUGH THE PENETRATION. THIS EVENT DID NOT AFFECT THE HEALTH OR S l

HATURAL END OF LIFE AFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 3.6.3, 6.9.1.9B.

OTHER ACTUATION SWITCH, MANUFACTURED BY MASTER SPECIALTIES. WAS F0ttND TO HAVE ITS BAKE-LITE NIPPLE BROKEN OFF, WHICH PREVENTED THE SWITCH ACTUATION PL UNGER FROM RESE1 TING THE SWITCH CONTACTS AFTER THE VALVE RAS CLOSED.

TH E ENTIRE SWITCH MODULE WAS REPL ACED AND THE VALVE WAS SUCcESSFULLY CYCLE D.

THIS IS CONSIDERED AN ISOLATED EVENT WITH NO FURTHER ACTION REQ.

DRUNSWICK-2 05000324 122580 DURING THE PERFORMANCE OF A CALIBRATION CHECK ON PRIMARY CONTAIFhENT ATM CNTHMNT COMBUS GAS CONTROL SYS 80-119/03L-0 012181 OSPHERIC MONITOR, 2-CAC-AT-1263, MODEL NO. 7C6A-1A3AX, IT WAS DISCOVERED INSTRUMENTATION + CONTRDLS 033703 30-DAY THAT THE MONI!OR HYDROGEN ANALYZER TRANSMITTER HAD NO OUTPUT SIGNAL.

T HIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SWITCH COMPONENT FAILURE SPECIFICATIONS 3.3.5.3, 6.9.1.9B.

ELECTRICAL DECKMAN INSTRUMENTS, INC.

THE MONITOR LOCAL / REMOTE SWITCH, LOCATED IN THE CONTROL ROOM HAD DIRTY C OHTACTS WHICH BLOCKED SIGNAL OUTPUT FROM HYDROGEN ANALYZER 8 PREVENTED I TS CALIBRATION. SWITCH CONTACTS WERE CLEANED 1 MONITOR WAS SUCCESSFULLY CALIBRATIDH CHECKED. AS THERE IS NO HISTORY OF PROBLEMS WITH THESE SWIT CHES THIS IS CONSIDERED AN ISCL EVENT WITH NO FURTHER ACTION REQUIRED.

BRUNSWICK-2 05000324 122780 DURING THE PERFORMANCE OF RHR SERVICE WATER SYSTEM COMPONENT TEST, PT 8.

RESIDUAL HEAT REMOV SYS + CONT 80-197/03L-0 012381 2.4, A VIBRATION OF 3.2 MILS WAS RECORDED FOR 2C RHR SW PUMP WHICH EXCEE PUMPS 033701 30-DAY DED THE SPECIFIED REQUIRED ACTION RANGE OF > 1.5 MILS.

THE PUMP WAS THE REFDRE DEOJRED INOPERABLE AS REQUIRED BY TECHNICAL SPECIFICATIONS. THI CENTRIFUGAL DESIGN / FABRICATION ERROR S EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SP DESIGN ECIFICATIONS 3.7.1.1, 6.9.1.93.

INGERSOLL-RAND CD THE PUMP DIFFUSER ANTI-ROTATING PIN DISLODGED FROM THE PUMP CASING ANG B ECAME EMBEDDED BETWEEN THE DIFFUSER VANE AND PUMP IMPELLER CAUSING A RUB BING CONDITION BETWEEN THE IMPELLER AND THE PIN WHEN THE PUMP WAS IN OPE RATION. PIN WAS REPLACED 2 PUMP RETURNED TO NORMAL OPERABILITY. THIS I S CONSIDERED AN ISOLATED EVENT WITH NO FURTHER CORRECTIVE ACTION REQ.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 19 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/MAMUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 122980 FOLLOWING A REACTOR SCRAM, REACTOR LEVEL INSTRUMENT, 2-B21-LI-R604A, DID OTHR INST SYS REQD FOR SAFETY 80-121/03L-0 012781 NOT TRACK PROPERLY TO DECREASING REACTOR LEVEL.

ALL OTHER LEVEL INDICA INSTRUMENTATION + CONTROLS 033704 30-DAY TIONS RESPONDED PROPERLY TO CHANGES IN REACTOR LEVEL.

THIS EVENT DID NO TRANSMITTER T AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 3 DESIGN / FABRICATION ERROR

.3.5.3, 6.9.1.93.

DESIGN YARWAY CORP.

THE GAIN SETTING ON THE INSTRUMENT LEVEL TRANSMITTER, 2-B21-LT-N026A, DR IFTED OUT OF CALIBRATICN. THE TRANSMITTER WAS THEN RECALIBRATED AND RET URNED TO NORMAL OPERATION.

A CHECK OF THE OTHER SIMILAR LEVEL TRANSMITT ERS ON BOTH UNITS DIo NOT REVEAL ANY PROBLEMS. THESE TYPE TRAHSM WILL BE REPLACED WITH MORE RELIABLE INSTRUMENTATION DURING A FUTURE OUTAGE.

BRUNSWICK-2 05000324 123180 DURING THE PERFORMANCE OF ADS HIGH DRYWELL PRESSURE CHANNEL CALIBRATION ENGNRD SAFETY FEATR INSTR SYS 80-116/03L-0 012351 AND FUNCTIONAL TEST, PT 11.1.4PC, 2-E11-PS-N010A, MODEL NO. D28-M18SS. A INSTRUMENTATION + CONTROLS 033700 30-DAY CTUATED AT 2.1 PSIG WHILE THE REPORTABLE LIMIT IS > 2.0 PSIG.

ALL OTHER SWITCH PRESSURE SWITCHES ACTUATED WITHIN SPECIFICATIONS. THIS EVENT DID NOT A OTHER FFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 4.3.

NOT APPLICABLE 3.1, 6.9.1.9B.

BARKSDALE COMPANY THE PRESSURE SWITCH WAS OUT OF CALIBRATION DUE TO INSTRUMENT DRIFT.

IT WAS RECALIBRATED ACCORDING TO THE PT AND RETURNED TO SATISFACTORY OPERAT ION.

THIS INSTRUMENT HAS A HISTORY OF RELIABLE OPERATION; HOWEVER, PERF CRMANCE OF OTHER SIMILAR INSTRUMENTS WILL BE REVIEWED IN ACCCRDANCE WITH THE?R PT SCHEDULE TO ENSURE THERE ARE NO FAILURE TRENDS.

BRUNSWICK-2 05000324 123180 DURING UNIT LOAD CHANGES WHILE MOVING CONTROL RODS, NO. 38-11 POSITION I REACTIVITY CONTROL SYSTEMS 80-118/03L-0 012281 HDICATION SHOWED A SUPERIMPOSED "3" DVER THE "8" DIGIT WHEN AT POSITION INSTRUMENTATION + CONTROLS 033702 30-DAY "48".

ALL OTHER CONTROL ROD POSITIDH INDICATIONS WERE NORMAL.

THIS EVE SWITCH NT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFI COMPONENT FAILURE CATIONS 3.1.3.F, 6.9.1.98.

ELECTRICAL GENERAL ELECTRIC CO.

A REED SWITCH PROBLEM IN THE ROD PIP PROBE IS SUSPECTED AS THE CAUSE OF THIS EVENT.

THIS PROBLEM WILL BE CORRECTED DURING THE NEXT GUTAGE OF SU FFICIENT LENGTH THAT ALLOWS ACCESS TO THE DRYWELL.

BRUNSWICK-2 05000324 010481 DURING THE P RFORMANCE OF THE DRYWELL 10 SUPPRESSION CHAMBER VACUUM BREA REACTOR CONTAINMENT SYSTEMS 81-002/03L-0 013081 KERS' FUNCTIONAL TEST, PT 2.3.1, VACUUM BREAKER X-18A HAD DUAL OPEN-CLOS VALVES 036090 30-DAY E POSITION INDICATION WHILE IN THE CPEN POSITION.

ALL OTHER VACUUM BREA CHECK KER POSITION INDICATIONS WERE NORMAL.

THIS EVENT DID NOT AFFECT THE HEA OTHER LTH OR SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 3.6.4.1, 6.9.1.9B NOT APPLICABLE GENERAL PRECISION INC.

THIS EVENT IS BELIEVED TO HAVE BEEN CAUSED BY A PROBLEM WITH THE VACUUM BREAKER POSITION LIMIT SWITCHES.

THE PROBLEM WILL BE FULLY INVESTIGATED AND RESOLVED DURING THE NEXT OUTAGE OF SUFFICIENT LENGTH THAT ALLCMS FE RSONNEL ACCESS TO THE DRYWELL.

MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 20 I

PROCESSED DURING MARCH. 1981 FOR POWER REACTORS 3

FACILITY / SYSTEM /CCMPONENT/

DOCKET NO./

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COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

I CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION BRUNSWICK-2 05000324 011081 DURING A NORMAL REACTOR STARTUP, IRM "A" DID NOT RESPOND TO CHANGES IN I REACTOR TRIP SYSTEMS 81-004/03L-0 020581 TS INPUT SIGNAL UHILE IRM "C" INDICATED DOWNSCALE WHEN ON RANGE 7.

ON J INSTRUMENTATION + CONTROLS 036091 30-DAY ANUARY 11. 1981 IRM *E" INDICATED DOWNSCALE WHILE FRM "C" WAS STILL IMO-POWER SUPPLY PERABLE FROM THE PREVIOUS DAY.

THESE EVENTS DID NOT AFFECT THE HEALTH 0 COMPONENT FAILURE R SAFETY OF THE PUBLIC.

TECHNICAL SPECIFICATIONS 3.3.1 6.9.1.9B NATURAL END OF LIFE GENERAL ELECTRIC CD.

IRM "A" HAD 2 FAILED CAPACITORS IN ITS HIGH VOLTAGE POWER SUPPLY. IRM "C

" HAD A FAILED HIGH FREQUENCY CHANNEL TRANSISTOR, AND IRM "E" HAD AN OPE N SIGNAL AT THE MONITOR PEE

THE FAILED COMPONENTS IN IRN

'S A AND C WERE REPLACCD F40 THE CONNECTOR OF IRM "E" WAS REPAIRED WHICH i

RETURNED ALL THREE IRM't TG NORMAL OPERATION.

BRUNSWICK-2 05000324 011381 DURING NORMAL SURVEILLANr&- IT MAS DISCOVERED THAT THE SECONDARY CONTAIN REACTOR CONTAINMENT SYSTEMS 81-005/03L-0 021181 MENT 20' ELEVATION OUTER air LOCK PERSONNEL DOOR WAS NOT SEALING CUE To PENETRATIONS.PRIMRY CONTAINMNT 036092 30-DAY A DAMAGED SECTION OF GASKET SEALING MATERIAL MAKING THE DOOR INDPERABLE.

PERSONNEL ACCESS THIS EVENT DID NOT AFFECT THE HEALTH OR SAFETY OF THE PUBLIC.

TECHNICA COMPONENT FAILURE L SPECIFICATIONS 3.6.S.I. 6.9.1.9B NATURAL END OF LIFE OTHER j

HIGH PERSONNEL TRAFFIC THROUGH tJCt, MANUFACTURED BY PROTECTED DOOR INDU STRIES. CAUSED GASKET TO BECOME DA1 AGED.

GASKET WAS REPAIRED 8 COOR WAS RETURNED TO NORMAL OPERATION. DCOR MANUFACTURER FACTORY REPRESENTATIVE HAS INSPECTED D00R & HAS MADE RECGdMENDATIONS TO ASSIST IN DEVELOPING A

)

PRFVENTATIVE MAINTENANCE PROCEDURE TO INSPECT DOORS ON A REGULAR BASIS.

BRUNSWICK-2 05000324 011581 DURING NORMAL PLANT OPERATION A GROUP I ISOLATION SIGNAL WAS RECEIVED ON REACTOR TRIP SYSTEMS 81- 0 0 7/ 0 3L-0 021081 THE "B" RPS TRIP CHANNEL. ALL-REACTOR OPERATING PARAMETERS REMAINED NO RELAYS 036093 30-DAY RMAL DURING AND FOLLOWING THIS EVENT.

THIS EVENT DID Nf1T AFFECT THE HEA OTHER LTH OR SAFETY OF THE PUBLIC. TECHNICAL SPECIFICATIONS 3.3.2. 6.9.1.9B COMPONENT FAILURE NATURAL END OF LIFE GENERAL ELECTRIC CD.

THE *B" RPS TRIP CHANNEL RELAY COIL FAILED DUE TO AN INSULATION BREAKDOW N.

THIS COIL. MODEL NO. P/M 12HFAS1A49F. IS DESIGNED TO BE CONSTANTLY E HERGIZED FOR CONTINUGUS SERVICE. THIS TYPE COIL IS UTILIZED THROUGHOUT THE RPS TRIP SYSTEM AND HAS NO PREVIOUS HISTORY OF SIMILAR FAILURES. RE LAY COIL WAS REPLACED.

BRUNSWICK-2 05000324 011581 DURING THE PERFORMANCE OF MAIN STEAM LINE ISOLATION VALVE CLOSURE CHANNE.

MAIN STEAM SUPPLY SYS + CONT 81-006/03L-0 020S81 L FUNCTIONAL TEST. P.T.

1.3.1P-2 WHEN MSIV F028C WAS REOPENED MAIN STEA VALVES 036167 30-DAY M LINE "C" INDICATED MINIMUM FLOW.

IT IS BELIEVED THAT A STEM-DISC SEPA 1

GLOBE RATION HAS DCCURRED IN THE OUTBOARD MSIV ON MAIN STEAM-LINE "C".

BOTH M COMPONENT FAILURE SIV's IN f1AIN STEAM LINE "C" WERE THEN SHUT AND DEACTIVATED. TECHNICAL OTHER SPECIFICATIONS 3.6.3. 6.9.1.9B.

ROCKWELL~ MANUFACTURING CD.

AT THIS TIME THE EXACT CAUSE OF THE MINIMUM STEAM FLOW IN MAIN STEAM LIN E "C" HAS NOT BEEN DETERMINED. AN INVESTIGATION WILL BE PERFORMED DURIN G A FUTURE OUTAGE.

A SUPPLEMENT TO THIS REPORT WILL BE SUBMITTED FOLLOW ING A DETERMINATION AND REPAIR-OF THE PROBLEM CAUSING THIS EVENT.

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MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 21 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTEM NO.

REPORT TYPE CAUSE DESCRIPTION I

BRUNSWICK-2 05000324 011981 WHILE PERFORMING PT 9.3A, HPCI SYSTEM COMPONENT TEST. IT WAS DETERMINED EMERG CORE COOLING SYS + Co*'

81-013/03L-0 020381 THAT THE PERIODIC TEST COULD HOT BE COMPLETED DUE TJ A FAILED MOTOR ON T VALVE OPERATORS 036048 30-DAY HE CST SUCTION VALVE, F004.

THIS EVENT DID NOT AFFECT THE HEALTH OR SAF ELECTRIC MOTOR - DC ETY OF THE PUBLIC AS THE SYSTEM WAS LINED UP TO USE THE SUPPRESSION POOL COMPONENT FAILURE FOR ITS WATER SOURCE.

TECHNICAL SPECIFICATIONS 3.51, 6.9.1.9C.

ELECTRICAL LIMITORQUE CORP.

THE MOTOR WHICH OPERATES THE F004 VALVE FAILED AND HAS BEEN SENT TO A SE RVICE CONTRACTOR FOR REPAIR.

THE PLANT IS PRESENTLY ATTEMPTING-TO LOCAT l

E ANOTHER MOTOR IN THE INDUSTRY FOR USE UNTIL OURS IS REPAIRED.

THIS IS CONSIDERED AN ISOLATED EVENT AND NO FURTHER ACTION IS REQUIRED.

j GRUNSWICK-2 05000324 012881 FOLLOWING THE COMPLETION OF A PLANNED CONTROLLED RELEASE OF LIQUID RADIO i

I LIQ RADIDACT WSTE MANAGMNT SYS 81-009/04L-0 021181 ACTIVE WASTE. THE RADWASTE SYSTEM LICUID EFFLUENT DISCH ARGE HIGH RANGE I l

l INSTRUMENTATION + CONTROLS 036168 30-DAY NDICATOR/ RECORDER, UTILIZED FOR THE RELEASE, WAS FOUND TO HAVE INDICATED TRANSMITTER AND RECORDED A RELEASE FLOW RATE THAT WAS LESS THAN THE-ACTUAL CAUSING l

COMPONENT FAILURE THE SPECIFIED MAXIMUM ALLOWED RELEASE RATE TO BE EXCEEDED. ENVIRONMENTA l

MECHANICAL L TECPMICAL-SPECIFICATIONS 3.5.1.E. 5.4.2B.

GENERAL ELECTRIC CO.

l MECHANICAL LINKAGE BETWEEN FLOW PADDLE & TRANSMITTER BECAME LOOSE CAUSIN G THE FALSE FLOW INDICATION. PROBLEM WAS CORRECTED 3 INSTRUMENT RETURNE D TO NORMAL OPERATION. THIS IS CONSIDERED AN ISOLATED EVENT WITH NO FUR THER ACTION REQUIRED. PLANT PREVENTATIVE MAINTENANCE PROCEDURES WILL BE REVISED TO CALIBRATE THIS INDICATOR / RECORDER & TRANSMITTER QUARTERLY.

CALVERT CLIFFS-1 05000317

.122280 18C TECHNICIANS INVESTIGATING A GREATER THAN 0.1 VOLT DEVIATION BETWEEN ENGNRD SAFETY FEATR INSTR SYS 80-069/03L-0 012181 12 STEAM GENERATOR PRESSURE ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION + CONTROLS 033705 30-DAY CHANNEL ZD AND OTHER CHANNELS DETERMINED THAT E/E CONVERTER WAS DEFECTIV INDICATOR E FOR CHANNEL ZG.

E/E CONVERTER WAS REPL ACED AND CHANNEL' ZG RETURNED TO COMPONENT FAILURE SERVICE AT 1115.

THE THREE REDUNDANT CHANNELS REMAINED OPERABLE.

LER' OTHER S 79-70 AND 80-13 (U-1) DESCRIBE SIMILAR EVENTS.

VITRO ENGINEERING DIVISION THE CAUSE FOR THE DEVIATION WAS CHANNEL D BISTABLE VOLTMETER HAVING ZERO j

-SHIFTED OUT OF TOLERANCE. PROBABLE CAUSE WAS REFUELING OUTAGE WORK REQ IRING CABINET POWER REMOVAL AND RESTORATION. THE BISTABLE (VITRO NO. 16 28-1042) METER WAS RECALIBRATED. NO FURTHER ACTION IS DEEMED HECESSARY.

CALVERT CLIFFS-1 05000317 122580 AT 0940. DURING HORMAL OPERATION, CONTROL' ROOM OPERATOR DISCOVERED #11 C COOL SYS FOR REAC AUX + CONT 80-072/03L-0 012381 OMPONENT COOLING HEAT EXCHANGER OUTLET THROTTLE VALVE (1-SW-5206-CV) WOU VALVE OPERATORS 033706 30-DAY LD NOT OPEN RENDERING HEAT EXCHANGER INOPERABLE (T.S. 3.7.3.1).

  1. 11 COM PNEUMATIC / DIAPHRAGM / CYLINDER PONENT COOLING HEAT EXCHANGER WAS RETURNED TO SERVICE AT 1820 ON 12-26-8 DESIGN / FABRICATION ERROR 0.
  1. 12 CCMPONENT COOLING HEAT EXCHANGER REMAINED OPERABLE. LER 79-58 (

CONSTRUCTION / INSTALLATION U-1) DESCRIBES A SIMILAR OCCURRENCE.

BETTIS CORPORATION 1-CV-5206 WOULD NOT OPERATE BECAUSE THE KEY CONNECTING THE VALVE OPERATO R TO VALVE STEM HAD DROPPED FROM SHAFT DURING REASSEMBLY AFTER OUTAGE RE LATED MAINTENANCE. THE KEY WAS REINSTALLED, STAKED TO THE SHAFT AND THE OPERATOR REINSTALLED. THE VALVE WAS TESTED SATISFACTORILY.

1 MAR 26, 1981 LER MOH1HLY REPORT SORTED BY FACILITY PAGE 22 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-1 0S000317 011381 AT 1110. STEAM GENERATOR (SG) #11 LEVEL CHANNEL "D" WAS PLACED DUT OF SE REACTOR TRIP SYSTEMS 81-006/03L-0 021281 RVICE PER TECHNICAL SPECIFICATION 3.3.1.1 TO CORRECT A PROBLEM WITH ITS VALVES 036230 30-DAY REFERENCE LEG. #11 SG LEVEL CHANNEL "D" WAS RETURNED TO SERVICE AT 1100 OTHER ON 1-14-81.

THE THREE REDUNDANT CHANNELS REMAINED OPERABLE DURING THE E OTHER VENT.

THIS IS NOT A REPETITIVE OCCURRENCE.

NOT APPLICABLE FISCHER & PORTER CO.

LEVEL TRANSMITTER EQUALIZING VALVE LEAK-THROUGH IS BEiIEVED TO HAVE CAUS D AN INDICATION DEVIATION AMONG REDUNDANT SAFETY CHANNELS.

BOTH 1-LT-11 13D AND PARALLEL-CONNECTED 1-LT-1111 (CONTROL CHANNEL) WERE AFFECTED.

I NDICATION RETURNED TO NORMAL AFTER BLOUCOWN OF THE SHARED REFERENCE LEG AND TRANSMITTER PIPING. NO PREVENTIVE ACTION IS DEEMED HECESSARY.

CALVERT CLIFFS-1 05000317 011981 AT 0430. DURING THE PERFORMANCE OF SURVEILLANCE TESTING, 214 CONTAINMENT CNTHMNT HEAT REMOV SYS + CONT 81-005/03L-0 021781 COOLER UOULD NOT START IN SLOW SPEED (TECH SPEC 3.6.2.2).

CORRECTIVE R CIRCUIT CLOSERS / INTERRUPTERS 036185 30-DAY EPAIRS WERE t1ADE AND THE UNIT RETURNED TO SERVICE AT 2055.

THREE CONTAI STARTER NMENT COOLERS REMAIFED OPERABLE DURING THE EVENT.

THIS HAS NOT BEEN A R P ER SO M'i' ERROR EPETITIVE EVENT.

MAIN)ENANLE & REPAIR PERSONNEL I-T-E CIRCUIT BREAKER THE SLOW SPEED MOTOR STARTER INTERLOCK CONTACT ASSEMBLY WAS FOUND TO BE INOPERATIVE DUE TO DAMAGE CAUSED BY OVER11GHTENED MOUNTING SCREWS.

THE CASE WAS CRACKED, PREVENTING CONTACTS FR0t' CLOSING.

THE PART WAS REPLAC ED WITH A SPARE.

ELECTRICAL MAINTENANCE PERSONNEL WILL BE INSTRUCTED IN THESE CONSEQUENCES AND METHODS TO FREVENT SIMILAR REPORTS.

CALVERT CLIFFS-1 05000317 012381 DURING POWER OPERATION, A BROKEN HIPPLE WAS DISCOVERED ON VALVE CV-5178, COOL SYS FOR REAC AUX + CONT 81-010/03L-0 022081 SALT WATER EMERGENCY RETURN ISOLATION FROM ECCS PUMP ROOM COOLERS. ISOL VALVES 036187 30-DAY ATIO" 2 REPAIR RESULTED IN TEMPORARY LOSS OF REDUNDANCY IN SALT WATER, S BUTTERFLY ERVICE WATER, & COMPONENT COOLING SYSTEMS PER TECH. SPEC.

3.7.3.1, 3.7.4 PERSONNEL ERROR 1,

8 3.7.5.1.

VALVE WAS REPAIRED 8 AFFECTED SYSTEMS RETURNED TO NORMAL CONTRACT. 8 CONSULT. PERSONNEL ON 01/25. REDUNDANT COOLING SYSTEMS ret 1AINED OPERABLE DURING THIS EVENT.

MASONEILAN INTERNATI0HAL, INC.

EVENT HAD NO EFFECT ON PUBLIC HEALTH OR SAFETY 8 WAS NONREPETITIVE.

NIPPLE WAS BROKEN OFF OF THE VALVE BY A LEAD BRICK WHICH FELL DURING CON STRUCTION OF A-LEAK SHIELD WALL. VALVE WAS ISOLATED AND THE NIPPLE WAS R EPLACED. TO PREVENT RECURRENCE. INSTRUCTIONS HAVE BEEN ISSUED TO PERSONN EL, ADDRESSING PROPER METHOD OF STACKING LEAD BRICK AND ATTENTIVENESS WH ILE PERFORMING THIS WORK NEAR SAFETY-RELATED EQUIPitENT.

CALVERT CLIFFS-1 05000317 020381 DURING NORMAL POWER OPERATION OF U-1 AND REFUELING OPERATIONS ON U-2, DI FIRE PROTECTION SYS + CONT 81-008/01T-0 021781 SCOVERED THAT WHEN A NUMBER OF FIRE HOSE STATIONS WERE ISOLATED, BACKUP COMPONENT CODE NOT APPLICABLE 036186 2-WEEK FIRE HOSES WERE NOT ROUTED AS REQUIRED BY T.S.

3.7.11.4.A.

BACKUP FIRE SUBCOMPONENT NOT APPLICABLE HOSES WERE THEN ROUTED TO ALL AFFECTED HOSE STATIONS. BACKUP FIRE HOSE PERSONNEL ERROR STATIONS WERE AVAILABLE HEAR MOST AFFECTED LOCATIONS.

ALSO, FIRE WATCHE LICENSED 2 SENIOR OPERATORS S WERE STATIONED AT VARIOUS LOCATIONS DURING THIS EVENT.

THIS IS A NOM-ITEM NOT APPLICABLE REPETITIVE EVENT AND HAD NO IMPACT ON PUBLIC HEALTH OR SAFETY.

THE SHIFT SUPERVISOR HAD BEEN MISINFORMED OF THE STATUS OF THE FIRE PROT ECTION SYSTEM. UPON DISCOVERY OF THIS PROBLEM, BACKUP FIRE HOSES WERE R OUTED AS REQUIRED BY T.S.

3.7.11.4.A.

THIS EVENT HAS BEEN REVIEWED WITH THE PLANT FIRE PROTFerION INSPECTOR AND THE SHIFT SUPERVISOR INVOLVED.

ALL OPERATIONS PERSUANEL WILL BE INFORMED OF Ti;E DETAILS OF THIS EVENT.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 23 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-2 05000318 122680 AT 1945, WHILE INVESTIGATING ABNORMAL CONTAINMENT AIR PARTICULATE AND GA AIRBORNE RADIDACT MONITOR SYS 80-059/03L-0 012681 SEOUS READINGS, FOUND CONTAINTIENT ATMOSPHERE SAMPLE ISOL ATION VALVE SHUT VALVE OPERATORS 033707 30-DAY (TECHNICAL SPECIFICATION 3.4.6.1).

VALVE WAS REOPENED AND GASEOUS READ PNEUM ATIC/DI APHR AGM/CYLIt' DER INGS RETURNED TO NOPMALs HOWEVER, APD REMAINED INOPERABLE (REFERENCE (U-PER3ONNEL ERROR

2) LER 80-60).

GRAL SAMPLES TAKEN BOTH PRIOR TO AND DURING EVENT.

CTMT LICENSED & SENIOR OPERATORS SUMP LEVEL ALARM OPERABLE. NOT REPETITIVE.

MASONEILAN INTERNATIONAL, INC.

OPERATOR INADVERTENILY SHUT SAMPLE ISOLATION VALVE AFTER DRAINING CTMT S UMP AT APPROXIMATELY 2300 ON 12-25-80.

ALL LICENSED OPERATORS TO BE MAD E AWARE OF THIS EVENT.

ALSO, DURING CUR ~ENT GUTAGE, ONE OF THE TWO CTMT SUMP VALVE HAND SWITCHES WILL BE MADE SPRING RETURN TO CLOSE (REFERENCE FFCR 80-85).

CALVERT CLIFFS-2 05000318 122680 AT 1945,AFTER RETURNING CONTAINMENT (CTMT) AIR PARTICULATE (APD) AND GAS AIRBORNE RADIDACT MONITOR SYS 80-060/03L-0 012681 EOUS MONITORS TO SERVICE (REF. LER 80-59 U-2), APD REMAINED INOPERABLE.

INSTRUMENTATION + CONTROLS 033708 30-DAY APD WAS REPAIRED AND RETURNED TO SERVICE AT 1330 ON 12-30-80.

GRAB SAMP OTHER LES TAKEN PRIOR TO AND DURING EVENT.

CTMT SUMP LEVEL ALARM AND GASEOUS COMPONENT FAILURE MONITOR MERE OPERABLE DURING THE EVENT.

THIS HAS NOT BEEN A REPETITIVE NATURAL END OF LIFE EVENT.

WESTINGHOUSE ELECTRIC CORP.

A3.R PARTICULATE' DETECTOR JUNCTION BOX CONNECTOR (DEUTSCH DS07-12S-059) F AILED RESULTING IN ABNORMAL HIGH INDICATION. CONNECTOR WEAR FROM HANDLI NG OURiF6 PREVENTIVE AND CORRECTIVE t1AINTENANCE CONTRIBUTED TO END-OF-LI FE FAILURL WITH LOOSENED CONNECTIO;45. NO PREVENTIVE ACTION IS DEEMED NE CESS ARY A7 THIS tit 1E.

CALVERT CLIFFS-2 05000318 010781 AT 0930. CHANNEL B REACTOR PROTECTIVE SYSTEM TRIP UNITS FOR HI POWER, TH REACTOR TRIP SYSTEMS 81-001/03L-0 020581 ERMAL MARGIN / LOW PRESSURE AND AXIAL FLUX OFFSET WERE BYPASSED FOR TROUBL INSTRUMENTATION + CONTROLS 036026 30-DAY ESH00 TING THE LINEAR POWER RANGE INSTRUMENT. THE DETECTOR CUTPUT WAS FA OTHER ULTY; THEREFORE, CHANNEL B HI POWER, TM/LP AND AFD TRIP UNITS WERE PLACE COMPONENT FAILURE D IN THE TRIPPED CONDITION AT 1255 ON 1/8/81 PER TECHNICAL SPECIFICATION NATURAL END OF LIFE 3.3.1.1 THE THREE REDUNDANT CHANNELS WERE OPERABLE.

LER'S 79-50 AND OTHER 80-05 (U-2) REPORT EARLIER SYMPTOMS OF THE PROBLEM.

THE UPPER SUBCHANNEL DETECTOR'S FIELD CABLE CONNECTOR (KING ELECTRONICS CO.,

INC. SKH5905) MAS FOUND LOOSENED, MAKING INTERMITTENT CONTACT.

THE CONNECTOR WILL BE REPLACED DURING THE CURRENT REFUELING OUTAGE.

THIS H AS NOT BEEN A REPETITIVE FAILURE; IT IS CONSIDERED TO BE DUE TO WEAR AND HANDLING DURING ITS SERVICE. N3 PREVENTIVE ACTION IS NECESSARY.

l CALVERT CLIFFS-2 05000318 011381 AT 1115. DURING THE PERFORMANCE OF SURVEILLANCE TESTING, #1? DIESEL GENE EMERG GENERATOR SYS + CONTROLS 81-006/03L-0 021281 RATOR SUITCHGEAR UGULD NOT CLOSE IN ON 821 4KV BUS PER THE REQUIREMENTS CIRCUIT CLOSERS / INTERRUPTERS 036189 30-DAY OF TECHNICAL SPECIFICATION 3.8.1.1.

THE DIESEL WAS DECLARED INOPERABLE A SWITCHGEAR ND THE REDUNDANT POWER SOURCES VERIFIED. #12 DIESEL GENERATOR WAS TESTE OTHER D AND RETURNED TO SERVICE AT 1415.

THIS IS NOT A REPETITIVE OCCURRENCE.

NOT APPLICABLE GENERAL ELECTRIC CO.

CONTINUITY OF THE CLOSING CIRCUIT INTERLOCKS WAS VERIFIED. THE SWITCHGE AR (G.E. CO. TYPE At1H-4.76-250-ID) MAS CYCLED IN TEST AND NORt1AL POSITIO NS.

CONCLUSION: A HIGH RESISTANCE EXISTED AT A SECONDARY DISCONNECT WHI CH CLEARED UPON REINSERTING THE SWITCHGEAR. DISCONNECT CONTACT INSPECTI ON IS PART OF EXISTING PM PROCEDURE.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 24 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMFONENT/

DOCKET NO./

EVENT DATE/

COMP 0HENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REFORT TYPE CAUSE DESCRIPTION CALVERT CLIFFS-2 05000318 011381 AT 1025. DURING NORMAL OPERATION. ENGINEERED SAFETY FEATURES (ESFAS) CHA ENCHRD SAFETY FEATR INSTR SYS 81- 0 0 8/ 0 3 L-0 021281 NNEL "ZD" WAS DEENERGIZED FOR MAINTENANCE ON #22 STEAM GENERATOR PRES $UR INSTRUMENTATION + CONTROLS 036191 30-DAY E AND BLOCK MODULES (TECH. SPEC.

3.3.2.1).

THE THREE REDUNDANT CHANNELS OTHER REMAINED OPERABLE DURING THIS EVENT.

ESFAS CHANNEL "ZD" WAS RETURNED T.

COMPONENT FAILURE O SERVICE AT 1110.

LER'S 05000317/80-69 AND 05000318/78-16 DESCRIBE SIM INSTRUMENT ILAR EVENTS.

VITRO ENGINEERING DIVISI0H

' TECHNICIANS. INVESTIGATING A DEVIATION IN INDICATIGN AMONG PRES $URE CHAN HELS. FOUND #22 "ZD" SG PRESSURE BISTABLE METER WOULD NOT CALIBRATE. DUR ING THE METER REPLACEMENT 2-E/E-1023A (TRANSMATION MODEL 230IT) FAILED G 1

IVING A LOW OUTPUT. IT IS BELIEVED THAT THIS INSTRUMENT CONTRIBUTED TO T HE DEVIATION IN INDICATION. BOTH INSTRUMENTS WERE REPLACED WITH SPARES.

OALVERT CLIFFS-2 05000318 011881 AT 0847.WITH THE REACTOR COOLANT SYSTEM (RCS) AT 220 DEGREES F AND 230 P j

OTHR INST SYS REQD FOR SAFETY 81-005/01T-0 012981 SIA. A PRESSURE TRANSMITTER FAILED HIGH CAUSING POWER RELIEF VALVE RC-40 INS 1RUNENTATION + CONTROLS 036027 2-WEEK 4-ERV TO OPEN.

AFTER THE OPERATOR VERIFIED THE OPEN VALVE. HE CLOSED TH TRANSMITTER E BLOCKING VALVE TERMINATING THE DISCHARGE. RELIEF VALVE WAS OPEN IN LE PERSONNEL ERROR SS THAN ONE MINUTE AND RCS PRESSURE DECREASED LESS THAN 6 PSI.

THIS REP MAINTENANCE & REPAIR PERSONNEL ORT IS BEING MADE PER IRE INSPECTION REPORT 317-79-23.

THIS IS NOT A RE FISCHER 4 PORTER CO.

PETITIVE OCCUR *.ENCE.

THE CAUSE OF nHE EVENT WAS A LOOSE OSCILLATOR / AMPLIFIER ASSEMBLY WITHIN TRANSMITTER 2-PT-103-1 (F3P CO. 50EP1041 BONS).

THE ASSEMBLY MOUNTING SO REWS WERE FOUND LOOSE AND INTERMITTENT CONTACT THROUGH ITS CONNECTOR CAU SED SIGNAL CURRENT TO INCREASE DRIVING CONTROLLER 2-PIC-101-1 TO MAXIMUM PRESSURE INDICATION. NO REOCCURRENCE SINCE MOUNTING SCREWS TIGHTENED.

CALVERT CLIFFS-2 05000318 01188' AT 1730. WITH THE bMIT IN MODE 5. FOR A SCHEDULED REFUELING OUTAGE. #21 MAIN STEAM ISOL SYS + CONTROLS 81-007/03L-0 02178%

AND #22 MAIN STEAM ISOLATION VALVES FAILED TO SHUT IN </: 3.6 SECONDS AS VALVE OPERATORS 036190 30-DAY REQUIRED BY TECHNICAL SPECIFICATION 4.7.1.5 DURING A ROUTINE TEST.

THE HYCRAULIC VALVES ARE ONLY REQUIRED TO OPERATE IN MODES

1. 2. AND 3.

NO SIMILAR'E OTHER VENTS HAVE BEEN REPORTED.

NOT APPLICABLE GREER HYDRAULICS, INC.

THE SPECIFIC CAUSES OF THIS FAILURE ARE NOT KNOWN AT THIS TIME.

AH UPDA TED REPORT WILL BE ISSUED UPON COMPLETION OF THE INVESTIGATION.

CALVERT CLIFFS-2 05000318 012381 DURING MODE 6 OPERATION. SHUTDOWN COOLING FLOW WAS STOPPED FOR S MINUTES RESIDUAL HEAT REMOV SYS + CONT 81-003/03L-0 022081

. ACTIONS WERE TAKEN AS' REQUIRED BY TECH. SPEC.

3.9.8.A.

AT 0655. VALV VALVES 036138 30-DAY E POSITION INDICATION WAS LOST FOR MOV-652. A SHUTDOWN COOLING RETURN HE GLOBE ADER ISOLATION VALVE.

QUESTIONING THE ACTUAL VALVE POSITION. THE OPERAT OTHER

-OR STOPPED FLOW TEMPORARILY. AT 0700 VALVE POSITION INDICATION AND FLOW NOT APPLICABLE WERE RESTORED.

THERE WAS NO INCREASE IN DECAY HEAT LOAD OR DECREASE IN OTHER RCS BORON CONCENTRATION DURING THIS NON-REPETITIVE EVENT.

CAUSE OF THE LOSS OF VALVE POSITION INDICATION FOR MOV-652, WAS A MCC PO WER TRANFER.

THE TRANSFER WAS OVER IN 5 MINUTES AND VALVE POSITION INDI

~ CATION AND SHUTDOWN COOLING WERE RESTORED. A RECENT PROBLEM WITH PT-103-1 CONTRIBUTED TO THE DECISION TO STOP FLOW. THIS PROBLEM HAS SINCE BEEN CORRECTED. LICENSED PERSONNEL WILL BE INFORMED OF THIS EVENT.

~-

MOR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 25 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO / EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAVSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION C00PER-1 05000298 112080 THE REACTOR WAS IN A COLD SHUTDOWN CONDITION. WHILE PERFORMING ROUTINE MAIN STEAM ISOL SYS + CONTROLS 80-049/03L-0 121980 SURVEILLANCE TEST PROCEDURE 6.3.9.4, MSIV 86A WAS FOUND TO HAVE A CLOSUR VALVES 033666 30-DAY E TIME SLOWER THAN ALLDUED BY TECH. SPEC.

3.7.D.

SEVEN OF THE EIGHT MSI GLOBE V'S WERE WITH1N THE TECHNICAL SPECIFICATION LIMITS SO THIS OCCURRENCE PR COMPONENT FAILURE ESENTED HO ADVERSE CONSEQUENCES FROM THE STANDPOINT OF PUBLIC HEALTH AND OTHER SAFETY.

(REFERENCE LER 80-21)

ROCKWELL-INTERNATIONAL THE CLOSURE TIME OF MSIV 86A WAS GREATER THAN 5 SECONDS.

IMMEDIATE CORR ECTIVE ACTION WAS TO ADJUST CLOSING TIME FOR MSIV 86A.

REASON FOR THIS CHANGE HAS NOT BEEN IDENTIFIED. FURTHER EVAL. WILL BE PERFORMED. VALVE IS AN AIR OPERATED ROCKWELL EDWARDS 24" ANGLE GLOBE VALVE, MODEL #1612-JMMY.

RALPH A HILLER CO. SUPPLIED THE AIR OPERATOR #SA-A051.

C00PER-1 05000298 121680 DURING SURVEILLANCE TESTING OF RHR MOTOR OPERATED VALVES, RHR-MO-25B, TH RESIDUAL HEAT REMOV Sfs + CONT 80-050/03L-0 011481 E LOOP "B" INJECTION LINE INBOARD ISOLATION WOULD NOT OPEN.

THE "A" LOO WALVES 033709 30-DAY P WAS OPERABLE AS WELL AS BOTH DIESEL GENERATORS. THE SUBJECT VALVE IS GATE NORMALLY CLOSED AND IS REQUIRED TO OPEN FOR LPCI INJECTION. THERE WERE COMPONENT FAILURE NO ADVERSE AFFECTS TO THE PUBLIC HEALTH AND SAFETY.

(RTS 3.5.A).

OTHER ANCHOR / DARLING VALVE CO.

VALVE IS 24",

900#, ANCHOR / DARLING GATE VLV. CLOSING TORQUE SWITCH SET T 00 CLOSE TO MFG RECOMMENDED SETTING UHICH CAUSED VLV DISK TO STICK IN SE AT. VLV MANUALLY OPENED. CLOSE TORQUE SWITCH ADJUSTED TO LOWER SETTING I DENTICAL TO "A" LOOP ISOL VLV. VLV SATISF TESTED. EVAL BEING PERFORf1ED &

UPDTD LER WILL BE SUDMITTED IF DETERMINED HYDRAULIC LOCK COULD EXIST.

COOPER-1 05000298 121680 DURING ROUTINE SURVEILLANCE TESTING. THE HPCI TURBINE STOP VALVE WOULD N EMERG C5RE COOLING SYS + CONT 80-051/03L-0 011381 OT OPEN. THE HPCI SYSTEM WAS DECLARED INOPERABLE. THE REDUNDANT SYSTEM, VALVE OPERATORS 033710 30-DAY ADS. WAS OPERABLE AS WAS RCIC AND ALL THE LOW PRESSURE SYSTEMS,'WITH EXC HYDRAULIC EPTION OF THE B-LOOP OF LPCI, WHICH WAS INOPERABLE FOR 2 HOURS 48 MINUTE PERSONNEL ERROR S DURING THE HPCI OUTAGE. AN EVENT OF A SIMILAR HATURE HAS OCCURRED (REF MAINTENANCE 8 REPAIR PERSONNEL

. LER 79-19) BUT CAUSE OF THIS OCCURRENCE IS NOT THE-SAME. THIS EVENT HA MILLER FLUID POWER CO.

D NO ADVERSE AFFECT ON THE PUBLIC HEALTH AND SAFETY.

FAILURE OF THE STOP VALVE TO OPEN WAS CAUSED BY EXCESS TEFLON SEAL MATER IAL (MILLER FLUID POWER, "SHEF SEAL", PART NO. 110-ES006-1200) WHICH INT ERFERED WITH OPERATION OF RELAY VALVE ON HYDRAULIC ACTUATOR. GASKET MATE RIAL MAS INSTALLED BY MAINTENANCE PERSONNEL DURING 1980 REFUELING OUTAGE

. EXCESS SEAL MATERIAL WAS REMOVED. NO FURTHER ACTION IS PLANNED.

COOPER-l 05000298 123080 DURING HORMAL SURVEILLANCE TESTINC OF THE RHR SERVICE WATER SYSTEM, SW-M RESIDUAL HEAT REMOV SYS + CONT 80-052/D3L-0 012981 0-89A.-THE LOOP "A" SYSTEM THROTTLF. VALVE ON THE DISCHARGE OF THE "A" RH UALVE OPERATORS 033750 30-DAY R HEAT EXCHANGER, AFTER OPENING TO THE MINIMUM FLOW POSITION WOULD NOT R ELECTRIC MOTOR - AC ESPOND TO THE REMOTE CONTROLLER. THE REDUNDANT LOOP WAS OPERABLE AS WEL OTHER L AS BOTH DIESEL GENERATORS. THERE WERE NO ADVERSE EFFECTS TO THE PUBLI NOT APPLICABLE C HEALTH AND SAFETY.

(RTS 3.5.B).

LIMITORQUE CORP.

SM-MO-89A IS A 18",

3003 GLOBE VALVE WITH A LIMITORQUE SMB-3 MOTOR OPERA TOR.

THE CAUSE OF THE PROBLEM IS UNKNOWN.

THE FAILURE COULD NOT BE REP EATED.

RECORDERS ARE MONITORING OUTPUT OF THE CONTROLLER, FEEDBACK FROM THE VALVE POSITIONER, AND THE OPEN AND CLOSE CONTACTS ON THE OPERATOR M OTOR FOR 5 SUBSEQUENT VALVE OPERATIONS TO VERIFY OPERABILITY.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 26 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/PANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION C00PER-1 05000298 010281 DURING NORMAL STEADY STATE OPERATION, HYDRAULIC SHOCK SUPPRESSOR RF-54 W SYSTEM CODE NOT APPLICABLE 81-001/03L-0 013081 AS DISCOVERED INOPERABLE PER RTS 3.6.H.3.

OTHER SEISMIC RESTRAINTS WERE.

HANGERS. SUPPORTS. SHOCK SUPPRSS 036169 30-DAY AVAILABLE. THE REDUNDANT ADS AND RCIC SYSTEMS WERE OPERABLE.

THERE WE SNUBBERS RE NO ADVERSE EFFECTS TO THE PUBLIC HEALTH AND SAFETY. PREVIOUS SIMILAR.

PERSONNEL ERROR EVENT REPORTED ON LER 80-45.

MAINTENANCE 4 REPAIR PERSONNEL ITT GRINNELL RF-SE IS A GRINNEL FIG. 200 HYDRAULIC SEISMIC SHOCK SUPPRESSOR. THIS SU PPRESSOR WAS INSTALLED W/ RESERVOIR CONNECTING PIPE AT HIGHER END OF RESE RVOIR INSTEAD OF LOWER END.

SUPPRESSOR WAS REORIENTED PROPERLY.

ALL OT HER SUPPRESSORS INSTALLED DURING 1980 REFUELING OUTAGE CHECKED FOR PROPE R INSTALL.

OCC HAS BEEN REVIEWED WITH-APPROPRIATE STATION PERSONNEL.

CRYSTAL RIVER-3 05000302 121580 AT 1525 DURING HORTIAL OPERATION IT WAS DISCOVERED THAT THE MECHANICAL SE CNTHMNT AIR PURI + CLEANUP SYS 81-005/03L-0 021781 AL FOR BUILDING SPRAY PUMP BSP-1A WAS LEAKING GREATER THAN 6 GAL /HR.

TH

-PUMPS 036097 30-DAY IS CREATED AN EVENT CONTRARY TO TECH. SPEC.

3.6.2.1.

MAINTENANCE WAS IN CENTRIFUGAL ITIATED 8 OPERABILITY WAS RESTORED AT 1305 12/17/80.

THERE WAS NO EFFEC COMPONENT FAILURE T ON THE PUBLIC HEALTH OR SAFETY.

THIS WAS FIRST OCCURRENCE FOR BSP-1A MECHANICAL

& THIS IS FIRST EVENT REPORTED UNDER THIS SPECIFICATION.

WORTHINGTON PUMP CORP.

.THE CAUSE OF THIS EVENT IS ATTRIBUTED TO A DEFECTIVE MECHANICAL SEAL.

T HE SEAL WAS REPLACED AND FUNCTIONALLY TESTED SATISFACTORY. THE SEAL NAY HAVE BE5N DAMAGED DURING' IMPELLER MAINTENANCE ACTIVITIES. A REVIEW OF THE SUSPECTED MAINTENANCE PROCEDURE IS BEING CONDUCTED TO PREVENT RECURR ENCE.

CRYSTAL RIVER-3 05000302 010781 AT 1210 DURING PERFORMANCE OF SP-511, QUARTERLY BATTERY CHECK (UNITS t 1 0FFSITF POWER SYSTEMS + CONTRL 81- 0 01/ 01 T- 0 020681 2), UNIT #2 BATTERY DID NOT MEET REQUIREMENTS OF T.S. SURVEILLANCE 4.8.

BATTERIES + CHARGERS 036028 2-WEEK 1.1.1.C.2.B). AND WAS CONTRARY TO T.S. 3.8.1.1 REDUNDANCY WAS PROVIDED SUBCOMPONENT NOT APPLICABLE BY UNIT #1 BATT & BY DIESEL-1A 8 1B.

AT 1700. THE D/G-1A FUEL DIL STOR OTHER AGE TANK HAD LESS THAN 400 GAL; DFP-1A 8 1C WERE NOT OPERATING BUT COULD NOT APPLICABLE OPERATE BY MANUAL CONTROL.

STH OCCUR FOR UNIT 1 4 2 BATTERIES, 1ST FOR EXIDE INDUSTRIAL DIV DAY TANK LEVEL AND TRANSFER PUMPS. AND 21ST REPORT UNDER THIS SPEC.

THE SPECIFIC' GRAVITY OF ONE CELL HAD DECREASED BY 0.013 (MORE THAN 0.01 ALLOWABLE) FROM THE PREVIOUS READING.

FOLLOWING AN OVERNIGHT EQUALIZE C HARGE. OPERABILITY WAS RESTORED AT 0925 ON 1/8/81 ALSO, A MALADJUSTMEN T IN THE FUEL DIL TANK LEVEL SulTCH WAS CORRECTED & OPERABILITY WAS REST ORED AT 0730 ON 1/7/81.

T.S. WILL BE REVISED RE UNITS 18 2 BATTERIES.

CRYSTAL RIVER-3 05000302 010981 AT 2245 DURING NORMAL OPERATION. CONTAINMENT ISOLATION VALVE CAV-1 WOULD CNTHMNT ISOLATION SYS + CONT 81-002/03L-0 020681 NOT CLOSE AFTER SAMPLING THE PRESSURIZER STEAM SPACE.

THIS EVENT WAS C VALVE OPERATORS 036029 30-DAY OMTRARY TO TECHNICAL SPECIFICATION 3.6.3.1.

THE AFFECTED PENETRATION WA ELECTRIC MOTOR - AC S ISOLATED BY USE OF MANUAL VALVES AND MAINTENANCE WAS INITIATED. THERE COMPONENT FAILURE WAS NO EFFECT UPON THE GENERAL PUBLIC HEALTH CR SAFETY.

THIS IS THE TH ELECTRICAL IRD OCCURRENCE FOR CAV-1 AND THE THIRTY-FIRST EVENT REPORTED UNDER THIS LIMITORQUE CORP.

SPECIFICATION.

CAUSE OF EVENT ATTRIBUTED TO FAILED CONTACTS IN THE TORQUE SWITCH OF THE VALVE OPERATOR. SWITCH WAS REPLACED AND A FUNCTIONAL TEST OF THE VALVE WAS PERFORMED. OPERABILITY WAS RESTORED AT 0600 ON 1/10/81.

NO FURTHE R CORRECTIVE ACTION DEEMED NECESSARY AT THIS TIME.

A REVIEW OF FAILURE OF THE CONTAINMENT ISOLATION VALVES IS CURRENTLY BEING CONDUCTED.

.. ~

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 27 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION CRYSTAL RIVER-3 05000302 011981 AT 0113 AFTER ROUTINE SAMPLING, POSITION INDICATION FOR CONTAINMENT ISOL.

CNTNMNT ISOLATION SYS + CONT 81-004/03L-0 021681 ATION VALVE CAV-2 WAS FOUND TO BE INOPERABLE CONTRARY TO TECH SPEC 3.6.3 INSTRUMENTATION + CONTROLS 036096 30-DAY 1 AT 0648 WHILE RETURNING CAV-126 TO SERVICE,.ITS POSITION INDICATION-INDICATOR WAS FOUND TO BE INOPERABLE CONTRARY TO T.S. 3.6.3.1 IN EACH CASE VALVE COMPONENT FAILURE WAS ISOLATED 8 MAINTENANCE PERFORMED. OPERABILITY RESTORED TO CAV-2 AT 0 OTHER 600 3 TO CAV-126 AT 1327. NO EFFECT DN HEALTH OR SAFETY. 6TH OCCURRENCE OTHER FOR CAV-2, 2ND FOR CAV-126, & 32ND REPORTED UNDER THIS TECH SPEC.

THE CAUSE OF THE FIRST OCCURRENCE IS UNKNOWN AT THIS TIME.

AN ENGINEERI NG EVALUATION OF CAV-2 OPERATING PROBLEMS IS IN PROGRESS.

THE SECOND OC CURRENCE WAS CAUSED BY A DEFECTIVE BREAKER IN THE MAIN POWER SUPPLY TO THE VALVE.

THE BREAKER WAS REPLACED 8 CAV-126 WAS FUNCTIONALLY TESTED S ATISFACTORILY.

CRYSTAL RIVER-3 05000302 012381 AT 1710 DURING NORMAL OPERATION IT WAS DISCOVERED THAT THE BREAKER FOR C CONT ROOM HABITBLTY SYS + CONT 81-006/03L-0 021981 ONTROL COMPLEX EMERGENCY VENTILATION FAN AHF-18A WAS OPEN.

THIS CREATED CIRCUIT CLOSERS / INTERRUPTERS 036156 30-DAY AN EVENT CONTRARY TO TECHNICAL SPECIFICATION 3.7 7.1.

THE BREAKER WAS CIRCUIT BREAKER SHUT AND OPERABILITY CHECKS WERE PERFORMED. OPERABILITY WAS RESTORED AT PERSONNEL ERROR 1804 THERE WAS NO EFFECT UPON THE HEALTH OR SAFETY OF THE GENERAL PUB OTHER LIC.

THIS IS THE FIRST OCCURRENCE FOR AHF-18A AND'THIS IS THE FIFTH EVE THOMPSON TANK 8 MFG. CO.

HT REPORTED UNDER THIS SPECIFICATION.

THE CAUSE OF THIS EVENT IS ATTRIBUTED TO INADVERTENT BUMPING OF THE BREA KER.

ALL PERSONNEL HAVE BEEN ADVISED TO EXERCISE EXTREME CAUTION WHILE WORKING AROUND ELECTRICAL BREAKERS.

CRYSTAL RIVER-3 05000302 012681 AT 1000 AFTER ROUTINE FILTER CHANGE, RADIATION MONITOR RM-A5 WOULD NOT R CONT ROOM HABITBLTY SYS + CONT 81-007/03L-0 022381 ESTART. THIS CREATED AN EVENT CONTRARY TO TECHNICAL SPECIFICATION 3.7.7.

CIRCUIT CLOSERS / INTERRUPTERS 036231 30-DAY 1.

CONTROL COMPLEX VENTILATION WAS PLACED IN EMERGENCY MODE FULL RECIRC OTHER AND MAINTENANCE WAS INITIATED. OPERABILITY WAS RESTORED AT 1400.

THER COMPONENT FAILURE E WAS NO EFFECT UPON THE HEALTH OR SAFETY OF THE GENERAL PUBLIC.

THIS W OTHER AS THE FIRST OCCURRENCE OF THIS TYPE, THE FOURTH OCCURRENCE FOR RM-A5 AN TRAPELO D THE SIXTH EVENT REPORTED UNDER THIS SPECIFICATION.

THE CAUSE OF THIS EVENT IS ATTRIBUTED TO A BLOWN FUSE.

NO FAULT WAS DIS COVERED IN THE CIRCUIT.

THE FUSE -WAS REPLACED AND OPERABILITY WAS RESTO RED.

NO FURTHER CORRECTIVE ACTION DEEMED NECESSARY AT THIS TIME.

CRYSTAL RIVER-3 05000302 012981 AT 1145 DURING PERFORMANCE OF SP-179. CONTAINMENT LEAKAGE TYPES "B"'t "C IT WAS DISCOVERED THAT CONTAINMENT ISOLATION VALVES AHV-1C 3 1D WERE CNTHMNT' ISOLATION SYS + CONT 81-003/01T-0 021281 VALVES 036095 2-WEEK IMOP. CONTRARY TO T/S 3.6.3.1 VALVES WERE CLOSED & AN INVESTIGATION OF BUTTERFLY EVENT WAS INITIATED, AT 1340 IT WAS DETERMINED THAT LEAK RATE WAS CONTRA DESIGN / FABRICATION ERROR RY TO T/S 3.6.1.2 & THAT T/S 3.0.3 APPLIED TO SITUATION. POWER REDUCTICH MANUFACTURING TOWARD HOT STANDBY WAS INIT. OPERABILITY WAS REST 0n!ED AT 1351 2 POWER R PRATT, HENRY CD.

EDUCTION WAS HALTED. THERE WAS NO EFFECT UPON PUBLIC HEALTH I SAFETY.

CAUSE OF EVENT IS ATTRIBUTED TO FAILURE OF VALVE TO SEAL AT LOW AMBIENT TEMP DURING PURGE. CONDITIONS. INVESTIGATION OF EVE 4T HAS INCLUDED SOME L IMITED TESTING TO CONFIRM: EFFECTS OF LOW AMBIENT TEiT ? nFVELOPMENT OF A MECHANISM TO PREVENT RECURR. FURTHER CONTAINMENT PURGE AB0ve MUDE a E" L BE RESTRICTED TO TESTING OF DESIGN CHANGES IMPL FOR PROBLEM RESOLUTICH

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY

' PACE 28 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION D. C.

C00K-1 05000315 011281 UNIT IN MODE 1 AT 100% POWER.

AT 1100 HOURS. ROUTINE SAMPLING OF BIT AN EMERG CORE COOLING SYS + CONT 81-001/03L-0 021381 D NORTH BAST REVEALED THE BORON CONCENTRATION IN BOTH TANKS WAS 19,300 P COMPONENT CODE NOT APPLICABLE 036184 30-DAY PM.

THIS IS BELOW THE 20,000 PPM LOWER CONCENTRATION PERMITTED BY TECH SUBCOMPONENT NOT APPLICABLE SPEC. 3.5.4.1B.

ACTION ITEM OF T.S.

FULFILLED. BIT AND MIDDLE BAST WE OTHER RE ABOVE 20,000 PPM AT 1326 HOURS.

THERE WAS NO EFFECT ON THE HEALTH AN NOT APPLICABLE D SAFETY OF THE PUBLIC. PREVIOUS OCCURRENCES80-236,.79-299,78-570.

ITEM NOT APPLICABLE THE EXACT CAUSE OF THE DILUTION HAS NOT BEEN DETERMINED. TO INCREASE TH E BIT BORON CONCENTRATION, THE BIT WAS LINED UP TO RECIRCULATE WITH THE MIDDLE BAST AND THE BIT AND MIDDLE BAST WERE BOTH DETERMINED TO BE >/: 2 0,000 PPM AT 1326 HOURS.

THE NORTH BAST WAS >/: 20,000 PPM AT 1740 HOUR 5.

INVESTIGATION IS CONTINUING.

D. C. C00K-2 05000316 120680 WHILE PULLING SHUTDOWN CONTROL RODS IN PREPARATION FOR GOING CRITICAL, R OTHR INST SYS REQD FOR SAFETY 80-035/03X-1 022081 OD POSITION INDICATION FOR ROD N-9 DID NOT RESPOND PROPERLY.

THE REACTO ELECTRICAL CONDUCTORS 033495 OTHER R TRIP BREAKERS WERE OPENED.

THIS EVENT WAS NON-CONSERVATIVE IN RESPECT SUBCOMPONENT NOT APPLICABLE TO TECHNICAL SPECIFICATION 3.1.3.3.

COMPONENT FAILURE ELECTRICAL OTHER THE PROBLEM WAS TRACED TO A CONNECTOR ON TOP OF THE ROD POSITION DETECTO R ASSEMBLY. A SPARE CABLE WAS SUBSTITUTED FOR THE ORIGINAL AND ROD POSI TION INDICATION FOR ROD N-9 WAS DECLARED OPERABLE. THE DEFECTIVE CONNEC TOR APPEARED TO HAVE BEEN STEPPED ON.

THE AREA ABOVE THE REACTOR HEAD I S A DIFFICULT AREA TO WORK IN.

D. C. C00K-2 05000316 010381 DURING NORMAL OPERATIONS, THE EAST MOTOR DRIVEN AUXILIARY FEED PUMP WAS FEEDWATER SYSTEMS + CONTROLS 81-002/03L-O 012881 REMOVED FROM. SERVICE TO REPAIR THE EMERGENCY LEAKOFF LINE CHECK VALVE FW V A L'J ES 036050 30-DAY

-153, AND INSTALL A SPOOL PIECE IN PLACE OF THE-SUCTION STRAINER PER AN CHECK EMERGENCY DESIGN CHANGE.

THIS CONSTITUTED AN INOPERABLE PUMP PER TECHNI COMPONENT FAILURE CAL SPECIFICATION 3.7.1.2.

THE WEST PUMP REMAINED IN SERVICE AND THE AC MECHANICAL TION REQUIREMENTS WERE MET.

PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.

DRESSER INDUST. VALVE & INST D CHECK VALVE FW-153 HAD SEAT LEAKAGE DURING A TEST OF THE WEST PUMP.

THA T ALLOWED OVERPRESSURIZATION OF THE SUCTION STRAINER OF EAST PUMP WHICH RESULTED IN A CRACK IN THE STRAINER CASING.

THE CHECK VALVE DISC, DRESS ER PART NO. 7484A26GN WAS REPLACED AND THE SEAT WAS LAPPED.

A SPOOL PIE CE WAS INSTALLED IN PLACE OF THE STRAINER.

D. C. C00K-2 05000316 010381 DURING NORMAL OPERATION, AN ANNUNCIATOR WAS RECEIVED WHICH INDICATED THE RESIDUAL HEAT REMOV SYS + CONT 81- 0 01/ 0 3 L- 0 012381 LOSS OF CONTROL VOLTAGE TO THE WEST RHR PUMP. THUS MAKING THE TR AIN OF CIRCUIT CLOSERS / INTERRUPTERS 036094 30-DAY RHR INOPERABLE WHICH IS CONTRARY TO TECH SPEC 3.5.2.

THE REDUNDANT TRAI CIRCUIT BREAKER H OF RHR WAS AVAILABLE AND OPERABLE. THERE WAS NO EFFECT ON THE PUBLIC COMPONENT FAILLRE HEALTH OR SAFETY.

THIS IS THE FIRST OCCURRENCE OF THIS NATURE AND THE T ELECTRICAL OTAL TINE OF PUMP INOPERASILITY WAS 1 HOUR AND 46 MINUTES.

ITE IMPERIAL CORPORATION THE CAUSE FOR THIS INCIDENT WAS DISCOVERED TO BE A LOOSE FUSE CLIP DN TH E MAIN CONTROL FUSES.

THE FUSE CLIP WAS PROPERLY ADJUSTED & THE BREAKER WAS CYCLED SEVERAL TIMES.

PUMP WAS PLACED ON MINI-FLOW FOR OPERABILITY-

. A STEP HAS BEEN ADDED TO MAINTENANCE INSPECTION PROCEDURE FOR 4KV CIR CUIT BREAKERS TO CHECK 4 ADJUST THESE FUSE CLIPS DURING EACH INSPECTION.

LER MONTHLY REPORT SORTED BY FACILITY PAGE 29 MAR 26, 1981 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION D.

C. C00K-2 0500D316 0'1281 DURING NORMAL OPERATION, SG BLOWDOWN STARTUP FLASH TANK WAS IN SERV TO R PRCSS + EFF RADIOL MONITOR SYS 81-001/04T-0 020281 EDUCE SECONDARY SYSTEM CHEMICAL CONTAMINATION FROM CONDENSER INLEAKAGE.

INSTRUMENTATION + CONTROLS 036049 2-WEEK ON 1/22/81 IT WAS DETERMINED THAT ON 1/12/81 AT ~ 2200 THERE HAD BEEN NO FLOW THROUGH RAD MON. R-19 FROM #21 SG. NONCONSERVATIVE IN RESPECT TO A OTHER PPENDIX "B" T/S 2.4.2.C. UNIT IS EXPERIENCING A SMALL PRIMARY TO SECONDA COMPONENT FAILURE RY LEAK. BLOUDOWN WAS STOPPED ON 1/13/81, AT 0318 1 0334 BLOWDOWN WAS AG OTHER BROOKS INSTRUMENT COMPANY AIN EST. THROUGH NORMAL BLOWDOWN TANK WHERE ADD'l EFFL' RAD MON. POSSIBLE THE LOSS OF FLOW TO R-19 FR0rt #21 STEAM GENERATOR WAS APPARENTLY DUE TO.

A BA0 DIAPHRAGM IN THE ROTO-METER'S FLOW REGULATOR. MANUFACTURED BY BRO OKS INSTRUMENT COMPANY-MODEL NUMBER 1358CC2CICAA.

DAVIS-BESSE-1 05000346 120580 (NP-33-80-115) DN 12/5/80 AT 1730 HRS. DURING SURVEILLANCE TESTING, SETP ENGN'RD SAFETY FEATR INSTR SYS 80-090/03X-1 021381 OINT FOR BORATED WATER STORAGE TANK LOW LEVEL BISTABLE BA312 WAS FOUND 0-INSTRUMENTATION + CONTROLS 033401 OTHER UT OF TOLERANCE (00T). ON 12/6/80 AT 0750 HRS DURING TESTING, SETPOINT F OR CONT AINMENT PRESSURE BIST ABLE B A309 MAS ALSO FOUND 00T. BOTH OCCURREN SWITCH CES PLACED UNIT IN ACTION STATEMENT 9 0F TECH. SPEC.

3.3.2.1, NO DANGER COMPONENT FAILURE TO HEALTH / SAFETY OF PUBLIC OR STATION PERSONNEL. REMAINING 3 SFAS CHANN INSTRUMENT ELS WERE OPERABLE. SEE LERS 78-39, 78-70,78-119, 79-21 8 79-45.

CONSOLIDATED CONTROLS CORP.

CAUSE OF THESE OCCURRENCES CAN BE ATTRIBUTED TO A CCMPONENT FAILURE. BIS TABLES ARE SUBJECT TO INSTRU DRIFT. UPON FINDING BA312 3 BA309 OUT OF CA LIBRATION, THEY WERE IMMEDIATELY RECALIB. AS PER' TEST (ST 5031.01) PROCE DURE TO WITHIH TECH SPEC LIMIT. VOLTAGE BETWEEN COMMON 1 GROUND WILL BE CHECKED ON A MONTHLY BASIS TO ENSURE AC VOLTAGE DOES NOT GO UNDETECTED.

i DAVIS-BESSE-1 05000346 010681 (NP-33-81-02) OH-1/6/81 AT 1600 HRS. A CONTROL ROOM OPERATOR INTENDING T AC ONSITE POWER SYS + CONTROLS 81-003/03L-0 020381 0 MATCH A SWITCH FLAG POSITION WITH BREAKER INDICATION LIGHT, INADVERTEN CIRCUIT CLOSERS / INTERRUPTERS 036030 30-DAY TLY TRIPPED BREAKER HX02B WHICH DE-ENERGIZED VITAL BUS B, 1 0F 2 13.8 KV SWITCH (OTHER THAN SENSOR)

BUSSES. THIS REDUCED ELEC DISTRIBUTION TO LESS THAN THAT REQ BY T.S.

3-

.8.1.1, 3.8.2.1 2 3.8.2.3, THERE WAS HD DANGER TO THE HEALTH & SAFETY 0 PERSONNEL ERROR F THE PUBLIC OR TO STATION PERSONNEE.

THE BREAKERS WERE ALL RESTORED WI LICENSED 8 SENIOR OPERATORS THIN 15 MINUTES.

THIS IS THE FIRST REPORT OF THIS TYPE PERSONNEL ERROR.

ITEM NOT APPLICABLE CAUSE WAS PERSONNEL ERROR BY OPERATOR. IN ATTEM* TING TO MATCH SWITCH FL AG COLOR WITH BREAKER. INDICATION, HE ACCIDENTALLY TURNED SUITCH THE WRON G DIRECTION EVEN THOUGH HE WAS AWARE OF ITS FUNCTION. RESTORATION OF BR EAKERS WAS ATTAINED WITHIN 15 MIN.

OPERATIONS PERSONNEL BEING MADE'AWAR E OF OCCURRENCE TO EMPHASIZE NEED FOR ATTENTIVENESS DURING OPERATIONS.

DAVIS-BESSE-1 05000346 010781 (NP-33-81-03) OH 1/7/81 AT 1632 HOURS, A CONTROL ROOM OPERATOR ATTEMPTED EMERG CORE COOLING SYS + CONT 81-004/03L-O 020681 TO START DECAY HEAT (DH) PUMP 1-1 AS A NORMAL STEP IN ESTABLISHING DH R CIRCUIT CLOSERS / INTERRUPTERS 036031 30-DAY EMOVAL FLOW FOLLOWING ENTRY INTO MODE 4.

A SECOND ATTEMPT WAS SUCCESSFUL AFTER BREAKER WAS RACKED OUT AND THEN RACKED BACK IN. BEING IN MODE 4, CIRCUIT BREAKER-STATION DID NOT ENTER ACTION STATEMENT OF TECH. SPEC.

3.5.3.

THIS EVENT COMPONENT FAILURE IS BEING REPORTED TO DOCUMENT A COMPONENT FAILURE. THERE WAS NO DANGER ELECTRICAL TO HEALTH & SAFETY OF PUBLIC OR STATION PERSONNEL. (1 PREV. LER 78-011.)

WESTINGHOUSE ELECTRIC CORP.

CAUSE OF PUMP FAILING TO START CAN BE ATTRIBUTED TO A BREAKER PROBLEM. E LECTRICIANS RACKED OUT EREAKER. FINDING NO OBVIOUS PROBLEM, BREAKER WAS RACKED IN. A SECOND ATTEMPT TO START PUMP WAS THEN SUCCESSFUL. PUMP WAS DECLARED OPERABLE AT 1647 HRS THE SAME DAY & PLACED IN SERVICE. FURTHER INVESTIGATION UNDER MWO 31-1301 ON 1/13/81 DID HOT LOCATE SOURCE OF PROB

- ~. - -

MAR 26, 1911 LER MONTHLY REPORT SORTED BY FACILTTY PAGE 30 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTIC'1 i

DAVIS-BESSE-1 05000346 011481 (NP-33-81-04) ON 1/14/81. REACTOR COOLANT SYS (RCS) CHLORIDE CONCENTRATI REACTOR VESSEL INTERNALS 81-005/03L-0 021381 DN WAS FOUND IN EXCESS OF STEADY STATE LIMIT OF 0.15 PPM.

LEVEL WAS 0.6 COMPONENT CODE NOT APPLICABLE 036098 30-DAY 4 PPM.

ON 1/ 18/8 1 LEVEL REACHED 1.28 PPM.

LIMIT WAS EXCEEDED FOR TWO D SUBCOMPONENT NOT APPLICABLE AYS EACH TIME.

ITS CAUSE WAS DETERM TO BE FROM USE OF SPOTCHECK IN CLEA DEFECTIVE PROCEDURES HING REACTOR COOLANT PUMP (RCP) SEAL CAVITIES.

TO FURTHER CLEAN SYS REQ NOT APPLICABLE UIRED SOME HEATING TO DECOMPOSE SOLVENT SO THAT CHLORIDES COULD 6E REMOV ITEM NOT APPLICABLE ED BY DEMINERALIZATION. LIMITS EXCEEDED AGAIN ON 1/26/81 AND 1/27/81.

CAUSE WAS A LACK OF ADEQUATE WARNING TO ANDICATE DETRIMENTAL EFFECTS TO SYS IF USED IMPROPERLY.

"SPOTCHECK" IS LABELED AS NUCLEAR GRADE & CHLOR IDE FREE.

IT IS IN FACT A CHLORINATED HYDROCARBON WHICH WHEN HEATED DEC OMPOSES TO CHLORIDES. ADMIN MEMO NO. 4 WAS ISSUED TO PROV SPECIFIC INSTR UC FOR USE OF ANY SOLVENT THAT COULD COME IN CONTACT WITH REACT COOL SYS DAVIS-BESSE-1 05000346 011981 (NP-33-81-05) ON 1/19/81. AT 1550 HRS DURIGG PERFORMANCE OF SAFETY FEATU ENGNRD SAFETY FEATR INSTR SYS 81-006/03L-0 021381 RES ACTUATION SYS (SFAS) GROUNDING TEST, TP 520.02, POWER WAS LOST TO SF COMPONENT CODE NOT APPLICABLE 036099 30-DAY AS CHANNEL 1 CABINET. THIS MADE SFAS CHANNEL 1 CONTAINMENT RADIATION ING SUBCOMPONENT NOT APPLICABLE PERABLE. UN :T ENTERED ACTION STATEMENT 9 0F TECH. SPEC. 3.3.2.1 WHICH WA DEFECTIVE PROCEDURES S SATISFIED SINCE CONTAINMENT BISTABLE TRIPPED UPON LOSS OF POWER. THERE NOT APPLICABLE WAS NO DANGER TO HEALTH 3 SAFETY OF FUBLIC GR STATION PERSONNEL. REMAIN ITEM NOT APPLICABLE ING THREE CHANNELS WERE OPERABLE DURING THIS TIME.

CAUSE WAS LACK OF PROPER WARNING IN PROCEDURE TP 520.02 8 VENDOR'S TEST OUTLINE. INSTRU 8 CONTROLS PERSONNEL WERE INSTALLING A JUMPER BETWEEN TE RMINAL 12 0F TB121 8 INSTRU GROUND. IN ATTEMPT, AN ARC OCCURRED, 8 SUPPL Y FUSE FROM PANEL Y-1 BLE

W. PROCEDURE

DID NOT CONT AIN A WARNING THAT TER MINAL 12 WAS 118 VAC SUPPLY TO SFAS CAB. MOD T-5361 WRITTEN TO PROCEDURE DAVIS-BESSE-1 05000346 012281 (NP-33-81-06) ON 1/22/81, AT 0850 HRS. STATION PERSONNEL REPORTED THAT D OTHER ENGNRD SAFETY FEATR SYS 81-007/03L-O 022081 00R 306 (FUEL HANDLING AREA, ELEVATION 585) WAS PARTIALLY OPEN.

WITH DO OTHER COMPONENTS 036159 30-DAY OR OPEN, SPENT FUEL POOL EMERG VENTILATION SYS WOULD NOT HAVE BEEN ABLE SUBCOMPONENT NOT APPLICA6LE TO MAINTAIN SPENT FUEL POOL AREA AT A NEG PRESS OF >/= 1/8" WATER' GAUGE.

COMPONENT FAILURE ACTION STATEMENT OF T/S 3.9.1.2 PROHIBITS FUEL HANDLING OPER & MOVEMENT MECHANICAL S OF LOADS OVER POOL WITHOUT AN OPER SYS.

THESE RESTRICTIONS WERE N3T V OTHER IOLATED.

NO. DANGER TO HEALTH / SAFETY OF PUBLIC OR STATION PERSONNEL.

THE DOOR WAS IMMEDIATELY CLOSED AND LATCHED.

THE CAUSE OF 1HE FINDING W AS A DOOR CLOSURE WHICH NEEDED ADJUSTMENT. IT WAS NOT CLOSING HARD ENOU GH TO LATCH THE DOOR.

MAINTENANCE WORK ORDER 81-1187-009 WAS ISSUED THE SAME DAY TO CHECK AND ADJUST THE CLOSURE.

DAVIS-BESSE-1 05000346 012781 (HP-33-81-08) 1/27/81, a 2222 HRS, 345 KV SWITCHYARD BUS K TRIPPED 8 LOC OFFSITE POWER SYSTEMS + CONTRL 81- 0 0 8/ 3 3 L-0 022681 KED OUT, DE-ENERGIZING STARTUP TRANSFORMER 02. PLANT WAS IN MODE 5.

IT TRANSFORMERS 036157 30-DAY WAS RETURNED TO SERVICE 1/28/81. ON 2/1/81, 3 0620 HRS, A SIMILAR INSTAN SUBCOMPONENT NOT APFLICABLE CE OCC IN WHICH J BUS TRIPPED 8 LOCKED OUT DE-ENERGIZING STARTUP TRANSFO EXTERNAL CAUSE RMER 01 STATION WAS IN MODE 3.

STATION ENTERED ACTION STATEMENT OF T/

~,

NOT APPLICABLE S 3.8.1.1 AT 2ND OCC.

NO DANGER TO PUBLIC OR STATION _PERS.

IN BOTH CAS OTHER ES, AN AUTOMATIC TRANSFER OF LOADS TO OPERABLE STARTUP TRANSFORMER OCC.

"K" BUS TRIP OCCURRED DUE TO ACTION FROM DIRECTIONAL GROUND CURRENT RELA Y8 THAT C PHASE LIGHTNING ARRESTER ON STARTUP TRANS. (SU XFMR) 02 APPEA RED CHARRED. B PHASE LIGHTNING ARRESTER ON SU XFMR Of HAD FAULTED.

UNDE R MMO 81-1400 SU XFMR 02 WAS RETURNED TO SERVICE AT 2331 HRS ON 1/28/81.

UNDER MWO 81-1426, SU XFMR 01 WAS RETURNED TO NORMAL a 1920 HRS 2/1/81

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 31 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION DAVIS-BESSE-1 0S00'346 012881 (NP-33-81-07) ON 1/28/81 AT 0330 HRS. DURING PERFORMANCE OF DIESEL-GENE EMERG GENERATOR SYS + CONTROLS 81-0 0' / 43L-0 022781 RATOR MONTHLY TEST ST 5081.01 D/G 1-2 COULD NOT BE STARTED WITH LEFT SI MOTORS 03t158 30-DAY DE SET OF AIR START MOTORS.

IT WOULD START WITH RIGHT SIDE MOTORS.

STA SUECOMPONENT NOT APPLICABLE TION WAS IN MODE 5.

8 REQUIREf1ENTS OF TECH. SPEC. 3.8.1.2 WERE BEING MET COMPONENT FAILURE

. THERE WAS NO 3 ANGER TO THE HEALTH 8 SAFETY OF THE PUBLIC OR STATION P MECHANICAL ERSONNEL.

D/G 1-1 AND 1-2 WERE OPERABLE DURING THIS TIME.

THIS EVENT I INGERSOLL-RAND CD S BEING REPORTED TO DOCUt ENT A COT 1P0HENT FAILURE.

CAUSE OF OCCURRENCE WAS FAILURE OF ONE AIR STt.RT MOTOR.

AIR START MOTOR HAD A BROKEN SDLENDID DRIVE SHAFT.

BREAK IS CONSIDERED A RANDOM FAILUR E.

UNDER T1AINT EN ANCE WORK ORDER 81-1406. AIR START MOTOR WAS REPLACED.

EMERGENCY DIESEL GENERATOR 1-2 WAS SUCCESSFULLY TESTED UNDER ST 5081.01 AND LECLARED OPERABLE AT 1415 HOURS ON JANUARY 18. 1981 DRESDEN-1 0S000010 121080 DURING UNIT OUTAGE WHILE PROCESSING WATER INTO HOLD-UP TANK. OPERATORS C LIQ RADICACT WSTE MANAGMNT 5YS 81-001/03L-0 020981 HECKED 1ANK LEVELS AT EACN ADDITION. BUT DID NOT SAMPLE TANK UNTIL IT WA OTHER COMPONENTS 036100 30-DAY S 95% FULL.

A PERIOD OF 131 HOURS HAD ELAPSED WITHOUT SAMPLING. WHICH E SUBCOMPONENT NOT APPLICABLE XCEEDED TECH. SPEC.

4.8.D.

THAT REQUIRES SAMPLING EVERY 72 HRS. UNLESS N PERSONNEL ERROR 0 TANK AD?ITIONS HAVE BEEN MADE SINCE LAST SAMPLE.

NO EFFECT ON HEALTH NONLIC. OPERATIONS PER$0NNEL OR SAFETY OF PUDLIC SINCE NO TANK RELEASE OCCURRED. SIMILAR EVENT 0CCUR ITEM NOT APPLICABLE RED AS REPORTED DY R.O.

880-04. DOCKET 050-010.

CAUSE DUE TO FAILURE OF PERSONNEL TO FOLLOW PROCEDURE GOVERNING SAMPLING OF RADWASTE STORAGE TANKS.

PERSONNEL REIN $TRUCTED ON HEED FOR CAREFUL EXAMINATION OF CONDITIONS AND FREQUENCY FOR SAMPLING OF SUBJECT TANKS.

SIGNS HAVE BEEN POSTED IN THE AREA 0F TANKS TO REf11ND PERSONNEL OF SAMPL ING REQUIREMENT. NO FURTHER CORRECTIVE ACTION DEET 1ED NECESSARY.

DRESDEN-2 05000237 121980 DURING NORTIAL UNIT OPER ATION. WHILE CONDUCTING ROUTINE OPERATOR ROUNDS.

ENGNRD SAFETY FEATR INSTR S'S 80-048/03L-0 011481 THE ISOLATION VALVE TO PRESSURE SWITCH PS-1628B. USED IN THE AUTOMATIC B VALVES 033667 30-DAY LOWDOWN SYSTEM. WAS FOUND CLOSED. MINIMAL EFFECT ON PUBLIC HEALTH AND 5 GATE AFETY BECAUSE THE REM 41HING SWITCHES WERE AVAILABLE TO PERFORT1 THEIR INT-PERSONNEL ERROR ENDED SAFETY FUNCTION.

SIMILAR OCCURRENCEI R.0, 880-026/03L-0.

MAINTENANCE 8 REPAIR. PERSONNEL STATIC-0-RING REASON FUR VALVE BEING CLOSED IS UNKNOWN. BUT CAN BE ATTRIBUTED TO PERs0 NNEL ERROR.

IM:1EDIATE CORRECTIVE ACTION WAS.TC OPEN THE VALVE.

INSrRUM ENT MECHANIC SURVEILLANCE INDICATES VALVE WAS OPENED AFTER COMPLETION OF TESTS.

DRESDEN-2 0S000237 122980 UNIT 2 WAS AT STEADY POWER OPERATION. AND DTS 1600-2 " SECONDARY CONTAINM CNTHMNT ISOLATION SYS + CONT 80-049/03L-0 012281 ENT LEAK RATE TEST" HAD BEEN PERFORMED.

AT THE COMPLETION OF THE TEST.

VALVE OPERATORS 033711 30-DAY THE REACTOR BUILDING VENTILATION ISOLATION VALVE 2A-5742 UOULD NOT DPEN, PHEUMATIC/ DIAPHRAGM / CYLINDER THERE WAS NO HAZARD TO PUBLIC BECAUSE STANDBY GAS TREATMENT SYSTEM WAS COMPONENT FAILURE RUNNING AND THE OTHER THREE ISOLATION VALVES HERE OPERABLE. THERE HAS B INSTRUMENT EEN NO PREVIOUS REPORT OF AN EVENT.0F THIS TYPE.

UT. YANKEE NUCLEAR POWER CORP.

THE FOUR WAY DIRECTIONAL CONTROL SOLENOID VALVE IN VALVE A0-2A-5742 OPER-ATOR STUCK IN THE " CLOSED" POSITION DUE.TO ACCUMULATION OF DIRT-IN THE V ALVE INTERN ALS.

THE SOLEHOID VALVE AND COIL WERE REPLACED AND A0-2A-574 2 WAS TESTED FOR PROPER OPERATION PRIOR TO RETURNING TO SERVICE. NO FUR THER CORRECTIVE ACTION REQUIRED.

't 5

i MAR 26, 1981

- LER MONTHLY REPORT SORTED BY FACILITY PAGE 32 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS'

. FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT TATE /

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION i

DRESDEN-2 05000237-123180 DURING NORMAL OPERATION, WHILE PERFORMING DRYME8.L HI PRESSURE CONTAINMEN.

ENERG CORE COOLING SYS + CONT 80-050/03L-0 012681 Y SPRAY INTERLOCK SURVEILLANCE. THE 1501-62D PRESSURE SWITCH ACTUATED AT INSTRUMENTATION + CONTROLS 033712 30-DAY 44.2 INCHES OF WATER PRESSURE. TECHNICAL SPECIFICATION LIMIT IS LESS T SWITCH HAN OR EQUAL TO 41.6 INCHES OF WATER INCREASING. THE HEALTM AND SAFETY COMPONENT FAILURE OF THE GENERAL.PUBLIC WAS NOT AFFECTED, SINCE REDUNDANT INSTRUMENTATION MECHANICAL WAS AVAILABLF. THIS IS THE FIRST OCCURRENCE OF THIS TYPE.

ITEM NOT APPLICABLE _

THE CAUSE WAS MISALIGNMENT OF THE ACTUATING ARM AND MICROSWITCH ADJUSTIN G SCREu BEING SET TOO HIGH.

THE ACTUATING BAR WAS REALIGNED AND THE MIC ROSWITCH ADJUSTED. THE PRESSU?.E OWITCH WILL CONTINUE TO BE CHECKED PER THE SURVEILLANCE SCHEDULE.

DRESDEN.

05000237 010481-DURING A REACTOR SCRAM, REQUIRED BY~I.E.-BULLETIN 80-17, SUPP. 4 FAILED.

UTHR INST SYS REQD FOR SAFETY 81-001/03L-0.012881 TO RECEIVE CRD VOLUME HI-HI LEVEL AL ARM OH 3 0F THE 4 CHANNELS. THE SA INSTRUMENTATION + CONTROLS 036032-

.30-DAY FETY SIGNIFICANCE OF THIS EVENT WAS MINIMAL SINCE IT DID NOT AFFECT THE-SENSOR / DETECTOR / ELEMENT SCRAM FUNCTION, THE CONTROL ROOM AL ARM CAME UP, AND THE SCRAM DISCHARGE DESIGN / FABRICATION ERROR INSTRUMENT VOLUME LEVEL SWITCHES WERE OPERABLE. PUBLIC HEALTH AND SAFET l'

CONSTRUCTION / INSTALLATION Y WERE. HOT"AFFECTED.

PREVIOUS OCCURRENCE DOCKET 50-237, 80-46/03L.

1 NORTEC THE CAUSE IS ATTRIBUTED TO TRANSDUCER PL ACEMENT AND MOUNTING, AND NOISE DUE TO HIGH GAIN.

THE SCRAM DISCHARGE VOLUME WILL BE HYDROLIZED. TRANSD i

UCERS MOVED AND BETTER MOUNTING BRACKETS INSTALLED PRIOR TO STARTUP.-

DRESDEN-2 05000237 010581 DURING UNIT 2 REFUELING OUTAGE, LPCI TEST SPRAY VALVE FAILED TO SHUT ELE ENERG CORE COOLING SYS + CONT 81-002/03L-0 012981 CTRICALLY. CNE SET OF THERMAL CONTACTS !!OULD NOT-RESET.

THE SAFETY SIG f

~ VALVE OPERATORS 036192 30-DAY NIFICANCE WAS MINIMAL SINCE THE VALVE COULD BE MANUALLY SHUT AND THE REA_

ELECTRIC MOTOR - AC CTOR WAS IN COLD SHUTDOWN. THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFE

-COMPONENT FAILURE TY. - THIS IS THE FIRST OCCURRENCE OF THIS TYPE FOR THIS VALVE.

ELECTRICAL LIMIl0RQUE CORP.

'THE CAUSE-OF FAILURF. WAS STUCK AUXILIARY-CONTACTS. THE AUXILIARY CONTAC TS WERE REPLACED AND VALVE OPERATID PROPERLY. MOTOR CONTACTOR BREAKER C.

OMPARTMENTS WILL CONTINUE TO BE CHECKED DURING OUTAGES PER ESTABLISHED P ROCEDURES.

DRESDEN-2 05000237 011781 DURING LOCAL LEAK ' RATE TESTING OF' CONTAINMENT VENT LINE, THE. MEASURED LE CNTNMNT ISOLATION SYS + CONT 81-005/03L-0 012981 AKAGE WAS 1715.55 SCFH WHICH EXCEEDS TECH. SPEC. 4.7.A FOR SINGLE ISOLAT VALVES 036101 30-DAY ION (29.38 SCFH).

INVESTIGATION SHOWED LEAKAGE THROUGH A0-2-1601-23.

N BUTTERFLY O LEAKAGE WAS DETECTED THROUGH ANY OTHER VALVE. -THE SAFETY SIGNIFICANCE COMPONENT FAILHRE WAS MINIMAL SINCE ALL LEAKAGE WAS CONTAINED IN THE VENT LINE.

SIMILAR NATURAL END OF LIFE EVENTS:

50-249/80-07.

HEALTH AND SAFETY OF THE PUBLIC WAS NOT.AFFECTED PRATT, HENRY CD.

VALVE A0-2-1601-23 WILL BE REPAIRED BEFORE START-UP OF THE UNIT.

A SUPP LEMENTAL REPORT WILL BE SENT AFTER INVESTIGATION OF THE VALVE FAILURE M0 DE HAS BEEN COMPLETED.

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MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 33 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION DRESDEN-2 05000237 012381 DURING UNIT 2 REFUELING OUTAGE, LLRT PERFORMED ON THE FEEDWATER CHECK VA FEEDWATER SYSTEMS + CONTROLS 81-006/01T-0 020581 LVES MEASURED THROUGH LEAKAGE IN EXCESS OF THAT ALLOWED BY TECH. SPEC. 4 VALVES 036193 2-MEEK

.7.A FOR: (1) A SINGLE PENETRATION (29.38 SCFH), (2) TOTAL PENETRATION A CHECK ND ISOL ATION VALVE LEAKAGE (176.29 SCFH) AND (3) TOTAL CONTAINMENT LEAKA COMPONENT FAILURE GE (783 SOFH).

THIS WAS OF MINIMAL SAFETY SIGNIFICANCE SINCE THE FEEDWA MECHANICAL TER LINE IS CAPABLE OF BEING ISOLATED BY A MOTOR OPERATED VALVE UPSTREAM CRANE COMPANY OF THE CHECK VALVES.

SIMILAR EVENT:

50-237/30-06.

THE FEEDWATER CHECK VALVES HAVE NOT BEEN REPAIRED AS OF THIS DATE.

A SU PPLEMENTAL REPORT WILL BE SENT WHEN ALL REPAIRS AND CORRECTIVE ACTIONS H AVE BEEN COMPLETED.

DRESDEN-3 05000249 121980 DURING NORMAL OPERATION, WHILE PERFORMING LPCI VALVE OPERABILITY SURVEIL EMERG CORE COOLING SYS + CONT 80-045/03L-0 011381 LANCE, THE DRYt' ELL SPR AY HEADER OUTBCERD ISOL ATION VALVE WOULD NOT CLOSE VALVE OPERATORS 033668 30-DAY FROM THE CONTROL ROOM.

THE HEALTH AND SAFETY OF'THE GENERAL PUBLIC WAS ELECTRIC MOTOR - AC NOT ENDANGERED BECAUSE THE INBOARD ISOLATION VALVE WAS OPERABLE AND MAI COMPONENT FAILURE NTAINED CLOSED UNTIL THE OUTBOARD VALVE WAS S*UT.

THIS IS THE FIRST OCC ELECTRICAL URRENCE OF THIS TYPE FOR THIS VAltf.

GENERAL ELECTRIC CO.

SUSPECTED CAUSE OF FAILURE WAS A STUCK PLUNGER ON CLOSING COIL OF VLV MO TOR BREAKER.

PLUNGER WAS FREED BY MOVING CLOSING COIL BY HAND.

VLV WAS CYCLED SEVERAL TIMES WHILE MONITORING COIL.

NO PROBLEMS WERE NOTED.

I N ADDITION, SINCE FAILURE TO OPER, VLV HAS BEEN CYCLED GN THREE DIFFEREN T OCCASIONS AS PART OF REQ'D SURV.

NO FURTHER ACTION DEEMED NECESSARY.

DRESDEN-3 05000249 122380 DURING UNIT SHUTDOWN, WHILE TESTING GROUP 2 AND 3 ISOLATION CIRCUITRY. S RESIDUAL HEAT REMOV SYS + CONT 80-048/03L-0 012081 HUTDOWN COOLING SYSTEM INBOARD ISOLATION VALVE DID NOT CLOSE.

VALVE CLO CIRCUIT CLOSERS / INTERRUPTERS 033713 30-DAY SED AFTER RESETTING THERMAL OVERLOADS AND ADJUSTING BREAKER D002 INTERLD CONTACTOR CK.

THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WAS NOT ENDANGERED SINC COMPONENT FAILURE E PRIMARY CONTAINMENT INTEGRITY WAS NOT REQUIRED AND ALL OTHER SHUTDOMM ELECTRICAL COOLING SYSTEM ISOLATION VALVES FUNCTIONED AS DESIGNED. THIS IS THE FIR GENERAL ELECTRIC CO.

ST OCCURRENCE OF THIS TYPE FOR THE VALVE.

THE THERMAL OVERLOADS WERE RESET AND BREAKER DOOR INTERLOCK WAS ADJUSTED

. VALVE WAS TAKEN OUT OF SERVICE IN THE CLOSED POSITION.

INVESTIGATION IS CONTINUING ON THE EXACT CAUSE OF FAILURE.

DRESDEN-3 35000249 122580 DURING NORMAL GNIT OPERATION, AIR WAS DISCOVERED BLOWING FROM AIR START EMERG GENERATOR SYS + CONTROLS 80-049/03L-0 011981 REGULATOR VALVE FOR THE UNIT 3 DIESEL GENERATOR. DIESEL GENERATOR WAS D VALVES 033714 30-DAY ECLARED IHOPERABLE, AND ALL REQUIRED SURVEILLANCES PERFORMED.

EVENT OF DIAPHRAGM MINIMAL SAFETY SIGNIFICANCE SINCE THE 2/3 DIESEL GENERATOR WAS CAPABLE O COMPONENT FAILURE F PROVIDING EMERGENCY POWER.

FIRST EVENT OF THIS TYPE AT DRESDEN STATIO MECHANICAL N.

PARKERSBURG RIG & REEL THE CAUSE WAS A BAD SEAL IN THE AIR START REGULATOR VALVE.

THE REGULATO R VALVE WAS REPLACED, AND THE UNIT 3 DIESEL GENERATOR WAS DEMONSTRATED T 0 BE OPERABLE. NO FURTHER ACTION DEEMED NECESSARY.

-.m

+ - "

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 34 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/

DOCKET NO./

EVENT DATE/

COMPONENT SUSCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE EUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION DRESDEN-3 05000249 010281 DURING STEADY STATE OPERATION ON 2 JAN 81, IT WAS DETERMINED THAT A SURV SYSTEM CODE NOT APPLICABLE 81-004/03L-0 012881 EILL ANCE TH AT WAS TO BE PERFORMED NO L ATER THAN 1 JAN. 81 WAS NOT PERF0 INSTRUMENTATIch + CONTROLS 036052 30-DAY MED.

THE PROCEDU2E (DIS 500-8, EHC LOW OIL PRESSURE SCRAM) IS REQUIRED OTHER TO BE PERFORMED BY TABLE 4.1.1 OF THE TECHNICAL SPECIFICATIONS AND THE F PERSONNEL ERROR REQUENCY INTERVAL EXCEEDED THAT DEFINED IN TECH. SPECS.

THERE WAS NO EF MAINTENANCE

  • REPAIR PERSONNEL FECT ON THE PUBLIC HEALTH OR SAFETY.

SIMILAR OCCURRENCE; R.O.

879-049/0 ITEM NOT APPLICA5tE 3L-0.

THE CAUSE WAS DUE TO PERSONNEL ERROR BY FAILING TO ACCOUMT FOR THE NEW Y EARS DAY HOLIDAY WHEN SCHEDULING SURVEILLANCES. THE SURVEILLANCE WAS PE RFORMED ON THE DAY OF DISCOVERY. THE CAUSE OF THE OCCURRENCE WAS REVIEW ED WITH ALL PERSONMEL INVOLVED. NO FURTHER CORRECTIVE ACTION NECESSARY.

DRESDEN-3 05000249 011381 DURING HORMAL OPERATION WITH REACTOR LEVEL INSTRUMENT SURVEILLANCE IN PR CNTHMNT ISOLATION SYS + CONT 81-002/03L-0 012881 OGRESS, LEVEL SWITCM LIS 3-263-58A TRIPPED AT LESS THAN THE TECHNICAL SP INSTRUMEhTATION + CONTROLS 036051 30-DAY ECIFICATION lit 1IT (TABLE 3.2.1) 0F 84 INCHES. THE SAFETY SIGNIFICANCE O SWITCH F THIS EVENT WAS MINIMAL SINCE THE REMAINING THREE INSTRUMENTS WERE OPER COMPONENT FAILURE ABLE.

THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY.

PREVIOUS DCCURRE INSTRUMENT NCES:

R.O.

76-57/03L, DOCKET 50-237; 77-51/03L. 80-23/0LL AND 80-24/03L YARWAY CORP.

DOCKET 50-249.

THE CAUSE IS ATTRIBUTED TO SETPOINT DRIFT.

THE INSTRUMENT WAS IMMEDIATE LY ADJUSTED AND TESTED, WITH SATISFACTORY RESULTS. SUBSEQUENT TESTS WER E PERFORMED, AND EACH TIME THE RESULTS WERE SATISFACTORY. DIS 500-2 WIL L CONTINUE TO BE DONE MONTHLY.

DUANE ARNOLD 05000331 071280 FOLLOWING A PLANT SHUTDOWN THE RCIC SYSTEM WAS BEING USED TO CONTROL REA SAFETY RELATED DISPLAY INSTR 80-029/01X-1 020581 CTOR PRESSURE.

DUE TO OPERATION OF THE RCIC SYSTEM SUPPRESSIDH CHAMBER COMPONEMT CODE NOT APPLICABLE 033748 OTHER WATER LEVEL BEGAN INCREASING AND OPERATIONS PERSONNEL INDICATED AC' ION T SUBCOMPONENT NOT APPLICABLE O LOWER THE WATER LEVEL.

DURING THE WATER' LEVEL REDUCTION, THE SUPPRESS OTHER ION CHAMBER LOW WATER LEVEL ALARM DID HOT ANNUNCIATE AND THE WATER VOLUM NOT APPLICABLE E WAS INADVERTENTLY REDUCED TO 57,000 CUBIC FEET.

THE TECH. SPEC. 3.7.A ITEM NOT APPLICABLE 1 NINIMUM VOLUME IS 58,000 CUBIC FEET.

NO PREVIOUS OCCURRENCES.

HUMAN ENGINEERING DESIGN DEFICIENCY WITH A CONTRIBUTING CAUSE OF INSTRUM ENT FAILURE.

THE MINIMUM REQUIRED WATER VOLUME WAS RESTORED APPROXIMATE LY 14 MINUTES AFTER DISCOVERY OF LOW WATER CONDITION. ALARM CONNECTIONS RESOLDERED 8 TESTED SATISFACTORILY. REDUNDANT TORUS WATER LEVEL INDICA TIONS TO BE INSTALLED ON FRONT PANEL TO IMPROVE MONITORING CAPABILITY.

DUANE ARNOLD 05000331 121580 DURING NORMAL OPERATION IT WAS DISCOVERED THAT SURVEILLANCE TESTING REQU RESIDUAL HEAT REMOV SYS + CONT 80-066/03L-0 011481 IRED BY TECH. SPEC. 3.5.G.1 WHEN ONE STANDBY DIESEL GENERATOR IS INOPERA ENGINES, INTERNAL COMBUSTION 033670 30-DAY BLE WAS NOT PROPERLY COMPLETED. FOLLOU7NG REMOVAL OF 1G-21 DIESEL FROM SUBCOMPONENT NOT APPLICABLE SERVICE FOR MAINTENANCE. THE "B" CORE SPRAY SYSTEM WAS NOT TESTED.

THE PERSONNEL ERROR "A" CORE SPRAY SYSTEM AND ALL OTHER SYSTEMS REQUIRED TO BE TESTED WERE T LICENSED 8 SENIOR OPERATORS ESTED WITH SATISFACTORY RESULTS. THERE HAVE BEEN NO PREVIOUS SIMILAR OC ITEM NOT APPLICABLE CURRENCES.

OPERATOR ERROR.

OPER. PERSONNEL DID HOT VERIFY ALL REQUIRED SURV. TESTI NG HAD BEEN PROPERLY COMPLETED. OPER PERS UERE REINSTRUCTED BY MEETING

& MEMORANDUM ON THE NEED FOR STRICT ADHERENCE TO PLANT PROCEDURES 8 T/S REQMTS.

ALSO IN FUTURE STA'S WILL HELP REVIEW SURV TESTING DOCUMENT PAC KAGES TO PREVENT RECURRENCE.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 35 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION DUANE ARNOLD 05000331 121680 DURING SURV. TESTING SUPPRESSION CHAMBER PURGE INLET VALVE CV-4308 WOULD CNTNMNT ISOLATION SYS + CONT 80-065/03L-0 011481 NOT CYCLE.

CV-4308 IS A CONTAINMENT ISOLATION VLV REQUIRED TO BE OPERA VALVE OPERATORS 033669 30-DAY BLE BY T/S SECTION 3.7.D.1.

WHILE THIS PROBLEM WAS BEING INVESTIGATED A PNEUMATIC / DIAPHRAGM / CYLINDER SOLENDID VLV ASSOCIATED WITH VLV OPERATOR FOR CV-4308 WAS JARRED 1 CV-4 COMPONENT FAILURE 303 BEGAN WORKING PROPERLY. VIV WAS CONSIDERED OPER. BUT FURTHER MAINT.

MECHANICAL ACTION INITIATED. MAINT. ACTION COMPLETED WITHIN 8 HOURS.

NO PREVIOUS MILLER FLUID POWER CO.

SIMILAR OCCURRENCES WITH CV-4308.

AIR SUPPLY SOLENOID VLV FOR CV-4308 WAS DISASSEMBLED 8 INSPECTED WITH NO PROBLEMS FOUND.

CV-4308 OPER. DISASSEMBLED & PISTON WAS FOUND TO BE ST ICKING.

OPER. WAS CLEANED, LUBRICATED 8 REASSEMBLED.

CV-4303 WAS TESTE D SAT.

VLV OPER. MANUFACTURED BY MILLER FLUID POWER.

OILER WILL BE ADD ED TO THE OPERATOR DURING 1981 REFUEL TO PRECLUDE RECURRENCE.

DUANE ARNOLD 05000331 122680 DURING NORMAL OPERATION, REACTOR WATER CLEANUP SYSTEM TO MAIN CONDENSER REAC COOL CLEANUP SYS + CONT 80-067/03L-0 012181 CONTROL VALVE CV-2729 DEVELOPED A BODY LEAK.

THE LEAK WAS SPRAYING WATE VALVES 033715 30-DAY R ON ELECTRICAL EQUIPMENT WHICH RESULTED IN THE REACTOR WATER CLEANUP (R GATE WCU) SYSTEM ISOLATING. REACTOR WATER CONDUCTIVITY SAMPLING WAS SHIFTED COMPONENT FAILURE TO THE REACTOR RECIRCULATION SYSTEM SAMPLE POINT IN ORDER TO SATISFY THE MECHANICAL S AMPLING REQUIREMENTS OF TECHNICAL SPECIFICATION 3.6.B.3.A.

NO PREVIOU ACF INDUSTRIES INC.

S SIMILAR OCCURRENCES HAVE BEEN RECORDED.

THE LEAK WAS CAUSED BY HIGH VELOCITY WATER FLOW THROUGH THE VALVE WHICH RESULTED IN A HOLE BEING ERODED IN THE VALVE BODY. THE VALVE BODY WAS WE LD kEPAIRED AN7 HYDR 0 STATICALLY TESTED WITH SATISFACTORY RESULTS. THE VA LVE WAS MANUF/L " RED BY ACF INDUSTRIES. A REPLACEMENT VALVE WILL BE INST ALLED DURIHF 'HE '981 REFUELING OUTAGE.

DUANE ARHOLD 05000331 010181 DURING N0? MAL POWEk OPERATION, THE "B" DRYWELL PARTICUL ATE RADI ATION ELE REAC COOL PRES BOUN LEAK DETEC 81-001/03L-0 013081 MENT, RE C1B, Ef* LD NOT RESPOND TO A SOURCE CHECK.

REDUNDANT ELEMENT, IOUSLY BEEN DECLARED INOP. IODINE 8 GASEQUS RAD MONITO INSTRUMENTATION + CONTROLS 036053 30-DAY RE 8101A *50 PS' OTHER RS RESPONDE; ~~~ cRLY. TECH SPEC. 3.6.C.2 NECESSITATES BOTH SUMP 8 AIR S

~

COMPONENT FAILURE AMPLING SYSTEM 5 BE OPERABLE DURING REACTOR OPERATION. A7 DAY LCO WAS IN MECHANICAL ITIATED IN ACCORDANCE WITH THIS TECH SPEC. MOISTURE CARRYOVER TO RE 8101 NUCLEAR MEASUREMENTS CORP.

A/B IS A RECURRINC PROBLEM. SEE LER 80-038, 78-09, 77-04, AND 77-03.

MOISTURE CARRIED OVER TO THE PARTICULATE FILTER FROM THE DRYWELL SAMPLIN G POINT CAUSED THE FILTER TO FAIL.

THE FAILED FILTER INADEQUATELY REMOV ED PARTICULATE FROM THE AIRSTREAM AND THE DETECTOR WAS SUBSEQUENTLY CONT AMINATED. DETECTOR WAS DECONTAMINATED AND FILTER REPLACED. RE 8101B WA S SOURCE CHECKED-SAT. RE 8101B IS MFG BY NMC. INITIATED DESIGN REVIEW.

DUANE ARHOLD 05000331 010681 DURING SURVEILLANCE TESTING. TURBINE BUILDING HIGH TEMPERATURE SWITCH TI MAIN STEAM ISOL SYS + CONTROLS 81-002/03L-0 020581 5 4477, ZONE 2.

TRIPPED AT GREATER THAN 204 DEGREES F. TECHNICAL SPECIFI INSTRUMENTATION + CONTROLS n36194 30-DAY CATION TABLE-3-A REQUIRES THE SETPOINT BE LESS THAN OR EQUAL TO 200 DEGR SWITCH EES F.

THE INSTFUMENT TOLERANCE IS +/- 4 DEGREES F.

REDUNDANT SWITCHES' COMPONENT FAILURE IN LOGIC WERE TESTED AND FOUND TO BE IN TOLERANCE. THIS SWITCH IS PART INSTRUMENT OF THE LOGIC WHICH ISOLATES THE MAIN STEAM LINES ON TURBINE BUILDING HI ROSEMONT ENGINEERING CD.

GH TEMP. REPETITIVE OCCURRENCE FOR THIS TYPE SWITCH (R0 80-025,78-028).

INSTRUMENT DRIFT, TIS 4477 WAS RECALIBRATED AND TESTED SATISFACTORILY PR IOR TO BEING RETURNED TO SERVICE. TIS 4477 IS A ROSEMOUNT SERIES 3000A TEMPERATURE INDICATING SWITCH. NO FURTHER CORRECTIVE ACTION IS PLANNED AT THIS TIME.

t

MAE 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 36 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAUSE DESCRIPTION DUANE ARNOLD 05000331 010881 DURING NORMAL POWER OPERATION, THE "B" DRYWELL PARTICULATE RADIATION ELE REAC COOL PRES BOUN LEAK DETEC 81-303/03L-0 020581 MENT, RE 3101B, WAS UNRESPONSIVE TO A SOURCE CHECK.

REDUNDANT ELEMENT R INSTRUMENTATION + CONTROLS 036054 30-DAY E 8101A, HAD PREVIOUSLY BEEN DECLARED IHOPERABLE. MOISTURE ON THE RADIA SENSOR / DETECTOR / ELEMENT TION ELEMENT AND PARTICULATE DETECTOR IS A RECURRING PROBLEM.

SEE RO 77 COMPONENT FAILURE

-03, 77-04, 78-09,80-038, AND 81-001 INSTRUMENT NUCLEAR MEASUREMENTS CORP.

CONDENSATE WHICH HAD COLLECTED ON RE 8101B AND ITS PARTICULATE DETECTOR CAUSED SENSOR FAILURE. A NEW RADIATION ELEMENT, MYLAR WINDOW, AND BETA PHOSPHOR WERE INSTALLED TO RETURN THE DETECTOR TO OPERATION. RE 8101B W AS SOURCE CHECKED-SAT PRIOR TO RETURN TO SERVICE. RE 8101B IS AM NMC MO DEL RAK-221F RADIATION ELEMENT. DESIGN REVIEW HAS BEEN INITIATED.

-DUANE ARNOLD 05000331 011181 DURING NORMAL POWER OPERATION, THE "B" DRYWELL PARTICULATE RADIATION MON REAC COOL PRES BOUN LEAK DETEC Si-004/03L-0 020581 ITOR FAILED DOWNSCALE. REDUNDANT RADIATION MONITOR ELEMENT RE 8101A HAD INSTRUMENTATION + CGNTROLS 036195 30-DAY PREVIOUSLY BEEN DECLARED INOPERABLE. THIS PLACED THE PLANT IN A 7-DAY LC SENSOR / DETECTOR / ELEMENT 0 IN ACCORDANCE WITH TECH. SPEC. 3.6.C.2 WHICH REQUIRES BOTH THL SUMP AN COMPONENT FAILURE D AIR SAMPLING SYSTEMS BE OPERABLE DURING REACTOR POWER OPERATION. MOIST OTHER URE ON THE DETECTOR IS A REPETITIVE PROBLEM. SEE LER'S81-003, 81-001, NUCLEAR MEASUREMENTS CORP.80-038, 78-09, 77-04, AND 77-03.

CAUSE WAS DETERMINED TO BE CONDENSATE ON RE 8101B.

THE MOISTURE WAS REM OVED FROM THE DETECTOR PRIOR TO BEING REINSTALLED. DETECTOR WAS SOURCE C HECKED-SAT. RE 8101B IS AN NMC MODEL RAK-221F RADIATION ELEMENT. DESIGN REVIEu HAS BEEN INITIATED. AS AN INTERIM MEASURE HP PERSONNEL ARE EXAMIN ING THE PARTICULATE AND IODINE FILTERS ONCE PER DAY.

DUANE ARNOLD 05000331 011381 DURING SURVEILLANCE TESTING CONDENSATE STORAGE TANK (CST) tT-5B LOW LEVE CONDENSATE STORAGE FACILITIES 81-005/03L-0 020581 L $ WITCH LS-5219 UAS FOUND INOPERABLE. THIS SWITCH PROVIDES A LOW LEVEL INSTRUMENTATION + CONTROLS 036178 30-DAY ALARM FOR THE CST'S AND SHIFTS HPCI PUMP SUCTION TO TORUS ON CST LOW LE SWITCH VEL.

TECH SPEC 3.2-B REQUIRES THIS SWITCH BE OPERABLE DURING REACTOR PO COMPONENT FAILURE WER OPERATION. LS 5218 WAS TESTED AND FOUND OPERATING SAT.

THIS PROBLE ELECTRICAL M IS PRESENTLY THE SUBJECT OF A DESIGN REVIEW. REPETITIVE OCCURRENCE.

G-W CONTROLLER SEE LER 80-045 AND LER 76-038.

MOISTURE ON THE PROBE'S LEADS WITHIN THE TERMINAL BOX CAUSED THE TRIP SI GNAL TO BE GROUNDED. THE MOISTURE WAS REMOVED FROM THE LEADS AND TERMIN AL BOX, AND THE STAKE-ONS WERE FILLED WITH RTV TO HELP KEEP THE MOISTURE AWAY FROM THE LEADS. A DESIGN REVIEW IS PRESENTLY UNDERWAY TO DETERMIN E HOW TO ALLEVIATE THE MOISTURE PROBLEM IN THE TERMINAL BOX.

EDWIN I. HATCH-1 05000321 121980 ON 12/19/80, WITH REACTOR SHUTDOMN, RCIC SYS WAS BEING USED TO CONTROL REAC CORE ISOL COOL SYS + CONT 80-123/03L-0 011581 REACTOR WATER LEVEL.

AFTER THREE STARTS TURBINE TRIP & THROTTLE VALVE F VALVES 033673 30-DAY AILED TO 0?EN ON FOURTH START.

THEN ON 12/26/80, DURING TURBINE EXHAUST GATE PRESSURE INSTRUMENT FUNCTIONAL TEST 1 CALIBRATION, TRIP & THROTTLE VALV COMPONENT FAILURE E FAILED TO TRIP.

RCIC WAS DECL ARED INOPERABLE AFTER EACH INCIDENT.

TH MECHANICAL IS IS A REPETITIVE EVENT AS LAST REPORTED ON RO 50-321/1979-02.

PUBLIC VERRY STEAM TURBINE COMPANY HEALTH AND SAFETY WERE NOT AFFECTED.

FIRST FAILURE WAS DUE TO A GALL ON VALVE POPPET & VALVE BODY CAUSING VAL VE TO STICK.

GALL WAS REMOVED 8 VALVE RETURNED TO SERVICE ON DECEMBER 2 5,

1980.

SECOND FAILURE WAS CAUSED BY A LIMIT SWITCH HAVING BEEN SET WR ONG DURING REPAIR OF PREVIOUS INCIDENT. SWITCH WAS RESET 4 RCIC PROVEN OPERABLE ON DECEMBER 26, 1980.

d MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 37 PROCESSED DURING MARCH, 1951 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-1 05000321 122380 WHILE THE UNIT WAS IN STEADY STATE OPERATION,RESEARCH FOR AND PREPARATI0 SYSTEM CODE NOT APPLICABLE 80-127/03L-0 011331 N OF THE UNIT 1 FIVE-YEAR ISI REPORT REVEALED A LACK OF HARD DOCUMENTATI COMPONENT CODE NOT APPLICABLE 033675 30-DAY ON PROVING VISUAL INSPECTION OF AT LEAST $0% OF THE UNIT 1 CLASS 1 VALVE SUBCOMPONENT NOT APPLICABLE (GREATER THAN 3" IN DIAMETER) INTERNALS AS REQUIRED SY TECH SPECS 4.6.K DEFECTIVE PROCEDURES

. THIS EVENT IS NONREPETITIVE. THE HEALTH AND SAFETY OF THE PUBLIC WER NOT APPLICABLE E UNAFFECTED.

ITEM NOT APPLICABLE PLANT PROCEDURES HAVE NOT STRESSED INSPECTION OF CLASS 1 VALVE (GREATER THAN 3") INTERNAL

S. PROCEDURE

S FOR UNIT 1 WILL BE REVISED SO A QC INSPE CTION OF APPLICABLE VALVE INTERNALS WILL BE DONE UHEN THE VALVE IS DISAS SEMBLED FOR MAINTENANCE. UNIT 2 PROCEDURES WILL BE REVIEWED AND AN UPDA TED REPORT SUBMITTED.

EDWIN I. HATCH-1 O$000321 122850 WITH THE PLANT AT A STEADY STATE OF OPERATION, WHILE PERFORMING HNP-t-39 AIR COND, HEAT, COOL, VENT SYSTEM 80-124/03t-0 011581 37, CONTROL ROOM AIR INTAKE ISOLATION VALVE OPERABILITY, THE 1Z41-F012 V UALVES 033674 30-DAY ALVE FAILED TO MEET ACCEPTABLE CLOSING TIME CRITERIA PER TECH. SPECS. 3.

DIAPHRAGM 12.B.

PLANT OPERATION WAS NOT AFFECTED AS A RESULT OF THIS EVENT.

THIS COMPONENT FAILURE WAS NOT A REPETITIVE OCCURRENCE. PUBLIC HEALTH AND SAFETY WERE NOT AFF ELECTRICAL ECTED BY THIS INCIDENT.

ASCD THE CAUSE OF THE VALVE FAILING TO CLOSE IN THE DESIRED LENGTH OF TIME WA 5 DUE TO A FAULTY PILOT SOLENOID OPERATOR. THE PILOT SOLENDID WAS REPLA CED AND HNP-t-3973 PERFORMED SATISFACTORILY.

i EDWIN I. HATCH-1 0$000321 123080 ON DECEMBER 30, 1980, WHILE AT 637 MUE AND PERFORMING HIGH DRYMELL PRESS REACTOR TRIP SYSTEMS 80-128/03L-0 012781 URE FUNCTION TEST, HNP-1-3002, PER TECH. SPECS. 3.1-1 B & C.

ONE OF THE RELAYS 033718 30-DAY DRYUELL HIGH PRESSURE RELAYS, 1C71-K43, DID NOT FUNCTION PROPERLY. THIS CONTROL, SEALED RELAY FAILED AGAIN ON JANUARY 1,

1981 PRICR TO THESE FAILURES, THIS W COMPONENT FAILURE AS A NON-REPETITIVE EVENT.

SAFE PLANT OPERATION WAS NOT AFFECTED NOR WA ELECTRICAL S THERE ANY EFFECT ON THE HEALTH ANU SAFETY OF THE PUBLIC DUE TO THIS EV GENERAL ELECTRIC CD.

ENT.

THE FIRST EVENT WAS CAUSED BY BROKEN INSULATION ON THE RELAY, PREVENTING THE RELAY CONTACTS FROM DE-ENERGIZING.

IT WAS REPAIRED AND FUNCTIONALL Y TESTED WITH SATISFACTORY RESULTS.

THE SECOND FAILURE WAS DUE TO A COI L FAILURE. THE RELAY WAS REPLACED AND RETURNED TO SERVICE.

EDWIN I. HATCH-1 0$000321 010181 WITH THE REACTOR AT 401 MWE, A LEAK OF MORE THAN FIVE (S) GPM DEVELOPED COOLANT RECIRC SYS + CONTROLS 81-002/03L-0 012781 IN THE DRYWELL.

PER TECHNICAL SPECIFICATIONS 3.6.G.1, THE REACTOR WAS B PUMPS 036034 30-DAY ROUGHT TO COLD SHUTDOUN WITHIN 36 HOURS.

THIS IS A NON-REPET?TIVE EVENT CENTRIFUGAL

. SAFE PLANT OPERATION WAS NOT AFFECTED HOR WAS THERE ANY EFFECT ON THE COMPONENT FAILURE HEALTH AND SAFETY OF THE PUBLIC.

INSTRUMENT DYROM JACKSON PUMPS. INC.

THE CAUSE OF THE EVENT WAS A MECHANICAL SEAL LEAKING WATER FROM THE REAC TOR RECIRC PUMP, IB31-C001A.

THE SEAL WAS REPLACED, FUNCTIONALLY TESTED AND RETURNED TO SERVICE.

MAR 2G, 1991 '

LER MONTHLY REPORT SORTED BY FACILITY PAGE 38 4-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS i

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REPORT TYPE CAUSE DESCRIPTION l

l EDWIN I. HATCH-1 05000321 010681 OH 1-6-81. WITH UNIT I IN STEADY STATE POWER OPER

  • WITH UNIT II SHUTDOW l

SYSTEM CODE NOT APPLICABLE 81-004/03L-0 012951 N FOR REFUELING, A QA AUDIT OF HATCH PROCEDURE PROGRAM SHOWED THAT HNP-8 COMPONENT CODE NOT APPLICABLE 036107 30-DAY

18. " TEMPORARY PROCEDURE CHANGE" DID NOT FULLY MEET T.

S. SECTION 6.8.3.

SUBCOMPONENT NOT APPLICABLE C REQUIREMENT THAT TEMP CHANGES BE DOCUMENTED, PRB REVIEWED 8 AFPROVED B DEFECTIVE PROCEDURES Y PLANT MANAGER WITHIN 14 DAYS OF IMPLEMENTATION.

IT ONLY REQUIRED THAT MBT APPLICABLE THEY BE DOCUMENTED A PRB REVIEWED WITHIN 14 DAYS.

THIS IS A NON-REPETI ITEM NOT APPLICABLE TIVE EVENT AND POSED NO THREAT TG THE PUBLIC.

REQUIREMENT FCR PLANT MANAGERS SIGNATURE ON PROCEDURE REVISION REQUEST W AS DELETED ON 3-10-80.

HNP-818 " TEMPORARY PROCEDURE CHANGE" WAS REVISED-TO REQUIRE THE PLANT MANAGERS' SIGNATURE GN THE PROCEDURE REVISION REGU EST SHEET IN ACCORDANCE WITH TECH. SPEC. SECTION 6.8.3.C.

THE SRO CHANG ED FROCEDURES WERE SIGNED BY THE PL ANT MANAGER.

EDWIN I. HATCH-1 05000321 011981 DURING NORMAL OPERATION, WHILE PERFORMING STANDBY LIQUID CONTROL (SBLC) 1 OTHER ENGNRD SAFETY FEATR SYS 61-006/03L-0 021081 PUMP OPERABILITY AND RELIEF VALVE TEST PROCEDURE, HNP-1-3702, SBLC "A" D

VALVES 036108 30-DAY ISCHARGE RELIEF VALVE. 1C41-F029A. OPERATED AT 1200 PSIG.

THE ACCEPTABL ANGLE E RANGE IS 1325 +/- 75 PSIG PER TECH SPECS 4.4.A.2.A.

THE REDUNDANT LOO COMPONENT FAILURE P "B" WAS OPERABLE. THIS IS A REPETITIVE EVENT AS LAST REPORTED ON REPO MECHANICAL RTABLE OCCURRENCE REPORT NO. 50-321/1980-010.

SAFE PLANT OPERATION & PU LONEGAN, J.

E. COMPANY BLIC HEALTH AND SAFETY WERE NOT AFFECTED BY THIS EVENT.

THE CAUSE OF THE EVENT WAS SETPOINT DRIFT ON SBLC PUMP "A" RELIEF VALVE.

1C41-F029A.

THE VALVE WAS RESET TO 1350 PSIG PER SBLC PUMP OPERABILITY AND RELIEF VALVE TEST PROCEDURE. HNP-1-3702.

THE SYSTEM WAS RETESTED S ATISFACTORILY AND RETURNED TO SERVICE.

EDWIN I. HATCH-2 05000366 040480 WITH THE UNIT IN COLD 5HUTDOWN, A LEAK RATE TEST WAS PERFORMED ON THE AD EMERG CORE COOLING SYS + CONT 80-045/01X-3 021781 S VALVES AIR SUPPLY ACCUMULATOR CHECK VALVES.

THE AE DETERMINED THAT TH VALVES 030767 OTHER E LEAKAGC RATES THAT WERE FOUND WERE UNACCEPTABLE AND THAT A LOSS OF AIR CHECK SUPPLY COULD LEAD TO ADS INOPERABILITY. LEAKAGE RATES FOR CORRESPONDIN DESIGN / FABRICATION ERROR G UNIT 1 VALVES ARE UNKNOWN.

THIS EVENT CAUSED NO THREAT TO PUBLIC HEAL CONSTRUCTION / INSTALLATION TH OR SAFETY.

THIS IS A NONREPETITIVE EVENT FOR THESE VALVES.

ROCKWELL-INTERNATIONAL CAUSE OF THIS EVENT IS BELIEVED TO BE HEAT DAMAGE FROM INSTALLATION WELD ING.

THESE VALVES WERE TO BE REPLACED WITH SOFT-SEATED VALVES DURING TH E CURRENT REFUELING OUTAGE, HOWEVER, PARTS ARE UNAVAILABLE AT THIS TIME, INSTALLATION WILL BE DEL AYED UNTIL NEXT REFUELING OUT AGE.

PROCEDURES F OR BOTH UNITS HAVE BEEN REVISED TO INFORM OPERATORS OF THIS FATLURE MODE EDWIN I.' HATCH-2' 05000366 011981 ON JANUARY 19, 1981, WHILE IN COLD SHUTDOWN AND PERFORMING CRD HCU PRESS OTHR INST SYS REQD FOR SAFETY 61-008/03L-0 021281 URE INDICATOR AND SWITCH CALIBRATION, HNP-2-5329, PER TECH SPECS 4.1.3.5 INSTRUMENTATIDH + CONTROLS 036174 30-DAY

.B.2.,

62 0F 137 PRESSURE SWITCHES WERE FOUND OUT OF TOLERANCE OF 955 +/

SWITCH

- 15 PSIG.

ACTUATION PRESSURE OF THESE SUITCHES WAS APPROXIMATELY'935 P COMPONENT FAILURE SIG.

THERE WAS NO EFFECT ON SAFE PLANT OPERATION NOR WERE THERE ANY EFF INSTRUMENT ECT ON H/S OF PUBLIC DUE TO THIS EVENT.

THIS IS A REPETITIVE EVENT AS L BARKSDALE COMPANY AST REPORTED ON REPORTABLE OCCURRENCE REPORT NO. 50-366/1980-076.

THE CAUSE OF THIS EVENT HAS BEEN ATTRIBUTED TO SETPOINT DRIFT.

THE PRES SURE SWITCHES WERE RECALIBRATED AND RETURNED TO SERVICE.

ce t

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+

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w yev y we

--t m

y

l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 39 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION EDWIN I. HATCH-2 05000366 012681 DURING REACTOR SHUTDOWN FOR REFUELING.THE R.P.V.

HYDRO VALVE LINEUP PER RESIDUAL HEAT REMOV SYS + CONT 81-005/01T-0 020981 HNP-2-1230 WAS BEING PERFORMED WHEN IT WAS DISCOVERED AT APPROXIMATELY 1 COMPONENT CODE NOT APPLICABLE 036109 2-WEEK 430 THAT BOTH CORE SPRAY MANUAL INJECTION VALVES HAD BEEN CLOSED AT APPR SUBCOMPONENT NOT APP 6ICABLE OXIMATELY 0900 RENDERING BOTH CORE SPRAY LOOPS INOPERABLE.

THIS WAS IN DEFECTIVE PROCEDURES VIOLATION OF TECH. SPECS.

3.5.3.1.B.2.B.

THIS IS NOT A REPETITIVE EVENT NOT APPLICABLE AND THERE WERE NO EFFECTS ON PUBLIC HEALTH OR SAFETY.

ITEM NOT APPLICABLE THIS EVENT WAS CAUSED BY PROCEDURE HNP-2-1230 BEING PERFORMED TO SUPPORT R.P.V.

HEAD TENSIGNING.

THE PROCEDURE CALLED FOR CORE SPRAY MANUAL-INJ ECTION VALVES 2E21-F007A 8 B TO BE CLOSED.

THE VALVES WERE IMMEDIATELY REOPENED AND HNP-2-1230 WAS CHANGED TO REQUIRE 2E21-F007A 8 B TO BE IN T HE OPEN POSITION.

FITZPATRICK-1 05000333 020580 DURING ROUTINE SHUTDOWN AND COOLDOWN OPERATIONS, THE PLANT STACK GAS MON-PRCSS + EFF RADIOL MONITOR SYS 80-020/04X-1 013081 ITORING SYSTEf1 WAS INOPERABLE DUE TO FREEZE UP OF THE SAMPLE LINE.

CONT INSTRUMENTATION + CONTROLS 030342 OTHER INUOUS MONITORING 15 REQUIRED BY ETS 2.3.A.9 WITH DEGRADED MODE OPERATIO OTHER H PERMIT 7CD FOR 10 DAYS.

NO SIGNIFICANT HAZARD EXISTED.

OTHER NOT APPLICABLE ITEM NOT APPLICABLE COLD WEATHER CONDITIONS IN CONJUNCTION WITH HUMID AIR AND WATER VAPOR FR CM CONDENSER AIR REMOVAL SYSTEM RESULTED IN SAMPLE LINE FREEZE UP.

BLOW DOWN OF THE SAMPLE LINE WITH DRY NITROGEN CLEARED THE LINE WITHIN 1 HOU R.

INSPECTION OF LINE DURING REFUEL OUTAGE DID NOT INDICATE ANY HEAT TR ACE PROBLEM.

SECOND SAMPLE PROBE WAS INSTALLED AS BACKUP.

FITZPATRICK-1 05000333 061080 DURING NORMAL SHUTDOWN AND DURING SURVEILLANCE TESTING, FOLLOWING ROUTIN EMERG GENERATOR SYS + CONTROLS 80-056/03X-1 020281 E PREVENTIVE MAINTENANCE WORK, EMERGENCY DIESEL GENERATOR "C"

TRIPPED ON CIRCUIT CLOSERS / INTERRUPTERS 031597 OTHER HIGH CIRCULATING CURRdNT. SUBSEQUENT TESTS COULD NOT DUPLICATE THE PRO SWITCH (OTHER THAN SENSOR)

BLEN.

THE OTHER EDG SYSTEM WAS OPERABLE MEETING TECHNICAL SPECIFICATI0H COMPONENT FAILURE 3.9.D REQUIREMENTS. THE EVENT DID NOT REFRESENT A SIGNIFICANT HAZARD T ELECTRICAL 0 THE PUBLIC HEALTH AND SAFETY.

CUTLER-HAMMER THE CAUSE WAS DUE TO HIGH RESISTANCE CONTACTS ON THE REGULATORY DROOP SW ITCH RESULTING IN TRIP.

THIS DETERMINATION WAS MADE FOLLCMING A RECURRE NCE ON 1/6/81 (SEE LER 81-004 ). SWITCHES WERE REPLACED. NO ADDITIONAL ACTION IS REQUIRED.

FITZPATRICK-1 05002533 122980 DURING NORMAL OPERATION, WHILE PERFORMING SURV5ILLANCE TO SATSIFY TECH.

REACTOR TRIP SYSTEMS 80-096/03L-0 012781 SPEC. TABLE 4.2-1, REACTOR LEVEL SUITCH 02-3-LIS-101B WAS FOUND SET 2.3 i

INSTRUMENTATION + CONTROLS 033716 30-DAY INCHES BELOW THE +12.5 INCH REQUIREMENT. ON JANUARY 9, 1981 LIS-101B WA SWITCH S FOUND SET 0.5 INCHES ABOVE THE +58 INCH REQUIREMENT.

IN BOTH CASES TH COMPONENT FAILURE E OTHER'THREE SWITCHES WERE WITHIN TECH. SPEC. LIMITS AND LIS-101B WAS I HATURAL END OF LIFE MMEDIATELY CALIBRATED. NO SIGNIFICANT HAZARD EXISTED.

BARTON INSTRU CO.,

DIV 0F ITT l

CAUSE OF BOTH FAILURES IS ATTRIBUTED TO NORMAL WEAR AND TEAR (AGE).

AFT l

ER FIRST FAILURE, SURVEILLANCE WAS INCREASED TO WEEKLY.

AFTER SECOND FA ILURE, INSTRUMENT WAS REPLACED. NEW INSTRUMENT' TESTED SATISFACTORY AND

(

WAS RETURNED TO SERVICE. NO ADDITIONAL ACTION REQUIRED.

l

MAR 26, 1981 LER MONTHLY REPORT SCRTED BY FACILITY PAGE 40 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAU5E DESCRIPTION FITZPATRICK-1 05000333 010681 DURING NORMAL OPERATION, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH.

CNTHMNT ISOLATION SYS + CONT 81-003/03L-0 020281 SPEC. lABLE 3.2-6, CONTAINMENT ISOLATION VALVE 16-1-A0V-102A WOULD NOT C VALVES 036056 30-DAY LOSE.

THE OTHER VALVE IN THE SAME LINE (A0V-1023) WAS CLOSED AND IS BEI GLOBE NG CHECXED DATLY AS REQUIRED BY TECH. SPEC.

3.7.D.

THE PENETRATION IS A COMPONENT FAILURE SENSING LINE FOR TORUS PRESSURE WHICH IS ALSO AVAILABLE FROM ANOTHER PE.

NATURAL END OF LIFE NETRATION. NO SIGNIFICANT HAZARD EXISTED.

ASCO THE CAUSE OF FAILURE IS ATTRIBUTED TO HATURAL END OF LIFE CAGE).

THE LI NE REMAINS ISOLATED WHILE A NEW ENVIRONMENTALLY QUALIFIED REPLACEMENT IS PROCURRED. NO ACTION IN ADDITION TO VALVE REPLACEMENT IS REQUIRED.

FITZPATRICK-1 05000333 011081 DURING HORMAL OPERATION, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH.

EMERG GENERATOR SYS + CONTROLS 81-004/03L-0 020981 SPEC.

4.9.B.

EMERGENCY DIESEL GENERATOR "D" EXHIBITED LOAD SWINGS (HUNTI CIRCUIT CLOSERS / INTERRUPTERS 036197 30-DAY NG) AND THEN TRIPPED ON HIGH CIRCULATING CURRENT.

INITIAL OPERATION (ST SWITCH (OTHER THAH SENSOR)

ARTING AND FORCE PARALLELING WITH EDG-B) WAS SATISFACTORY. THE REDUNDAN COMPONENT FAILURE T EMERGENCY DIESEL SYSTEM AND OFFSITE POWER WERE AVAILABLE AND OPERABLE ELECTRICAL AT ALL TIMES.

NO SIGNIFICANT HAZARD EXISTED.

CUTLER-HAMMER CAUSE OF THE FAILURE WAS DEFECTIVE REGULATOR DROOP SWITCH.

OPERATION UN DER EMERGENCY CONDITIONS (LOCA OR LOSS OF NORMAL POWER) WOULD NOT HAVE B EEN AFFECTED BECAUSE THE SWITCH IS USED ONLY FOR TEST.

SWITCH WAS REPLA CED IN BOTH EMERGENCY POWER SYSTEMS. NO ADDITIONAL ACTION IS REQUIRED.

LER 30-056 IS A RELATED EVENT.

FITZPATRICK-1 05000333 011281 DURING NORMAL OPERATION, ROD BLOCK MUNITOR "B" FAILED TO NULL WHEN A CON ENGNRD SAFETY FEATR INSTR SYS 81-006/03L-0 021181 TROL ROD WAS SELECTED.

THE INSTRUMENT WAS REQUIRED TO BE OPERABLE BY TE RELAYS 03617S 30-DAY CHNICAL SPECIFICATION TABLE 3.2-3.

THE REDUNDANT ROD BLOCK MONITOR WAS MINIATURE VERIFIED OPERABLE AS REQUIRED. NO SIGNIFICANT HAZARD EXISTED.

COMPONENT FAILURE NATURAL END OF LIFE GENERAL ELECTRIC CO.

THE ROD BLOCK MONITOR DID NOT NULL BECAUSE A RELAY FAILED (DUE TO END OF-NATURAL LIFE) AND DID NOT ALLOW THE MONITOR TO RECOGNIZE THAT A CONTROL ROD WAS SELECTED. REPLACEMENT OF RELAY BOARD AND OPERABILITY TESTING R ESTORED THE INSTRUMENT TO SERVICE ON THE FOLLOWING DAY.

NO ADDITIONAL A CTION 15 REQUIRED.

FITZPATRICK-1 05000333 011281 7URING NORMAL OPERATION, AS PART OF A ROJTINE Q.A.

AUDIT, IT WAS DETERMI GAS RADIDACT WSTE MANAGMNT SYS 81-005/04L-0 020981 NED THAT ANNUAL TEST OF THE OFFGAS AUTOMATIC ISOLATION WAS NOT PERFORMED COMPONENT CODE NOT APPLICABLE 036177 30-DAY AS REQUIRED BY ENVIRONMENTAL TECHNICAL SPECIFICATICWS (ETS) 2.3.B.10.

SUBCOMPONEHT NOT APPLICABLE FOLLOWING DISCOVERY, THE ISOLATION FUNCTION WAS TESTtD ON 1/19/81 TEST OTHER S HAD BEEN PERFORMED AS REQUIRED BY OPERATING TECHNICAL SPECIFICATIONS (

NOT APPLICABLE OTS) 4.2.D, TABLE 4.2-4 AND TABLE 4.2-6 NOTE 4.

NO SIGNIFICANT HAZARD E ITEM NOT APPLICABLE XISTED.

CONFLICT BETWEEN ETS (2.3.B10) AND OPERATING T.S.

(TABLE 2-4 AND 4.2-6, NOTE 10) CAUSED MISSED SURVEILLANCE. TEST WAS CONDUCTED DURING FIRST 0U TAGE THAT PERNITTED. SURVEILLANCE TEST WAS REVISED TO REFLECT ETS REQUI REMENT AND CHANGE TO ETS MAY BE REQUESTED. NO ADDITIONAL ACTION IS REQU IRED.

MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 41 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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EVENT DES'CRIPTION/

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION FITZPATRICK-1 05000333 011381 DURING NORMAL OPERATION. WHILE CONDUCTING SURVEILLANCE TO SATISFY TECHNI EMERG CORE COOLINb SYS + CONT 81-007/03L-0 021281 CAL SPECIFICATION TABLE 4.2-2, CORE SPRAY PIPE PREAK D/P SWITCHES 14-DPI INSTRUMENTATION + CONTROLS 036176 30-DAY S-43A AND 43B WERE FOUND SET AT 1.08 AND 0.77 WHEN REQUIRED BY TECHNICAL-SWITCH SPECIFICATION TABLE 3.2-2 TO BE SET AT EQUAL TO OR LESS THAN 0.5.

SUIT COMPONENT FAILURE CH 43A WAS ALSO FOUND SET AT 0.72 ON 1/23/81.

IN EACH CASE THE SWITCHES INSTRUMENT WERE IMMEDIATELY RECALIBRATED AND RETURNED TO SERVICE.

NO SIGNIFICANT BARTON INSTRU CO., DIV 0F ITT HAZARD EXISTED.

INSTRUMENT DRIFT IS BELIEVED TO BE THE CASE.

SURVEILLANCE HAS BEEN INCR EASED.

FITZPATRICK-1 05000333 011481 DURING NORMAL OPERATION. THE RESIDENT INSPECTOR NOTED.THAT DAILY REACTOR SYSTEM CODE NOT APPLICABLE 81-008/03L-0 021431 COOLANT LEAKAGE DETERMINATION REQUIRED BY TECH. SPEC. 4.6.D WAS NOT CAL COMPONENT CODE NOT APPLICADLE 036198 30-DAY CULATED ON 1/13/81 THE LEAKAGE RATE WAS IMMEDIATELY CALCULATED FOR A 3 SUBCOMPONENT NOT APPLICABLE 9 HOUR PERIOD INCLUDING 1/13/81 AND A PORTION OF 1/14/81 THE AVERAGE L PERSONNEL ERROR EAKAGE RATE OVER THE 39 HOUR PERIOD WAS 1.81 GPM AND 1.64 GPM COMPARED T LICENSED 2 SENIOR OPERATORS 0 TECH. SPEC. LIMITS OF 25 AND 5 GPM.

NO SIGNIFICANT HAZARD EXISTED.

ITEM NOT APPLICABLE PERSONNEL ERROR WAS THE CAUSE.

IMMEDIATE CORRECTIVE ACTION, AS NOTED AB OVE, REVEALED LEAKAGE WAS WITHIN LIrlITS. ALTHOUGH THE ERROR IS CONSIDER ED AN ISOLATED EVENT, PERSONNEL RESPONSIBLE FOR CONDUCT AND REVIEW OF TH E SURVEILLANCE WILL BE REQUIRED TO REVIEW THIS LER TO PREVENT RECURRENCE FITZPATRICK-1 05000333 011581 DURING NORi1AL OPERATION. AS A RESULT OF ADMINISTRATIVE REVIEW, IT WAS DI FIRE PROTECTION SYS + CONT 81-009/03L-0 021681 SCOVERED THAT FIRE HOSE GASKET INSPECTION AND HOSE RERACK REQUIRED BY TE COMPONENT CODE NOT APPLICABLE 036199 30-DAY CH. SPEC. TABLE 4.12.3 ONCE EACH 1.5 YEARS HAD NOT BEEN COMPLETED WHEN R SUBCOMPONENT NOT APPLICABLE EQUIRED DURING PART OF 1979 AND 1980.

THE REQUIRED INSPECTION WAS COMPL PERSONNEL ERROR ETED FOUR (4) MONTHS AFTER THE DUE DATE.

NO SIGNIFICANT HAZARD EXISTED.

LICENSED 2 SENIOR OPERATORS ITEM NOT APPLICABLE REVIEW OF RECORDS INDICATES THAT OUTDATED PROCEDURE DATA SHEETS WERE USE D FOR 8 ft0NTHS AFTER PROCEDURE REVISION.

THE CAUSE WAS PERSONNEL ERROR.

It1 PROPER DATA SHEETS WERE NOT USED AFTER MAY, 1980.

TO PREVENT RECURRE NCE, PERSONNEL INVOLVED WILL BE REQUIRED TO REVIEW THIS LER.

NO ADDITIO NAL ACTION WILL DE REQUIRED.

FITZPATRICK-1 05000333 012481 DURING NORMAL SHUTD0'N, WHILE CONDUCTING SURVEILLANCE TO SATISFY TECH. S EMERG CORE COOLING SYS + CONT 81-013/03L-0 022081 PEC. 4.5.C.1 THE HPCI SYSTEM' FLOW SQUARE ROOT COMPUT ATION MODULE WAS FO INSlRUMENTATION + CONTROLS 036232 30-DAY UND OUT OF CALIBRATION. UHEN FLOW INDICATION WAS AT A RATED VALUE OF 42 COMPUTATION MODULE 50 GPM THE ACUTAL FLOW WOULD HAVE BEEH 4203 GPM.

THE SYST EM 'JAS ' NOT REQ COMPONENT FAILURE UIRED TO BE OPERABLE. NO SIGNIFICANT HAZARD EXISTED.

INSTRUMENT GENERAL ELECTRIC CO.

INSTRUMENT DRIFT IS BELIEVED TO BE THE CAUSE.

FOLLOWING CALIBRATION THE INSTRUMENT WAS RETURNED TO SERVICE. NO ADDITIONAL ACTION ~IS REQUIRED.

t MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PROCESSED DURING MARCH, 1981 FOR POWER REACTORS PAGE 42 FACILITY /SYSTEP/ COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE EVENT DESCRIPTION /

-CAUSE DESCRIPTION FT. CALHOUN-1 05000285 122780 DURING POWER OPERATION, ONE OF FOUR CURRENT LOOPS INDICATING PRESSURIZER REACTOR TRIP SYSTEMS 80-033/03L-0 122980 PRESSURE AND INPUT INSTRUMENTATION + CONTROLS 033717 30-DAY REACTOR PROTECTIVE SYSTEM CHANNELTO THE THERMAL MARGIN / LOW ONE POWER SUPPLY AND ONE SAFETY INJECTION ACTUATION CH AHMEL FAILED LOW, PLACING THE SIAS IN HALF TRIP AND TRIPPING ONE TM/LP C t

COMPONENT FAILURE ELECTRICAL HANNEL OF THE RPS. THE RPS "B" CHANNEL WOULD NOT HAVE TRIPPED ON HIGH PR GENERAL ELECTRIC CO.

.ESSURIZER PRESSURE.

THE RPS WAS PLACED IN TWO-0UT-OF-THREE LOGIC BY BYP ASSING "B" CHANNEL TM/LP BISTABLE. TECH. SPEC. Z 15 APPLIES.

AFTER INVESTIGATION, IT WAS DISCOVERED THAT THE CURRENT LOOP FUSE IN THE GE/MAC TYPE 570 POWER SUPPLY FOR THE B/ PIA-102Y LOOP HAD BLOWN.

TPE FU SE WAS REPLACED AND THE LOOP RETURNED TO NORMAL AFTER COMPARING THE LOOP CURRENT WITH THE OTHER THREE LOOP CURRENTS t1EASURING THE SAME PR.0 FT. CALHOUN-1 05000285 011481 AS REQUIRED BY I.E.

BULLETIN 79-01B, FT-236, CHARGING HEADER FLOW LACKS SAFETY RELATED DISPLAY INSTR 8 ?-0 01/01T-0 011581 COMP' ETE INFORMATION 10 qu ALIFY IT FOR THE HARSH RADIATION SERVICE INTEN INSTRUMENTATION + CONTROLS 036033 2-WEEK DED.

THE TRANSMITTER DESIGN / FABRICATION ERROR ILIARY PRESSURIZER SPRAY.IS USED FOR LONG TERM CORE COOLING FLOW TO T TRANSMITTER IF fHE TRANSMITTER SHOULD FAIL IN A POST ACCI DESIGN DENT SITUATION, CHARGING HEADER PRESSURE, FOXBORO CO.,

THE AND PJMP CURVES CAN BE USED TO DETERMINE Flou.HIGH PRESSURE INJECTION FLOW, A CGMPLETE MATERIALS LIST IS NOT AVAILABLE TO DETERMINE RADIATION DOSE L INITS OR QUALIFIED LIFE.

ALTHOUGH THE TRANSMITTER IS NOT EXPECTED TO FA IL. IT WILL BE REPL ACED WITH A QUALIFIED TRANSMITTER BY THE END OF THE 981 1

REFUELING OUTAGE.

FT. ST. VRAIN-1 05000267 0u0480 DURING A MAINTENANCE SHUTDOWN, WHILE PERFORMING ROUTINE SURVEILLANCE TES REACTOR VES. + APPURTENANCES 80-049/03X-1 011381 TING OF PCRV RUPTURE DISC, M-11702, OTHER COMPONENTS 032835 OT IER G. THIS IS OUTSIDE THE 812 PSIG +/- ITS SETPOINT WAS FOUND TO BE 826 PSI SUBCOMPONENT NOT APPLICABLE 1% ALLOWED BY FORT ST. VRAIN TECH. S OTHER PEC. LSSS 3.3.2(C) AND IS BEING REPORTED PER FORT ST. VRAIN TECH. SPEC.

NOT APPLICABLE AC 7.5.2(B)1.

THE REACTOR HAD NOT BEEN OVERPRESSURIZED DURING THIS SURVE-CALMEC ILLANCE INTERVAL AND THERE WAS NO EFFECT ON PLANT OPERATION.

NO EFFECT ON PUBLIC HEALTH OR SAFETY.

SIMILAR REPCRT RO 79-15.

RUPTURE DISC MOVEMENT EVILLE WASHER OPERATING POINT.SETPOINT GUT OF TOLERANCE DUE TO DRIF THAT THE RUPTURE DISC SETPOINT WASTWO ADDITIONAL SNAP-0VER TESTS REVEA IN TOLERANCE.

FT. ST. VRAIH-1 05000267 123080 DURING AN INTERNAL AUDIT OF SURVEILLANCE TESTS. IT WAS DISCOVERED THAT S 6

SPENT FUEL STORAGE FACILITIES 80-078/03L-0 012981 R 5.7.2B-A, THE CALIBRATION AND FUNCTIONAL TEST OF FUEL STORAGE FACILITY INSTRUMENTATION + CONTROLS 033740 30-DAY INDICATOR COOLING SYSTEM FLOW INDICATORS AND FLOW AND TEMPERATURE ALARMS, HAD NOT PERSONNEL ERROR BEEN COMPLETED WITHIN REQUIRED INTERVAL. SPENT FUEL WAS IN STORAGE DUR LICENSED & SENIOR OPERATORS ING THIS PERIOD.

THIS IS REPORTABLE PER FORT ST. VRAIN TECHNICAL SPECIF OTHER ICATION AC 7.5.2(B)3.

NO ACCOMPANYING OCCURRENCE. NO EFFECT ON PUBLIC HEALTH OR SAFETY.

RESULTS ENGINEERING SUPERVISOR INCORRECTLY ASSUMED ALL SPENTFUEL HAD BE EN SHIPPED OFF SITE AND INFORMED SURVEILLANCE CLERK NOT TOISSUE SURVEIL LANCE TEST AS SCHEDULED. WHEN SITUATION WAS DISCOVERED, SURVEILLANCE WA S ISSUED AND COMPLETED. TEST RESULTS DISCLOSED NO PROBLEMS WITH THE SY TEM.

w-4

-r-.

-y3y-

,e'y Y

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 43 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION FT. ST. VRAIN-1 05000267 123080 FROM 1530 HOURS ON 12/30/80, UNTIL 0100 HOURS ON 12/31/80. WITH THE PLAN COOLANT RECIRC SYS + CONTROLS 81-001/03L-0 013081 T OPERATING AT APPROXINATELY 55% THERMAL POWER, THE OUTLET TEMPERATURE O INSTRUMENTATION + CONTROLS 036103 30-DAY F LOOP 2 PCRV COOLING WATER SYSTEM EXCEEDED 120 F.

THIS CONSTITUTES OPE CONTROLLER RATION IN A DECRADED MODE OF LCO 4.2.15B 2 IS REPORTABLE PER FORT ST. VR PERSONNEL ERROR AIN TECHNICAL SPECIFICATION AC 7.5.2(B)2.

NO ACCOMPANYING OCCURRENCE OR LICENSED & SENIOR OPERATORS PROBABLE CONSEQUENCES. NO EFFECT ON PUBLIC HEALTH & SAFETY SIMILAR R FOXBORO CO., THE EPCRT R0 80-46.

CAUSE FOR INCREASED TEMP. WAS COOLING WATER TEMP. CONTROLLER BEING SET A T A HIGHER THAN NORMAL SETPOINT FOLLOWING CALIBRATION. ON DISCOVERY OF HIGH TEMP, TEMP. CONTROLLER WAS RESET TO PROPER SETPOINT.

TEMP. DECREAS ED TO AN ACCEPTABLE VALUE BY 0100 HRS OH 12/31/80, 1 NO FURTHER DEGRADED MODE OF OPERATION WAS OBSERVED.

OPERATORS WILL BE REINSTRUCTED.

FT. ST. VRAIN-1 05000267 010681 DURING TEST, IT WAS FOUND THAT ONE CHANNEL OF ID HELIUM CIRCULATOR DRAIN ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 020331 MALFUNCTION WAS INOPERABLE.

THIS EVENT CONSTITUTES OPERATION IN A DEGR INSTRUMENTATION + CONTROLS 036057 30-DAY ADED MODE OF LCO 4.4.1, TABLE 4.4-3 AND 15 REPORTABLE PER FORT ST. VRAIN SWTTCH TECHNICAL SPECIFICATION AC 7.5.2(B)2.

NO EFFECT UPON PUBLIC HEALTH OR COMPONENT FAILURE SAFETY.

NO ACCOMPANYING OCCURRENCE. REDUNDANT CHANNELS WERE-AVAILABLE ELECTRICAL AND OPERABLE. NO SIMILAR REPORTS.

GENERAL ATOMIC CO.

CAUSE OF THE CHANNEL INOPERABILITY WAS A BLOWN FUSE IN SWITCH McDULE. M0 DEL Su-2D. NO CAUSE FOR THE FUSE BLOWING COULD BE FOUND. FUSE WAS REPLAC ED 4 CHANNEL RETURNED TO SERVICE. FUSE IS A 0.5 AMP MINIATURE 8 NAS OPER ATED WITH'HO PROBLEMS SINCE REPLACEMENT. NUCLEAR PROJECTS DEPT. REQUESTE D TO EVAL. CIR. DESIGN TO DETERMINE IF BLOWN FUSE INDICATION IS FEASIBLE FT. ST. VRAIN-1 05000267 010781 WHILE PERFORMING SURVEILLANCE TEST SR 5.4.1.3.3C-R. THE TRIP SETTING ON COOLANT RECIRC SYS + CONTROLS 81-005/03L-0 020381 PDIS-21177. BEARING WATER DIFFERENTIAL PRESSURE SUITCH, WAS FOUND BELOW INSTRUMENTATION + CONTROLS 036058 30-DAY THE LIMIT OF LCO 4.4.1 TABLE 4.4.3.

REPORTABLE PER TECH. SPEC. AC 7.5.

SWITCH 2(B)1 8 AC 7.5.2(B)2.

THE LCO SPECIFIES A TRIP SETTING OF EQUAL TO OR G COMPONENT FAILURE REATER THAN 475 PSID AND THE SWITCH TRIPPED AT 380 PSID.

NO EFFECT nN P INSTRUMENT UBLIC HEALTH OR SAFETY.

NO ACCOMPANYING OCCURRENCE. REDUNDANT SYSTEMS ITT-BARTON WERE AVAILABLE 1 OPERABLE. SIMILAR EVENTS REPORTED AS RO 79-60 1 79-11 ONE ITT BARTON MODEL 288A PRESSURE DIFFERENTIAL INDICATING SWITCH HAD A SETPOINT LESS CONSERVATIVE THAN LCO 4.4.1 DUE TO INSTRUMENT DRIFT.

THE SWITCH WAS ADJUSTED TO THE CORRECT SETPOINT AND RETURNED TO SERVICE. SU RVEILLANCE TEST SUCCESSFULLY COMPLETED.

FT. ST. VRAIN-1 05000267 010781 DURING ANNUAL TESTING 1 CALIBRATION, 6 0F THE 12 HELIUM CIRCULATOR SEAL COOLANT RECIRC SYS + CONTROLS 81-006/03L-0 020381 MALFUNCTION PRESSURE DIFFERENTIAL-SWITCH UNITS WERE DISCOVERED TO HAVE A INSTRUMENTATION + CONTROLS 036059 30-DAY TRIP POINT OUTSIDE LIMITS OF LCO 4.4.1 TABLE 4.4-3.

THESE ARE REPORTAB SWITCH LE PER FORT ST. VRAIN TECH. SPECS. AC 7.5.2CB)1 8 AC 7.5.2(B)2.

NO EFFE COMPONENT FAILURE CT ON PUBLIC HEALTH OR SAFETY. REDUNDANT SYSTEM AVAILABLE 8 OPERABLE. $I INSTRUMENT MILAR REFORTS ARE RO 77-47, FINAL & PRELIMINARY REPORTS RO 78-27, 79-32.

BARTON INSTRU CO., DIV 0F ITT 79-56, 80-07. 80-16, 80-20, 80-26, 80-34, 80-41, 80-51, AND 80-72.

ITT BARTON MODEL 289 PRESSURE DIFFERENTIAL SWITCHES FAILED TO ACTUATE AT TRIP POINT DUE TO DIRT ACCU *1ULATION IN ELECTRTCAL SWITCHES. AFFECTED $

WITCHES READJUSTED TO PROPER TRIP POINTS. SURVEILiANCE TEST SATISFACTOR ILY COMPLETED.

TRIP SETTINGS BEING CHECKED ON A MONTHLY BASIS.

REDESIG N OF SYSTEM BEING EVALUATED.

t MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 44 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION FT. ST. VRAIN-1 05000267 010881 WHILE EVALUATING PCRV COOLING WATER SYSTEM DATA IN PREPARATION OF A REPO COOLANT RECIRC SYS + CONTROLS 81-007/01T-0 020381 RTABLE OCCURRENCE. IT WAS DETERMINED THAT A VIOLATION OF AN LCO HAD OCCU COMPONENT CODE NOT APPLICABLE 036201 2-WEEK RRED RATHER THAN OPERATION IN A DEGRADED MODE AS WAS ORIGINALLY BELIEVED SUBCOMPONENT NOT APPLICABLE

. LOOP 2 INLET 3 OUTLET AVG. TEMP WAS < 100 F. FROM 0430 HRS ON 1/3/81 PERSONNEL ERROR UNTIL 1000 HRS ON=1/10/81 CONTRARY TO LCO 4.2.15(E) 2 REPORT ABL E PER T/

LICENSED 8 SENIOR OPERATORS S AC 7.5.2(B32. PREVIOUS OPERATION < 100 F WAS REPORTED IN 79-07 2 77-28 ITEM NOT APPLICABLE

. NO CONSEQUENCES OF THIS EVENT 4 NO EFFECT ON PUBLIC HEALTH 1 SAFETY.

CAUSE OF THE EVENT WAS FAILURE TO MAINTAIN SUFFICIENT HEAT INPUT TO THE COOLING SYSTEM FROM THE SURGE TANK HEATING COILS. LOW HEAT INPUT ALLOWED C00 LINO WATER SYSTEM TEMP TO DECREASE BELOW LCO LIMIT WHILE REACTOR WAS SHUTDOWN. ALL LICENSED OPERATORS WILL BE REINSTRUCTED IN PCRV COOLING W ATER SYSTEM OPERATION. EVAL OF EFFECTS ON TOP HEAD LINER MAT'l REQUESTED FT. ST. VRAIN-1 05000267 011581 DURING A MAINTENANCE SNUTDOHN PERIOD. OPERATIONS PERSONNEL CHLORINATED T CIRCULATING WATER SYS + CON 81-004/03L-0 021381 HE CIRCULATING WATER SYSTEM AND COLLECTED THE PLANT LIQUID EFFLUENT SAMP COMPONENT CODE NOT APPLICABLE 036200 30-DAY LE AS REQUIRED.

THE SAMPLE INDICATED THAT THE RESIDUAL CHLORINE WAS IN SUBCOMPONENT NOT APPLICABLE EXCESS OF THE LCO NR 1.1 LIMIT.

THIS IS REPORTABLE PER FORT ST. VRAIN T OTHER ECHNICAL SPECIFICATI0H AC 7.5.2(B)2.

NO EFFECT ON PUBLIC HEALTH OR SAFE NOT APPLICABLE TY.

NO ACCOMPANYING OCCURRENCE.

ITEM NOT APPLICABLE CHLORINE CONSUMPTION IN CIRCULATING WATER SYSTEM IS A COMPLEX PROCESS DE PENDENT UPON SrVERAL VARIA3LES. AFTER HIGH RESIDUAL CHLORINE LEVEL IN PL ANT LIQUID EFFLUENT, PLANT CHEMIST CHECKED CHLORINATION SYSTE1 & COULD N OT IDENTIFY ANY CAUSE FOR HIGH CHLORINE LEVEL. SUBSEQUENT CHLORINATION 3 SAMPLES DID NOT REVEAL A RECURRENCE OF THE HIGH CHLORINE LEVEL.

FT. ST. VRAIN-1 05000267 011781 DURING THE PERIOD FROM JANUARY 16, 1981 TO JANUARY 31, 1951. THE PLANT COOLANT RECIRC SYS + CONTROLS 81-009/03L-0 021381 WAS OPERATED IN A DEGRADED MODE OF LCO 4.2.10 ON FOUR OCCASICNS AND IN A COMPONENT CODE NOT APPLICABLE 036202 30-DAY DECRADED MODE OF LCO 4.2.11 ON ONE OCCASION. THESE EVENTS ARE REPORTABL SUBCOMPONENT NOT APPLICABLE E PER FORT. ST. VRAIN TECH. SPEC. AC 7.5.2(B)2. THERE ARE NO PROBADLE CO OTHER NSEQUENCES. THERE IS NO EFFECT ON PUBLIC HEALTH OR SAFETY. RELATED REPCR NOT APPLICABLE TS ARE: 77-36. 78-12, 78-18, 78-37 78-39, 79-01, 79-02. 79-24, 79-30 7

ITEM NOT APPLICABLE 9-45, 79-53. 80-11 80-19, 80-22, 30-25, 80-36, 80-59. 80-66,

  • 80-75.

IN ALL EVENTS, THE CAUSE WAS MOISTURE OUT-CASSING FROM THF. CORE GRAPHITE RESULTING FROM INCREASED POWER LEVEL. CORRECTIVE ACTION IN THE CASE OF LCO 4.2.10 DEGRADED MODE OPERATION WAS TO REDUCE AVERAGE CORE OUTLET TE MP BELOW 1200 F. MAKING THE LCO NOT APPLICABLE. PURIFICATION SYSTEM REM OVED MOISTURE TO CORRECT THE L CO 4.2.11 DEGRADED MODE OPERATION.

FT. ST. VRAIN-1 05000267 012081 DURING A SHUTDOUN MAINTENANCE PERIOD, THE INSTRUMENT PERSONNEL PERFORMED ENGNRD SAFETY FEATR INSTR SYS 81-005/03L-0 021981 THE PRIMARY COOL ANT PRESSURE SCRAM CALIBRATION AND FOUND THREE PRESSURE INSTRUMENTATION + CONTROLS 036233 30-DAY TRANSMITTERS WERE INDICATING LOW PRES $URE 8 COULD HAVE CAUSED PRIMARY C SENSOR / DETECTOR / ELEMENT 00LANT HIGH PRESSURE SWITCHES TO TRIP ABOVE LIMITS OF LCO 4.4.1.

TABLE 4 COMPONENT FAILURE

.4-1 THIS IS BEING REPORTED PER FORT ST. VRAIN TECH. SPEC AC 7.5.2(B)1 INSTRUMENT

& AC 7.5.2(B)2.

NO EFFECT ON PUBLIC HEALTH OR SAFETY.

NO EFFECT ON PL' GENERAL ATOMIC CO.

ANT OPERATION.

SIMILAR OCCURRENCES RO 79-57 AND RO 77-46.

LON PRESSURE SIGNALS WERE DUE TO INSTRUMENT DRIFT OF THE PRESSURE TRANSM ITTER. PRESSURE TRANSMITTERS WERE CALIBRATED 1 SURVEILLANCE TEST SUCCESS FULLY COMPLETED. ONCE A MONTH, ON A TEMPORARY BASIS. PRESSURE TRANSMITTE RS VOLTAGE OUTPUTS WILL BE CHECKED AGAINST REACTOR PRESSURE TO DETERf1INE IF FURTHER INSTRUMENT DRIFT IS OCCURRING.

?

?

F MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 45-PROCESSED DURING MARCH. 1981.FOR POWER REACTORS i

FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTIDH/

r CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION' 1

FT. ST. VRAIN-1 05000267 012081 DURING THE ANNUAL CALIBRATION OF THE PRIMARY COOLANT DEWPOINT NOISTURE M ENGNRD SAFETY FEATR INSTR SYS 81-010/03L-0 021981 OHITOR FLOW INSTRUMENTATION,-IT WAS DISCOVERED THAT FIVE OF THE SAMPLE F INSTRUMENTATION + CONTROLS 036234 30-DAY LOW CIRCUITS WERE OUT OF CALIBRATION EITHER BEFORE OR AFTER-THE CALIBRAT-i S ENSOR/DET ECTOR/ EL EMENT ION PROCEDURE WAS COMPLETED. THIS IS REPORTABLE PER FORT ST. VRAIN TECH-COMPONENT FAILURE

. SPEC. AC 7.5.2(B)1 AS' SETPOINTS BEING LESS CONSERVATIVE THAN REQUIRED INSTRUMENT BY THE LCO AND BY TECH. SPEC. AC 7.5.2(B)2 AS A DEGRADED MODE OF THE LCO j

HASTINGS RAYDIST

. NO SIMILAR REPORTABLE OCCURRENCES.

CAUSE OF FLOW TRANSMITTERS BEING OUT OF TOLERANCE WAS CHANGE OF THE INST l

RUMENT CHARACTERISTICS. THE CALIBRATION VALUES WERE REVISED AND THE FLO W TRANSMITTERS RECALIBRATED. THE ALARM SETPOINT FUNCTIONAL TEST VALUES-WERE ALSO CHANGED TO VERIFY FLOWS AS REQUIRED BY LOC 4.4.1 NOTE (T).

r FT. ST. VRAIN-1 05000267 012181 ON JANUARY 21, 1981.'WITH THE REACTOR OPERATING AT APPROXIMATELY 40% THE i

OTHER AUX SYSTEMS + CONTROLS

.81-011/03L-0 021981 RMAL POWER, THE LIQUID HITROGEN STORAGE TANK LEVEL WAS DETERMINED TO BE COMPONENT CODE NOT APPLICABLE 036235 30-DAY LESS THAN THE MINIMUM 650 GALLONS REQUIRED BY TECHNICAL SPECIFICATICHS.

SUBCOMPONENT NOT APPLICABLE DEGRADED MODE OF LCO 4.2.12.

REPORTABLE PER FORT ST. VRAIN TECHNICAL-SP l

OTHER ECIFICATION AC'7.5.2(B)2.

N0' ACCOMPANYING OCCURRENCE OR PROBABLE CONSEQ NOT APPLICABLE UENCE. NO EFFECT ON THE PUBLIC HEALTH OR SAFETY.

SIMILAR-0CCURRENCE RO i.

ITEM NOT APPLICABLE 80-39.

g SYSTEM USAGE AND LATE DELIVERY OF A SCHEDULED LIQUID HITROGEN DELIVERY R i

t ESULTED IN LIQUID HITROGEN STORAGE TANK LEVEL BEING LESS THAN REQUIRED B Y TECHNICAL SPECIFICATIONS. RECEIPT OF THE SCHEDULED DELIVERY RESTORED STORAGE TANK LEVELS TO ACCEPTABLE ~ VALUES. A SECOND LOAD WAS ORDERED AND DELIVERED,TO TOP OFF THE STORAGE TANK.

FT. ST. VRAIN-1 05000267 020351 ON TUESDAY, FEBRUARY 3, 1981 AT 1115 HOURS, IT WAS DETERMINED'THAT THE OTHER SYSTEMS 81-013/01T-0 021781 CONCENTR ATION OF TRITIUM IN AN UNRESTRICTED AREA FOLLOWING LIQUID WASTE -

OTHER COMPONENTS 036203 2-WEEK RELEASE 429. WHICH WAS MADE CH JANUARY.23 AND 24, 1981 EXCEEDED THE LIM SUBCOMPONENT NOT APPLICABLE IT SPECIFIED IN LCO 4.8.2(A).

REPCRTABLE PER FORT ST. VRAIN TECH. SPEC.

DESIGN / FABRICATION ERROR AC 7.5.2(A)2.

HO' ACCOMPANYING OCCURRENCE. HO EFFECT ON PUBLIC HEALTH DESIGN OR SAFETY.

REPORTABLE OCCURRENCE RO 80-52 AND REPORT ABLE OCCURRENCE RO.

l OTHER 80-67 DEAL WITH A RELATED SUBJECT AREA.

THE DESIGN OF THE FORT ST. VRAIN LIQUID WASTE DISCHARGE SYSTEM WAS INADE

- i QUATE TO AVOID PROBLEMS ARISING FROM :THE EXISTENCE OF AN OIL' SEPARATOR 0 -

l N THE LIQUID WASTE DISCHARGE LINE.

LIQUID WASTE RELEASES SUSPENDED. BY PASS INSTALLED AROUND THE OIL SEPARATORJ SDP CHANGED TO PROVIDE FOR USE t

0F BYPASS. FLUSH OF DEAD LEG PIPING.

H. B. ROBINSON-2 05000261

'121680 SPECIAL REPORT - THE ENGINE DRIVEN FIRE PUMP WAS REMOVED FROM SERVICE TO FIRE PROTECTION SYS + CONT ~

80-000/13X-0 011481 CHANGE THE PRIME MOVER FROM A PROPANE ENGINE'TO A DIESEL ENGINE PER HRC-IN3TRUMENTATION + CONTROLS 033752 OTHER REQUIREMENTS. BECAUSE OF THE CHANGE. THE OPERABILITY PERIODIC TEST HAD SWITCH TO BE DELAYED. WHEN THE OPERABILITY TEST WAS PERFORMED, THE ENGINE DRI-COMPONENT FAILURE VEN FIRE PUMP FAILED TO START.

ALTERNATE FIRE PUMP:WAS OPERABLE.

INSTRUMENT MERCOID CORP THE PUMP FAILED TO START BECAUSE OF A DEFECTIVE PRESSURE SWITCH ON THE F -

IRE PUMP' CONTROLLER. A NEW PRESSURE SWITCH WAS INSTALLED AND THE ENGINE DRIVEN FIRE PUMP WAS VERIFIED TO BE OPERABLE ON 12/24/80.

TIME LIMIT 0 F 7 DAYS FOR OPERABILITY TESTING PEh TECHNICAL SPECIFICATION 3.14.2.2.

i.

m. mm.

.m

.m.m.

m m-m--

-.m-~

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.-- -- d

l MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY

.PAGE 46-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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-COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION H.

B.

ROBINSON-2 05000261 010981 ON 1/9/81. WITH UNIT AT 100% POWER, IT WAS DETERMINED THAT OPERATION OF OTHR INST SYS REQD FOR SAFETY 81-001/01T-0 012381 UNIT ON 1/7/81, WITH RPI SYSTEM INPUT TO TURBINE RUNBACK & AUTO ROD WITH INSTRUMENTATION + CONTROLS 036214 2-WEEK DRAWAL DEFEATED 8 POWER RANGE CHANNEL N41 INPUT GUT-OF-SERVICE IS CONTRA SENSOR / DETECTOR / ELEMENT RY TO ASSUMPTIONS IN SAFETY ANALYSIS PREPARED DURING FUEL RELCAD SAFETY DEFECTIVE PROCEDURES EVALUATION. STILL THE PROBABILITY OF NOT SENSING A DROPPED ROD IS SMALL NOT APPLICABLE SINCE THREE OF THE POWER RANGE DETECTORS HERE OPERALLE. REPORTABLE PER T WESTINGHOUSE ELECTRIC CORP.

ECH. SPEC. 6.9.2.A(6). NO ADVERSE CONSEQUENCES RESULTED FROM CONDITION.

H.

B.

ROBINSON UNIT 2 FSAR & FUEL RELOAD SAFETY EVALUATION IDENTIFIED TH AT ROD DROP ANALYSIS ASSUMES THAT TURBINE RUNBACK OCCURS 8 THAT AUTO RCD WITHDRAWAL IS DEFEATED. NO PROCEDURES EXISTED TO PREVENT BYPASSING BOTH SIMULTANEOUSL

Y. PROCEDURE

S ARE BEING DEVELOPED TO PROHIBIT HAVING BOTH RPI BOTTOM INDICATION SYSTEM 3 1 POWER RANGE DETECTOR 005'SIMULTANECUSLY H.

B. ROBINS 0H-2 05000261 011381 A REVIEW OF SERV'CE WATER SYSTEM REVEALED A POTENTI AL UNtt0NITORED RELEAS STATION SERV WATER SYS + CONT 81-002/01T-0 012781 E PATH TO ENVIR0uMENT. THIS IS DUE TO LACK OF RADIATION MONITORING ON S INSTRUMENTATION + CONTROLS 036215 2-WEEK ERVICE WATER RETURN LINES FROM CONTAINMENT FOR 4 HVH MOTOR COOLERS (FAN CONTROLLER COOLER RETURHS ARE MONITORED). THEREFORE, AN UNMONITORED RELEASE PATH FO DESIGN / FABRICATION ERROR R ACTIVITY FROM CONTAINMENT COULD RESULT WHEN POST ACCIDENT CONTAINMENT DESIGN PRESS IS ABOVE SERVICE WATER SYSTEMS PRESS & THERE EXISTS A SYS LEAK INS OTHER IDE CONT AINITENT. REPORTABLE PER TECH. SPEC. 6.9.2.A.(9).

CONFIGURATION IS A RESULT OF ORIGINAL SYSTEM DESIGN. SERVICE WATER CYSTE M INSIDE CONTAINMLHT IS BEING INSPECTED DAILY FOR LEAKS. AS A FOLLOW-UP TO IE BULLETIN 80-24, SERVICE WATER SYSTEM TO CONTAINMENT, INCLUDING FAN COOLER PIPING CONFIGURATION, IS UNDERGOING A THOROUGH REVIEW. ADDITIONA L CORRECTIVE ACT13N IS EXPECTED AS A RESULT OF THIS REVIEW.

H. B.

ROBINS 0H-2 05000261 011481 ON JANUARY 24, 1981, IT WAS DETERMINED THAT BOTH CHANNELS OF HEAT TRACIN CHEM, VOL CONT + LIQ POISN SYS 81-003/01T-0 012881 G FOR BOTH BORIC ACID TRANSFER PUMPS WERE INOPERABLE CONTRARY TO TECH. S CIRCUIT CLOSERS / INTERRUPTERS 036216 2-WEEK PEC.

3.2.3.B.

A REDUCTICH OF REACTOR POWER WAS IMMEDIATELY COMMENCED. T CIRCUIT BREAKER HE SITUATION WAS CORRECTED APPROXIMATELY FIVE MINUTES AFTER ITS DISCOVER DEFECTIVE PROCEDURES Y AND THE UNIT WAS RETURNED TO FULL POWER.

NO ADVERSE CONSEQUENCES RESU NOT APPLICABLE LTED FROM THIS CONDITIvN.

THIS CONSTITUTES A REPORTABLE OCCURRENCE AS P WESTINGHOUSE ELECTRIC CORP.

ER TECHNICAL SPECIFICATION 6.9.2.A.2.

CONDITION WAS PRIMARILY CAUSED BY A MISLEADING STEP IN PROCEDURE USED TO TAKE "A" BORIC ACID TRANSFER PUMP 005 WHICH RESULTED IN DEENERGIZING OF HEAT TRACING TO BOTH BORIC ACID TRANSFER PUMPS. CONTRIBUTING TO CAUSE W AS FACT THAT OP FAILED TO VERIFY THAT ONLY DESIRED CIRCUIT WOULD BE DEEN ERGIZED PRIOR TO OPENING BREAKERS. REV PROC TO CLARIFY MISLEADING STEP.

H.

B. ROBINSON-2 05000261 011681 AT 1228 HRS., DURING NORMAL OPER ON 1-16-81, INDICATION OF LEAKAGE TO CC PROCESS SAMPLING SYSTEMS 81-004/03L-0 021381 W SYS PROMPTED A RCS LEAK RATE TEST WHICH VERIFIED 2.37 GPM LEAKAGE AT HEAT EXCHANGERS 036217 30-DAY 1244 HRS.

SUBSEQ INVESTIGATION REVEALED A LEAK PATH FROM PRESSURIZER T COOLER HROUGH PRES $URIZER LIQUID SPACE SAMPLE COOLER TO CCW SYS VIA A LEAKING T COMPONENT FAILURE UBE BUNDLE IN SAMPLE COOLER. SAMPLE LINE ISOL & LEAKAGE TERMINATED AT 12 NATURAL END OF LIFE 45.

LEAKAGE CONTRARY TO T.S.

3.1.5.2 8 REPORTABLE PER T.S.

6.9.2.B(2).

SENTRY EQUIPMENT CORP.

LEAKAGE TOTALLY CONTAINED WITHIN A CLOSED PLANT RADIDACTIVE SYSTEM.

ROOT CAUSE OF EVENT WAS S*MPLE COOLER TUBE BUNDLE LEAKAGE BELIEVED DUE'T 0 NORMAL OPERATIONAL WEAR.

IMMEDIATE CORRECTIVE ACTION TAKEN TO ELIMINA TE LEAKAGE WAS CLOSURE OF SAMPLE LINE ISOLATION VALVES.

SAMPLE COOLER T UBE DUNDLE WAS SUBSEQ REPLACED TO PREVENT RECURRENCE. ADDL EVAL OF EVEN T WILL BE CONDUCTED TO DETERMINE IF FURTHER CORRECTIVE ACTION IS APPROP.

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MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 47 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORY DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION H.

B. ROBINSON-2 05000261 0129?1 ON t/29/81, AT 0624 HOURS, A SPURIOUS SAFEGUARDS ACTUATION & REACTOR TRI-CHEM, VOL CONT + LIQ POISH SYS 81-005/01T-0 021281 P WERE RECEIVED FROM A HIGH STEAM FLOW SPIKE CAUSED BY TURBINE GOVERNOR PIPES, FITTINGS 036136 2-WEEK VALVE /E-H OIL PROBLEMS.-SHORTLY THEREAFTER. LETDOWN FLOW WAS RESTORED 3 LESS THAN 4 INCHES RCS PRESSURE BEGAN DECREASING WITH CONTAINMENT PRESSURE 2 DEW POINT INCR COMPONENT FAILURE EASING. UPON CONTAINTIENT ENTRY, A LETDONN LINE DRAIN VALVE (CVCS-200E) W MECHANICAL AS FOUND PARTIALLY OPENED 1 LEAKING THROUGH WITH ITS PIPE END-CAP MISSIN EBASCO SERVICES INC.

G.

LEAK RATE WITH LETDOUN UNISOLATED WAS ESTIMATED AT APPROX. 100 GPM.

VALVE CVCS-200E IS A NORMALLY CLOSED DRAIN VALVE WITH A PIPE CAP DN 00TL ET. PROBABLE CAUSE IS ATTRIBUTED TO VALVE VIBRATING OPEN & PIPE CAP. WHI' CH WAS SERVING AS A PRESSURE BOUNDARY, FAILING TO HOLD FOLLOUING FIRST S I. APPROX. 4500-6000 GALS.. OF WATER LEAKED TO CONTAINMENT SUMP DURING EV ENT.

HADDAM NECK-1 05000213 121780 DN 12/17/80, 1,023 FISH WERE IMPINGED ON THE INTAKE SCREENS; 1,004 SPOTT ULTIMATE HEAT SINK FACILITIES 8 ?-0 01/04X-0 011381 AIL SHINERS WITH 19 OTHER FISH REPRESENTING 6 OTHER SPECIES, 24 HOUR PER COMPONENT CODE NOT APPLICABLE 036236 OTHER IOD.

ON 12/18 8 12/19, 5,896 SPOTTAIL SHINERS WITH 80 OTHER FISH REPRES SUBCOMPONENT NOT APPLICABLE ENTING 7 SPFCIES WERE IMPINGED, (22 HOUR PERIOD). -SUBSEQUENT 24 HOUR C0 EXTERNAL CAUSE UNTS WERE 285, 436. 156 AND 394 FISH IMPINGED.

NOT APPLICABLE ITEM NOT APPLICABLE INCREASED IMPINGEMENT RATES OF SPOTTAIL SHINER $ HAVE BEEN NOTED IN PREVI 005 YEARS DURING THE DECEMBER-JANUARY PERIOD. SCHOOLING HABIT OF THIS F ISH PLUS FREEZING OF TRIBUTARIES MAY HAVE RESULTED IN AN UNEVEN SPATIAL DISTRIBUTION IN THE RIVER.

HUMBOLDT BAY 05000133 122280 WITH NUCLEAR UNIT SHUTDOWN, A BREAKER SUPPLYING ELECTRICAL POWER TO 1 0F AC ONSITE POWER SYS + CONTROLS 80-008/03L-0 012181 4 SCREEN WASH PUMPS IN ADJACENT FOSSIL UNITS FAILED. TIP OF A MOVABLE C CIRCUIT CLOSERS / INTERRUPTERS 033719 30-DAY ONTACT HAD BROKEN OFF. THESE PUMPS ARE BACKUP SOURCES OF COOLING WATER T CONTACTOR 0 SUPPRESSION POOL COOLER. ALL 4 PUMPS HAVE SAME TYPE BREAKER. THIS IS R COMPONENT FAILURE EPORTADLE UNDER T.

S.

IX.I.2.B.(2), & HAS BEEN SUBJECT OF LERS 80-0348 ELECTRICAL 0-04. THERE WERE NO ADVERSE EFFECTS FROM THIS EVENT; ALTERNATE COOLING S GENERAL ELECTRIC CO.

00RCES WERE AVAILABLE EVEN THOUGH NOT NEEDED BECAUSE OF LENGTH OF SHUTDW CONTACTS ARE BELIEVED TO HAVE FAILED FROM SHOCK OF REPEATED CYCLING (ERE AKER WAS OVER 22 YEARS OLD).

BREAKER IS G.E.

TYPE AK-1-15; CONTACT PART HUMBER 6372777G1, CONTACTS WERE REPLACED. FINAL ACTION IS TO REPLACE A LL SUCH BREAKERS WITH NEWER MODEL PRIOR TO POWER OPERATION.

INDIAN POINT-2 05000247 122380 DURING PERFORMANCE OF 1HE HYDRAULIC SNUBEER FUNCTIONAL TEST PROGRAM, IT-OTHER SYSTEMS 80-017/03L-0 012081 WAS DETERMINED THAT 5 0F THE FIRST 10 SNUBBERS TESTED DID NOT MEET THE A HANGERS, SUPPORTS, SHOCK SUPPRSS G33720 30-DAY CCEPTANCE CRITERIA ESTABLISHED BY CON EDISDN FOR LOCK-UP RATE AND BLEED.

SNUBBERS THE FUNCTIONAL TEST PROGRAM-IS CONTINUING. UPON COMPLETION OF THE PROG COMPONENT FAILURE RAM, THE RESULTS WILL BE EVALUATED FOR APPROFRIATE ACTION. RELATED EVEN MECHANICAL T: LER 78-9.

BERGEN-PATTERSON PIPE SUPPORT PRELIMINARY RESULTS OF THE HYDRAULIC SNUBBER FUNCTIONAL TEST PROGRAM IND ICATE SEVERAL BERGEN-PATTERSON HYDRAULIC SNUBBERS MODEL HSSA-3-6, DID H OT MEET THE FUNCTIONAL TEST ACCEPTANCE CRITERIA.

DEFECTIVE SNUBBERS WIL L BE REPLACED. A REVISED LER WILL BE SUBMITTED FOLLOWING TEST PROGRAM'C OMPLETION.

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i MAR 26,.1981 LER MONTHLY REPORT SORTED MY FACILITY-PAGE 48 PROCESSED DURING MARCH, 1981 FOR F0WER REACTORS i

FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

i' CAUSE SUBCCDE/ MANUFACTURER

' CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION f

INDIAN POINT-2 05000247 010681 DURING CYCLE 4/5 FUEL SHUFFLE OPERATIONS, GRID STRAP DAMAGE IN THE FORM REACTOR CORE 81-002/99X-0 011581 0F TORN OR MISSING CORNERS HAS BEEN OBSERVED ON A NUMBER OF FUEL ASSEMBL FUEL ELEMENTS 036204 OTHER IES.

NO DAMAGE TO THE FUEL CLADDING HAS BEEN IDENTIFIED.

SUBCOMPONENT NOT APPLICABLE COMPONENT FAILURE MECHANICAL WESTINGHOUSE ELECTRIC' CORP.

THE CAUSE OF GRID STRAP DAMAGE TO WESTINGHOUSE 15 X 15 (9 GRID) FUEL ASS EMBLIES AND CORRECTIVE ACTIONS REQUIRED ARE UNDER EVALUATION. A REVISED LER WILL BE SUBMITTED FOLLOWING COMPLETION OF THESE EVALUATIONS.

INDIAN POINT-2 05000247 011881 DURING A REFUELING MAINTENANCE OUTAGE. IT WAS NOTED IN THE COURSE OF CON OTHER COOLANT SUBSYS + CONTROL 81-004/03L-0 0Z1881 DUCTING SURVEILLANCE TEST PT-R35. INSERVICE VALVE TEST, THAT THE OPENING VALVES 036238 30-DAY TIME FOR ONE OF THE TWC POWER OPERATED RELIEF VALVES, PCV-456 WAS 2.5 GLOBE SECONDS LONGER THAN PERMITTED BY THE TEST ACCEPT ANCE CRITERI A.

THE REDU OTHER NDANT VALVE, PCV-455C, FUNCTIONED AS REQUIRED.

NOT APPLICABLE OTHER THE EVENT CAUSE AND REQUIRED CORRECTIVE ACTIONS ARE UNDER INVESTIGATION.

A REVISED LER WILL BE ISSUED FOLLOWING INVESTIGATION COMPLETION.

P INDIAN POINT-2 05000247 011981 DURING A REFUELING MAINTENANCE OUTAGE, IT WAS NOTED IN THE COURSE OF CON COOL SYS FOR REAC AUX + CONT 81-003/03L-0 021881

. DUCTING SURVEILLANCE TEST PT-R35.-INSERVICE VALVE TEST THAT THE SHUTOFF' VALVES 036237 30-DAY VALVE, NO. 822B, IN THE COMPONENT COOLING WATER RETURN FROM NO. 21 RHR GATE HEAT EXCHANGER. WOULD NOT FULLY OPEN (TECHNICAL SPECIFICATION 3.3).

THE OTHER REDUNDANT VALVE, NO. 822A, FUNCTIONED AS REQUIRED.

NOT APPLICABLE OTHER THE EVENT CAUSE AND REQUIRED CORRECTIVE ACTIONS ARE UNDER INVESTIGATION.

A REVISED LER WILL BE ISSUED FOLLOWING INVESTIGATION COMPLETION.

l INDIAN POINT-2 05000'247 012081 DURING A REVIEW OF THE VIDEO INSPECTION TAPE OF FUEL ASSEMBLY NO.

E-42,-

REACTOR CORE 81-005/01T-0 020381 IT WAS DETERMINED THAT THERE WAS AN APPARENT CLAD PERFORATION ON A FUEL.

FUEL ELEMENTS 036205 2-WEEK ROD WITHIN THE ASSEMBLY. THIS DEFECT IS NOT EXPECTED TO DEGRADE DURING SUBCOMPONENT NOT APPLICABLE FURTHER ASSEMBLY USE NOR WOULD IT BE EXPECTED TO RESULT IN SIGNIFICANT C COMPONENT FAILURE 00LANT ACTIVITY.

CORRUSION WESTINGHOUSE ELECTRIC CORP.

A PERFORATION OH A FUEL ROD WITHIN A WESTINGHOUSE 15 X 15 (9 GRID) FUEL ASSEMBLY H*S BEEN JUDGED T0-BE A HYDRIDE DEFECT. THE FUEL MANUFACTURER HAS REVIEUED THE DEFECT AND A DETERMINATION HAS BEEN MADE THAT NO CORREC-TIVE ACTION IS REQUIRED.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 49 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

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REPCRT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION INDIAN POINT-3 05000286 110980 SPECIAL REPORT - WHILE AT COLD SHUTDOWN, DURING' PERFORMANCE OF A RETEST EMERG CORE COOLING SYS + CONT 80-000/13X-0 120980 FOR A MODIFICATION TO THE ENGINEERED SAFETY FEATURES SYSTEM, TWO MESTING RELAYS 033751 OTHER HOUSE MG-6 RELAYS IN TRAIN "A" FAILED TO LATCH MECHANICALLY AFTER RECEIP CONTROL, GENERAL PURPOSE T OF THE SAFETY INJECTION ACTIVATION SIGNAL.

THIS CONDITION DOES NOT ON COMPONENT FAILURE ITS OWN PREVENT THE SATISFACTORY OPERATION OF THE ENGINEERED SAFETY FEA ELECTRICAL TURES SYSTEM AND IS THEREFORE NOT REPORTABLE UNDER THE TECHNICAL SPECIFI WESTINGHOUSE ELECTRIC CORP.

CATIONS.

THE LATCH MECHANISMS ASSOCIATED WITH RELAYS CB-1 AND V-1 (WESTINGHOUSE S TYLE MG-6, MODEL NO. 289B36A11) WERE FOUND TO BE OUT OF ADJUSTMENT. THE SE WERE THEN READJUSTED TO PROVIDE MECHANICAL LATCH-UP FEATURE UPON SAFE TY INJECTION ACTIVATION SIGNAL, AS REQUIRED. NO SIMILAR EVENTS HAVE BEE N REPORTED TO DATE.

INDIAN POINT-3 05000286 010881 WHILE OPERATING AT 100%, IT WAS IDENTIFIED THAT CUR SERVICE WATER RETURN CNTNMNT HEAT REMOV SYS + CONT 81-001/01T-0 012281 FROM THE CONTAINMENT FAN COOLER UNIT MOTOR COOLERS HAD NO DIRECT MEANS INSTRUMENTATION + CONTROLS 036206 2-WEEK OF RADIATION MONITORING. THIS COULD LEAD TO A LEAKAGE OF RADI0 ACTIVITY CONTROLLER UPON THE. SIMULTANEOUS OCCURRENCE OF A LOCA, A MOTOR COOLER LEAK AND A CD DESIGN / FABRICATION ERROR HTAINMENT PRESSURE BUILDUP.

iHIS ASPECT OF THE SERVICE WATER SYSTEM IS DESIGN NOT INCLUDED IN'THE SAFETY ANALYSIS AND THE POTENTIAL FOR A FUTURE PROBL OTHER EM UNDER TECH SPEC 6.9.1.7.1 EXISTS.

A RADIATION MONITOR HAS BEEN ATTACHED TO THE RETURN PIPE IN ORDER TO DET ECT POTENTIAL RADI0 ACTIVE LEAKAGE INTO THE SERVICE WATER SYSTEM. ANALYS IS IS CURRENTLY UNDERWAY TO IN3 TALL A MORE PERMANENT SOLUTION TO THIS SI TUATION, PERFORMANCE OF THE PLANT WAS NOT AFFECTED BY THIS INCIDENT. H 0 SIMILAR EVENT HAS BEEN REPORTED TO DATE.

INDIAN POINT-3 05000286 011181 THE MAGNITUDE OF A PLANNED RELEASE WAS HIGHER THAN EXPECTED. THE RELEAS LIQ RADIDACT WSTE MANAGMNT SYS 81-001/04L-0 012181 E BEGAN AT 0038 AND LASTED UNTIL 0249 (131 MIN.).

THE PEAK PERIOD WAS T PIPES FITTINGS 036239 30-DAY HE FIRST 10 MIN. WHEN ABOUT 25% OF THE ACTIVITY WAS RELEASED. ENVIRONME LESS THAN 4 INCHES NTAL TECH. SPEC. LIMIT OF APP. B SECTION 2.4.2.A WAS NOT EXCEEDED. TOTA COMPONENT FAILURE L NOBLE CAS RELEASED: 81.1 CI; 75.7% OF TECH. SPEC. LIMIT.

TOTAL IODINE MECHANICAL

-131 RELEASED: 4.48E-6 CI; 0.02% OF TECH. SPEC. LIMIT.

OTHER RELEASE OCCURRED WHILE PREPARING TO SAMPLE THE VOLUME CONTROL TANK.

.HE CAUSE WAS A LEAK IN A CONNECTING SAMPLING SYSTEM.

INDIAN POINT-3 05000286 012481 WHILE OPERATING AT 100 PERCENT POWER, AT 0915 HOURS, THE OUTPUT FROM BAT EMERG GENERATOR SYS + CONTROLS 81-002/03L-0 021881 TERY CHARGER NO. 32 WAS OBSERVED TO BE DROPPING. AS THE CHARGER WAS NO BATTERIES + CHARGERS 036207 30-DAY LONGER CAPABLE OF SUPPLYING DC BUS LOADS FROM THE BATTERY, IT WAS DECLAR SUBCOMPONENT NOT APPLICABLE ED INOPERABLE.

TECH. SPEC. 3.7.A.6 REQUIRES ALL 3 BATTERY CHARGERS TO B DESIGN / FABRICATION ERROR E OPERABLE WHEN THE REACTOR IS ABOVE COLD SHUTDOWN.

TECH. SPEC. 3.7.C.1 DESIGN REQUIRES DESCENT TO HOT SHUTDOWN UPON BATTERY CHARGER FAILURE. NO SIMI WESTINGHOUSE ELECTRIC CORP.

LAR EVENTS.

DESCEN1 TO HOT SHUTDOWN WAS INITIATED, IN ACCORDANCE WITH THE REQUIREMEN TS OF TECH SPECS.

AT 0930 HOURS THE VOLTAGE AND CURRENT CONTROLLER PC B OARD NO. S-1492A10G03 WAS REPLACED. BATTERY CHARGER NO. 32 WAS THEN DEC' LARED OPERABLE, AND THE PLANT RETURNED TO 1C0 PERCENT POWER.

MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 50 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMP 9NENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION JOSEPH M.

FARLEY-1 05000348 110880 ON 11/08/80 DURING PERFORMANCE OF FHP-1-STP-608.0 (MAIN STEAM LINE SAFET MAIN STEAM SUPPLY SYS + CONT 80-079/03L-0 012381 Y VALVE TEST) MAIN STEAM SAFETY VALVE Q1N11V010B FAILED TO MEET THE TECH VALVES 033671 30-DAY NICAL SPECIFICATION 3.7.1.1 LIFT SETTING REQUIREMENTS (1101 PSIG ACTUAL-GLOBE VS 1088 PSIG + 1 '4 REQUIRED). UPON DISCOVERY OF THE OUT OF SPEC. CONDITI OTHER ON, THE VALVE WAS IMMEDIATELY ADJUSTED AND RETURNED TO SERVICE. HEALTH /

HOT APPLICABLE SAFETY OF THE PUBLIC WERE NOT AFFECTED.

DRESSER INDUSTRIES, INC.

THIS INCIDENT IS ATTRIBUTABLE TO SETPOINT DRIFT.

L ATE SUEMITT AL OF THIS LER IS DUE TO A PROCEDURAL INADEQ. WHICH FAILED TO ADEQ. SPECIFY IMMEDI ATE NOTIFICATION OF OUT OF SPEC. CONDITION TO OPER. PERSONNEL.

THIS LAC K OF NOTIFICATION WAS DISCOVERED BY A QA AUDIT CN 12/30/80.

A REVISION WILL BE MADE TO SUR

V. PROCEDURE

TO CLEARLY IDENTIFY NOTIFICATION REQMTS.

JOSEPH M.

FARLEY-1 05000348 122580 AT 2350 ON 12/25/80, WITH THE PRESSURE VESSEL HEAD REMOVED FOR REFUELING RESIDUAL HEAT REMOV SYS + CONT 80-080/03L-0 012881 THE LOOP SUCTION VALVE FOR "B" TRAIN RHR CLOSED WHICH RESULTED IN THE WALVES 033672 30-DAY OPERATING "B" TRAIN RHR BECOMING INOPERABLE.

TECH. SPEC. 3.9.8 REQUIRES GATE AT LEAST ONE RHR LOOP TO BE IN OPERATION.

TECH. SPEC. 3.9.8 ACTION STA OTHER TEMENT REQUIREMENTS WERE MET.

HEALTH / SAFETY OF THE PUBLIC WERE NOT AFFE NOT APPLICABLE CTED BY THIS OCCURRENCE.

COPES-VULCAN, INC.

SUCTION VALVE WAS CLOSED BY A SIGNAL FROM REACTOR COOLANT SYS PRESSURE T RANSt1ITTER LOOP.

LOOP WAS BEING DE-TERMINATED FROM ITS ELECT. PENETRATI ON WHILE ENERG. IN ORDER TO REPAIR PENETRATION WHEN INSTRUMENT LEADS WER.

E INADVERTENTLY SHORTED RESULTING IN CLOSING SIGNAL.

VLV WAS REOPENED &

RHR PUMP IB WAS RETURNED TO SERVICE AT 2355 ON 12/25/80.

JOSEPH M.

FARLEY-1 05000348 011681 AT 1429 OH 1-16-81, RHR FLOW WAS LOST AS A RESULT OF A LOSS OF POWER TO RESIDUAL HEAT REMOV SYS + CONT 81- 0 01/ 0 3 L-0 021281 THE 1A RHR PU"F.

(A LOSS OF POWER TO START-UP TRANSFORMER 1A DE-ENERGI CIRCUIT CLOSERS /IETERRUPrERS 036102 30-DAY ZED 416 0V. BUS 1F WHICH IN TURN CAUSED A LOSS OF POWER TO THE RHR PUMP).

CIRCUIT BREAKER TECH. SPEC.

3.4.1.

IN PART, REQUIRES AT LEAST ONE RC LOOP TO BE IN OPER PERSONNEL ERROR ATION WITH AN ASSOCIATED RC OR RHR PUMP.

TECH. SPEC. 3.4.1 ACTION STATE MAINTENANCE 8 REPAIR f ERSONNEL MENT REQUIREMENTS WERE MET.

HEALTH / SAFETY OF THE PUBLIC WERE NOT AFFECT OTHER ED.

POWER WAS LOST AS A RESULT OF A FEEDER BREAKER TO START-UP TRANSFORMER 1 A OPENING. NO RELAY TARGETS WERE ACTUATED ON START-UP TRANSFORMER SUPPLY BREAKER TO INDICATE REASON FOR TRIP. MAINT. ACTIVITY ONGOING IN VICINIT Y OF RELAY PROBABLY CAUSED BREAKER TO TRIP. DIESEL GENERATOR 1-2A ENERGI ZED BUS 1F 8 RHR PUMP WAS RESTARTED AT 1430 ON 1/16/8 1 JOSEPH M.

FARLEY-1 05000348 020281 AS A RESULT OF INSPECTION ACTIVITIES ON THE J. M. FARLEY NUCLEAR PLANT U AC ONSITE POWER SYS + CONTROLS 81-002/01T-0 020681 HIT 2. A GENERIC DEFICIENCY WAS IDENTIFIED WITH BROKEN PUFFER TUBES ON 4 CTRCUIT CLOSERS / INTERRUPTERS 036055 2-WEEK 160V CIRCUIT BREAKERS. INVESTIGATION HAS REVEALED THAT FOLLOWING A TUBI CIRCUIT BREAKER NG BREAK, THE TUBING INNER SUPPORT SPRING COULD MIGRATE FROM WITHIN THE COMPONENT FAILURE TUBE TO ENERGIZED AREAS OF THE BREAKER CAUSING A PHASE TO GROUND FAULT.

LLECTRICAL THIS INFORMATION IS BEING SUBMITTED IN ACCORDANCE WITH TECH. SPEC.

6.9.

AliIS CHALMERS 1.8.I AND 10 CFR 21.

THF 'UFFER TUBES BREAK AS A RESULT OF MATERIAL AGING.

AS A PERMANENT CD RRECTIVE ACTION, PUFFER TUDES OF A DIFFERENT MATERIAL WILL BE USED TO RE PLACE ALL PUFFER TUBES.

THE REPLACEMENT TUBES WILL BE EQUIPPED WITH COM PRESSION DEVICES TO RETAIN THE INNER SUPPORT SPRING IN THE EVENT OF TUBE FAILU?E.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE St PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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RFPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBC00E/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION JOSEPH M.

FARLEY-1 05000348 020281 AT 1730 ON 2/2/81. RADIATION MONITOR R25B (FUEL STORAGE POOL AREA GASE00 AIRBORNE RADIOACT MONITOR SYS 81-003/03L-0 022381 S ACTIVITY - VENTILATION SYSTEM ISOLATION) WAS DECLARED INOPERABLE DUE T PUMPS 036196 30-DAY 0 THE DRIVE BELT BREAKING.

TECH. SPEC. SECTION 3.3.3.1 AND TABLE 3.3.6 VANE TYPE REQUIRES A MINIMUM OF TWO RADIATION MONITOR CHANNELS TO BE OPERABLE FOR COMPONENT FAILURE THE FUEL STORAGE AREA.

TECH. SPEC. 3.3.3.1 ACTION STATEMENT REQUIREMENT MECHANICAL S WERE MET.

A SIMILAR OCCURRENCE WAS REPORTED IN LER 80-004/03L-0.

HEA VICT0REEN INSTRUMENT DIV.

LTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

R258 WAS DECL ARED INOPERABLE DUE TO ITS-DRIVE BELT BREAKING. THE BELT W AS REPLACED AND R25B WAS RETURNED TO SERVICE AT 1300 OH 2/5/81.

%EWAUNEE-1 05000305 121280 WITH THE FACILITY AT 100% POWER, DURING THE TESTING OF 1B DIESEL GENERAT EMERG GENERATOR SYS + CONTROLS 80-042/03X-2 021281 OR (D/G), THE AIR START MOTORS FAILED TO DISENGAGE AFTER THE D/G STARTED VALVES 033512 OTHER AND ALSO WHEN THE D/G WAS SHUTDOWN.

1A D/G WAS TESTED OPERABLE AND IB GLOBE D/G WAS TAKEN OUT-OF-SERVICE PUTTING THE FACILITY UNDER LCO TECH. SPEC.

COMPONENT FAILURE 3.7.B.2 AND THUS REPORTABLE PER TECH. SPEC. 6.9.2.B.(2).

THERE WAS NO E CORROSION FFECT ON PUBLIC SAFETY OR PLANT OPERATION.

WESTERN ENGINE CO.

CORROSION OF THE VALVE STEM AND DISC. FROM MOISTURE IN THE AIR SUPPLY. C AUSED VALVE TO STICK OPEN RESULTING IN A FAILURE OF AIR START MOTORS TO DISENGAGE. CORRODED PARTS WERE REPLACED 8 D/G RETURNED TO SERVICE WITHIN TIME LIMITS OF TECH. SPEC.

3.7.B.2.

DESIGN CHANGE IS IN PROGRESS TO IN STALL AIR DRIERS IN D/G AIR START SYSTEM. NO FURTHER CORRECTIVE ACTIONS.

KEWAUNEE-1 05000305 121680 DURING A REVIEW OF EQUIPMENT QUALIFICATIONS, AS REQUESTED BY IE BULLETIN CHEM. VOL CONT + LIQ POISN SYS 80-041/01X-2 020681 79-01B, THREE LIMIT SWITCHES HAVE BEEN IDENTIFIED THAT ARE NOT SEALED I INSTRUMENTATION + CONTROLS 033430 OTHER NSTALLATIONS. AND MAY BEC6FE SUBMERGED POST-LOCA.

IN A SUBMERGED CONDIT SWITCH ION THESE SWITCHES COULD DE SUSCEPTIBLE TO FAILURE POSSIBLY RESULTING IN DESIGN / FABRICATION ERROR AN INADVERTENT OPENING OF LETDOWN ISOLATION VALVES LD-4A/4B/4C UPON RES DESIGN ET OF CONTAINMENT ISOLATION. EVENT IS REPORTABLE PER T.S. 6.9.2.A(9) &

NAMCO CONTROLS IEB 79-01B.

NO EFFECT ON PUBLIC SAFETY OR PLANT OPERATION.

AT DATE OF INSTALLATION, REQMT TO OPER IN A SUBMERGED CONDITION WAS NOT EVIDENT. TO ASSURE PROPER OPER OF ABOVE NAMED VLVS. CONTROL OPER HAVE B EEN INSTRUCTED TO PLACE CONTROL SWITCHES FOR LD-4A/4B/4C IN CLOSED POSIT IDH PRIOR TO RESETTING CONTAINMENT ISOL.

LIMIT SWITCHES WILL BE PROPERL Y SEALED DURING FJRST OUTAGE OF SUFFIC. DURATION AFTER RECEIPT OF EQUIP.

%EWAUNEE-1 05000305 122380 WHEN ATTEMPTING TO RECIRCULATE BORIC ACID (BA) STORAGE TANKS PRIOR TO SA CHEM, VOL CONT + LIQ POISH SYS 80-043/03L-0 012281 MPLING, tA BA TRANSFER PUMP MOTOR TRIPPED ON OVERLOAD.

TECH SPEC 3.2.C.

PUMPS 033576 30-DAY 2 ALLOWS ONE BA TRANSFER PUMP OUT OF SERVICE 24 HOURS, PUTTING PLANT UND CENTRIFUGAL ER AN LCD REPORTABLE PER TECH. SPEC. 6.9.2.(B)2.

THIS EVENT IS SIMILAR COMPONENT FAILURE TO THAT REPORTED IN LER-80-043.

THREE METHODS OF SUPPLYING BORATED WAT MECHANICAL ER TO REACTOR CORE WERE STILL AVAILABLE.

THERE WAS NO EFFECT ON PUBLIC GOULDS PUMPS INC.

SAFETY OR FLANT OPERATION.

PUMP MOTOR TRIP ON OVERLOAD HAS BEEN ATTRIBUTED TO BA CRYSTALLIZATION IN SEALS DURING PERIODS OF NON-USE.

SEAL DEGRADATION IS EVIDENT BY ABNOR MAL SEAL LEAKAGE.

LEAKAGE DOES NOT PROHIBIT USE OF PUMP; PUMP WAS RESTA RTED AND RETURNED TO SERVICE WITHIN TIME LIMIT OF TS 3.2.C.2.

PUMP SEAL S WILL BE REPLACED BY 2-1-81 NO FURTHER CORRECTIVE ACTIONS ARE REQUIRED

i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 52 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS 4

FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTICH KEWAUNEE-1 0500030$

122980 THE RCS 02 SAMPLE TEST WAS PERFORMED ONLY TWICE DURING THE WEEK ENDING 1 REAC COOL CLEANUP SYS + CONT 80-044/03L-0 012881 2-26-80.

THIS IS NOT IN ACCORDANCE WITH THE SURVEILLANCE REQUIREMENTS 0 COMPONENT CODE NOT APPLICABLE 033721 30-DAY F TECH. SPEC. 4.1.B 8 TABLE T.S. 4.1-2 WHICH REQUIRES SAMPLE TEST TO BE l

SUBCOMPONENT NOT APPLICABLE PERFORMED THREE TIMES PER WEEK, MININUM, WITH A MAXIMUM OF FOUR DAYS BET PERSONNEL ERROR WEEN SAMPLE TESTS. MAXIMUM OF FOUR DAYS BETWEEN SAMPL E TESTS WAS NOT EX OTHER CEEDED.

SUBSEQUENT SAMPLE TESTS SHOWED 02 CONCENTRATIONS WITHIN T.S.

LI ITEM NOT APPLICABLE MITS.

THERE WAS NO EFFECT ON PUBLIC SAFETY OR PLANT OPERATION.

FAILURE TO PERFORM SAMPLE TEST HAS BEEN ATTRIBUTED TO LACK OF SUFFICIENT INSTRUCTION, TO LAB PERSONNEL, BY CHEMISTRY SUPERVISION: THIS IS REPORT ABLE AS AN INADEQUACY IN IMPLEMENTATION OF PROCEDURAL CONTROLS (T.S. 6.9

.2.B.(3)).

PROCEDURE WAS REVIEWED WITH LAB PERSONNEL UITH EMPHASIS ON R EQUIRED ANALYSIS. NO FURTHER CORRECTIVE ACTION IS REQUIRED.

i KEWAUNEE-1 05000305 010781 DURING TESTING OF CONTAINMENT FAN COIL.(F/C) SERVICE WATER LOW FLOW ALAR CNTNMNT HEAT REMOV SYS + CONT 81-001/03L-0 020681 M.

THE DISCHARGE VALVE ON 1B F/C UNIT WOULD NOT OPEN ON DEMAND.

BY DEFI-UALVE OPERATORS 036060 30-DAY NITION THIS F/C UNIT WAS NOT OPERABLE, PLACING THE FACILITY UNDER LCO TE ELECTRIC MOTOR - AC CH. SPEC. 3.3.B.2.A (ONE F/C UNIT MAY BE OUT OF SERVICE FOR UP TO SEVEN COMPONENT FAILURE DAYS) AND THUS REPORTABLE PER TECH. SPEC. 6.9.2.B.(2).

THE THREE REMAIN MECHANICAL ING F/C UNITS WERE OPERABLE. THERE WAS NO EFFECT ON PUBLIC SAFETY OR PL LIMITORQUE CORP.

ANT CPERATION.

THE FAILURE OF THE MOTOR OPERATOR HAS BEEN ATTRIBUTED TO A LOOSE TORQUE ADJUSTMENT SWITCH.

THE VALVE WAS MANUALLY OPENED TO PLACE THE F/C UNIT-BACK IN SERVICE. THE SWITCH WAS READJUSTED AND THE OPERATOR TESTED SATI SFACTORILY WITHIN THE SEVEN DAY TIME LIMIT.

THIS IS CONSIDERED AN ISOLA TED OCCURRENCE REQUIRING NO FURTHER CORRECTIVE ACTION.'

KEWAUNEE-1 35000305-. 021281 ROM SERVICE, 1B D/G FAILED TO START.

T.S.

3.7.B.2 ALLOWS ONE D/G TO BE 011381 WHILE TESTING 1B DIESEL GENERATOR (D/G) OPERABLE FOR REMOVAL OF.1A D/G F EMERG GENERATOR SYS + CONTROLS 81-002/03L-0 MOTORS 036110 30-DAY OUT OF SERVICE FOR UP TO SEVEN DAYS PROVIDED THAT THE OTHER D/G IS TESTE SUBCOMPONENT NOT APPLICABLE D OPERABLE ON A DAILY B ASIS.

ONE TRAIN OF EMERGENCY POWER WAS-STILL AVA COMPONENT FAILURE Ti. ABL E.

THIS IS REPORTABLE PER T.S. 6.9.2.B.(2).

THERE WAS NO EFFECT 0 CORROSION N PUBLIC SAFETY OR PLANT OPERATION.

WESTERN ENGINE CD.

WATER IN AIR SUPPLY PREV AIR START MOTORS FROM ENGAGING PROPERLY.

1A D/

G WAS IMMED VEP1FIED OPERABLE 8 1B D/G TAKEN OUT OF SERVs CHECK VLV WAS kEPLACED

  • SOLEHOID 8 RELAY VLVS WERE CLEANED 8 REINSTALLED. EVENT SIMI LAR TO 80-042.

A DESIGN CHANGE IS IN PROGRESS TO INSTALL AIR DRIER $ IN D/G AIR START SYSTEM. NO FURTHER CORRECTIVE ACTIONS ARE ANTICIPATED.

KEWAUNEE-1 05000305 012281 DURING TESTING OF VALVE CC4003 (COMPONENT COOLING WATER INLET-TO 1B RESI l

COOL SYS FOR REAC AUX + CONT 81-003/03L-0 022088 DUAL HEAT EXCHANGER) FOLLOWING THE REINSTALLATION OF THE MOTOR OPERATOR.

UALVE OPERATORS o 6240 30-DAY THE SUPPLY THERMAL OVERLOADS TRIPPED. THIS PUT THE FACILITY UNDER LCO ELECTRIC MOTOR - AC-TECHNICAL SPECIFICATION 3.3.A.2.C (ONE RHR HEAT EXCHANGER MAY BE OUT OF PERSONNEL ERROR SERVICE FOR UP TO 48 HOURS) AND THUS IS REPORTABLE PER TECH. SPEC. 6.9.2 MAINTENANCE 8 REPAIR PERSONNEL

.B.2.

SINCE THIS VALVE WAS MANUALLY OPERABLE, 8 SECOND RHR HEAT EXCHANG LIMITORQUE CORP.

ER WAS AVAILABLE, THERE WAS NO EFFECT OH PUBLIC SAFETY / PLANT OPERATION.

THE MOTOR OPERATOR FAILURE HAS BEEN ATTRIBUTED TO A WIRING ERROR BY A PL ANT ELECTRICIAN, WHICH RESULTED IN THE THERMAL OVERLOADS TRIPPING. THE WIRING FAULT WAS IDENTIFIED AND CORRECTED, AND THE VALVE /0PERATOR TESTED

-SATISFACTORILY.

THE PROCEDURE WAS REVIEWED WITH THE ELECTRICIAN. NO F URTHER CORRECTIVE ACTION IS NECESSARY.

i

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 53 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPONEHT/

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION MAINE YANKEE 05000309 060480 DURING 1980 REFUELING OUTAGE. A REACTOR VESSEL WALL SURVEILLANCE CAPSULE REACTOR VES. + APPURTENANCES 80-014/01X-1 021381 WAS REMOVED FROM THE REACTOR & SENT TO BATTELLE COLUMBUS LABORATORIES F VESSELS. PRESSURE 033749 OTHER OR ANALYSIS. RESULTS OF THAT ANALYSIS INDICATE A CONSIDERABLY HIGHER SH REACTOR VESSEL IFT OF RT(NDT) THAN WAS ORIGINALLY PREDICTED. THE NEUTRON FLUENCE FOR T DEFECTIVE PROCEDURES HE CAPSULE AS ANALYZED WAS 6.9E18 N/SQ. CM. (E) 1 MEV).

THIS IS A FACTO NOT APPLICABLE R OF 2.3 HIGHER THAN ORIGINAL ESTIMATE OF 3.0E18 N/SQ. CM. THIS RESULTS OTHER IN MORE LIMITING CURVES RELATIVE TO REACTOR VES HEATUP & C00LDOWN RATES.

BATTELLE UTILIZED COMPUTER CODE DDT 3.5, UHICH USES TWO-DIMENSIONAL GEOM ETRY, 8 DELAY COMPUTER CODE WAS USED TO COMPLETE CALCULATIONS. ORIGINAL ANALYSIS UTILIZED A SIHGLE DIMENSIONAL CODE COMBIHATION OF ANISN-SHADRA C.

DIFFERENCE COULD BE DUE TO CALCULATION PROGRAMS AND/OR ERRORS IN ORI GINAL METHODOLOGY. NEW HEATUP/COOLDOWN CURVES & T.S.

CHANGES BEING FREP.

MILLSTONE-2 05000336 010181 DURING ROUTINE POWER OPERATION, THE OUTPUT FROM STEAM GENERATOR DIFFEREN REACTOR TRIP SYSTEMS 81-001/03L-0 012881 TIAL PRESSURE TRANSMITTER, PDT-121B, FAILED LOW CAUSING A LO4 FLOW TRIP INSTRUMENTATION + CONTROLS 036035 30-DAY ON CHANNEL "B" 0F THE REACTOR PROTECTION SYSTEM.

THE CHANNEL WAS BYPAS$

SWITCH ED AND THE UNIT OPERATED FOR 8 HOURS UNDER THE ACTION STATEMENT OF TECHN COMPONENT FAILURE ICAL SPECIFICATION 3.3.1.1..

SIMILAR EVENTS: NONE ELECTRICAL METER DEVICES CD.

A DIRTY KNIFE SWITCH CONTACT CAUSED AN OPEN CIRCUIT BETWEEN THE DIFFEREN TIAL PRESSURE TRANSMITTER AND THE LOW FLOW TRIP BISTABLE RESULTING IN TH E CHANNEL TRIP.

THE SWITCH CONTACTS WERE CLEANED AND THE SWITCH WAS RET URNED TO SERVICE. THE SWITCH WAS MANUFACTURED BY METER DEVICES CO.

MILLSTONE-2 05000336 010281 DURING A PLANT C00LDOWN, COHTAINMENT PRESSURE DECREASED BELOW NEGATIVE 1 CNTNMNT HEAT REMOV SYS + CONT 81-004/03L-0 013081 2 INCHES HG. CONTAINMENT COOLING WAS BEING SUPPLIED BY THREE CAR FANS IN VESSELS. PRESSURE 036063 30-DAY FAST WITH HORMAL AND EMERGENCY RBCCW COOLING. CONTAINMENT TEMPERATURE CONTAINMENT /DRYWELL DROPPED FROM 103 TO 90 DEGREES F.

THE PLAMT WAS OPERATED IN ACCORDANCE PERSONNEL ERROR WITH TECHNICAL SPECIFICATION ACTION STATEMENT 3.6.1.4.

THERE ARE NO SIM LICENSED 8 SENIOR OPERATORS ILAR INCIDENTS.

BECHTEL CORP.

CONTAINMENT COOLING WAS NOT CHANGED TO MATCH DECREASING HEAT LCADS DURIN G THE C00LDOWN.

CAR FANS WERE SHIFTED TO SLOW WITH NORMAL RBCCW FLOW ON LY.

CONT AINMENT PRESSURE INCREASED ABOVE NEGATIVE 12 INCHES HG WITHIN 1 0 MINUTES. OPERATORS HAVE BEEN CAUTIONED TO BALANCE CONTAIHMENT COOLING WITH HEAT LOADS DURING HEATUPS AND COOLDOWNS MILLSTOHE-2 05000336 010281 DURING A DIESEL GENERATOR (D/G) RESPONSE TO A LOSS OF NORMAL POWER, A D/

STATION SERV WATER SYS + CONT 81-005/03L-0 013081 G SERVICE WATER FLANGE LEAKED.

THE LEAK W'.TTED THE ENGINE CAUSING A DIE PIPES, FITTINGS 036172 30-DAY SEL TRIP.- THE LEAK ALSO WETTED THE AMPHEN0L PL JG CN THE WOODWARD GOVENO 6 TO 10 INCHES R CAUSING THE PLUG TO FAIL.

THE FACILITY OPERATED IN ACCORDANCE WITH TE DESIGN / FABRICATION ERROR CHNICAL SPECIFICATION ACTION STATEMENT 3.8.1.1.D FOR APPROXIMATELY 6 HOU CONSTRUCTION / INSTALLATION RS.

AT WHICH TIME OPERABILITY OF OTHER D/G WAS DEMONSTRATED & PLANT OPE FLAGG, C.

N.

CO.

R WITHIN ACTION STATEMENT 3.8.1.1.A UNTIL COLD SHUTDOWN WAS ACHIEVED.

DURING A RECENT:0UTAGE THE D/G SERVICE WATER PIPING WAS MODIFIF9. THE F AILED GASKET HAD BEEN IMPROPERLY COMPRESSED CAUSING THE GASKET TO BE BLO WN-0UT DURING THE SUDDEN PRESSURE SURGE WHEN THE D/G WAS STARTED. THE G ASKET AHD AMPHEN9L PLUG WERE REPLACED. A VERIFICATION OF PROPER COMPRES SION WAS MADE ON THE REMAINING FLANGES IN THE D/G ROOMS.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE S4 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TY?E CAUSE DESCRIPTION MILLSTONE-2 05000336 010381 DURING A ROUTINE CONTAINMENT INSPECTION A LEAK WAS FOUND AT A SOCKET WEL ENERG CORE COOLING SYS + CONT 81-002/03L-0 013081 D IN THE SAFETY INJECTION TEST HEADER NEAR RELIEF VALVE 2-51-466.

INVES PIPES FITTINGS 036061 30-DAY TIGATION IDENTIFIED A SMALL CRACK-IN THE TOE OF THE WELD.

SIMILAR PEPOR LESS THAN 4 INCHES 15: 80-27 (8'25/80), 77-37 (9/t7/77), 77-10 (3/21/77).

COMP 0HENT FAILURE METALLURGICAL OTHER LOW CYCLE. HICH STRESS FATICUE CRACKING CAUSED BY IMPROPER SETTING OF RE LIEF VALVE 2-51-466.

THIS RELIEF VALVE WAS FOUND SET AT 100 PSIG VICE I TS PROPER SET'ING OF 48S PSIG.

THIS CAUSED REPEATED OPENING / CLOSING CYC LES WITH ATTENDANT PIPING VIBRATION. THE VALVE WAS RESET AND THE AFFECT ED PIPINO REPLACED.

MILLSTONE-2 0S0003$4 010681 DURING A ROUTINE INSPECTION, MAIN STEAM LINE SNUBBER 413019 WAS FOUND WI MAIN STEAM SUPPLY SYS + CONT 81-003/03L-0 013081 TH NO VISIBLE FLUID LEVEL.

AT THE TIME OF THE DISCOVERY THE PLANT WAS I HANGERS,5UPPORTS,$ HOCK SUPPRSS 036062 30-DAY N A LOLD SHUIDOWN CONDITION. THE SNUBBER IS AN ITT GRINNELL, FIG. 200, SHUBBERS 4 INCH BORE BY S INCH STROKE UNIT.

SIMILAR LERS 77-47, 79-28, 80-12.

DESION/ FABRICATION ERROR CONS 1RUCTION/ INSTALLATION ITT GRINNELL THE PLASTIC FLUID RESERVOIR DEFORMED DUE TO OVERHEATING WHEN INSULATING PADS WERE INSTALLED OVER A PORTION OF THE SNUBBER AFTER RELOCATION OF TH E HANGER AND SHUBBER DURING A RECENT OUTAGE.

THE DEFECTIVE SHUBBER UAS REPLACED. AN INSPECTION WAS PERf 0RMED VERIFYING ADDITIONAL HANGER WORK HAS NOT CAUSED SIMILAR OCCURRENCES.

MILLSTONE-2 05000336 010881 DURING A ROUTINE PLANT HEATUP, AN UNIDENTIFIED LEAKAGE IN EXCESS OF THAT COOLANT RECIRC SYS + CONTROLS 81-006/03L-0 020681 ALLOWED BY TECHNICAL SPECIFICATIONS EXISTED BECAUSE 2-RC-1S AND 2-RC-30.

VALVES 036111 30-DAY NITROGEH ISOLATION VALVES TO THE PRESSURIZER, WERE LEFT OPEN.

THE PLA GLOBE NT WAS OPERATED IN ACCORDANCE WITH TECHNICAL SPECIFICATION ACTION STATEM DEFECTIVE PROCEDURES ENT 3.4.6.2.B.

SIMILAR EVENTS NONE.

NOT APPLICABLE VELAN VALVE CORP.

THE VALVES, 2-RC-IS AND 2-RC-30, WERE OUT OF POSITION DUE TO PROCEDURAL INADEQUACY.

THE SPECIFIC PROCEDURES WERE REVISED TO PREVENT RECURRENCE.

A GENERIC PROCEDURE WAS GEHERATED TO ESTABLISH A PROGRAM FOR INSURING P R0PER SYSTEM ALIGNMENTS FOLLOWING OUTAGES.

NINE MILE POINT-1 05000220 121680 DURING HORMAL OPER, WHILE PERFORMING EMERGENCY VENTILATION SYSTEM (STAND CNTHMNT AIR PURI + CLEAHUP SYS 80-032/03L-0 011681 BY GAS TREATMENT) HEPA FILTER COLD D.O.P.

SURVEILLANCE TEST, OHE FILTER FILTERS 033741 30-DAY BANK IN 911 BRANCH PRODUCED AN UNACCEPTABLE EFFICIENCY OF 8% LEAKAGE.

E SUBCOMPONENT N-3T APPLICABLE FFICIENCY REQUIRED BY STATION TECH. SPECS. IS LESS TFAN 1% BYPASS LEAKAG DTHER E.

THIS HAD NO SIGNIFICANT SAFETY OR ENVIRONMENTAL EFFECT SINCE OVERALL HOT APPLICABLE BRANCH EFFICIENCY WAS ACCEPTABLE AND ALTERNATE REDUNDANT SYSTEM WAS PRO CAMBRIDGE FILTER CORP.

VEN OPERABLE. ALL OTHER TESTING INVOLVED FROVIDED ACCEPTABLE RESULTS.

INSPECTION REVEALED THAT FILTER SEALING GASKET WAS DEFECTIVE.

EFFORTS T 0 RESEAL GASKET SURFACE WERE UNSUCCESSFUL SO A NEW FILTER UNIT WAS INSTA (LED.

TEST RESULTS OF HEW FILTER WERE *?CEPTABLE.

SURV TESTING ON THIS SYS CONTINUES ON A REGULAR BASIS OR AS LiRTAIN CONDITIONS HECESSITATE A S DESCRIBED IN TECHNICAL SPECIFICATIONS.

4 t r

~

y

i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 55 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION NENE MILE POINT-1 05000220 122480 DURING NORMAL OPERATIDH, THE LOSS OF A 115KV AUXILIARY POWER FEED TO AN AC ONSITE POWER SYS + CONTROLS 80-033/03L-0 012381 EMERGENCY POWER BUS WAS EXPERIENCED. THE EMERGENCY DIESEL GENERATOR AUT RELAYS 033742 30-DAY OMATICALLY CAME INTO SERVICE AS REQUIRED. THIS HAD NO ADVERSE AFFECT ON SWITCHGEAR. PROTECTIVE SAFE OPERATION SINCE THESE COMPONENTS OPERATED AS DESIGNED.

COMPONENT FAILURE OTHER GENERAL ELECTRIC CO.

A CALIBRATION CHECK OF OVER-FREQUENCY PROTECTIVE RELAY FOR FEEDER BREAKE R REVEALED THAT TRIP SETPOINT WAS FOUND TOO CONSERVATIVELY CLOSE TO NOMI HAL FREQUENCY, THUS CAUSING A SPURIOUS TRIP OF BREAKER.

RELAY WAS PROPE RLY RECALIBRATED TO PREVENT RECURRENCE.

THIS TYPE OF REL AY WILL DE CALI BRATED ON REFUEL CYCLE FREQUENCY FOR FUTURE' PREVENTATIVE ACTION.

NINE MILE POINT-1 05000220 122980 DURING NORMAL OPERATION, 1U0 PROCEDURES (ONE A FUEL HANDLING PROCEDURE A SYSTEM CODE NOT APPLICABLE 80-034/03L-0 012881 ND ONE AN INSTRUMENT SURVEILLANCE PROCEDURE FOR GASEQUS SYSTEM LEAK RATE COMPONENT CODE NOT APPLICABLE 033743 30-DAY TESTING) WERE NOT SORC REVIEWED WITHIN THE SEVEN DAY TIME PERIOD FOR TE SUBCOMP0HENT NOT APPLICABLE MPORARY CHANGES AS REQUIRED BY TECHNICAL SPECIFICATIONS. THIS HAD NO EN OTHER VIRONMENTAL SAFETY EFFECTS.

NOT APPLICABLE ITEM NOT APPLICABLE THE TIME PERIOD FOR SORC REVIEW WAS EXCEEDED DUE TO AN OVERSIGHT OF THE DUE DATE REQUIRED. THE REVIEW WAS PERFCRMED SHORTLY THEREAFTER WITH ALL APPROVALS COMPLETED.

FOR FUTURE PREVENTION A TICKLER SYSTEM FOR ITEMS NEEDING SORC REVIEW IS BEING IMPLEMENTED.

WINE MILE POINT-1 05000220 010781 DURING HORMAL OPERATION, WHILE PERFORMING TFE MONTHLY SURVEILLANCE, AN E EMERG GENERATOR SYS + CONTROLS 81 - 0 01/ 0 3 L -0 020681 MERGENCY DIESEL GENERATOR OUTPUT BREAKER TRIPPED ON EXCESSIVE CURRENT DU INSTRUMENTATION + CONTROLS 036171 30-DAY E TO FAILURE OF THE GENERATOR VOLTAGE REGULATOR. THIS HAD NO ADVERSE EF.

CONTROLLER FECT CH SAFETY SINCE THE ALTERNATE EMERGENCY DIESEL GENERATOR WAS PROVEN OTHER OPERABLE.

NOT APPLICABLE CAR-BEE IHC INVESTIGATION FOUND THAT PIECES OF BAILING WIRE USED IN THE AREA TO ATTA CH FRAMES FOR STRUCTURAL' FIRE PROOFING HAD FALLEN ON TOP OF CONTROL CABI NET & THROUGH PROTECTIVE SCREEN.

EVIDENCE OF SHDRTING WAS FOUND AT THE VOLTAGE REGULATOR CONTROL CIRCUIT CONTACTS, CAUSING PROTECTIVE FUSE TO B LOW & CONSEQUENTLY FAILURE OF THE VOLTAGE REGULATOR.

NORTH ANNA-1 05000338 102980 OH OCTOBER 29, 1980. IT WAS DISCOVERED THAT THE VALVE INSERVICE-INSPECTI EMERG CORE COOLING SYS + CONT 80-094/03L-0 111980 ON PERIODIC TEST-1-PT-133.1B WAS NOT PERFORMED AS REQUIRED BY IWV PROGRA VALVES 033677 30-DAY M.

VALVES WERE SUBSEQUENTLY TESTED AND FUNCTIONED PROPERLY.

THEREFORE, OTHER THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED. THIS ITEM IS RE PERSONNEL ERROR PORTABLE PURSUANT TO TECH. SPEC.

6.9.1.9.C.

NDHLIC. OPERATICHS PERSONHEL GTHER THIS EVENT WAS CAUSED BY PERSONNEL ERROR.

THE VALVES IN QUESTION WERE S UBSEQUENTLY TESTED WITH SATISFACTORY RESULTS.

I l

l l

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PACE 56 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATF/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

i CAUSE SUBCODE/ MANUFACTURER CGNTROL NO.

REPORT TYPE CAUSE DESCRIPTION NORTH ANNA-1 05000338 122980 ON DECEMBER 29, 1980, WITH THE UNIT IN MODE 5. THREE MOTOR-OPERATED VALV-CNTHMNT HEAT 9EMOV SYS + CONT 81-004/03L-0 012981 ES FAILED TO ACTUATE DURING THE CONTAINMENT DEPRESSURIZATION ACTUATION F VALVES 036209 30-DAY UNCTIONAL' TEST.

THE HEALTH AND SAFETY OF THE GENERAL-PUBLIC WERE NOT AF BUTTERFLY FECTED. SINCE REDUNDANT VALVES PROVIDED SIMILAR FUNCTIONS TO THE FAILED COMPONENT FAILURE VALVES.

THIS IS CONTRARY TO TECHNICAL SPECIFICATION 3.7.4.1 3.6.2.2 A ELECTRICAL HD REPORTABLE PURSUANT TO TECHNICAL SPECIFICATION 6.9.1.9 D.

DEVIATION ALLIS CHALMERS REPORTS SUBMITTED ON 91-06-81 MOV-SW-105C FAILED TO OPERATE BECAUSE OF A LOOSE LEAD ON THE BREAKER / CON TROLLER.

MOV-SW-108A FAILED TO OPERATE BECAUSE OF WATER IN THE MOTCR AN D THE CAUSE FOR MOV-RS-101A FAILURE TO OPERATE IS UNKNOWN.

EACH VALVE W AS REPAIRED AS REQUIRED, AND WILL BE RETESTED PRIOR TO ENTRY INTO MODE 4 NORTH ANNA-1

~ 05C00338 123180 DURING MODE 5 OPERATION, A PRESSURIZER POWER OPERATED RELIEF VALVE WAS D~

OTHER COOLANT SUBSYS + CONTROL 81-002/03L-0 011581 ECLARED INOPERABLE BECAUSE OF LOW HITROGEN GAS SUPPLY TANK PRESSURE IN 1 i

UALVES 036208 30-DAY

-GN-TK-1A.

A REACTOR COOL ANT SYSTEM VENT OF GREATER THAN 2.07 SQUARE IN l

OTHER CHES WAS ESTABLISHED IN ACCORDANCE WITH TECH. SPEC.

3.4.9.3.

THEREFORE, DESIGN / FABRICATION ERROR

-THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED. THIS ITEM IS RE DESIGN PORTABLE PURSUANT TO LECH.. SPEC.

6.9.1.9.B.

1 STONE & WEBSTER ENG. CORP.

~ THE PORV WAS DECLARED INOPERABLE DUE TO LOW NITROGEN PRESSURE CAUSED BY FREQUENT CYCLING OF THE VALVE TO REDUCE THE RCS PRESSURE TO ATMOSPHERIC WHEN THE UNIT WAS BEING PREPARED FOR REFUELING. A VENT PATH OF GREATER 1

. THAN 2.07 SQUARE INCHES WAS ESTABLISHED AS PER' TECH. SPEC. 3.4.9.3.

' NORTH. ANNA-1 05000338 018481 ON 1/4/81, WITH UNIT IN MODE 5. LOOP 3 REACTOR COOLANT FLOW PROTECTION C REACTOR TRIP SYSTEMS 81-003/03L-0 012981 HANNEL II (F-1435) WAS FOUND OUT OF TOLERANCE HIGH DURING THE 18 MONTH P.

-INSTRUMENTATION + CONTROLS 036112-30-DAY ERIODIC CHANHEL CALIBRATION CHECK. WORST CASE WOULD HAVE CAUSED BOTH IN 9

TRANSMITTER DICATOR & COMPUTER POINT TO READ 3.99% HIGHER THAN ACTUAL, RESULTING IN COMPONENT FAILURE A DELAYED REACTOR TRIP SIGNAL ON LOW FLOW FOR THAT CHANNEL. BECAUSE RED INSTRUMENT

' UNDANT LOOP' FLOW INSTRUMENTATION WAS OPERATIONAL, HEALTH / SAFETY OF PUBLI FOXBORO CO., THE C WAS NOT AFFECTED. REPORTABLE PURSUANT TO TECH. SPEC. 6.9.1.9.A.

THE CAUSE OF THE ERROR IN INDICATION WAS A VOLTAGE DRIFT IN THE FLOW TRA NSMITTER SERVING THE INSTRUMENT LOOP.

CORRECTIVE ACTION WAS TO PROPERLY' 1

RECALIBRATE THE CHANNEL IN ACCORDANCE WITH - APPROVED CALIBRATION PROCEDU RES AND RETURN IT TO SERVICE.

NORTH ANNA-1 05000338 010681 WHILE PERFORMING TYPE "C" PENETRATION LEAK TESTING. IT WAS DETERMINED TO CNTHMNT ISOLATION SYS + CONT 81-0 0 9/ 0 3 L-0 012881 DATE THAT 14 VALVES HAD COMBINED LEAMAGE THAT-EXCEEDED. ALLOWABLE LIMITS s

VALVES-036113 30-DAY

. SINCE THE PENEfRATIONS CONTAINING THE LEAKING VALVES DID HAVE ADDDITI OTHER ONAL ISOLATION VALVES OR'WERE IN CLOSED SYSTEMS, THE HEALTH AND SAFETY 0 COMPONENT FAILURE F THE PUBLIC WAS NOT JEOPARDIZED. THIS EVENT IS REPORTABLE PER TECHNICA.

OTHER L SPECIFICATION 6.9.1.9.D.

OTHER VALVE LEAKAGE IS BELIEVED TO BE DUE TO DETERIORATION OF VALVE SEATS'AND.

IN THE CASE OF MOV-HV-100D, THE LIMIT SWITCH WAS IMPROPERLY SET PREVENTI NG FULL CLOSURE OF THE VALVE.

IN ALL CASES, VALVES WILL BE REWORKED OR ADJUSTED UNTIL TOTAL-CONTAINMENT TYPE "C" LEAKAGE IS ACCEPTABLE.

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MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE $7 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION HORTH ANNA-1 05000338 011381 ON JANUARY 13, 1981, WHILE IN MODE 6 OPERATION, THE PRESSURIZER PRESSURE REACTOR TRIP SYSTEMS 81-006/03L-0 012981 TRANSMITTER PT 1457 WAS FOUND TO BE OUT OF CALIBRATION BY 100 MVAC.

TH INSTRUMENTATION + CONTROLS 036210 30-DAY IS WOULD CAUSE THE HIGH PRESSURE REACTOR TRIP SIGNAL TO ENERGIZE 10 PSI TRANSMITTER HIGHER THAN THE ALLOWED SET POINT (2405 PSI RATHER THAN 2395 PSI).

SINC COMPONENT FAILURE E THE UNIT WAS IN MODE 6, THERE WAS NO EFFECT ON THE HEALTH AND SAFETY 0 ELECTRONIC F THE PUBLIC.

THIS ITEM IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICATI WESTINGHOUSE ELECTRIC CORP.

OH 6.9.1.9.A.

THIS EVENT WAS CAUSED BY INSTRUMENT DRIFT.

THE CHANNEL WAS RFCALIBRATED AND RETURNED TO SERVICE.

NORTH ANNA-1 05000338 011781 ON 1/17/81, WHILE IN REFUELING MODE, "A" STEAM GENERATOR PROTECTION CHAN ENGNRD SAFETY FEATR INSTR SYS 81-008/03L-0 021181 NEL II HARROW RANGE LEVEL TRANSMITTER LT-147S WAS FOUND TO BE OUT OF CAL INSTRUMENTATION + CONTROLS 036115 30-DAY IBRATION-LOW. WORST CASE WOULD HAVE CAUSED INDICATOR TO READ 2.7% LOWER TRANSMITTER THAN ACTUAL, RESULTING IN DELAYED TURBINE TRIP 8 FEEDWATER ISOLATION SI COMPONENT FAILURE GNALS ON HI-HI LEVEL FCR THAT CHANNEL.

BECAUSE REDUNDANT HARROW RANGE L INSTRUMENT EVEL INSTRUMENTATION WAS EITHER OPERATIONAL OR IN TRIPPED CONDITION, HEA ROSEMOUNT, INC.

LTH/ SAFETY OF PUBLIC NOT AFFECTED. REPORTABLE PER T.S.

6.9.1.9.A.

THE CAUSE OF THE ERROR IN INDICATION WAS A VOLTAGE DRIFT IN THE LEVEL TR ANSMITTER SERVING THE INSTRUMENT LOOP.

THE CHANNEL WAS SATISFACTORILY R ECALIBRATED AND RETURNED TO SERVICE.

NORTH ANNA-1 05000338 011781 ON JANUARY 17, 1981, WITH UNIT 1 IN MODE 6, A LOSS OF POWER TO THE RADIA CREA MONITORING SYSTEMS 81-011/03L-0 02118t TION MONITOR COMMON ALARMS PANEL UAS EXPERIENCED FOR A PERIOD OF TIME OF INSTRUMENTATION + CONTROLS 036116 30-DAY LESS THAN FIVE MINUTES. SINCE THE POWER TO THE ALARMS WAS QUICKLY REST OTHER ORED WITHIN THE TIME REQUIREMENTS OF THE LCO, THE HEALTH AND SAFETY OF T PERSONNEL ERROR HE PUBLIC WERE NOT AFFECTED.

MAINTENANCE a REPAIR PERSONNEL WESTINGHOUSE ELECTRIC CORP.

THIS INCIDENT OCCURRED WITH AN ELECTRICIAN TRIPPING THE UNIT 1 480V BREA KER FOR THE COMMON RAD ALARM PANEL (AFTER VERIFYING UNIT 2-480V BREAKER CLOSED) BUT WITHOUT HAVING SWITCHED POWER TO UNIT 2 VIA A REMOTE SWITCH.

CORRECTIVE ACTION INCLUDED RESTORING POWER AND INFORMING THE MAINTENANC E PERSONNEL OF THEIR ERROR.

NORTH ANNA-1 05000338 011881 ON 1/18/81, WITH REFUELING OPERATIONS IN PROGRESS FUEL BLDG SUPPLY 8 EX QIR COND, HEAT, COOL, VENT SYSTEM 81-012/03L-0 021781 HAUST FANS TRIPPED OUT ON THE FREEZE PROTECTION INTERLOCK & EXHAUST FAN BLOWERS 036114 30-DAY SUCTION DAMPERS SWITCHED TO THEIR FAILED POSITION BYPASSING IODINE FILTE SUBCOMPONENT NOT APPLICABLE R BANK WHEN CONTROL AIR WAS INADVERTENTLY ISOLATED. BECAUSE OPERATIONS EXTERNAL CAUSE WAS INITI ALLY UNAWARE OF REPOSITIONING, FUEL MOVEMENT WAS ALLOWED TO RES NOT APPLICABLE UME WITH FUEL BLDG EXHAUST AIR DIVERTED FROM FILTERS. PUBLIC HEALTH & S BUFFALO FORGE AFETY WERE NOT AFFECTED. REPORTABLE PURSUANT TO TECH SPEC 6.9.1.9.B.

FANS TRIPPED BECAUSE OF LOW OUTDOOR TEMPERATURE. TO RAISE DUCT HEATING COIL DISCHARGE TEMP, STEAM VALVES WERE FAILED OPEN BY ISOLATING AIR TO A PANEL WHICH ALSO INADVERTENTLY ISOLATED AIR TO THE EXHAUST AIR DAMPERS.

OPERATIONS HAD NO INDICATION DUE TO DESIGN OF DAMPER POSITION SWITCHES.

UPON DISCOVERY, DAMPERS WERE POSITIONED TO EXHAUST THROUGH THE FILTER.

MAR 26, 1981 LER MONTHLY REPCRT SORTED BY FACILITY PAGE 58 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT' TYPE CAUSE DESCRIPTION NORTH ANNA-1 05000338 012481 DURING THE LAST REFUELING OUTAGE, THE FIRST ROW OF TUBES IN EACH STEAM G REACTOR VES. + APPURTENANCES 81-007/99X-0 020481 ENERATOR WAS EXPLOSIVELY PLUGGED DUE TO OBSERVED DEFECTS IN THE TUBE MAN

-HEAT EXCHANGERS 03606S OTHER UFACTURING. ON JANUARY 15, 1981, "C" STEAM GEMERATOR TUBE INS"ECTIONS R STEAM GENERATOR EVEALED THE PLUG MISSING FROM THE TUBE AT ROW 1.

COLUMN 12.

THE TUBE WA OTHER S REPLUGGED ON JANUARY 24, 1981 THIS INFORMATION IS BEING SUBMITTED TO NOT APPLICABLE SATISFY THE REPORTING REQUIREMENTS OF TECHNICAL SPECIFICATION 4.4.S.S.A WESTINGHOUSE ELECTRIC CORP.

. HEALTH 8 SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED BY THIS EVENT THE TUBE PLUG FELL OUT DURING UNIT OPERATION BECAUSE OF A BAD SEAL WHICH CAN RESULT WHEN PLUGS ARE INSTALLED BY EXPLOSIVE CHARGE.

CORRECTIVE AC TION WAS TO REPLUG THE TUBE MECHANICALLY.

NORTH ANNA-2 0S000339 123080 ON DECEMBER 30, 1980, WHILE OPERATING AT 100% POWER, THE BORON INJECTION EMERG CORE COOLING SYS + CONT 81-007/03L-0 012681 TANK AND THE UNIT'S BORIC ACID STORAGE TANK ("C" BAST) WERE SAMPLED AND ACCUMULATORS 036211 30-DAY FOUND TO CONTAIN A BORON CGNCENTRATION BELOW THE TECHNICAL SPECIFICATI0 SUBCOMPONENT NOT APPLICABLE N LIMIT r / 20,000 PPM.

REDUNDANT SYSTEMS HAVING THE REQUIRED CAPABILITY COMPONENT FAILURE FOR ret, TOR CONTROL WERE OPERABLE, AS A RESULT THE HEALTH AND SAFETY OF OTHER THE GENERAL PUBLIC WERE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUAN WESTINGHOUSE ELtCTRIC CORP.

T TO TECHNICAL SPECIFICATION 6.9.1.9.B.

IHLEAKAGE FROM AN UNKNOUN SOURCE IS BELIEVED TO BE DILUTING BIT SOLUTION WHICH IS ON RECIRC UITH "C" BAST.

BORIC ACID WAS BATCHED 8 TRANSFERRED TO "C" BAST UNTIL CHEMISTRY WAS RESTORED TO SPECS.

SAMPLING FREQUENCY OF TANK HAS BEE 4 CHANGED FROM UEEKLY TO DAILY 8 RESULTS ARE BEING PLOTTE D UNTIL LEAK IS FOUND 8 ISOLATED TO ENSURE CORRECT CHEMISTRY.

NORTH ANNA-2 05000339 010681 ON JANUARY 6, 1981, DURING STEADY STATE OPERATION, A GREATER THAN 12 STE OTHR INST SYS REQD FOR SAFETY 81-005/03L-0 012881 P DISAGREEMENT WAS NOTED BETWEEN THE INDIVIDUAL ROD POSITION INDICATION INSTRUMENTATION + CONTROLS 036118 30-DAY FOR ROD B08 IN CONTROL BANK "D" AND THE GROUP DEMAND POSITION. THE IRPI INDICATOR WAS IMMEDIATELY RECALIBRATED AND CORRECT INDICATION RESTORED, CONSEQUEN COMPONENT FAILURE TLY THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED.

THIS INSTRUMENT EVENT IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICATION 6.9.1.9.B.

WESTINGHOUSE ELECTRIC CORP.

THE CAUSE OF THIS INDICATOR DISAGREEMENT WAS A VOLTAGE DRIFT IN THE SIGN AL CONDITIONING CARD.

THIS IS A RECURRING PROBLEM AND IS GENERIC TO WES TINGHOUSE ANOLOG ROD POSITION INDICATION SYSTEMS.

THE ROD POSITION INDI CATOR CHANNEL FOR B08 WAS SATISFACTORILY RECALIBRATED AND RETURNED TO SE RVICE.

NORTH ANNA-2 0S000339 010781 ON JANUARY 7, 1981. WITH UNIT AT 1% POWER, THE AVERAGE REACTOR COOLANT S OTHR INST SYS REQD FOR SAFETY 81-006/03L-O 020481 YSTEM TEMPERATURE WAS LESS THAN S41 F WITH THE REACTOR CRITICAL ON TWO O COMPONENT CODE NOT APPLICABLE 036064 30-DAY CCASIONS. HOWEVER, ON EACH OCCASION, THE TEMPERATURE WAS RESTORED TO WI SUBCOMPONENT NOT APPLICABLE THIN ITS LIMITS (>/: S41 F) WITHIH IS MINUTES AS REQUIRED BY TECHNICAL S PERSONNEL ERROR PECIFICATIONS. CONSEQUENTLY, THE HEALTH AND SAFETY OF THE PUBLIC WERE N LICENSED 8 SENIOR OPERATORS OT AFFECTED.

ITEM NOT APPLICA6LE EACH EVENT WAS CAUSED BY OVERFEEDING OF THE STEAM GENERATORS. DUE TG FEE DWATER CONTROL PROBLEMS, AND DECREASING REACTOR COOLANT TEMPERATURES DUE TO XENON BUILDUP. CORRECTIVE ACTION WAS YO SECURE FEEDING THE STEAM GEN ERATORS, TO CLOSE THE CONDENSER STEAM DUMPS AND TO INCREASE REACTOR TEJP ERATURE BY DILUTION AND PULLING THE CONTROL RODS.

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MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 59 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSL 1ESCRIPTION NORTH ANNA-2 05000339 010781 ON JANUARY 7, 1981, UNIT 2 WENT ON LINE AFTER AN EIGHT HOUR CUTAGE AND I SYSTEM CODE NOT APPLICABLE 81-008/03L-0 020281 NCREASED POWER TO 30 PERCENT OF RATED THERMAL POWER.

A PRIMARY COOLANT COMPONENT CODE NOT APPLICABLE 036066 30-DAY 10 DINE ISOTOPIC ANALYSIS WAS NOT MADE WITHIN 2 TO 6 HOURS AS REQUIRED BY SUBCOMPONENT NOT APPLICABLE THE TECHNICAL SPECIFICATION FOR PCNER CHANGES EXCEEDING 15 PERCENT IN O PERSONNEL ERROR NE HOUR.

THIS EVENT IS REPORTAELE PURSUANT TD-TECH. SPEC.

6.9.1.9.C.

T LICENSED & SENIOR OPERATORS HE PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.

ITEM NOT APPLICABLE OPERATIONS PERSONNEL FAILED TO FOLLOW PROCEDURES AND TAILED TO NOTIFY CH EMISTRY PERSOMNZL THAT A PRIMARY COOLANT IODINE ISOTOPIC ANALYSIS WAS RE QUIRED.

A SAMPLE OF PRIMARY COOLANT WAS COLLECTED AND ANALYZED IMMEDIAT ELY AFTER THE NEED WAS IDENTIFIED. PERSONNEL INVOLVED WENE REINSTRUCTED TO ADHERE TO PROCEDUkE REQUIREMENTS.

NORTH ANNA-2 05000339 010781 ON JANUARY 1,

1981 DURING MODE 1 OPERATION, THE FLUX TENALTY SUMMINO AM REACTOR TRIP SYSTEMS 81-004/03X-1 012981 PLIFIER (NM-432A) WAS FOUND TO BE FAILED DURING A LOOP CALIBRA(ION CHECK' INSTRUMENTATION + CONTROLS 036117 OTHER

.WAS FUNCTIONING PROPERLY.

THEREFORE, THE HEALTH AND SAFETY OF THE PUBL THE FAILED CHANNEL IJAS IN THE TRIP POSITION AND THE REMAINING CHANNEL COMPUTATION MODULE COMPONENT FAILURE IC WERE NOT AFFECTED. THIS ITEM IS REPORTABLE PURSUANT TO TECHNICAL SPE ELECTRONIO CIFICATIDH 6.9.1.9.B.

WESTI*;GHOUSE EL ECTRIC CORP.

THIS FAILURE WAS CAUSED BY A FAULTY HSA CARD (C3-141).

THE CARD WAS REP LACED AND CALIBRATED. THE LOOP CALIBRATION CHECK WAS PERFORMED AND THE CHAMNEL RETURNED TO SERVICE.

NORTH ANNA-2 05000339 010781 ON JANUARY 7, 1981, WITH THE UNIT IN MODE 1,

THE CONTAINMENT PERSONNEL H REACTOR CONTAINMENT SYSTEMS 81- 0 0 9/ 0 3 L-0 012981 ATCH DUTER DOOR LEAKED AIR PAST ITS SEALS DURING A LEAK TEST.

SINCE THE PENETRATIONS,PRIMRY CONTAINMNT 036212 30-DAY INNER DOOR REMAINED OPERABLE AND THE OUTER DOOR WAS REPAIRED WITHIN 24 PERSONNEL ACCESS HOURS THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE NOT AFFECTED.

TH COMPONENT FAtLURE IS IS CONTRARY TO TECHN1LAL SPECIFICATION 3.6.1.3 AND REPORTABLE PURSUAN MECHANICAL T TO TECHNICAL SPECIFICATION 6.9.1.9.B.

CHICAGO BREDGE 8 IRON COMPANY THE CAUSE OF THE LEAKING SEALS ON THE OUTER HATCH DOOR WAS DUE TO IMPROP ER FITUP OF THE DOOR SEALS TO THE FRAME.

THE OUTER HATCH DOOR WAS ADJUS TED TO ALLOW THE SEALS TG MATE PROPERLY AND THE LEAK TEST WAS PERFORMED SATISFACTORILY.

NORTH ANNA-2 05000339 011381 ON JANUARY 13, 1981, WITH UNIT 2 AT '00 PERCENT POWER. AN OVERSPEED TRIP CONDNSATE + FEEDWTR SYS + CONT 81-010/03L-0 021181 0F THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP OCCURRED DURING SURVEILL.

MECHANICAL FUNCTION UNITS 036119 30-DAY ANCE TESTING. THIS EVENT IS REPORTABLE PURSUANT TO TECHNICAL SPECIFICAT-SUBCOMPONENI NOT APPLICABLE ION 6.9.1.9.B.

TWO REDUNDANT MOTOR. DRIVEN AUXILIARY FEEDWATER PUMPS WER COMPONENT FAILURE E OPERABLE.

THE ACTION STATEMENT OF THE LCO WAS MET.

THE PUBLIC HEALTH MECHANICAL AND SAFETY WERE NOT AFFECTED.

WOODWARD GOVERNOR CD.

THE TURBINE GOVERNOR FAILED TO CONTROL THE TURBINE SPEED PROPERLY. THE CAUSE OF THE GOVERNOR FAILURE WAS NOT DETERMINED. THE GOVERNOR WAS REPL ACED AND THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP WAS RETURNED TO OPE RABLE STATUS AFTER BEING TESTED IN ACCORDANCE WITH TECHNICAL SPECIFICATI ON AND IWP REQUIREMENTS.

[

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 60 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/

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l CAUSE SUBCODE/ MANUFACTURER CONTKOL NO.

REPORT TYPE CAUSE DESCRIPTION NORTH ANNA-2 05000339 011481 DN 1/ 14/81. WITH UNIT 2 AT 100% POWER. THE BREAKER FOR 2-QS-P-1A (QUENCH REACTOR CONTAINMENT SYSTEMS 81-011/03L-0 020481 SPRAY PUMP) WAS RACKED OUT AND THE SUCTION VALVE FOR THE PUMP (MOV-QS-2 VALVES 036067 30-DAY 00A) WAS CLOSED AND DE-EHERGIZED IN ORDER TO REPAIR A LEAKING VENT VALVE GATE ON THE QUENCE SPRAY PUMP DISCHARGE STRAINER. SINCE THE QUENCH SPRAY PU COMPONENT FAILURE MP WAS RETURNED TO SERVICE WITHIN THE TIME ALLOTED BY THE APPROPRIATE AC MECHANICA8 TION STATEMENT, AND OHE QUENCH SPRAY SYSTEM REMAINED OPERABLE, THE HEALT VELAM VALVE CORP.

H AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

THE LEAKING VALVE WAS A 1" VELAN CORPORATION VENT VALVE.

THE VALVE BONN ET WAS REMOVED, THE INTERNALS INSPECTED AND FOUND TO HAVE A DIRTY SEAT-.

THE VALVE SEAT WAS CLEANED, AND THE VALVE DISC WAS LAPPED IN ORDER TO C LEAN IT.

SUBSEQUENT T9 MAINTENANCE. THE VALVE WAS MANUALLY OPERATED AND FOUND TO OPERATE SATISFACTORILY.

NORTH ANNA-2 05000339 011481 OH JANUARY 14, 1981 DURING MODE 1 OPERATION, THE HYDROGEN RECOMBINER SY CNTNMHT COMBUS GAS CONTROL SYS 81-015/03L-0 020981 STEM WAS REMOVED FROM SERVICE FOR PIPING MODIFICATIONS CONTRARY TO TECHN 01HER COMPONENTS 036122 30-DAY ICAL SPECIFICATION 3.6.4.2.

SINCE THE REDUNDANT HYDROGEN RF MBINER WAS SUBCOMPONENT NOT APPLICABLE RETURHED TO SERVICE WITHIN 30 DAYS AS REQUIRED BY THE ACTION '. 1EMENT OTHER AND THE UNIT 2 HYDROGEN RECOMBINER REMAINED OPERABLE THE HEALTH AhD SAF NOT APPLICABLE ETY OF THE PUBLIC WERE NOT AFFECTED. THIS EVENT IS REPORTABLE PURSUANT ROCKWELL-INTERNATIONAL TO TECH. SPEC.

6.9.t.9.6.

THE UNIT 1 HYDROGEN RECOMBINER WAS REMOVED FROM SERVICE TO PERFORM A PIP ING MODIFICATION. WNEN COMALETED, THE RECOMBIHER WAS RETURNED TO SERVIC E.

NORTH ANNA-2 05000339 012181 OH 1/21/31,' l3ITH UNIT II AT ?00% POWER-UGHTAINMENT PRESSURE PROTECTION ENGHRD SAFETY FEATR INSTR SYS 81-012/03L-0 021181 CHANNEL III FAILED LOW.

THE CHANNEL WAS PLACED IN TRIP AND DECLARED INO INSTRUMENTATION + CONTROLS 036120 30-DAY

  1. 7RABLE.

SINCE CONTAIHMEPT PRESSURE CHANNELS I, II, AND IV REMAINED AVA INDICATOR

.;ABLE TO INITIATE CONTAINMENT DEPRESSURIZATION IF REQUIRED, AND CONTAIN COMPONENT FAILURE aENT PRESSURE CHANNELS I AND II WERE AVAILABLE TO INITIATE AN INTERMEDIA INSTRUMENT TE HIGH-HIGH OR A HIGH CONTAINMENT PRESSURE SIGNAL IF REQUIRED, THE HEAL WESTINGHOUSE ELECTRIC CORP.

TH AND SAFETY OF THE PU3LIC WERE NOT AFFECTED.

THE EVENT WAS CAUSED BY THE FAILURE OF A POWER SUPPLY CARD TO REACTOR CD NTAINMENT PRESSURE PROTECTION CHANNEL III.

THE FAILED CARD WAS REPLACED WIiH A CALIBRATED CARD, FUNCTIONALLY TESTED AND RESTORED TO A NORMAL CO HDITION.

NORTH ANNA-2 05000339 012281 ON JANUARY 22, 1981, WITH THE UNIT AT 100% POWER, WHILE POWER RANGE CHAN REACTOR TRIP SYSTEMS 81-014/03L-0 021181 NEL 3, N-43 WAS BEING TESTED AND IN THE TRIP MODE, A SPIKE OCCURRED ON INSTRUMENTATION + CONTROLS 036121 30-DAY CHANNEL 4.

H-44 WHICH GAVE 2/4 COINCIDENCE RESULTING IN AN IHADVERTANT POWER SUPPLY REACTOR TRIP. SINCE THE PLANT WAS SAFELY SHUT DOWN, THE HEALTH AND SAFET COMPONENT FAILURE Y OF THE GENERAL PUBLIC WERE NOT AFFECTED.

THIS IS CONTRARY TO TECHNICA INSTRUNENT L SPECIFICATION 3.3.1.1 SINCE THE MINIMUM NUMBER OF OPERATING CHANNELS W WESTINGHOUSE ELECTRIC COF.P.

ERE LESS THAN 1. AND REPORTABLE PURSUANT TO TECH SPEC 6.9.1.9.B.

THE CAUSE OF THE SPIKE ON N-44 IS UNKNOWN AT THIS TIME.

PRIOR TO STARTI NG UP THE UNIT, N-44 WAS CALIBRATED SUCCESSFULLY. SUBSEQUENT TO THE STA RTUP.; SURVEILLANCE TESTS WERE PERFORMED ON ALL OF 1HE POWER RANGE FLUX C HANNELS AND N-44 WAS AGAIN CALIBRATED. RECORDERS MONITORING.THESE CHANN ELS ARE REVIEWED DAILY AND NO ABNORMAL INDICATIONS HAVE BEEN FOUND.

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MAK 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 61 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION NORTH ANNA-2 05000339 012681 ON JANUARY 26, 1981, THE CONTAINMENT HI ANU ni-HI CHANNEL III ANNUNCIATO ENGNRD SAFETY FEATR INSTR SYS 81-013/03L-0 022581 R BECAME ENERGIZED. AFTER ENSURING THAT A HIGH PRESSURE DID NOT EXIST, INSTRUMENTATION + CONTROLS 036242 30-DAY THE CHANNEL MAS PLACtD IN THE TRIPPED CONDITION AND DECLARED INDPERABLE.

CONTROLLER CONTAINMENT PRESSURE CHANNELS I, II AND IV REMAINED OPERATIONAL TO INIT COMPONENT FAILURE IATE A CDA IF REQUIRED, THEREFORE THE HEALTH AND SAFETY OF THE PUBLIC WE ELECTRONIC RE NOT AFFECTED.

THIS EVENT IS REPORTABLE PURSUANT TO TECH. SPEC.

6.9.1.

WESTINGHOUSE ELECTRIC CORP.

.9.B.

THE POWER SUPPLY CARD (S/N 5088) DRIFTED HIGH CAUSING AN INCREASE IN OUT PUT VOLTACE. THE FAULTY CARD WAS REPLACED THE CHANNEL CALIBRATED AND D ECLARED OPERABLE.

NORTH ANNA-2 05000339 020581 ON FEBRUARY 5, 1981, WHILE OPERATING AT 100% POWER, THE TEMPERATURE INDI REACTOR TRIP SYSTEMS 81-016/03L-0 021981 CATOR ( T I-412 D ), ASSOCIATED WITH TAVG PROTECTION FOR LOOP "A",

WAS READI INSTRUMENTATION + CONTROLS 036243 30-DAY NG APPROXIMATELY 5F-15F LOW AND RESPONDING ERRATICALLY AFTER BEING PLACE OTHER D IN SERVICE UPON COMPLETION OF A PERIODIC TEST ON THE CHANNEL.. SINCE T COMPONENT FA?3.URE HE AFFECTED CHANNEL WAS PLACED IN THE TRIP CONDITION WITHIN ONE HOUR, TH INSTRUMENT E PUBLIC HEALTH AND SAFETY WERE NOT AFFECTED.

WESTINGHOUSE ELECTRIC CORP.

THE ERRATIC AND LOWER THAN NORMAL READINGS ON THE TEMPERATURE INDICATOR WERE CAUSED BY A FAILED RELAY CARD.

THE CARD WAS REPLACED, CALIBRATED A ND RETURNED TO SERVICE.

OCONEE-1 05000269 112480 ON NOVEMBER 24, 1980, THE LEVEL INDICATION WAS LOST TO THE STATION EWST.

STATION SERV WATER SYS + CONT 80-034/03X-1 021981-DURING THE TIME OF THE INOPERABILITY, BOTH NORMAL HPSW PUMPS AND THE HP INSTRUf1ENTATION + CONTROLS 033363 UTHER SU JOCKEY PUMP WERE OPERABLE, THUS ASSURING SAFE OPERATION OF THE PLANT INDICATOR BUT REQUIRING MANUAL START OF TPE PUMPS IF NEEDED.

IN. ADDITION, THE LEV EXTERNAL CAUSE EL IN THE EWST WAS MONITORED EVERY 2 HOURS.

IHUS, THIS INCIDENT WAS OF NOT APPLICABLE NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND THE HEALTH AND SAFETY OTHER OF THE PUBLIC WERE NOT AFFECTED.

THIS INCIDENT WAS CAU3ED BY WATER COLLECTING IN THE AIR COMPRESSOR LOCAT ED ON THE MICROWAVE TOWER WHICH PROVIDES INSTRUMENT AIR FOR THE EWST INS TRUMENTATION. IMMEDIATE CORRECTIVE ACTION WAS TO PLACE HPSW PUMPS IN MA NUAL MODE & ESTABLISH AN ALTERNATE MEANS OF INDICATING WATER LEVEL IN EW ST.

THE NORMAL INSTRUMENTATION WAS CHECKED, & THE AIR RECEIVER DRAINED.

OCONEE-1 05000269 120980 ON DECEMBER 9, 1980 THE ELEVATED WATER STORAGE TANK (EWST) AND A PORTION STATION SERV WATER SYS + CONT 80-236/03L-0 012281 0F THE HIGH PhESSURE SERVICE WATER (HPSW) FIRE PROTECTION YARD LOOP WER i

COMPONENT CODE NOT APPLICABLE 033722 33-DAY E REMOVED FROM SERVICE. A TEMPORARY FLOW PATH WAS ESTABLISHED TO PROVID-SUBCOMPONENT NOT APPLICABLE E FIRE PROIECTION TO CT-5.

TEMPORARY HOSE RUPTURED. HPSW PUMPS WERE AV DTHER AILABLE FOR MANUAL ACTIVATION IF REQUIRED. A FIRE WATCH WAS MAINTAINED-NOT APPLICABLE DURING THE PERIOD WHEN THE TEMPORARY HOSE RUPTURED. THERE WAS NO EFFECT ITEM NOT APPLICABLE ON HEALTH AND SArETY OF THE PUBLIC.

REMOVAL FROM SERV 1CE OF EUST & PORTION OF HPSW FIRE PROTECTION YARD LOOP WEPC PLANNED.

HOSE RUPTURE WAS DUE TO RESULTING FRESSURE SURGE WHEN HP SM PUMPS WERE PUT INTO SERVICE.

RUPTURED HOSES WERE EXPEDITIOUSLY REPLA CED WHILE FIRE WATCHES WERE POSTED. EWST WAS RETURNED TO SERVICE AS 500-N AS POSSIBLE.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 62 PROCESSED DURING MARCH, 1981 FOR PGMER REACTORS 4

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTICH OCONEE-1 05000269 011881 UNIT 1 WAS REDUCING POWER FROM 90% WHEN THE D.C.

INPUT FUSE IN THE 1DID ONSITE POWER SYSTEM + CONTROL 81-002/03L-0 021781 VITAL INVERTER BLEW, CAUSING THE INVERTER TO LOSE ITS POWER SOURCE.

fMR GENERATORS 036123 30-DAY EE VITAL INSTRUMENTATIDH POWER PANELBOARDS WERE STILL IN SERVICE. THESE INVERTER WOULD HAVE PROVIDED SUFFICIENT A.C.

VITAL INSTRUMENTATION TO SAFELY SHU CCMPONENT FAILURE T DOWN THE UNIT IF AN ACCIDENT HAD OCCURRED. THUS. THIS INCIDENT WAS OF ELECTRICAL NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND THE HEALTH AND SAFETY OTHER OF THE PUBLIC WERE NOT AFFECTED.

THE BLOWN POWER FUSE WAS POSSIBLY CAUSED BY POORLY MADE CONNECTIONS IN T HE LOGIC CARDS' " EDGE CONNECTORS" AND/OR INTERMITTENT COMPONENT PROBLEMS ON THE LOGIC CARDS.

THE DID INVERTER LOAD WAS IMMEDIATELY TRANSFERRED TO THE A.C. REGULATED BUS AND THE FUSES WERE REPLACED. THE LOGIC CARDS AND THEIR' EDGE CONNECTORS WILL BE INSPECTED ON ALL UNITS.

OCONEE-1 05000269 012581 ON JANUARY 25, 1981 D.C.

INPUT FUSE IN 1DID VITAL INVERTER BLEW, CAUSIN ONSITE POWER SYSTEM + CONTROL 81-003/03L-0 022481 G THE INVERTER TO TRIP 3 LOSE ITS PCWER SOURCE. IN ADDITION, 1DIB INVERT CIRCUIT CLOSERS / INTERRUPTERS 036241 30-DAY FD TFIPPED WHEN A.C.

OUTPUT BREAKER WAS APPARENTLY OPENED WHILE PERSONNE CIRCUIT BREAKER L WERE WORKING OH 1DID INVERTER. A SECOND TRIP OF 1DID INVERTER OCCURRED COMPONENT FAILURE WHEN PERSONNEL MISTAKENLY OPENED A.C. OUTPUT BREAKER WHILE DE-ENERGIZIN-OTHER G 1DID. ALTHOUGH BOTH 1KVID 4 1KVID WERE DE-ENERGIZED, THEY WERE NOT SIM EXIDE INDUSTRIAL DIV ULTANEOUS. THUS. THE HEALTH & SAFETY OF THE PUBLIC WERE NOT ENDANGERED.

THE FIRST TRIP OF 1DID WAS CAUSED BY BLOWN FUSES.

THE CAUSE OF THE 1DIB TRIP IS NOT EXACTLY KNOWN.

1DID TRIPPED AGAIN AS A RESULT OF THE A.C.

DUTPUT BREAKER MISTAKENLY BEING OPENED.

FUSES WERE REPLACED, INVERTERS WERE RETURNED TO SERVICE. AND CHANNELS WERE RESET ACCO#DINGLY. GUARDS W ILL BE INSTALLED ON ALL D.C.

INPUT AND A.C. DUTPUT 5%EA(ERS.

OCCHEE-2 05000270 101180 ON 10/21/80, IT WAS DISCOVERED THAT 4 HOLES HAD BEEN KNOCKED IN THE FIRE-FIRE PROTECTION SYS + CONT 80-022/01X-1 021981 BARRIER BETWEEN UNIT 2 CABLE SPREAD ROOM & TURBINE BUILDING. THIS INCID OTHER COMPONENTS 032843 OTHER ENT OCCURRED ON 10/11/80 & AN HOURLY FIRE WATCH HAD HOT BEEN ESTAB. SINC SUBCOMPONENT NOT APPLICABLE E BOTH MANUAL HOSE LINES & INSTALLED WATER SPRAY SYS WERE AVAILABLE, FIR DEFECTIVE PROCEDURES E PROTECTION CAPABILITIES OF THIS AREA WERE NOT UNDULY COMPROMISED. THUS NOT APPLICABLE THIS INCIDENT WAS OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION, A ITEM NOT APPLICABLE ND THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

THIS INCIDENT APPEARS TO BE 1HE RESULT OF THREE RELATED DEFICIENCIES INV OLVING THE FAILURE OF PROPER HOTIFICATION. AFTER DISCOVERY OF THE INCID ENT, AN HOURLY FIRE WATCH WAS ESTABLISHED. THE SLEEVES WERE ENCLOSED WI TH STRUCTURAL GROUT.

THE CHANGE IN PROCEDURES AND MAINTENANCE TRAINING ARE ADEQUATE TO PREVENT REOCCURRENCE.

OCONEE-2 05000270 121780 ON 12/17/80, 2B HPI PUMP WAS DECLARED INOPERABLE. PUMP HAD BEEN REMOVED EMERG CORE COOLING SYS + CONT 80-025/03L-0 013081 FROM SERVICE FOR A MOTOR DIL CHANGE.

CN FOUR CONSECUTIVE TEST RUNS AFT MOTORS 033723 30-DAY ER OIL CHANGE, MOTOR INDICATED HIGH UPPER BEARING TEMPERATURES PUMP WA SUBCOMPONENT NOT APPLICABLE S RETURNED TO SERVICE WELL WITHIN TIME PERMITTED. HPI PUMPS 2A 8 2C WER PERSONNEL ERROR E AVAILABLE AS WELL AS ALL OTHER ECC SYSTEMS.

THUS THIS INCIDENT WAS OF MAINTENANCE & REPAIR PERSONNEL NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION, & HEALTH 8 SAFETY OF PU OTHER BLIC WERE NOT AFFECTED.

CAUSE WAS PERSONNEL BEING CONFUSED & DOING JRONG THINGS.

EXACT CAUSE F0 R HIGH TEMPERATURES IS NOT KNOWN.

PERSONNEL HAVE BEEN INSTRUCTED NOT TO PERFORM ACTIONS THAT THEY KNOW ARE NOT CORRECT. FUTURE CORRECTIVE ACTI ONS PLANNED ARE TO HAVE APPRnP. PERSONNEL REVIEW INCIDENT 8 CORRECT PROB LEM WITH THE HIGH BEARING r ERATURES.

m

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 63 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAUSE DESCRIPTION OCONEE-2 05000270 121980 ON 12/19/80, THE CBAST PUMP WAS DECLARED INOPERABLE WHEN IT FAILED TO PU CHEM, VOL CD*1T + LIQ POISH SYS 80-026/03L-0 012081 MP FRCM CBAST TO LDST.

DURING PERIOD OF INOPERABILITY, EWST WAS AVAILAB PUMPS 033678 30-DAY LE.

ALSO CBAST PUMP WAS RETURNED TO SERVICE WITHIN TIME PERMITTED. THU DIAPHRAGM S, INCIDENT WAS OF NO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND HE COMPONENT FAILURE ALTH AND SAFETY OF PUBLIC WERE NOT AFFECTED. FAILURE OF CBAST PUMPS IS MECHANICAL A RECURRING PROBLEM AT OCONEE.

OTHER APPARENT CAUSE WAS DUE TO AIR BEING IN HYDRAULIC RESERVOIR. OIL LEVEL W AS FOUND TO BE LOW.

OIL WAS ADDED TO RESERVOIR. A STATION MODIFICATION HAS BEEN SUBMITTED REQUESTING THAT CURRENT LAPP PUMPS BE REPLACED WITH A CENTRIFUGAL TYPE PUMP.

OCONEE-2 05000270 012081 DN JANUARY 20, 1981, IT WAS DISCOVERED THAT THERE WAS NO FLOW OF LOW PRE CNTNMNT HEAT REMOV SYS + CONT 51-001/03L-0 021981 SSURE SERVICE WATER (LPSW) TO THE "2A" HPI PUMP.

AT THE TIME-IT WAS FOU VALVES 036160 30-DAY HD THAT THERE WAS NO FLOW IN THE "2A" BEARING COOLER, PUMPS "2B" AND "2C OTHER

" WERE AVAILABLE FOR USE.

THEREFORE, THE HPI SYSTEM WAS-NOT IMPAIRED.

ALSO THE USE OF "2A" WAS QUICKLY REGAINED WHEN FLOW WAS RESTORED.

THUS.

OTHER THIS INCIDENT WAS OF HO SIGNIFICANCE WITH RESPECT TO SAFE OPERATION AND NOT APPLICABLE THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

ITEM NOT APPLICABLE THE REASON FOR THE FLOW STOPPAGE IS NOT KNOWN AT THIS TIME. WHEN LACK 0

-F FLOW WAS ENCOUNTERED, VALVE 2/TVC/(RHO) MAS BYPASSED, AND FLOW WAS RES

TORED, FUTURE CORRECTIVE ACTION WILL BE TAKEN AS DEEMED HECESSARY AFTER THE CAUSE FOR THE FLOW STOPPAGE HAS BEEN DETERMINED.

OYSTER CREEK-1 05000219 071180 DN JULY 11, 1980, DURING A PLANT STARTUP, THE HIGH DRYWELL PRESSURE SENS EMERG CORE COOLING SYS + CONT 80-029/03L-1 020381 OR RV46B ACTUATED CAUSING THE CORE SPRAY PUMPS AND BOTH DIESEL GENERATOR COMPONENT CODE NOT APPLICABLE 032047 30-DAY S TO START.

AFTER VERIFYING THAT AN ACTUAL HIGH DRYWELL PRESSURE CONDIT SUBCOMPONENT NOT APPLICABLE ION DID NOT EXIST, THE PRIMARY CORE SPRAY PUMPS WERE TURNED OFF.

THIS C AUSED THE ALTERNATE PUMPS TO START AND THESE WERE ALSO STOPPED. UNDER T DESIGN / FABRICATION ERROR HESE CONDITIONS THE AUT0t1ATIC AND REMOTE MANUAL INITIAL FEATURES OF THE MANUFACTURING ALTERNATE CORE SPRAY PUMPS WERE DEFEATED.

ITT-BARTON THE INITIATING CAUSE'0F THE OCCURRENCE IS ATTRIBUTED TO INSTRUMENT SETPO INT SHIFT.

AFTER THE OPERATOR STOPPED THE PUMPS. THE ALTERNATE PUMPS WO ULD NOT HAVE STARTED AUTOMATICALLY BECAUSE OF THE DESIGN OF THE LOGIC CI RCUIT.

THE PLANT WAS SHUTDOWN AND ALL FOUR HIGH DRYWELL PRESSURE SENSOR S WERE RECALIBRATED.

0YSTER CREEK-1 05000219 121780 DURING FUNCTIONAL TESTING, SNUBBERS -19/11

-19/12 8 -19/13 (SERIAL NO.

EMERG CORE COOLING SYS + CONT 80-061/03L-0 011681 470915, 477361 & 477121) LOCATED ON CONTAINMENT SPRAY 8 CORE SPRAY SYSTE HANGERS, SUPPORTS, SHOCK SUPPRSS 033679 30-DAY M COMMON SUCTION HEADER, FAILED TO LOCK UP IN COMPRESSION MODE.

PLANS T SNUBBERS D PERFORM A DETAILED COMPUTER ANALYSIS WHICH MODELS EACH SNUBBER BASED 0 N ITS MODE OF FAILURE FOR 'sARIOUS MODES OF OPERATION ARE BEING MADE SO T-COMPONENT FAILURE HAT SAFETY SIGNIFICANCF AND PIPE STRESS MAGNITUDES CAN ACCURATELY BE REP MECHANICAL BERGEN-PATTERSON PIPE SUPPORT ORTED IN FORM OF A RFi1SION TO THIS REPORT.

CAUSE WAS ATTRIBUTED TO MAIN PISTON SEAL FAILURES. SEAL BREAKDOWN ALLOWE D MATERIAL TO GF7 INTO HYDRAULIC FLUID AND FLUID TO LEAK FROM CYLINDER.

THREE SNUBBEPS WERE REPLACED WITH OPERABLE SPARES.' DUE TO TOTAL NUf1BER OF SNUBBER FAILURES, ALL REMAINING HYDRAULIC SNUBBERS MUST NOW BE FUNCT IONALLY TESTED.

~.

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REPORT TYPE CAUSE DESCRIPTIDH OVSTER CREEK-1 05000219 010281 DURING SURVEILLANCE TESTING. THE CCNTAINMENT SPRAY SYSTEM HIGH DRYWELL P CNTHMNT HEAT REMOV SYS + CONT 81-001/03L-0 013081 RESSURE INDICATING SWITCH IP-15C WAS FOUND TO TRIP AT A VALUE GREATER TH INSTRUMENTATION + CONTROLS 036036 30-DAY AN THE 2.0 PSIG TECHNICAL SPECIFICATIONS LIMITS.

THE "AS FOUND" TRIP P0 SWITCF INT WAS 2.10 PSIG, S0 ITS ACTUATION WOULD HAVE BEEN DELAYED BY A FRACTIO COMPONENT FAILURE N OF A SECOND.

HOWEVER, THE REDUNDANT SWITCH IP-15A WOULD HAVE ACTUATED INSTRUMENT AT THE DESIRED SETPOINT, SO THE SAFETY SIGNIFICANCE OF THE EVENT IS CON ITT-BARTON SIDERED MINIMAL.

CAUSE WAS ATTRIBUTED TO INSTRUMENT REPEATABILITY. THE SWITCH WAS RESET TO TRIF UITHIN THE TECHNICAL SPECIFICATIONS LIMIT OF 2.0 PSIG, AND A STU DY IS PRESENTLY BEING DONE EXAMINING POSSIBLE SETPOINT CHANGES TO ACCOUN T FOR THIS REPEATABILITY. THE PORC HAS ALSO RECOMMENDED REPLACEMENT OF THESE SWITCHES WITH A MORE QUALIFIED MODEL.

GYSTER CREEK-1 05000219 010281 DURING NORMAL PLANT OPERATION, THE STACK GAS ACTIVITY WAS NOT CONTINUGUS PRCSS + EFF RADIOL MONITOR SYS 81-002/03L-0 013081 LY MONITORED AS REQUIRED BY TECH. SPEC. 3.6.A.3 DUE TO A TRIP OF THE STA PUMPS 036037 30-DAY CK GAS SAMPLE PUMP.

A REVIEW OF RECORDS FOR OTHER MONITORING SYSTEMS IN VANE TYPE DICATED THAT GASEOUS RELEASES TO THE STACK WERE NORMAL DURING THIS EVENT COMPONENT FAILURE THERE WERE NO ADVERSE EFFECTS CH PUBLIC HEALTH OR SAFETY.

NATURAL END OF LIFE GAST MANUFACTURING CORPORATION THE CAUSE OF THIS EVENT WAS ATTRIBUTED TG THE SAMPLE PUMP FAILING DUE TO NORMAL WEAR.

THE CARBON VANES OF THE PUMP THINNED OUT, BROKE UP INSIDE THE PUMP CAUSING IT TO TRIP DN OVERLOAD DUE T0' BINDING.

THE PUMP WAS R EPLACED WITH A SPARE.

OVSTER CREEK-1 05000219 010681 DURING AN OPERABILITY TEST TO CHECK INSTALLED AMMETERS. EMERGENCY SERVIC CNTNMNT HEAT REMOV SYS + CONT 81-005/03L-0 020681 E WATER PUMP 52B WAS FOUND TO DRAW LESS THAN 10 AMPERES CURRENT AND WAS PUMPS 036161 30-DAY FOUND TO HAVE A 0 PSIG DISCHARGE PRESSURE. THE ACCEPTABLE VALUES ARE 53 CENTRIFUGAL

+/- 3.0 AMPERES AND >/: 100 PSIG.

THE REDUNDANT PUMP IN SYSTEM-I (52A)

OTHER HAD ACCEPTABLE DATA. AND THE SYSTEM II ESW PUMPS (52C AND 52D) WERE ALS NOT APPLICABLE O SHOWN TO BE CPERABLE. DUE TO THE OPERABLE ALTERNATE LOOP AND THE OPER DYRON JACKSON PUMPS. INC.

ABLE REDUNDANT PUMP, THE SAFETY SIGNIFICANCE IS MINIMAL.

THE CAUSE WAS ATTRIBUTED TD A CLOGGED PUMP SUCTIDH STRAINER. THE PUMP S TRAINER WAS CLEARED BY USE OF A SERVICE AIR CONNECTIDH TO THE SUCTION PI PING, AND THE PUMP WAS TESTED AGAIN AND THE NEW DATA WAS ACCEPTABLE. TH E REMAINING ESW PUMPS WERE ALSO TESTED AND SHOWN TO BE OPERABLE AS REQUI RED BY THE TECHNICAL SPECIFICATIONS, FEEAGRAPH 3.4.C.4.

OYSTER CREEK-1 05000219 011281 0F JANUARY 12. DURING THE MONTHLY VISUAL INSPECTION OF FIRE HYDRANTS, HY FIRE PROTECTION SYS + CONT 81-003/03L-0 020931 DRANT 82 WAS FOUND TO HAVE WATER' FROZEN IN THE BARREL. RENDERING IT INOP VALVES 036124 30-DAY ERABLE. THE SIGNIFICANCE OF THIS EVENT WOULD HAVE BEEN MINIMAL DUE TO T OTHER HE CLOSE PROXIMITY OF FIRE HYDRANT #3.

PAST EXPERIENCE HAS SHOWN THAT T COMPONENT FAILURE HIS IS THE FIRST OCCURRENCE OF THIS TYPE AT OYSTER CREEK.

MECHANICAL KENNEDf VALVE MFG. CO.

THE CAUSE OF THE OCCURRENCE WAS DUE TO WATER LEAKING FROM THE HYDRANT VA LVE AND THEN FREEZING IN THE BARREL DURING SEVERE LOW TEMPERATURE CONDIT IONS.

FIRE HOSE WAS ROUTED FROM HYDRANT #3 TO HYDRANT #2, AND THE HYDRA NT WAS THAWED OUT AND LATER RETURNED TO SERVICE. THE FUTURE ACTION WILL BE TO REPAIR THE HYDRANT OPERATING VALVE.

i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 65 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAUSE DESCRIPTION OYSTER CREEK-1 05000219 011581 DURING SURVEILLANCE TESTING, THE REACTOR TRIPLE LOW WATER LEVEL INDICATO ENONRD SAFETY FEATR INSTR SYS 81-006/03L-0 020981 R SWITCH RE-18B TRIPPED AT A MANOMETER READING HIGHER THAN THE LIMIT OF INSTRUMENTATION + CONTROLS 036125 30-DAY 216.0"H2O AS GIVEN IN THE TECHNICAL SPECIFICATIONS, TABLE 3.1'.1, ITEM G.

SWITCH 2.

THE TRIP POINT VALUE WAS 129.0"H20.

THE SAFETY SIGNIFICANCE IS CONS COMPONENT FAILURE IDERED MINIMAL SINCE THE REDUNDANT TRIP SYSTEM WOULD HAVE INITIATED THE INSTRUMENT REQUIRED PROTECTIVE ACTIONS WITHIN THE TECHNICAL SPECIFICATION LIMIT.

ITT-BARTON THE CAUSE OF THE OCCURRENCE WAS INSTRUMENT DRIFT.

THE SWITCH WAS RESET TO TRIP WITHIN THE TECHNICAL SPECIFICATION LIMIT OF 121.0"H2O TO 123.0"H 20.

POSSIBLE SETPOINT CHANGES TO ACCOUNT FOR INSTRUMENT REPEATABILITY A RE CURRENTLY BEING STUDIED.

OYSTER CREEK-1 05000219 011681 RECENT STUDIES HAVE INDICATED THAT DURING A LOSS OF COOLANT ACCIDENT WIT EMERG GENERATOR SYS + CONTROLS 81-004/01T-0 013081 H A LOSS OF OFF-SITE POWER PLUS A SINGLE BUS FAILURE THE LOAD ON THE EME GENERATORS 036038 2-WEEK RGENCY DIESEL GENERATORS MAY EXCEED THE FULL LOAD RATING OF 2500 KW. THI GENERATOR S EVENT IS CONSIDERED REPORTABLE PER TECH. SPEC. 6.9.2.A(9). ALTHOUGH TH DESIGN / FABRICATION ERROR E LOAD ON THE DIESEL GENERATOR IS NOT EXPECTED TO EXCEED THE PEAK LOAD R DESIGN ATING OF 2750 KW THE OPERATORS HAVE BEEN PROVIDED GUIDANCE VIA A STANDIN ELECTRO-MOTIVE DIV.

G ORDER WHICH WILL REDUCE THE LOAD TO LESS THAN THE FULL LOAD RATING.

CAUSE WAS ATTRIBUTED TO USING MORE CONSERVATIVE METHODS OF DETERMINING T HE DIESEL GENERATOR LOAD DURING ACCIDENT CONDITIONS. A STANDING ORDER H AS BEEN ISSUED WHICH HILL REDUCE THE LOAD ON THE DIESEL GENERATOR TO HIT 1

HIN THE CONTINUOUS FULL LOAD RATING.

OTHER ANTICIPATED ACTIONS INCLUDE INSTALLING UNDERVOLTAGE DEVICES ON HON-ESSENTIAL LOADS.

PALISADES-1 05000255 010781 DURING ROUTINE TESTING OF SAFETY INJECTION EQUIPMENT, HPSI MOTOR-OPERATE EMERG CORE COOLING SYS + CONT 81-003/03L-0 020581 D VALVE MCV-3011 FAILED TO OPEN UPON INITIATION OF TEST SIGNAL.

REDUNDA RELAYS 036162 30-DAY NT EQUIPMENT WAS OPERABLE. VALVE WAS STROKED OPEN AND MAINTAINED OPEN U TIMER, SEQUENCER, T-S CONTROL HTIL REPAIRS WERE COMPLETED. LCO OF TECHNICAL SPECIFICATION 3.3.2E AND COMPONENT FAILURE REPORTING REQUIREMENTS OF TECH. SPEC. 6.9.2.32 APPLY.

ELECTRICAL FANSTEEL, INC.

INVESTIGATION REVEALED DIRTY CONTACTS'IN DBA SEQUENCER (34-3).

CONTACTS WERE CLEANED AND PROPER VALVE OPERATION WAS RESTORED.

PALISADES-1 05000255 011981 DURING PERFORMANCE OF FIRE SPRINKLER SYSTEM TESTING. THE DRAIN VALVE IN FIRE PROTECTION SYS + CONT 81-006/03L-0 021681 THE SOUTHWEST CABLE PENETRATION ROOM FIRE SPRINKLER SUPPLY LINE FAILED.

VALVES 036164 30-DAY THE CONDITION OCCURRED DURING OPENING OF THE VALVE.

A CONTINUOUS FIRE WATCH WITH FIRE SUPPRESSION EQUIPMENT WAS ESTABLISHED. SPRINKLER SYSTEM GATE COMPONENT FAILURE WAS INOPERABLE FOR APPROXIMATELY 20 MINUTES.

LCO OF TECHNICAL SPECIFIC-MECHANICAL ATION 3.22.3 AND REPORTING REQUIREMENT 5 OF TECH SPEC 6.9.2.32 APPLY.

EV POWELL, M.

W.,

CD.

ENT IS NOT REPETITIVE. NO ADVERSE EFFECT ON PUBLIC HEALTH OR SAFETY.

THE VALVE TMV 504 FPS) HAD A PREVIOUS HISTORY OF-LEAKAGE, WHICH HAD-BEEN CONTROLLED BY TIGHTENING OF THE VALVE BONNET.

OVERTIGHTENING APPARENTL Y OCCURRED, RESULTING IN WEAKENING OF THE VALVE AND LEADING TO' FAILURE (

BONNET BECAME SEPARATED FROM VALVE BODY).

VALVE WAS REPLACED.

PAGE 66 LER MONTHLY REPORT SORTED BY-FACILITY MAR 26, 1981 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAUSE DESCRIPTION PALISADES-1 05000255 012181 DURING NORMAL PLANT OPERATION, COPPER TUBING TO PS-1473 (1-2 DIESEL-GENE EMERG GENERATOR SYS + CONTROLS 81-005/01L-0 021681 RATOR SERVICE WATER LOW PRESSURE ALARM) BROKE.

TO MAKE REPAIRS, THE DIE ENGINES, INTERNAL COMBUSTION 036173 30-DAY SEL GENERATOR WAS MADE INOPERABLE; AS A RESULT, THE LCD OF-T.S. 3.7.2I W AS ENTERED.

ENGINE WAS RESTORED TO OPERABLE STATUS WITHIN TIME REQUIRED-SUBCOMPONENT NOT APPLICABLE BY T.S.

3.7.2I.

EVENT NOT REPETITIVE. NO THREAT TO PUBLIC HEALTH OR S COMPONENT FAILURE AFETY.

MECHANICAL ALCO ENGINE DIV., WHITE IND.

A CONTRACTOR WORKMAN ACCIDENTLY BUMPED THE TUBING, CAUSING IT TO BREAK.

THE WORKMAN IMMEDIATELY NOTIFIED THE PLANT SHIFT SUPERVISOR. THIS EVEN T HAS BEEN REVIEWED WITH THE CONTRACTOR SITE PROJECT ENGINEER: THE NEED-FOR WORKMEN TO EXERCISE CAUTION WHEN WORKING NEAR SAFETY RELATED EQUIPME NT WAS EMPHASIZED.

I PALISADES-1 05000255 012881 DURING EVALUATION OF MASONRY WALLS PER IE BULLETIN 80-11, IT WAS DETERMI OTHER SYSTEMS 81-004/01T-0 021181 NED THAT 28 MALLS DID NOT MEET ACCEPTANCE CRITERIA. A TOTAL OF 64 WALLS OTHER COMPONENTS 036163 2-WEEK WERE EVALUATED. THE 60 A 180 DAY RESPONSES TO BULLETIN 80-11 (CPCO LET TERS DATED 7/9/80 8 11/6/80) PROVIDE ADDITIONAL INFORMATION. FUTURE REP SUBCOMPONENT NOT APPLICABLE ORTS CONCERNING THIS f.ER WILL BE PROVIDED IN FOLLOW-UP RESPONSES TO IE B ULLETIN 80-11 DUE TO ANTICIPATED CHANGES IN ACCEPTANCE CRITERI A, IT IS l

DESIGN / FABRICATION ERROR DESIGN EXPECTED THE NUMBER OF DISCREPANT W.4LS WILL'BE REDUCED.

BECHTEL CORP.

THE ORIGINAL DESIGN OF BLOCK WILLS CONFORMED TO INDUSTRY STANDARDS IN EF FECT AT THE-TIME OF CONCTRUCTION AND APPARENTLY DID NOT CONSIDER ALL POS TULATED LOADINGS (EG. SEISMIC, TORNADO). t1ETHODS TO CORRECT DISCREPANCI ES ARE BEING DEVELOPED AND WILL BE IMPLEMENTED WHEN MATERIALS ARE AVAILA BLE AND SCHEDULING CONSIDERATI0HS PERMIT.

DURING CONTROL ROD AND RECIRC FLOW ADJUSTMENTS, WITH THE UNIT AT POWER, PEACH BOTTOM-2 05000277 010381 REACTOR TRIP SYSTEMS 81-0 0 7/ 0 3 L-0 020281 THE APRM FLUX SCRAM TRIP SETTING MAS BETWEEN 2.88 AND 5.60% HIGHER THAN THE SETTING SPECIFIED IN TECH. SPEC. 2.1.A.1 IT WAS OUT OF ADJUSTMENT COMPONENT CODE NOT APPLICABLE 036040 30-DAY FOR APPROXIMATELY 6 HOURS AND WAS PROMPTLY RESET WHEN DISCOVERED. BASED SUBCOMPONENT NOT APPLICABLE INDICATED CORE MAXIMUM FRACTION OF CRITICAL PCWER DURING THIS PERIOD ON PERSONNEL ERROR AND AS DISCUSSED IN TECH. SP EC. B ASES 2.1. A. NO SAFETY LIMIT WOULD HAV OTHER E BEEN EXCEEDED HAD A WORST CASE TRANSIENT OCCURRED.

ITEM NOT APPLICABLE THE EVENT UAS CAUSED BY AN ENGINEER'S FAILURE TO MAKE NECESSARY ADJUSTME NTS TO THE APRM GAINS.

THE GAINS WERE PROMPTLY RESET WHEN THE ERROR WAS DISCOVERED. 4 DISCUSSION WAS HELD BY THE STATION REACTOR ENGINEER WITH f

APPROPRI ATE N JCLEAR ENGINEERING PERSONNEL CONCERNING THE'IMPORTANCE OF MONITORING AND TIMELY ADJUSTMENT OF APRM GAINS.

PEACH BOTT0t-2 05000277 011681 DURING POWER OPERATIONS, A GROUP THREE ISOLATION WAS INITIATED. ONE GRO TORUS VENT VALVE A0-2514, FAILED TO CLOSE AUTOMATICALLY UP THREE VALVE.

CNTHMNT ISOLATION SYS + CONT 81-005/03L-0 012981 UPON RECEIPT OF THE ISOLATION SIGNAL AND WOULD HOT CLOSE USING THE REMOT VALVE OPERATORS 036039 30-DAY E VALVE CONTR0t % WITCH.

IM ACCORDANCE WITH TECH. SPEC. 4.7.D.2 THE OTHE R ISOL ATION VALVE IN THE LINE ( AO-2513) WAS VERIFIED CLOSED AND MONITORE SOLENDID - AC COMPONENT FAILURE D DAILY TO VERIFY THAT IT REMAINED CLOSED UNTIL REPAIRS WERE COMPLETED 0 MECHANICAL N A0-2514.

ASCO THE CAUSE OF FAILURE WAS A STICKING SOLENOID VALVE ( ASCO CAT. 38300 D9RF

).

ON JANUARY 16. THE SOLENDID WAS FREED AND THE VALVE SUCCESSFULLY CLO SED.

OH JANUARY 21 THE SOLENDID VALVE WAS REPL ACED IN KIND AND TESTED SATISFACTORILY.

MAR 26, 1981 LER MONTHLY REPORT SDRTED BY FACILITY PAGE 67 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAUSE DESCRIPTION PEACH BOTTOM-2 05000277 L11781 WITH THE PLANT AT POWER, THE

'D' MAIN STEAM LINE (MSL) RAD MONITOR FAILE REACTOR TRIP SYSTEMS 81-006/03L-0 021381 D IN THE TRIPPED CONDITION, AND WAS MAINTAINED TRIPPED PER TECH. SPEC. T INSTRUMENTATION + CONTROLS 036165 30-DAY ABLE 3.1.1.

DURING REPAIRS. THE ' A' MONITOR CABLE WAS ERRONEOUSLY DISCO SENSOR /C57ECTOR/ ELEMENT NNECTED. A PLANT SHUTDOWN WAS INITIATED PER TECH. SPEC. TABLE 3.1.1, UN PERSONNEL ERROR TIL THE MONITOR WAS RETURNED TO SERVICE IN APPROXIMATELY 2 HOURS.

BECAU MAINTENANCE 8 REPAIR PERSONNEL SE THE

'D' MONITOR REMAINED TRIPPED DURING THE EVENT, THE REQUIRED PROTE GENERAL ELECTRIC CO.

CTIVE ACTION WOULD HAVE BEEN INITIATED ON MSL HIGH RAD LEVELS.

THE CAUSE WAS TECHNICIAN ERROR.

REPAIR WORK WAS BEING DONE HURRIEDLY DU E TO EXTREMELY HIGH TEMPERATURES IN THE AREA AND IT UAS ASSUMED THE

'D' MONITOR WAS HEXT TO THE

'D' MS LINE.

PROPER INSTRUMENT IDENTIFICATION T ECHNIQUES UERE REVIEUED WITH THE TECHNICIANS. THE RAD MONITOR CABLES WI LL BE MORE CLEARLY MARKED DURING THE HEXT APPROPRIATE OUTAGE.

PEACH BOTTOM-3 05000278 121880 DURING SHUTDOUN OF UNIT, OPERATOR OBSERVED THAT RCIC INBOARD STEAM SUPPL REAC COPE ISOL COOL SYS + CONT 80-031/03L-0 011381 Y ISOLATION VALVE DID NOT AUTOMATICALLY CLOSE AS REQUIRED. APPLICABLE T VALVE OPERATORS 033680 30-DAY ECH SPEC IS 3.5.D.1.

DUTBOARD STEAM SUPPLY VALVE CLOSED AUTOMATICALLY A OTHER S REQUIRED. VALVES HORMALLY AUTOMATICALLY CLOSE WHEN MAIN STEAM PRESSUR COMPONENT FAILURE E DECREASES BELOW 105 PSIG.

LOW PRESSURE ISOLATION LOGIC WAS TOTALLY OP MECHANICAL ERABLE.

LIMITORQUE CORP.

VALVE CLOSING TORQUE SWITCH ON TYPE SMB LIMITORQUE OPERATOR FOR VALVE MD 3-13-15 WAS FOUND OPEN.

SWITCH WAS REPLACED. VALVE OPERATION AND RESP 0 NSE TO AN ISOLATION SIGNAL WERE SATISFACTORILY TESTED AND VALVE WAS RETU RNED TO SERVICE ON DECEMBER 19, 1980.

t PEACH BOTTOM-3 05000278 010981 DURING A ROUTINE SURVEILLANCE TEST WITH THE UNIT AT POWER, IT WAS FOUND EMERG CORE COOLING SYS + CONT 81- 0 0 2/ 0 3 L-0 020681 THAT A0-5247 (HPCI TURBINE EXHAUST INBOARD DRAIN ISOLATION VALVE) WOULD UALVES 036126 30-DAY NOT FULLY STROKE EITHER OPEN OR CLOSED. THE VALVE WAS DECLARED INOPERAB GLOBE LE AND OUTBOARD ISOLATION VALVE AD-5248 WAS CLOSED. THE VALVES UERE PLA COMPONENT FAILURE CED ON THE INOPERABLE ISOLATION VALVE DAILY LOG.

REPAIR WAS COMPLETED 0 MECHANICAL H A0-5247 ON THE SAME DAY (1/9/81).

APPLICABLE TECHNICAL SPECIFICATION BLACK-SIVALS-BRYSON IS 37D.

THE VALVE PACKING FOLLOWER WAS FOUND TO BE COCKED, WHICH PREVENTED FREE VALVE STEM TRAVEL.

THE VALVE IS A SIVALLS AND BRYSON MODEL, 70-271DRTSX GLOBE.

THE PACKING FOLLCUER WAS REALIGNED, THE PACKING RE-TENSIONED, A ND 1HE VALVE STROKED SUCCESSFULLY ON JANUARY 9, 1981.

PEACH BOTTOM-3 05000278 011381 DURING A SURVEILLANCE TEST, WITH THE UNIT AT FULL POWER, AN OIL LEAK OF CNTHMNT HEAT REMOV SYS + CONT 81-003/01T-0 012781 ABOUT 3 TO 5 GPM WAS DISCOVERED ON THE DIL SUPPLY LINE TO THE HPCI TURBI VALVES 036041 2-WEEK ME MANUAL /0VERSPEED TRIP MECHANISM.

IF HPCI TURBINE HAD STARTED WITH OI NEEDLE L LEAKING FR0il THE LINE, DIL WOULD STILL HAVE BEEN SUPPLIED TO THE BEARI COMPONENT FAILURE NGS FOR ABOUT 30 MINUTES AT REDUCED PRESSURE. AT THAT POINT A TURBINE B MECHANICAL EARING LOW PRESSURE ALARM WOULD HAVE BEEN RECEIVED. REMAINING ECCS SYST ROBERTSHAW CONTROLS CD.

EMS WERE IMMEDIATELY VERIFIED TO BE OPERABLE.

THE CAUSE WAS DETERMINED TO BE A RUPTURED DIAPHRAGM ON THE ROBERTSHAW OI L PRESSURE CONTROL VALVE MODEL VC-210.

A NEW-DIAPHRAGM WAS INSTALLED IN THE VALVE AND THE SYSTEM SATISFACTORILY TESTED AND RETURNED T0-SERVICE ON JANUARY 13, 1981

.~

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 68 PROCESSED DURING 11 ARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION PEACH BOTTOM-3 05000278 012781 DURING SURVEILLANCE TESTING WHILE AT POWER, THE SETPOINT OF TEMPERATURE EMERG CORE COOLING SYS + CONT 81-005/03L-O 021981 SWITCH TS 5943 B (HPCI STEAM LINE AREA HIGH TEMP. ISOLATION) WAS FOUND T INSTRUMENTATION + CONTROLS 036166 30-DAY 0 BE GREATER THAN THE TECHNICAL SPECIFICATION TABLE 3.2.B LIMIT OF 200 D SWITCH EG.

F.

BY 6 DEG.

F.

THIS IS ONE OF 16 SWITCHES IN FOUR TRIP SYSTEMS THA COMPONENT FAILURE T PROVIDE HPCI SYSTEM ISOLATION IN THE EVENT OF HIGH TEMPERATURE IN THE ELECTRONIC VICINITY OF THE HPCI STEAMLINE. THE REMAINING TEMPERATURE SWITCHES WERE OTHER OPERABLE.

THE INSTRUMFMTATION ERROR WAS CAUSED BY SETPOINT DRIFT.

THE INSTRUMENT (MODU-FLASH SERIES 600) WAS IMMEDIATELY RECALIBRATED TO WITHIN TECHNICAL SPECIFICATION LIMITS, TESTED, AND RETURNED TO SERVICE.

PILGRIM-1 05000293 120980 A FIRE WHICH OCCURRED IN THE SECURITY BUILDING'S MECHANICAL ROOM ON 12/9 SYSTEM CODE NOT APPLICABLE 80-095/03L-0 011981

/80, WAS DETECTED AT APPROXIMATELY 1552 HRS. BY SECURITY PERSONNEL AND E COMPONENT CODE NOT APPLICABLE 033681 30-DAY XTINGUISHED WITHIN TEN MINUTES.

THE SECURITY PERSONNEL IMMEDIATELY NOTI SUBCOMPONENT NOT APPLICABLE FIED THE CONTROL ROOM AND THE SENIOR FIRE PROTECTION ENGINEER, HOWEVER, OTHER STATION PROCEDURE NUMBER 5.5.1 WAS NOT FOLLOWED IN THAT THE WATCH ENGINE NOT APPLICABLE ER DID NOT SUMMON THE FIRE BRIGADE.

ITEM NOT APPLICABLE FIRE DID NOT INVOLVE PROCESS BUILDINGS. THIS KNOWLEDGE INHIBITED STATIO N PERSONNEL FROM SUMMONING FIRE BRIGADE.

A MEMO WILL BE ISSUED TO FIRE BRIGADE PERSONMEL CONCERNING NECESSITY TO SUMMON FIRE BRIGADE AS REQUIRE D BY PROCEDURE NUMBER 5.5.1.

ADDITIONALLY THE REQUIREMENT WILL BE EMPHA SIZED DURING THE NEXT FIRE BRIGADE TRAINING.

PILGRIM-1 05000293 010781 ON JANUARY 7, 1981, AT APFROXIMATELY 0113 AND AGAIN AT 1430 HOURS. THE M PRCSS + EFF RADIOL MONITOR SYS 81-002/03L-0 020681 AIN STACK SAMPLE FLOW ALARM WAS RECEIVED ON PANEL C903 IN THE CONTROL RO PUMPS 036127 30-DAY OM.

INVESTIGATION REVEALED THAT IN THE FORMER CASE, THE SUCTION LINE TO VANE TYPE THE STACK GAS SAMPLE PUMP P143 WAS PLUGGED, AND IN THE LATTER CASE, THE COMPONENT FAILURE PUMP'S FUSE WAS BLOWN.

ON BOTH OCCASIONS A CONTROLLED SHUTDOWN WAS INI ELECTRICAL TIATED AS REQUIRED BY TECHMICAL SPECIFICATION 3.8.B.5.

GAST MANUFACTURING CORPORATION ON THE FIRST OCCASION, THE SUCTION LINE WAS FOUND FROZEN. THE BREAKER W HICH ENERGIZES THE HEAT TRACING ON THE SUCTION LINE WAS FOUND "0FF" AND RETURNED TO THE "0N" POSITION. ON THE S3COND OCCURRENCE. THE PUMP'S POW ER SUPPLY FUSE WAS FOUND BL0uH AND REP! ACED.

CURRENT PLANT PRACTICES AR E ADEQUATE TO DETECT AND RESOLVE PROBLEMS OF THIS NATURE.

POINT BEACH-1 05000~266 121780 AT 1210 HOURS, 12/17/80, DURING TESTING,4D EMERGENCY DIESEL GENERATOR (C EMERG GENERATOR SYS + CONTROLS 80-016/03L-0 011581 OMMON TO UNITS 1 AND 2) FAILED TO CLOSE IN ON BUS.

3D EMERGENCY DIESEL MECHANICAL FUNCTION UNITS 033632 30-DAY GENERATOR WAS TESTED TO VERIFY ITS OPERABILITY. 4D EMERGENCY DIESEL GEN SUBCOMPONENT NOT APPLICABLE ERATOR WAS RETURNED TO SERVICE AT 1530 HOURS.

BECAUSE THE REDUNDANT EME COMPONENT FAILURE RGENCY DIESEL GENERATOR WAS OPERALLE, THE PUBLIC HEALTH 3 SAFETY WERE NO MECHANICAL T AFFECTED. EVENT LED TO A DEGRADED MODE OF OPERATION PERMITTED BY TECHN GENERAL MOTORS ICAL SPECIFICATIONS.

ADEQUATE ENGINE SPEED WAS NOT SENSED BY BUS BREAKER CLOSING LOGIC DUE TO SLIPPAGE OF A GENERAL MOTORS ELECTROMOTIVE DIVISION FLEXIBLE SHAFT COUP-LING (P.N. 8276102) ON THE SPEED SENSING FREQUENCY GENERATOR DRIVE SHAFT THE COUPLING WAS SECURED.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 69 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

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REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION POINT BEACH

  • 05900266 0?D281 AT 0139 HOURS ON 01/02/81 THE SUPPLY BREAKER FOR SAFEGUARDS MOTOR CONTR AC ONSITE POWER SYS + CONTROLS 81-001/01T-0 011681 OL CENTER 1B42 TRIPPED WHILE PERFORMING A MONTHLY VENTILATION SYSTEM TES CIRCUIT CLOSERS / INTERRUPTERS 036128 2-WEEK T.

THE UNIT MAS AT ABOUT 70% STEADY STATE POWER AT THE TIME.

THE LOSS CIRCUIT BREAKER OF 1B42 RESULTED IN A LOSS OF THE 1Y04 INSTRUMENT BUS.

THE LOSS OF THE OTHER 1YO4 BUS RESULTED IN A MOMENTARY VIOLATION OF THE MINIMUM DEGREE OF REDU NOT APPLICABLE NDANCY REQUIRED BY TECHNICAL SPECIFICATIONS AND IS REPORTABLE PER TECH.

WESTINGHOUSE ELECTRIC CORP.

SPEC.

15.6.9.2.A.2.

THE 1YO4 INSTRUMENT BUS WAS SHIFTED TO ITS ALTERNATE POWER SUPPLY AT 014 0 HOURS AND POWER WAS RESTORED TO 1B42 AT 0141 THE SAME DAY.

THE CAUSE OF THE BREAKER TRIP WAS FOUND TO BE DUST IN THE INSTANTANEOUS TRIP VALVE ON THE BREAKER.

THE WESTINGHOUSE TYPE DB-50 BREAKER WAS CLEANED, TESTE D, AND RETURNED-TO-SERVICE.

POINT BEACH-1 05000266 011381 ON 01-13-81, DURING NORMAL OPERATION, A POST ACCEPTANCE REVIEW OF THE AN CONT ROOM HABITBLTY SYS + CONT 81-002/03L-0 020481 NUAL TEST RESULTS FROM 04-80. FOR THE CONTROL ROOM EMERGENCY FILTRATION FILTERS 036213 30-DAY SYSTEM, REVEALED THAT THE 1980 ANNUAL TEST WAS NOT COMPLETE PER TECH. SP SUBCOMPONENT NOT APPLICABLE EC.

15.4.11.

AT THIS TIME. THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM PERSONNEL ERROR (COMMON TO BOTH UNITS) WAS DEEMED INOPERABLE BY TECH. SPEC. DEFINITION.

RADIATION PROTECTIDH PERSONNEL THIS LED TO A DEGRADED MODE OF OPERATION ALLOWED BY TECH. SPECS.

THE P ITEM NOT APPLICABLE UBLIC HEALTH & SAFETY WERE NOT AFFECTED AS SYS, IN REALITY, WAS OPER.

THE EVENT WAS CAUSED BY HEALTH PHYSICS PERSONNEL FAILING TO DETERMINE, D URING THE ACCEPTANCE REVIEW, THAT THE TEST L ACKED SYSTEM VELOCITY AND FL OW INFORMATION. THE TEST WAS REPEATED AND THE SYSTEM UAS FOUND TO PERF0 RM SATISFACTORILY ON 01-15-81.

THE TESTING PROCEDURES ARE BEIMG MODIFIE D TO ASSURE THAT SYSTEM VELOCITY AND FLOW INFORMATION IS INCLUDED.

PRAIRIE ISLAND-1 05000262 122280 DURING SURVEILLANCE TEST, ONE STEAM EXCLUSION ACTUATION BISTABLE TRIPPED AIR COND. HEAT, COOL. VENT SYSTEM 80-038/C3L-0 012181 AT 123F, 3F ABOVE THE 120F LIMIT.

REDUNDANT TRAIN WAS OPERABLE. NO EF INSTRUMENTATION + CONTROLS 033683 30-DAY FECT ON PUBLIC HEALTH AND SAFETY.

LAST SIMILAR EVENT WAS RO 79-22.

SWITCH COMPONENT FAILURE INSTRUMENT FOXBORO CO., THE DRIFT OF A FOXBORD MODEL 63U-CC-OHDR-F BISTABLE. INSPECTED AND CALIBRAT ED.

RETEST WAS SATISFACTORY.

PRAIRIE ISLAND-1 05000282 011281 WHILE PERFORMING PIPING MnDIFICATION WORK IN THE AREA 0F NO. 11 AUXILIAR FEEDWATER SYSTEMS + CONTROLS 81-001/03L-0 021081 Y FEEDAATER PUMP, A WORKMAN ACCIDENTALLY BUMPED THE OVERSPEED TRIP MECHA VALVE OPERATORS 036129 30-DAY NISM, TRIPPING THE VALVE AND MAKING THE PUMP INOPERABLE FOR ABOUT 12 MIN MECHANICAL UTES.

THE EVENT WAS ANNUNCIATED IN THE CONTROL ROOM.

RECENT SIMILAR EV PERSONNEL ERROR ENT WAS RO 80-26.

TECHNICAL SPECIFICATION 3.4.A.2.B APPLIES.

NO EFFECT MAINTENANCE & REPAIR PERSONNEL ON PUBLIC HEALTH OR SAFETY.

REDUNDANT EQUIPMENT WAS OPERABLE.

GIMBEL MACHINE WORKS PERSONNEL ERROR.

THE VALVE OPERATOR WAS RESET.

MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 70 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM /COMPONEN1/

DOCKET NO./

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REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION QUAD CITIES-1 05000254 121780 WHILE PLACING STANDBY CAS TREATMENT IN A NORMAL STANDBY OPERATION. SUCTI REACTOR CONTAINMENT SYSTEMS 80-033/03L-0 010681 ON VALVE MD-1-7503 FAILED TO OPEN FROM THE CONTROL ROOM.

THE MO-1-7503 CIRCUIT CLOSERS / INTERRUPTERS 033724 30-DAY VALVE WAS OPENED MANUALLY THUS ENABLING BOTH "A" AND "B" TRAINS OF STAND CONTACTOR COMPONENT FAILURE BY GAS TREATMENT TO BE OPERABLE AND CAPABLE OF NAINTAINING REACTOR BUILD ELECTRICAL ING NEGATIVE PRESSURE HAD THE NEED ARISEN.

CENERAL ELECTRIC C3.

INVESTIGATION OF THE VALVE BREAKER fdVEALED THAT THE AUXILIARY CONTACTS WERE DIRTY AND NOT MAKING PROPER CGNTACT.

THE AUXILIARY CONTACTS WERE R EMOVED. CLEANED. AND REPLACED. VALVE MD-1-7503 WAS TESTED AND OPERATED SATISFACTORILY FROM THE CONTROL ROOM ON DECEMBER 18. 1980.

QUAD CITIES-1 05000254 010581 AT 9: 10 A.M. WHILE PLACING THE "B" STANDBY GAS TREATMENT SYSTEM IN A NOR REACTOR CONTAINMENT SYSTEMS 81- 0 01/ 0 3 L-0 012081 MAL SHUTDOWN LINE-UP, DISCHARGE VALVE MD-1/2-7507B FAILED TO CLOSE WHEN CIRCUIT CLOSERS / INTERRUPTERS 036130 30-DAY OPERATED FROM THE CONTROL ROOM.

TPE "A" STANDBY GAS TREATMENT SYSTEM WA CONTACTOR COMPONENT FAILURE S DEMONSTRATED OPERABLE IN ACCORDAd'5 WITH TECHNICAL SPECIFICATION 3.7.B

.A.

AND WAS FULLY CAPABLE OF MAINTAfdTNG A NEGATIVE REACTOR BUILDING DIF ELECTRICAL FERENTIAL PRESSURE HAD THE NEED ARISEN.

GENERAL ELECTRIC CO.

UPON INVESTIGATION IT WAS DISCOVERED THAT THE BREAKER AUXILIARY CONTACTS WERE WORN AND STICKING: THUS PREVENTING VALVE MD-1/2-7507B FROM CLOSING

. THE CONTACTS WERE REPLACED WITH CONTACTOR KIT 500E17 AND THE VALVE WA S TESTED SATISFACTORILY. THE "B" STANDBY GAS TREATMENT SYSTEM WAS RETUR NED TO SERVICE AT 1:30 P.M. ON JANUARY 5.

1981.

QUAD CITIES-1 05000254 010781 WHILE DEMOHCTRATING UNIT 1 EMERGENCY DIESEL GENERATOR OPERABILITY AFTER EMERG GENERATOR SYS + CONTROLS 81-002/03L-0 012081 MONTHLY PREVENTATIVE MAINTENANCE INSPECTION, THE DIESEL C-ENERATOR TRIPPE ENGINES. INTERNAL COMBUSTION 036131 30-DAY D.

ATTEMPTS TO RESTART THE DIESEL GENERATOR FAILED WHEN PROPER SPEED CD SUBCOMPONENT NOT APPLICABLE NTROL COULD NOT DE ACHIEVED. THE DIESEL GENERATOR WAS DECLARED INOPERAT COMPONENT FAILURE IVE AT 0930.

ALL REDUNDANT SYSTEMS WERE IMMEDIATELY DEMONSTRATED UPERAB ELECTRICAL WESTERN ENGINE CO.

LE IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.9.E.1 INVESTIGATION SHOWED A LOOSE FUSE IN THE 125 VDC ENGINE STARTING AND FUE L CONTROL CIRCUIT. A SLIGHT MISALIGNMENT OF THE DIESEL GENERATOR'S OUTP UT BREAKER AUXILIARY CONTACTS WAS ALSO FOUND.

THE FUSE HOLDER WAS TIGHT ENED AND THE BREAKER AUXILIARY CONTACTS ADJUSTED. THE DIESEL GENERATOR WAS DEMONSTRATED UPERABLE AND RETURNED TO SERVICE AT 1705 OH 1/7/81.

OUAD CITIES-1 05000254 011481 WHILE PERFORMING THE HIGH DRYWELL PRESSURE ECCS INITIATION CALIBRATION A ENGNRD SAFETY FEATR INSTR SYS 81-003/03L-0 012181 ND FUNCTIONAL TES

T. PROCEDURE

QIS-7. PRESSURE SWITCH PS-1-1001-90D WAS F INSTRUMENTATION + CONTROLS 036132 30-DAY OUND TO TRIP AT 2.03 PSIC.

THIS WAS HIGHER THAN THE 2.0 PSIG LCO SETPOI-SWITCH HT DEFINED IN TECHNICAL SPECIFICATION TABLE 3.2-2.

THE REhAINING PRESSU COMPONENT FAILURE RE SWITCHES IN THE ONE-0UT-OF-TWO-TWICE LOGIC SCHEME WERE WITHIH THEIR R INSTRUMENT EQUIRED SETPOINTS AND WOULD HAVE PROVIDED AN ECCS INITIATION HAD THE NEE STATIC-0-RING D ARISEN.

THE CAUSE OF THIS OCCURRENCE WAS INSTRUMENT SETPOINT DRIFT. PRESSURE SW ITCH PS-1-1001-90D WAS IMMEDI*TELY RECALIBRATED AND FUNCTIONALLY TESTED SATISFACTORILY.

E v

i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FfCILITY PAGE 71 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /CDMPONENT/

DOCKET NO./

EVENT DATE/

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REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION i

OUAD CITIES-2 05000265 121080 A SERIES OF SIX TRIPS DCCURRED OF THE 2A REACTCR RECIRCULATION PUMP MOTO COOLANT RECIRC SYS + CONTROLS 80-038/03L-0 010781 R GENERATOR SET FIELD BREAKER. ON EACH OCCASICH THE RECIRCULATION PUMP' INSTRUMENTATION + CONTROLS 033684 30-DAY MOTOR GENERATOR SET WAS RESTARTED WITHOUT DIFFICULTY AND THE REQUIREMENT TRANSMITTER S OF TECH. SPEC. 3.6.H.3 WERE SATISFIED EACM TIME.

COMPONENT FAILURE i

ELECTRICAL GENERAL ELECTRIC CO.

AFTER EXTENSIVE TESTING BY COMMONWEALTH EDISCN COMPANY PERSONNEL AND A MANUFACTURER REPRESENTATIVE, IT WAS DETERTIINED THAT TACHCMETER WHICH CO HTROLS PUMP SPEED WAS DEFECTIVE. TACHOMETER WAS REPLACED CN DECEMBER 31 1980 AND THE RECIRCULATION PUMP MG SET HAS SHOWN SATISFACTORY PERFORM ANCE SINCE THAT TIME.

QUAD CITIES-2 05000265 122880 AFTER PUMPING THE ERYWELL EQUIPMENT DRAIN SUMP, CUTBOARD ISOLATION VALVE CNTHMNT ISOLATI0H SYS + CONT 80-035/03L-0 011681 A0-2-2001-16 REQUIRED APPROXIMATELY 15 MINUTES TO GIVE CLOSED INDICATI0 VALVE OPERATORS 033725 30-DAY N.

TECHNICAL SPECIFICATIONS REQUIRE A CLOSURE TIME OF LESS THAN OR EQUA PHEUMATIC/ DIAPHRAGM / CYLINDER L TO 20 SCCONDS. 'THE REDUNDANT ISCLATION VALVE AD-2-2001-15 WAS PLACED COMPONENT FAILURE IN THE CLOSED POSITION. I5OLATION CAPABILITY OF THE EQUIPMENT DRAIN SUM MECHANICA(

P WAS ALWAYS INTACT.

CRAME COMPANY THE POSITION INDICATION LIMIT SWITCH AND THE LENGTH OF VALVE STEM TRAVEL 1

WERE OUT OF ADJUSTMENT. THE STROKE OF THE VALVE STEM WAS LENGTHENED, T HE PACKING WAS ADJUSTED, AND THE LIMIT SWITCHES WERE ADJUSTED. THE A0-2

-2001-16 VALVE WAS CYCLED THREE TIMES SATISFACTORILY WITH A CLOSURE TIME OF 4.2 SECONDS.

QUAD CITIES-2 05000265 123080 AT 0840 WHILE ATTEMPTING TO TRANSFER WATER FROM THE SUPPRESSION CHAMBER RESIDUAL HEAT REMOV SYS + CONT 80-039/03L-0 012281 TO THE MAIN CONDENSER HOTWELL USING THE "A" RHR LOOP. VALVE MO-2-1001-34 CIRCUIT CLOSERS / INTERRUPTERS 033744 30-DAY ' A FAILED TO OPEN FROM THE CONTROL ROOM.

THE "B" LCOP OF RHR WAS DEMONST CONTACTOR RATED OPERABLE AND SURVEILLANCE WAS STARTED TO DEMONSTRATE ADEOUATE CORE COMPONENT FAILURE COOLING CAPABILITY IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.5.B.

T ELECTRICAL HE "A" LOOP OF RHR CONTAINMENT COOLING WAS OPERABLE AT 1100 DECEMBER 30,'

GENERAL ELECTRIC CO.

1980.

THE CAUSE OF MO-2-1001-34A NOT CPENING WAS CORRODED ELECTRICAL CONTACTS ON THE AUXILIARY CONTACTOR IN THE VALVE BREAKER.

THE CONTACTS WERE REPL ACED AND MD-2-1001-3( A WAS OPERATED TH2cE TIMES SATISFACTORILY.

QUAD CITIES-2 05000265 011681 WHILE PERFORMING THE HIGH DRYWELL PRESSURE CALIBRATION AND FUNCTIONAL TE REACTOR TRIP SYSTEMS 81-001/03L-0 012181 S

T. PROCEDURE

QIS-6, PRESSURE SWITCH PS-1-1001-88D WAS FOUND TO TRIP AT INSTRUMENTATION + CONTROLS 036133 30-DAY 2.13 PSIG.

THIS WLS HIGHER THAN THE 2.0 PSIG LCD SETPOINT DEFINED IN TE SWITCH CHNICAL SPECIFICATION TABLE 3.1-1 THE REMAINING THREE PRESSURE SWITCHE COMPONENT FAILURE S IN THE ONE-0UT-OF-TWD-TWICE LOGIC SCHEME WERE WITHIN THEIR REQUIRED SE INSTRUMENT TP0INTS AND WOULD HAVE PROVIDED A REACTOR SCRAM IF HIGH DRYWELL PRES 5URE

. STATIC-0-RING HAD OCCURRED.

THE CAUSE OF THIS OCCURRENCE WAS INSTRUMENT SETPOINT DRIFT.

PRESSURE SW ITCH PS-1-1001-88D WAS IMMEDIATELY RECALIBRATED AND FUNCTIONALLY TESTED SATISFACTORILY.

l MAR 26, 1981 LER MONTHLY REPORT SDRTED BY FACILITY PAGE 72 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

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REPORT DATE/

EVENT DESCRIPTION /

{

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION 1

QUAD CITIES-2 05000265 011681 WHILE PERFORMING ROUTINE SURVEILLANCE TEST QIS 40-1,-THE PRESSURE CONTRO MAIN STEAM SYSTEMS + CONTROLS 81-002/03L-0 020381 LLER FOR ELECTROMATIC RELIEF VALVE 2-203-3B WAS FOUND TO TRIP AT 1181 PS INSTRUMENTATION + CONTROLS 036134 30-DAY I.

THIS IS IN EXCESS OF THE 1130 PSI LIMIT SET'BY TECHNICAL SPECIFICATI t

7-SWITCH ON 4.6.E.

ALL OTHER ELECTROMATIC RELIEF VALVES WOULD HAVE OPENED AT THE t

COMPONENT FAILURE REQUIRED PRESSURE HAD THE NEED ARISEN AND ELECTROMATIC RELIEF VALVE 2-2 l

INSTRUMENT 03-3B COULD HAVE BEEN OPENED REMOTELY FROM THE CONTROL RCOM.

DRESSER INDUST. VALVE A INST D I

THE CAUSE OF THIS DCCURRENCE IS INSTRUMENT DRIFT.

THE PRESSURE CONTROLL ER WAS IMMEDIATELY RECALIBRATED AND TESTED SATISFACTORILY. A FAULTY MIC

{

ROSWITCH WITHIN THE CONTROLLER WAS SUSPECTED TO CONTRIBUTE TO THE INSTRU MENT DRIFT.

THE MICROSWITCH WAS REPLACED OH 1-31-81 AND THE INSTRUMENT

.WAS TESTED SATISFACTORILY. THE PRESSURE CONTROLLER IS MODEL 1539VX.

RANCHO SECO-1 05000312 010881 TO PROVIDE ADDITIONAL INFORMATION REGARDING ADEQUACY OF STATION ELECTRIC CONT ROOM HABITBLTY SYS + CONT 81-001/02T-0 012081 AL DISTRIBUTION SYSTEM VOLTAGE, DISTRICT CONTRACTED A/E TO PERFORM FIELD-CIRCUIT CLOSERS / INTERRUPTERS 036016 2-WEEK TESTS OH VARIOUS 820V AC CONTROL DEVICES. ~ON 1/8/81 A/E NOTIFIED DISTR i

STARTER ICT THAT ONE TYPE OF CONTROL DEVICE, SIZE 3 (NEMA) STARTER COILS WOULD N OTHER OT OPERATE AT A DEGRADED VOLTAGE OF 214KV IN SWITCHYARD. SAFETY RELATED NOT APPLICABLE EQUIPMENT AFFECTED IS EMERGENCY CONTROL ROOM AIR CONDITIDHER, U-545.

GENERAL ELECTRIC CD.

ACTUAL RECORDED DEGRADED VOLTAGE CONDITION ON GRID IS LOWER THAN ORIGINA LLY ANTICIPATED. DESIGN MODIFICATION WILL BE PERFORMED DURING 2/1/81 RE l

FUELING DUTAGE. ADMINISTRATIVE CONTROLS IN EFFECT PRECLUDE SAFETY RELAT ED BUSES BEING SUBJECTED TO DEGRADED VOLTAGE CONDITIONS ASSOCIATED WITH 214KV IN SWITCHYARD.

L RANCHO SECD-1 05000312 011281 DN 1-12-81, A CCW SYSTEM SAMPLE SHOWED A TRITIUM LEVEL GREATER THAN MDA.

.l COOL SYS FOR REAC AUX + CONT 81-002/03L-0 020581 A BACKUP SAMPLE VERIFIED THAT SOME LOW-LEVEL ACTIVITY WAS. IN FACT, PRE-HEAT EXCHANGERS 036135 30-DAY SENT IN'THE CCW SYSTEM. PER IE BULLETIN 80-10. A SAFETY EVALUATION WAS P COOLER ERFORMED. SAFETY EVALUATION DETERMINED THAT OPERATION OF SYSTEM DID NOT l

COMPONENT FAILURE CONSTITUTE AN UNREVIEWED SAFETY QUESTION HOR RERUIRE A TECH. SPEC.-CHANG 1

MECHANICAL E. CONTINUED OPERATION WAS IN COMPLIANCE WITH'ALL APPLICABLE REGULATIONS GRAHAM MANUFACTURING COMMITMENTS AND THE TECHNICAL SPECIFICATICNS.

A LEAK SEARCH PROGRAM DETERMINED THAT "A" LETDOWN COOLER, E-220A, WAS SO URCE OF CONTAMINATION.

"A" COOLER WILL BE ISOLATED DURING 7YCLE 5 OPERAT i

IONS EXCEPT DURING SPECIFIC PERIODS WHEN INCREASED COOLING CAPACITY IS'R EQUIRED.' OPERATION WILL BE IN COMPLIANCE WITH ALL APPLICABLE REGULATIONS f

COMMITMENTS AND THE TECHNICAL SPECIFICATIONS.

RANCHO SECD-1 05000312 012581 A REVIEW OF THE JANUARY 1981 EFFLUENT MONITORING CHARTS INDICATED THAT-r

}

COOL SYS FOR REAC AUX + CONT 81-005/04L-0 021881 THE PLANT LIQUID EFFLUENT PH EXCEEDED THE 8.5 LIMIT ESTABLISHED BY TECHN INSTRUMENTATION + CONTROLS 036244 30-DAY ICAL SPECIFICATIONS, APPENDIX B, SECTION 2.4.

OM JANUARY 25,.1981, THE OTHER tH MOMENTARILY INCREASED TO 8.6 FOR APPROXIMATELY 10 MINUTES. A SIMILAR COMPONENT FAILURE OCCURRENCE IN THE LATTER PART OF 1980 WAS REPORTED VIA LER 80-36.

0THER -

OTHER i

SINCE THERE WERE NO INDICATIONS THAT'AN EFFLUENT DIVERSION TO THE RETENT ION BASINS HAD OCCURRED, A CHECK OF THE DIVERSICH SYSTEM SETPOINT WAS MA l

DE..THE DIVERSION SETPOINT WAS SLIGHTLY OUT-OF-TOLERANCE (ACTUATED AT-8'

.55).

TO MINIMIZE RECURRENCE. THE DIVERSION SETPOINT WAS RESET TO 8.4 +

/

.1 AND THE ALARM SETPOINT WILL BE LOWERED TO 8.3 +/-

.1 I

t

., ~ - -.

.., ~ - +,

---,n.,

l' I

l l

l l

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 73 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS l

FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION ROBERT E. GINNA-1 05000244 010581 DURING MONTHLY SURVEILLANCE, OPERATOR NOTED LEAK ON "B" DIESEL EMERGENCY EMERG GENERATOR SYS + CONTROLS 81-001/03L-0 012881 GENERATOR (EG) iACKET COOLING WATER RETURN LINE TO EXPANSION TANK COMIN PIPES FITTINGS 036104 30-DAY G FROM A BROKEN BUSHING.

(TECHNICAL SPECIFICATION 3.7.1).

"A".EG WAS I LESS THAN 4 INCHES MMEDIATELY PLACED IN SERVICE.

PERSONNEL ERROR CONSTRUCTION PERSONNEL BECHTEL CORP.

POSSIBLE LACK OF CONNECTION OF SUPPORT DURING ORIGINAL CONNECTION OR PER SONNEL INVOLVED IN MODIFICATION INSTALLATION IN AREA MAY HAVE BUMPED LIN E.

BUSHING IS 3/4" PLASTIC FOR ATMOSPHFRIC PRESSURE SERVICE. REPLACED BUSHING, ADDED COUPLING FOR FUTURE NAINTENANCE EASE.

ROBERT E. GINNA-1 05000244 010981 DURING TEST "C" SI PUMP DID NOT START WITH BUS 16 BREAKER.

(TECHNICAL S EMERG CORE COOLING SYS + CONT 81-002/03L-0 013081 PECIFICATION 3.3.1.1C).

THE "C" PUMP HAD BEEN PROVEN OPERABLE USING EUS CIRCUIT CLOSERS / INTERRUPTERS 036105 30-DAY 14 BREAKER DURING THIS TEST AS MELL AS THE OTHER 2 PUMPS.

AFTER EXAMIN.

CIRCUIT BREAKER ING BREAKER FOR POSITION, BREAKER WAS FULLY RACKED OUT, THEN FULLY RACKE COMPONENT FAILURE D IN, AND OPERATION PROVED SUCCESSFUL.

ELECTRICAL WESTINGHOUSE ELECTRIC CORP.

BREAKER POSSIBLY IN "0FF-SET" POSITION INDICATED BY POSITIONING DEVICE P IN NOT MOVING FREELY IN POSITIONING STOP BRACKET FULLY-RACKED-IN SLOT.

AT NEXT TEST, ELECTRICIANS TO EXAMINE BREAKER BEFORE CLOSING 8 AFTER OPE HING.

TRAINING IN PROPER BREAKER ALIGNMENT 8 REPORTING RACK-IN PROBLEMS HILL BE EMPHASIZED. BREAKER IS WESTING 9 DB-50 AIR CIRCUIT BRK. 500-AMP ROBERT E. GINNA-1 05000244 011581 DURING NORMAL REACTOR COOLANT BORATION, OPERATOR OBSERVED ABSENCE OF BOR CHEM, VOL CONT + LIQ POISH SYS 81-003/03L-0 021381 IC ACID FLOW FROM "A" BORIC ACID PUMP. HE PUT "B" BORIC ACID PUMP IN 8 D VALVES 036106 30-DAY ECLARED "A" PUMP INOP. (TECH. SPEC. 3.2.3B). INVESTIGATION SHOMED SUCTIO DIAPHRAGM N VALVE PARTLY CLOSED. VALVE WAS IMMEDIATELY REOPENED. IT WAS FOUND THAT PERSONNEL ERROR DURING HORMAL SAMPLING. A H.P.

TECHNICIAN HAD THROTTLED THE VALVE 8 APP CONTRACT. & CONSULT. PERSONNEL ARENTLY REOPENED IT. HE NOTED DIAPHRAGM VALVE STEM INDICATION RISER WAS GRINNELL CORP.

LOOSE, 8 REPORTED THIS.

VALVE APPARENTLY WAS NOT FULL OPEN AFTER SAMPLING, 8 PIPEFITTER SCREWING IN STEM INDICATION RISER CAUSED VALVE TO FURTHER CLOSE. BORIC ACID SYST EM ALIGNMENT 4 TESTING OF "A" PUMP PERFORMED SATISFACTORILY. SUPT. SHALL ISSUE NOTICE STRESSING APPROVED MAIN

T. PROCEDURE

S FOR SAFETY RELATED SY STEMS. BORIC ACID PUMP SUCTION VALVES WILL BE LOCKED OPEN.

SALEM-1 05000272 060180 DURING ROUTINE SURVEILLANCE TESTING OF THE FIRE DETECTION INSTRUMENTION, FIRE PROTECTION SYS + CONT 80-030/03X-1 020481 THE FUSIBLE PLUG FOR THE BATTERY ROOM DETECTORS FOR BOTH UNIT 1 AND UNI INSTRUMENTATION + CONTROLS 031460 OTHER T 2 HAD MELTED DURING THE TESTING, RENDERING THEM INOPERABLE. ACTION ST SENSOR / DETECTOR / ELEMENT ATEMENT 3.3.3.6 WAS ENTERED AT 0700 HOURS.

DEFECTIVE PROCEDURES NOT APPLICABLE OTHER A HOT AIR BLOWER WAS USED TO RAISE TEMPERATURE OF THE DETECTOR TO AN ALA RM CONDITION, BUT WAS NOT REMOVED QUICKLY ENCUGH TO PREVENT DETECTOR DAM AGE. DETECTORS WERE REPLACED 8 TESTED SATISFACTORILY, TERMINATING ACTION STATEMENT AT 2106 HOURS ON 6/3/80. DESIGN CHANGES WERE INITIATED ON 9/

15/80, WHICH WILL REPLACE EXISTING DETECTORS WITH A NON-EXPENDADLE TYPE.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 74 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 072580 AT 0030 HOURS ON JULY 25, 1980, ALL OUTSIDE TELEPHONE COMMUNICATION WAS COMMUNICATION SYSTEMS 80-040/01X-1 020481 LOST INCLUDING THE DIRECT DEDICATED LINE BETWEEN SALEM STATION AND THE N ELECTRICAL CONDUCTORS 031918 OTHER RC INCIDENT RESPONSE CENTER IN BETHESDA MARYLAND.

SUBCOMPONENT NOT APPLICABLE OTHER NOT APPLICABLE WESTERN ELECTRIC APPARENTLY. A PERSON OR PERSONS UNKNOWN IN AN ACT OF MALICICUS VANDALISM OR DELIBERATE SABOTAGE CUT ALL THE PHONE LINES LEADING TO THE STATION.

EMERGENCY NEASURES WERE TAKEN TO MAINTAIN LIMITED OUTSIDE COMMUNICATION S UNTIL NORMAL PHONE LINES WERE RE-ESTABLISHED ON JULY 26, 1980.

THE NE W JERSEY STATE POLICE IS CONTINUING THEIR INVESTIGATION OF THIS EVENT.

SALEM-1 05000272 010581 DURING HORMAL OPERATIONS WITH THE REACTOR AT 89% OF RATED THERMAL POWER.

REACTOR CORE 81- 0 01/ 0 3 L- 0 013081 THE INDICATED AXIAL FLUX DIFFERENCE IN TWO CHANNELS DRIFTED OUT OF THE COMPONENT CODE NOT APPLICABLE 036068 30-DAY RZQUIRED TARGET BAND.

ACTION STATEMENT 3.2.1A.2 WAS ENTERED AT 0200 HOU SUBCOMPONENT NOT APPLICABLE RS ON JANUARY 5.

1981 THIS EVENT CONSTITUTES A REPORTABLE INCIDENT PER PERSONNEL ERROR TECHNICAL SPECIFICATION 6.9.1.9B.

LICENSED & SENIOR OPERATCRS ITEM NOT APPLICABLE ANTICIPATED INCREASE IN AXIAL FLUX DIFFERENCE WHILE INCREASING REACTOR P OMER LEVEL WAS CREATER IN MAGNITUDE THAN THAT EXPECTED BY OPERATING STAF F.

REACTOR POWER LEVEL WAS REDUCED TO 87% 1 AXIAL FLUX DIFFERENCES RETU RNED TO VALUES WITHIN REQUIRED TARGET BAND.

THIS IS THE FIRST ATTEMPT T 0 BRING THIS NEW CORE TO 100% RATED THERMAL POWER.

SALEM-1 05000272 010881 DURING NORMAL OPERATIONS AT 0530 HOURS ON JANUARY 8, 1981. INDICATION IN STATION SERV WATER SYS + CONT 81-002/03L-0 020581 THE CONTROL ROOM OF SERVICE WATER FLOW TO THE NO. 14 FAN COIL UNIT WAS HEATERS.ELEClRIC 036069 30-DAY LOST.

ACTION STATEMENT 3.6.2.3 WAS ENTERED AT THIS TIME.

THIS EVENT RE SUBCOMPONENT NOT APPLICABLE SULTED IN OPERATION IN A DEGRADED MODE PER TECHNICAL SPECIFICATION 6.9.1 PERSONNEL ERROR

.9.B.

LICENSED & SENIOR OPERATORS 2 TEM NOT APPLICABLE PORTABLE PROPANE HEATERS INSTALLED IN NORTH PENETRATION SERVICE WATER CD MPARTMENTS HAD RUN OUT OF FUEL.

SERVICE WATER IN INSTRUMENT LINES FROZE RESULTING IN NO INDICATION IN CONTROL ROOM.

EMPTY FUEL TANKS WERE REPL ACED WITH FULL TANKS.

ACTION STATEMENT WAS TERMINATED AT 16 30 HRS.

AS OF 1/20/81 ALL PORTABLE PROPANE HEATERS HAVE BEEN REPLACED W/ ELECTRIC.

SALEM-1 05000272 010981 DURING NORMAL OPERATION AT 0800 HOURS ON 1/9/81 THE #12 CCWHX WAS REMOV STATION SERV WATER SYS + CONT 81-003/03L-0 020581 ED FROM SERVICE TO REPAIR A LEAKING PIPE NIPPLE WHICH CONNECTS THE SERVI PIPES. FITTINGS 036070 30-DAY CE WATER DRAIN VALVE 125W124 WITH THE HEAT EXCHANGER TUBE SHEET.

ACTION LESS THAN 4 INCHES STATEMENT 3.7.3.1 WAS ENTERED SINCE TWO OPERABLE CCW LOOPS WERE NOT AVA COMPONENT FAILURE ILABLE FOR PLANT SERVICE PER TECHNICAL SPECIFICATION REQUIREMENTS.

METALLURGICAL D0YLE, M. J. CO.

WELD CONNECTING MONEL METAL TUBE SHEEi t THE CARBON STEEL PIPE NIPPLE WA S LEAKING NIPPLE WAS REPLACED & THE WitDED CONNECTION COMPLETELY REWOR KED.

A DESIGN CHANGE HAS BEEN INITIATED.'HICH WILL REPL ACE THE CARBON S TEEL PIPE NIPPLE W/0NE MADE OF MONEL METAL JHICH WILL-ALLOW A BETTER FUS ION OF WELD.

ACTION STATEMENT WAS TERMINATED AT 1400 HRS ON 1/11/31

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 75 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS

. FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 011581 DURING NORMAL OPERATIONS AT 0950 HOURS ON 1/15/81 WHILE PERFORMING TEST FIRE PROTECTION SYS + CONT 81-006/03L-0 020981 5 ON THE FIRE ALARM SYSTEM, IT WAS DISCOVERED THAT NO AUDIBLE FIRE ALARM INSTRUMENTATION + CONTROLS 036137 30-DAY WOULD SOUND.

ACTION STATEMENT 3.3.3.6 WAS INITIATED, AN OPERATOR WAS OTHER STATIONED AT THE FIRE ALARM PANEL IN THE CONTROL ROOM TO CONTINUALLY MON OTHER ITOR THE P ANEL FOR VISUAL FIRE ALARM SIGNALS.

NOT APPLICABLE GAI-TROMICS CORP AN IMPEDANCE MISMATCH WAS CREATED BETWEEN TONE GENERATOR OF FIRE ALARM S YSTEM & REMAINDER OF SYS WHEN ADDITIONAL PAGE EXTENSION PHONES & ROTATIN G FIRE ALARM BEACONS WERE ADDED AS ADDITIONAL LOADS TO TONE GEN. VOX-ANU X AMPLIFIER IN TONE GEN. UNIT WAS ADJUSTED TO OBTAIN CURRENT IMPEDANCE M ATCH. ACTION STATEMENT WAS TERMINATED AT 1225 HOURS ON 1/15/81.

SALEM-1 05000272 011981 WHILE IN THE HOT STANDBY CONDITION ON 1/19/81, AT 1500 HOURS. THE NRC RE EMERG CORE COOLING SYS + CONT 81-0 0 7/ 01T-0 013081 SIDENT INSPECTOR REQUESTED THAT THE THROTTLE VALVES WHICH BALANCE FLOW T VALVES 036071 2-WEEK HROUGH THE SAFETY INJECTION LOOPS BE INSPECTED TO VERIFY THAT THEY WERE GLOBE ALL IN THEIR REQ" IRED POSITIONS. VALVES 14SJ16, 11SJ138 12SJ138 AND 13S DEFECTIVE PROCEDURES J138 WERE NOT IN THEIR CORRECT POSITIONS. THE INCORRECTLY POSITIONED VA NOT APPLICABLE LVES MAY HAVE PREVENTED THE FULFILLMENT OF THE FUNCTIONAL REQUIREMENTS 0 ROCKWELL MANUFACTURING CO.

F THE SYSTEM TO COPE WITH ACCIDENTS ANALYZED IN THE SAR.

EVENT WAS THE RESULT OF PROCEDURE INADEQUACY. TO INSURE THAT ALL THROTT LING VALVES IN THIS SYSTEM ARE RETURNED TO THEIR EXACT REQUIRED POSITION S FOLLOWING ANY EVOLUTION RECUIRING A VALVE LINE-UP,-ON-THE-SPOT CHANGES HAVE BEEN MADE TO APPROPRIAIE PROCEDURES. AN ENGINEERING REVIEW OF EVE NT WILL BE MADE 8 RESULTS WILL BE REPORTED IN A SUPPLEMENTARY REPORT.

SALEM-1 05000272 011981 DURING NORMAL OPERATION ON JANUARY 19, 1981. WHILE PERFORMING A DAILY SU CONT ROOM HABITBLTY SYS + CONT 81-004/03L-0 021281 RVEILLANCE TEST ON THE CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM IS OTHER COMPONENTS 036245 30-DAY OLATION DAMPERS, DAMPER 1CAA3 FAILED TO CLOSE DURING THE TEST AND WAS DE SUBCOMPONENT NOT APPLICABLE CLARED INOPERABLE, PER TECHNICAL SPECIFICATION REQUIREMENTS, ACTIUN STA EXTERNAL CAUSE TEMENT 3.7.6.1.D WAS ENTERED AT 0810 HOURS.

NOT APPLICABLE AEROFIN CORP.

ICE HAD FORMED ON THE LOUVERS OF THE DAMPERS PREVENTING THEIR CLOSING.

THE ICE WAS THE RESULT OF UNUSUALLY COLD AMBIENT TEMPERATURES. WHEN MAI HTENANCE PERSONNEL ARRIVED AT THE DAMPER LOCATION, MOST OF THE ICE HAD M ELTED.

THE DAMPER WAS TESTED SATISFACTORILY AND DECLARED OPERABLE. THE ACTION STATEMENT WAS TERMINATED AT 1040 HOURS ON JANUARY 19, 1981.

SALEM-f 05000272 012481 DURING NORMAL OPERATION AT 0550 HOURS ON 1/24/81, THE CARRIAGE GUIDE WIR OTHER COOLANT SUBSYS + CONTROL 81-003/03L-0 021281 E OF THE AUXILIARY ANNUNCIATOR TYPEURITER BROKE.

THIS RESULTED IN THE L INSTRUMENTATION + CONTROLS 036246 30-DAY OSS OF THE CONTAINMENT SUMP LEVEL MONITORING SYSTEM.

ACTION STATEMENT 3 RECORDER 4.6.1.B WAS ENTERED.

A LAMP WAS CONNECTED ACROSS THE CONTAINMENT SUMP COMPONENT FAILURE PUMP BREAKER AND AN OPERATOR WAS STATIONED AT THE BREAKER TO RECORD THE MECHANICAL OPERATING TIME OF THE PUMP UNTIL REPAIRS TO THE TYPEWRITER WERE COMPLETE IBM CORP D.

THE BROKEN CARRIAGE GUIDE WIRE WAS REPLACED BY AN IBM MAINTENANCE TECHNI CIAN.

THE ACTION STATEMENT WAS TERMINATED AT 2106 HOURS ON 1/24/81.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 76 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 012681 DURING NORMAL OPERATION ON 1/26/81, #11 CONTAINMENT FAN COIL UNIT WAS DE STATION SERV WATER SYS + CONT 81-010/03L-0 021981 CLARED INOPERABLE IN ORDER TO REPLACE A LEAKING SPOOL PIECE IN THE SERVI PIPES. FITTINGS 036248 30-DAY CE WATER LINE TO UNIT.

ACTION STATEMENT 3.6.2.3 WAS ENTERED AT 1730 HOU to TO 16 INCHES RS.

AT 1907 HOURS, REACTOR TRIPPED.

IN ORDER TO CHANGE OPERATIONAL MOD COMPONENT FAILURE E,

FAN COIL UNIT HAD TO BE DECLARED OPERATIONAL. SURVEILLANCE TEST SP(0 METALLURGICAL

) 4.6.3.2(A) MAS PERFORMED WITH SATISFAC10RY RESULTS AND FAN COIL UNIT W D0YLE, M.

J. CO.

AS DECLARED OPERATIONAL. ACTION STATEMENT WAS TERMINATED AT 2106 HOURS.

NO REPAIRS WERE MADE AT THIS TIME.

SALEM-1 05000272 012881 DURING NORMAL OPERATION WHILE PERFORMING A ROUTINE FUNCTIONAL TEST ON TH REACTOR TRIP SYSTEMS 81-005/03L-0 021281 E REACTOR PROTECTION SYSTEM (HIGH STEAM FLOW, CHANNEL II FOR SAFETY INJE INSTRUMENTATION + CONTROLS 036218 30-DAY CTION) AT 0820 HOURS ON JANUARY 28, 1981, THE SAFETY INJECTION SIGNAL CO OTHER ULD NOT BE GENERATED. PER TECH. SPEC. 3.3.2.B NORMAL OPERATION CONTINUE COMPONENT FAILURE D WITH THE INOPERABLE CHANNEL PLACED IN THE TRIPPED CONDITION. A MORK 0 ELECTRONIC RDER WAS ISSUED TO TROUBLESHOOT AND REPAIR THE CHANNEL.

PREVIOUS SIMILA HAGAN CORPORATION R EVENTS WERE:

77-42, 78-44, 78-64, 79-34 AND 80-46.

UPON TRCUBLESH00 TING THE CHANNEL, IT WAS FOUND THAT THE COMPARATOR UNIT (HAGAN MODEL 4111082-001) HAD FAILED.

THE DEFECTIVE MODULE WAS REPLACED WITH A SPARE.

THE REPLACEMENT UNIT WAS CALIBRATED AND A SATISFACTORY C HANNEL FUNCTIONAL TEST WAS COMPLETED. THE CHANNEL WAS RETURNED TD GPERA TION AT 1050 HOURS ON 1/28/81 SALEM-1 05000272 012981 DURING NORMAL OPERATIONS ON 1/29/81, IT WAS DISCOVERED THAT THE CCNTAIAN REAC COOL PRES BOUN LEAK DETEC 81-009/01L-0 021281 ENT SUMP HAD 4.3 GPM OF UNIDENTIFIED LEAKAGE.

THE EXCESS LEAKAGE WAS MI INSTRUMENTATION + CONTROLS 036247 30-DAY STAKENLY ASSUMED TO BE COMING FROM THE #12 CONTAINMENT FAN COOLING UNIT SENSOR / DETECTOR / ELEMENT AND PER HRC IE BULLETIN NO. 80-24. THE NRC UAS NOTIFIED OF A SERVICE MAT COMPONENT FAILURE ER LEAK IN CONTAINMENT. ON 1/30/81, IT WAS DISCOVERED THAT THC #12 SUMP MECHANICAL PUMP WAS OPERATING ERRATICALLY AND CALCULATIONS.0F ITS DISCHARGE RATE L MANGETROL, INC.

ED OPERATIONS TO BELIEVE THERE WAS AN UNIDENTIFIED LEAK.

APPARENTLY, THE FLOAT ON LD7750 IS LOOSE OR CANTED INSIDE ITS RELL.

THE DETECTOR HAS BEEN ISOLATED AND WILL BE REPLACED OR REPAIRED DURING THE NEXT MAINTENANCE OUTAGE.

A SUPPLEMENTARY REPORT WILL BE SUBMITTED WHEN REPAIRS ARE COMPLETED.

SALEM-1 05000272 020181 DURING NORMAL OPERATION ON 2/1/81, THE #12 CENTRIFUGAL CHARGING PUMP WAS EMERG CORE COOLING SYS + CONT 31-013/03L-0 021981 DECLARED INOPERABLE BECAUSE OF A LEAK IN THE PUMPS OIL COOLER. ACTION l

HEAT EXCHANGERS 036250 30-DAY STATEMENT 3.5.2.A WAS ENTERED AT 0220 HOURS.

SIMILAR OCCURRENCES:

76-2 COOLER 3, 77-34, 77-72, 79-68, 80-38, 80-41 AND 80-49.

COMPONENT FAILURE MECHANICAL AMERICAN STANDARD INDUSTRIES THE LEAKING DIL COOLER WAS REPLACED IN KIND.

THE ACTION STATEMENT WAS T ERMINATED AT 0440 HOURS.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 77 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE'SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SALEM-1 05000272 020181 DURING NORMAL OPERATION ON 2/1/81 THE #12 CENTRIFUGAL CHARGING PUMP WAS EMERG CORE COOLING SYS + CONT 81-014/03L-0 021931 DECLARED INOPERABLE BECAUSE OF OIL LEAKAGE.

ACTION STATEMENT 3.5.2.A W PUMPS 036251 30-DAY AS ENTERED AT 1700 HOURS.

SIMILAR OCCURRENCES:

76-23, 77-34, 77-72, 79 CENTRIFJGAL

~68, 80-38, 80-41, 80-4 9 AND 81-13.

COMPONENT FAILURE MECHANICAL PACIFIC PUMPS LOSS OF OIL CAUSED THE THRUST BEARING TO OVERHEAT AND THE MAIN BEARING T 0 PARTIALLY WIPE.

THE BEARINGS WERE REPLACED.

THE OIL RESERVOIR, ALL B EARING HOUSINGS AND ALL DIL LINES WERE CLEANED AND FLUSHED. A SATISFACT ORY SURVEILLtNCE TEST WAS PERFORMED AND THE ACTION STATEMENT WAS TERMINA TED AT 1400 HOURS ON 2/3/81.

SALEM-1 05000272 020481 DURING NORMAL OPERATION ON 2/4/81, THE #2 FIRE PUMP IN THE FIRE SUPPRESS FIRE PROTECTION SYS + CONT 81-012/03L-0 021981 ION MATER SYSTEM WAS DECLARED IMOPERABLE IN ORDER TO REPAIR A LEAKING IN PIPES, FITTINGS 036249 30-DAY LET COOLING WATER LINE.

ACTION STATEMENT 3.7.10.1CA) WAS ENTERED AT 162 LESS THAN 4 INCHES S HOURS.

COMPONENT FAILURE MECHANICAL

-ANACONDA METAL HOSE CO.

A CORRUGATED STAINLESS STEEL HOSE THAT CONNECTS THE COMMON COOLING MATER PIPING SHARED BY THE PUMP AND ITS STARTING DIESEL WAS LEAKING.

THE HDS E WAS REPLACED IN KIND.

THE ACTION STATEMENT WAS TERMINATED AT 2140 HOU RS.

SALEM-2 05000311 082080 DURING A COOLDOWN, THREE SPURIOUS SIGNALS WERE RECEIVED THAT RESULTED IN REACTOR TRIP SYSTEMS 80-019/03X-1 021981 THE 2C SEC SAFEGUARDS EQUIPMENT BEING STARTED.

TO PRECLUDE UNNECESSARY RELAYS 032059 OTHER OPERATION OF THE-EQUIPr1ENT, THE 2C SEC WAS DE-ENERGIZED AND ACTION STAT SOLID STATE (SCR'S)

EMENT 3.3.2.1 WAS ENTERED AT 1418 HPURS.

SIMILAR OCCURRENCES 12.

OTHER NOT APPLICABLE WESTINGHOUSE ELECTRIC CORP.

WHEN ENTRY INTO MODE S WAS ACHIEVED AT 2310 HRS ACTION STATEMENT WAS TE RMINATED.

LATCHING RELAYS WERE INSTALLED IN PARALLEL WITH XK1 8 XK2 COI LS TO DETECT TRANSIENTS FROM SOLID STATE PROTECTION SYSTEM WHICH COULD C AUSE SEC TO OPERATE.

THESE RELAYS WERE INSTALLED ON 7/28/80 & REMOVED 0 N 9/3/80.

DURING THIS TIME, NO TRANSIENTS DCCURRED. NO ACTION PLANNED.

SALEM-2 05000311 123080 WHILE PERFORMING ROUTINE SURVEILLANCE ON 82B DIESEL GENERATOR. IT WAS DI EMERG GENERATOR SYS + CONTROLS 80-031/03L-0 012981 SCOVERED THAT THE COUPLING CONNECTING TWO SECTIONS OF THE CAMSHAFT HAD A ENGINES, INTERNAL COMBUSTION 033726 30-DAY LL EIGHT OF ITS ATTACHING ~ BOLTS SHEARED. THIS EQUIPMENT FAILURE WAS DIS SUBCOMPONENT NOT APPLICABLE COVERED WITH THE PLANT IN THE COLD SHUTDOWN, BUT THIS EVENT MUST BE REPO COMPONENT FAILURE RTED AS IF THE PLANT HAD BEEN OPERATING IN A DEGRADED MODE IN ACCORDANCE MECHANICAL WITH TECHNICAL SPECIFICATION 6.9.1.9B.

ALCO ENGINE DIV., WHITE IND.

INSPECTION OF THE COUPLING REVEALED THAT ONE OF THE NUTS WAS NOT ATTACHE D TO ITS EOLT.

THIS WOULD INDICATE THAT THE. JOINT MAY NOT HAVE BEEN PRO PERLY LIGHTENED DURING INITIAL ASSEMBLY. TWO NEW CAMSHAFT SECTIONS WITH THEIR ATTACHING BOLTS AND NUTS HAVE BEEN ORDERED. REPAIRS ARE EXPECTED TO BE COMPLETED ON JANUARY 26, 1951

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 78 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SALEM-2 05000311 010481 OURING COLD SHUTDOWN. THE DIESEL UNIT TRIP RELAY ON #2A DIESEL GENERATOR EMERG GENERATOR SYS + CONTROLS 81-001/03L-0 020351 TRIPPED. SINCE DIESEL 82B WAS IHOPERABLE AWAITING REPAIRS. THE MINIMUM ENGINES. INTERNAL COMBUSTION 036072 30-DAY OF TWO OPERABLE DIESEL GENERATORS REQUIRED BY TECHNICAL SPECIFICATIONS SUBCOMPONENT NOT APPLICABLE COULD NOT BE MET.

ACTION STATEMENT 3.8.1.2 WAS ENTERED AT 1353 HCURS.

OTHER NOT APPLICABLE ALCO ENGINE DIV.. WHITE IND.

THE CAUSE OF THE RELAY TRIP REMAINS UNDETERMINED. THE RELAY WAS RESET A ND THE DIESEL GENERATOR WAS DETERMINED OPERABLE UPON THE SATISFACTORY CD MPLETION OF THE REQUIRED SURVEILLANCE TESTS.

THE ACTION STATEMENT-WAS T ERMINATED AT 1556 HOURS.

SAN ONOFRE-1 05000206 112280 WITH RCS DRAINED TO MID LOOP & TRANSFERRING A 4KV BUS POWER SUPPLY FROM-AC ONSITE POWER SYS + CONTROLS 80-038/03L-1 020281 AUX. TRANSFORMER C TO AUX. TRANSFORNER A8B. AC POWER TO ALL STATION AUXI CIRCUIT CLOSERS / INTERRUPTERS 033347 30-DAY LIARIES WAS LOST FOR 15 SECS DUE TO BRKR MISALIGNMENT. IT WAS ALSO NOTED CIRCUIT BREAKER THAT SOURCE BRKR TO 4KV BUS 1C DID NOT DPEN ON LOSS OF VOLTAGE DUE TO A~

PERSONNEL ERROR H OPEN D.C.

SUITCH SUPPLYING POWER TO STATIDH UNDERVOLTAGE SCHEME. THERE LICENSED & SENIOR OPERATORS WAS NO EFFECT UPON PUBLIC HEALTH & SAFETY NOR WAS THERE ANY IMPACT ON PL OTHER ANT SAF. BOTH EMERG. D/G STARTED AUTO. 8 WERE AVAILABLE FOR LOADING.

A LICENSED GPERATOR INTENDING TO OPEN AUXILIARY TRANSFORMER C BUS SUPPLY BREAKERS INADVERTENTLY CPENED THE AKV SUS TIE BREAKERS. THE D.C. PCWER SUPPLY SWITCH TO STATION UNDERVOLTAGE SCHEME WAS INADVERTENTLY OPENED BY PERSONNEL RACKING OUT A NEARBY BRKR.

ADMINISTRATIVE CONTROLS ON SAFETY RELATED D.C. CIRCUITS WILL BE IMPLEMENTED TD PRECLUDE RECURRENCE.

SAN DNOFRE-1 05000206 011681 UNDER A SISLOP CONDITION. IF THE SAFETY INJECTION ACTUATION PARAMETERS 0 EMERG CORE COOLING SYS + CONT 81- 0 01/ 01T-0 011981 SCILLATE ABOUT THEIR SAFETY INJECTIGN SETPOINTS. THE SEQUENCER WILL RESE RELAYS 036219 2-WEEK T AND RE-SEQUENCE THE SAFETY INJECTION LOADS.

IF THESE OSCILLATIONS OCC l

TIMER. SEQUENCER, T-S CONTROL UR PRIOR TO THE COMPLETE LOADING OF THE SIS LOADS. SOME LOADS WILL NOT B DESIGN / FABRICATION ERROR E AUTOMATICALLY-LOADED.

DESIGN CONSOLIDATED CONTROLS CORP.

FOLLOWING A SISLOP.0SCILLATION OF THE SAFETY INJECTION PARAMETERS ABOUT THE SETPOINTS COULD CAUSE RE-SEQUENCING OF THE SIS LOADS SUCH THAT SOME L

LO ADS WOULD NEVER BE LOADED.

THE SEQUENCER SYSTEM IS BEING REDESIGNED $

UCH THAT THIS SCENARIO WILL NOT OCCUR.

SAN ONOFRE-1 05000206 020281 DURING A FIELD VERIFICATION / INSPECTION IN ACCORDANCE WITH IE BULLETIN 79 FEEDWATER SYSTEMS + CONTROLS 81-002/01T-0 021681

-14 SEVERAL MISSING BOLTS WERE DISCOVERED CH FEECWATER LINE 392-10"-EG.

HANGERS. SUPPORTS. SHOCK SUPPRSS 036138 2-WEEK SUBSEQUENT CALCULATIONS INDICATED THAT. WITHOUT THE LOLTS. THE STIFFNES SUPPORTS S CALCULATIONS WOULD BE INVALIDATED AND THE ALLOWABLE PIPING STRESS WOUL COMPONENT FAILURE D PROBABLY BE EXCEEDED DURING AN EARTHQUAKE AS DEFINED IN THE FSAR.

THI MECHANICAL 5 REFORT IS IN CONFORMANCE WITH TECHNICAL SPECIFICATION 6.9.2.A.

BECHTEL CORP.

THE SUPPORTS (BOLTS) WERE REQUIRED BY DESIGN D1SCLOSURE DOCUMENTS; HOWEV ER. IN THE FIELD. SEVERAL BOLTS WERE DISCOVERED MISSING. THE BOLTS WILL BE REPLACED PRIOR TO RETURN TO SERVICE FROM THE CURRENT GUTAGE TO CONFO RM THE SUPPORTS TO THE SEISMIC ANALYSIS INPUT INFORMATION.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 79 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SEQUOYAH-1 05000327 120180 SPECIAL REPORT 80-6.

DURING STEAM GENERATOR MOISTURE CARRYOVER TESTS PE STEAM GEN BLCWDOWN SYS + CONT 80-006/04L-0 123180 RFORMED ON 12/1 3 12/2/80, AN INADVERTENT, UNCONTROLLED DISCHARGE OF THE VALVES 033753 30-DAY RADI0 ACTIVE TRACER (50DIUM-24) OCCURRED. DISCHARGE EVENTUALLY REACHED OTHER THE TENNESSEE RIVER.

APPROX. 79,400 GALS WERE RELEASED OF CONCENTRATION DEFECTIVE PROCEDURES BETWEEN 6.9E-3 TO 0.37 CI.

CAUSE OF EVENT WAS ERROR IN VALVE LINE-UP.

NOT APPLICABLE OTHER THE INCIDENT RESULTED DIRECTLY FROM INADECUATE TEST INSTRUCTIONS AND IMP ROPER COMMUNICATIONS BETWEEN THE TEST DIRECTIONS AND LABORATORY PERSONNE L.

NO PERSONNEL RECEIVED MEASURABLE EXPOSURE. NO DETECTABLE RADICACTIV ITY WAS RELEASED TO THE TENNESSEE RIVER.

TEST INSTRUCTIONS HAVE BEEN CL ARIFIED.

SEQUDYAH-1 05000327 122580 AT 0631 CST WITH UNIT 1 AT'86% RTP, RWST LEVEL INDICATOR t-LI-63-50 FAIL ENGNRD SAFETY FEATR INSTR SYS 80-206/03L-0 012281 ED HIGH.

THE PL ANT ENTERED ACTION STATEMENT 16 0F LCO 3. 3.2.1 AND ACTIO INSTRUMENTATION + CONTROLS 033685 30-DAY N STATEMENT "A" CF LCD 3.3.3.7 UNTIL THE INSTRUMENT CHANNEL WAS RETURNED TRANSMITTER TO SERVICE AT 0928 CST.

THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY OTHER

. f'REVIOUS OCCURRENCES - NONE.

NOT APPLICABLE BARTON INSTRU CO., DIV 0F ITT INSTRUMENT LINES FOR LEVEL TRANSMITTER WERE FROZEN INSIDE INSULATED CABI NET HOUSING TRANSMITTER. DOOR TO CABINET WAS DISCOVERED TO BE AJAR ALLO WING LINES TO FREEZE. LINES WERE THAWED USING A HEAT GUN AND INSTRUMENT LOOP WAS RETURNED TO SERVICE. CABINET DOOR WAS LOCKED TO PREVENT REOCC URRENCE.

SEQUOYAH-1 05000327 122580 AT 86% RTP, S/G-3 TRAIN "A" STEAMLINE PRESSURE I FLOW CHANNELS TAILED HI SAFETY RELATED DISPLAY INSTR 80-202/03L-O 012281 GH AT 0441 CST. ACTION STATEMENTS OF LCO 3.3.3.7(A), 3.3.9 M~J.

& 3.3.2 INSTRUMENTATION + CONTROLS 033727 30-DAY

.1( 16 ) WERE IN EFFECT UNTIL OPER. WAS RESTORED AT 062' UST. AT 0649 CST TRANSMITTER S/G-te 2, & 4 TRAIN "B" FECDWATER FLOW CHANNELS FAILE.1 LOW 3 PLANT "NTER DESIGN / FABRICATION ERROR ED ACTION STATEMENT 7 0F LCO 3.3.1.1 WHEN S/G-1 TRAIN "A" FEEDWATEM FLO DESIGN W CHANNEL SUBSEQ. FAILED LOW AT 0852 CST, PLANT PREPARED FOR SHUTDOWN PE FOXBORO CO.,

THE R LCD 3.0.3 BUT REMAINED AT POWER WHEN OPER. WAS RESTORED AT 0934 CST.

THE INSTRUMENT CHANNELS BECAME INOPERABLE DUE TO FREEZING OF UNPROTECTED SENSE LINES.

THE LINES WERE THAWED BY APPLYING TEMPORARY HEAT AND INSU LATION.

DESIGN CHANGES HAVE BEEN INITIATED TO HAVE THE REQUIRED HEAT TR ACING AND INSULATION INSTALLED TO PREVENT REOCCURRENCE.

SEQUOYAH-1 05000327 122880 WITH UNIT 1 AT 86% RTP, REMOTE SHUTDOWN MONITORING INDICATORS 1-LI-68-32 OTHR INST SYS REQD FOR SAFETY 80-207/03L-0 012681 5C 8 1-LI-68-326C (PRESSURIZER LEVEL) WERE DECLARED INOPERABLE AT 0435 C INSTRUMENTATION + CONTROLS 033686 30-DAY ST WHEN INDICATORS WERE OBSERVED TO BE READING TWELVE PERCENT HIGHER THA TRANSMITTER H INDICATORS IN MAIN CONTROL ROOM.

PLANT ENTERED ACTION STATEMENT "A" 0

OTHER F LCO 3.3.3.5 UNTIL INDICATORS WERE RETURNED TO SERVICE AT 1430 CST ON 1 NOT APPLICABLE

/2/81.

THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY. PREVIOUS OCCURR FOXBORD CO.,

THE ENCES - NDHE.

THE ERRONEDUS INDICATION WAS CAUSED BY A LEAKING VALVE IN A COMMON DRAIN LINE FOR THE TRANSMITTERS. AFTER THE VALVE WAS TIGHTENED DOWN, THE IHS TRUMENT LOOPS WERE RETURNED TO SERVICE AND PROPER OPERATION OF THE. INSTR UMENT LOOPS WERE VERIFIED.

j MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 80 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION

?

SEQUDYAH-1 05000327 122980 UNIT IN MODE 1 AT 86% REACTOR PCMER.

ON 12-29-80 AND AGAIN ON 1-$-81 T

CNTNMNT HEAT REMOV SYS + CONT 80-205/03L-0 012681 WO ICE CONDENSER INTERMEDIATE DECK DOORS BELOW AHU-3A MERE FOUND FROZEN PENETRATIONS.PRIMRY CONTAINMNT 033728 30-DAY CLOSED.

LCO 3.6.5.3 WAS ENTERED ON BOTH OCCASIONS. THERE WAS N3 EFFECT OTHER UPON PUBLIC HEALTH OR SAFETY.

PREVIOUS OCCURRENCES - 2 (REFERENCE SQR0 COMPONENT FAILURE 327/80-170 AND 80-203).

MECHANICAL WESTINGHOUSE ELECTRIC CORP.

ICE WAS REMOVED FROM DOORS WITHIN 24 HOURS ON BOTH OCCASIONS. WATER FR0 ZEN IN ANU-3A DRAIN LIHE DID NOT ALLOM WATER T3 PASS DURING DEFROST CYCL ES.

THE WATER SPILLED OVER FROM DRIP PAN ONTO THE DOORS CAUSING COORS T 0 BECOME FROZEN CLOSED.

SEQUOYAH-1 050C0327 010281 WITH UNIT 1 AT 90% RTP. CONDENSATE STORAGE TANK LEVEL CHANNEL 0-L-2-230 PRCSS + EFF RADIOL MONITOR SYS 81-001/03L-0 013081 WAS DECLARED INOPERABLE AT 1330 CST WHEN THE CONTROL ROOM INDICATOR FAIL PIPES, FITTINGS 036073 30-DAY ED LOU.

THE PLANT ENTERED ACTION STATEMENT 34 0F LCO 3.3.3.9 UNTIL THE LESS THAN 4 INCHES INSTRUMENT CHANNEL WAS RETURNED TO SERVICE AT 1600 CST.

THERE WAS NO EF OTHER FECT ON PUDLIC HEALTH OR SAFETY. NO PREVIOUS OCCURRENCES.

NOT APPLICABLE OTHER THE APPARENT CAUSE OF THE FAILURE WAS AN IMPROPERLY TIGHTENED COMPRESSIO N FITTING ON THE INSTRUMENT SENSE LINE WHICH DECAME DISCONNECTED. THE S ENSE LINE WAS PROPERLY CONNECTED AND THE LEVEL CHANNEL WAS RETURNED TO S ERVICE.

SEQUDYAH-1 05000327 010581 AT 0645 CST ON 1/5/81, WITH UNIT 1 AT 92% RTP. MAIN FEEDWATER FLOW CHANN REACTOR TRIP SYSTEMS 81-003/03L-0 093081 EL F-3-35B (S/G #3) FAILED LOW.

ON 1/12/81 WITH UNIT 1 AT 100% RTP. FE r

INSTRUMENTA1 ION + CONTROLS 036220 30-DAY EDWATER FLOW CHANNEL F-3-35B FAILED AT 0445 CST AND FEEDuaTER FLOW CHANN TRANSMITTER El F-3-90B (S/G #1) FAILED A' 3615 CST.

IN EACH CASE THE PLANT ENTERED DESIGN / FABRICATION ERROR ACTION STATEMENT 7 0F LCO 3.3.1.1.

THERE WAS NO EFFECT ON PUBLIC HEALTH DESIGN OR SAFETY. FOR PREVIOUS DCCURRENCES REFER TO SCRO-50-327/80-202.

FOXBORO CO., THE THE FEEDWATER FLOW CHANNELS FAILED DUE TO FREEZING OF. INADEQUATELY PROTE CTED INSTRUMENT SENSE LINES.

THE LINES WERE THAWED USING A HEAT GUN AND RETURNED TO SERVICE. A PLASTIC ENCLOSURE CONTAINING HEATERS.HAS BEEN E RECTED AROUND THE SENSE LINES TO PREVENT RECURRENCE UNTIL DCR-P-999 (PRE VIOUStY INITIATED) CAN BE IMPLEMENTED.

SEQUOYAH-1 05000327 010981 UNIT 1 IN MODE 1 AT 90% REACTOR POWER.

DURING ROUTINE INSPECTION OF THE CNTNMNT HEAT REMOV SYS + CONT 81-002/03L-0 020481 ICE CONDENSER, TWO INTERMEDIATE DECK DOORS WERE FOUND FROZEN CLOSED.

L PENETRATIONS.PRIMRY CONTAINMNT 036074 30-DAY CO 3.6.5.2 utS ENTERED. THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFET OTHER Y.

PREVIOUS OCCURRENCES - 3 (REFERENCE SCRO-50-327/80-170.80-203. AND

. COMPONENT FAILURE 80-205).

METALLURGICAL WESTINGHOUSE ELECTRIC CORP.

ICE WAS REMOVED FROM DOORS WITHIN 24 HRS.

WATER WAS LEAKING FROM AHU-3A DEFROST DRAIN LINE FLANGE DUE TO LODSE FLANGE BOLTS.

BOLTS WERE RETIGH

'ENED.

INVESTIGATION TO DETERMINE CAUSE OF FLANCE BEING LOOSE DID NOT R T

l EVEAL A CONCLUSIVE OR LOGICAL EXPLANATION. FLANGE IS BEING PERIODICALLY MONITORED IN AN ATTEMPT TO DETERMINE CAUSE & TO PREVENT REOCCURRENCE.

l

- ~ _ _ _,

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 81-PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SEQUDYAH-1 05000327 011281 AT 040C CST WITH UNIT 1 AT 100% RTP, RWST LEVEL CHANNEL L-63-53 FAILED, ENGNRD SAFETY FEATR INSTR SYS 81-004/03L-0 020681 PLACING THE PLANT IN ACTION STATEMENT 18 0F LCO 3.3.2.1 AND ACTION STATE INSTRUMENTATION + CONTROLS 036075 30-DAY MENT "A" 0F LCO 3.3.3.7.

THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY TRANSMITTER

. ONE PREVIOUS OCCURRENCE:

SQRO-50-327/80-206.

DESIGN / FABRICATION ERROR CONSTRUCTION / INSTALLATION 9ARTON INSTRU CO., DIV 0F ITT THE INSTRUMENT CHANNEL FAILED DUE TO FREEZING OF ITS SENSE LINES INSIDE THE INSULATED CABINET HOUSING THE LEVEL TRANSMITTER. AN INVESTIGATION I DENTIFIED THAT INSUFFICIENT INSULATION HAD BEEN INSTALLED AROUND THE SEN SE LINES 8 ON THE SIDES OF THE CABINET. STRIP HEATERS WILL BE USED TO P REVENT RECURRENCE UNTIL PROPER THICKNESS'0F INSULATION CAN BE INSTALLED.

SEQUOYAH-1 05000327 011481 UNIT IN MODE 1 WITH RCS TEMPERATURE 578 DEGREES F AND PRESSURE 2235 PSIG EMERG CORE COOLING SYS + CONT 81-006/03L-0 020281 IT WAS DISCOVERED DURING A REVIEW OF MR'S THAT ON 9/29/80, DURING THE VALVES 036076 30-DAY

. PERFORMANCE OF SI-166.10, VALVE 1-FCV-63-38 WAS FOUND TO BE LEAKING APP OTHER ROXINATELY 3 GPM.

AN MR WAS INITIATED TO REPAIR THE VALVE.

AFTER COMPL DEFECTIVE PROCEDURES ETION OF MAINTENANCE THE VALVE WAS NOT STROKE TESTED AS REQUIRED BY SURV NOT APPLICABLE EILLANCE REQUIREMENT 4.0.5.

THERE WAS NO EFFECT UPON PUBLIC HEALTH OR S OTHER AFETY.

PREVIOUS DCCURRENCES SQRO-50-327/80-190 AND 80-200.

THE FAILURE TO PERFORM THE TESTING AS REQUIRED BY SURVEILLANCE REQUIREME NT IS ATTRIBUTED TO AN INADEQUATE PROCEDURE. THE APPROPRIATE STANDARD P RACTICE IS BEING REVISED TO INSURE SURVEILLANCE INSTRUCTIONS ARE PERFORM ED FOLLOWING MAINTENANCE. THE VALVE WAS SATISFACTORILY TESTED ON 11/20/

80.

SEQUOYAH-1 05000327 011481 AT 1005 (C) ON 1/14/81, VITAL INVERTER 2-II FAILED RENDERING VITAL INSTR ONSITE POWER SYSTEM + CONTROL 81-005/03L-0 020581 UMENT POWER BOARD 2-II INOPERATIVE. THERE WAS NO EFFECT CN PUBLIC HEALT GENERATORS 036139 30-DAY H OR SAFETY.

PREVIOUS OCCURRENCES TOTAL OCCURRENCES FOR ALL EIGH INVERTER T INVERTERS.

COMPONENT FAILURE ELECTRICAL STATIC FR0 DUCTS THE FOLLOWING TWO COMPONENTS FAILED WHILE IN SERVICE: C1A CAPACITOR IN T-HE A10 POWER SUPPLY AND THE RB-8 CONTROL-CARD.

THESE COMPONENTS WERE RF-PLACED AND THE INVERTER WAS RETURNED TO SERVICE AT 1755 (C) ON 1/14/81.

PREPARATIONS ARE IN PROGRESS TO REPLACE THIS INVERTER WITH A NEW INVERT ER IDENTICAL TO THOSE INSTALLED ON UNIT 1.

SEQUDYAH-1 05000327 011681 AT 1035 CST WITH UNIT 1 AT 50% RTP, THE LEVEL CHANNEL FOR STEAM GENERATO REACTOR TRIP SYSTEMS 81-007/03L-0 020581 R 33 (L-3-97) UAS DECLARED INOPERABLE WHEN THE TRIP BISTABLE (1-LS-3-97F INSTRUMENTATION + CONTROLS 036077 30-DAY

) FAILED TO DEENERGIZE DURING THE PERFORMANCE OF THE SCHEDULED FUNCTIONA SWITCH L TEST.

THE BISTABLE WAS MANUALLY TRIPPED IN ACCORDANCE WITH ACTION STA COMPONENT FAILURE TEMENT 7 0F LCO 3.3.1.1 THERE WAS NO EFFECT ON PUBLIC HEALTH OR SAFETY-ELECTRONIC

. NO PREVIOUS OCCURRENCES.

FOXBORO CO., THE THE LEVEL CHANNEL FAILED BECAUSE'THE BISTABLE WOULD NOT DEENERGIZE. THE MODULE WAS REPLACED, CALIBRATED, AND RETURNED TO SERVICE. SINCE THIS I S THE FIRST OCCURRENCE OF THIS TYPE, THE FAILURE IS NOT CONSIDERED TO BE-A GENERIC PROBLEM.

i

' MAR 26 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 82 PROCESSED DURING MARCH. 1931 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION i

SEQUDYAH-1 05000327 011681 UNIT IN MODE 1 AT 50% REACTOR POWER. DURING ROUTINE INSPECTION OF THE IC CNTNMNT HEAT REMOV SYS + CONT 81-008/03L-0 001081 E CONDENSER. THREE INTERMEDIATE DECK DOORS WERE FOUND FROZEN CLOSED.

TH PENETRATIONS.PRIMRY CONTAINMNT 036140 30-DAY E DUORS ARE LOCATED UNDER AIR HANDLING UNITS 6A. 8A. AND 8B.

LCO 3.6.5.

OTHER 3 MAS ENTEPED.

THERE WAS NO EFFECT UPON PUBLIC HEALTH OR SAFETY.

PREVI COMPONENT FAILURE 005 OCCURRENCES - 4 (REFERENCES SQRO-50-327/80-170 80-203.80-205. AND ELECTRICAL 81-002).

WESTINGHOUSE ELECTRIC CORP.

WATER FR02E IN THE AIR HANDLING UNITS DEFROST DRAIN LINES CAUSING THE DR AIN LINES TO RUPTURE.

THE WATER FROZE IN THE DRAIN LINES DUE TO A FUSE FAILURE IN THE CONTROLLER FOR ONE SECTION OF HEAT TAPE.

DURING SUBSEQUE NT DEFROST CYCLES WATER SPILLED FROM DRAIN LINES AND FROZE ON DOORS.

IC E WAS REMOVED FROM DOORS WITHIN 24 HOURS.

SEQUDYAM-1 05000327 012781 WITH UNIT 1 IN MODE 3 AND RCS AT 360 F AND 1500 PSIG. CONTAINMEhT SUMP L ENGNRD SAFETY FEATR INSTR SYS 81-009/03L-0 022481 EVEL LOOP L-63-177 WAS DECL ARED INOPERABLE AFTER A CHANNEL CHECK MAS PER INSTRUMENTATION + CONTROLS 036252 30-DAY FORMED.

THE ASSOCIATED BISTABLE WAS PLACED IN THE BYPASS MODE IN ACCORD TRANSMITTER ANCE WITH ACTION STATEMENT 18 0F LCO 3.3.2.1.

THERE WAS NO EFFECT ON PU CCMPONENT FAILURE BLIC NEALTH OR SAFETY. NO PREVIOUS OCCURRENCES.

INSTRUMENT BARTON INSTRU CD.. DIV 0F ITT THE CAUSE FOR THE CALIBRATION DRIFT WAS DIAGNOSED AS A PROBLEM WITH THE LEVEL TRANSMITTER. THE LEVEL TRANSMITTER HAS BEEN REPLACED AND IS BEING TESTED.

FINAL TESTING AND ADDITIONAL REPAIR WORK. IF NEEDED. ARE SCHED ULED TO BE COMPLETED DURING THE UNIT DUTtGE NOW IN PROGRESS.

2EQUOYAH-t 05000327 012881 AT 1515 (C) ON 1/28/81, MODE 1 NOTIFICATION WAS RECEIVED THAT DURING TH COOL SYS FOR REAC AUX + CONT 81-010/ 0 3 L-0 021381 E IEB 79-14 REVIEW A WEIGHT DISCREPANCY (180 LB. LIGHT) WAS DISCOVERED W HANGERS. SUPPORTS. SHOCK SUPPRSS 036141 30-DAY HICH ALTERED SUPPORT DESIGN REQUIREMENTS. TRAIN "A" 0F COMPONENT C00LIN SUPPORTS G WATER WAS DECLARED INOPERABLE THUS ENTERING LCO 3.7.3.1 ACTION STATENE DESIGN / FABRICATION ERROR HT.

THERE WAS NO EFFECT TO PUBLIC HEALTH OR SAFETY.

PREVIOUS OCCURRENC DESIGN ES - HONE.

TENNESSEE VALLEY AUTHORITY INCORRECT WEIGHTS WERE USED IN THE COMPUTER ANALYSIS WHICH COULD LEAD TO A LINE BREAK DOWN STREAN OF VALVE PCV-70-90 CURING DESIGN BASE EARTHQUA KE.

TWO SUPPORTS WERE MODIFIED FOR INTERIM USE UNTIL THE FIRST REFUELIN G OUTAGE WHEN REDESIGNED SUPPORTS WILL BE INSTALLED. TRAIN "A" 0F COMPO NENT COOLING WATER DECLARED OPERABLE AT 0811 (C) ON 1/30/81.

ST. LUCIE-1 05000335 022280 AT FULL POWER "B" DIESEL GENERATOR FAILED TO REACH RATED SPEED DURING OP EMERG GENERATOR SYS + 00NTROLS 80-012/03X-1 011481 ERATIONAL CHECK.. ENGINES WERE TRIPPED 1 FOUND ENGINE INJECTOR LINKAGES S ENGINES, INTERNAL COMBU2 TION 030829-OTHER TICKY.

INJECTOR CONTROL LEVERS-MANUALLY EXERCISED AND ENGINES RETESTED SUBCOMPONENT NOT APPLICABLE

' SATISFACTORILY. NO ADDITIONAL PROBLEMS NOTED.

PREVIOUS ENGINE STARTING COMPONENT FAILURE FAILURES REPORTED IN LER'S 76-21 76-44. 77-3, 77-15. AND 79-28. -HOWEV METALLURGICAL ER'LER 77-3 IS THE ONLY RELATED FAILURE.

GENERAL MOTORS PROBLEM WAS FIRST REPORTED 10 BE STICKING INJECTOR LINKAGES 8 SOLUTION W AS TO BE A MAINTENANCE ITEM TO PERIODICALLY LUBRICATE THEM.

DETAILED EV ALUATION HAS SHOUN, HOWEVER. THAT ALL CRITICAL LINKAGE BEARINGS ALREADY RECEIVE ADEQUATE LUBRICATION 1 ITEM WAS DELETED. CAUSE OF ORIGINAL EVEN T IS AS YET UNIDENTIFIED. BUT EVENT HAS NOT REPEATED.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 83 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT TYPE CAUSE DESCRIPTION S?. LUCIE-1 05000335 113080 DURING NORMAL FULL POWER OPERATION IT WAS DISCOVERED THAT SOME REACTOR T REACTOR TRIP SYSTEMS 80-067/01X-1 011681 RIP BREAKERS WOULD NOT TRIP ON UNDERVOLTAGE (UV) AS EXPECTED. THE TRIP CIRCUIT CLOSERS / INTERRUPTERS 033466 OTHER BREAKERS HAVE REDUNDANT UV AND SHUNT TRIP DEVICES. ONE DEVICE WOULD NOT CIRCUIT BREAKER TRIP AND TWO OTHERS TRIPPED SLUGGISHLY. THE ABILITY OF THE REACTOR TO COMPONENT FAILURE TRIP EITHER MANUALLY OR UPON RPS SIGNAL WAS NOT COMPROMISED AS SHOWN BY ELECTRICAL AN UNRELATED PLANT TRIP WHICH OCCURRED DURING THIS INVESTIGATION. THIS GENERAL ELECTRIC CO.

IS BEING REPORTED PER T.S.

6.9.1.8.I.

THIS IS THE IST LER OF THIS TYPE.

THE IHOPERABLE UV DEVICE ARMATURE WAS REALIGNED AND ALL 7 OTHER UV DEVIC ES WERE MANUALLY EXERCISED, LUBRICATED, AND TESTFD SATISFACTORILY. THE UV AND SHUNT TRIP DEVICES WERE PREVIOUSLY TESTED SIMULTANEOUSLY EVERY MO NIH.

A NEW PREVENTATIVE MAINTENANCE PROGRAM HAS BEEN INITIATED TO CHECK THE UV COILS INDEPENDENTLY MONTHLY. THE BREAKERS ARE GE TYPE AK-2A.

ST. LUCIE-1 05000335 120180 AT FULL POWER IT BECAME NECESSARY TO ISOLATE "B" CCW HEAT EXCHANGER TO R COOL SYS FOR REAC AUX + CONT 80-066/03L-0 123180 EPAIR A LEAK IN ICW DISCHARGE PIPING FROM "B" CCW HEAT EXCHANGER.

LEAKI PIPES. FITTINGS 033730 30-DAY NG ELBOW REPAIRED AND TWO INDEPENDENT CCW LOOPS REESTABLISHED IN 48 HOUR 16 INCHES AND LARGER S (WITHIH 72 HOURS ALLOWED BY T.S.

3.7 3.1.).

HEAT REMOVAL CAPABILITY 0 COMPONENT FAILURE F HEAT EXCHANGER NEVER IMPAIRED. TWO INDEPENDENT LOOPS COULD HAVE BEEN.

NATURAL END OF LIFE ESTABLISHED AT ANY TIME.

ITEM NOT APPLICABLE THE ICW PIPING SHOWED NORMAL SIGNS OF WEAR AND CORROSIVE ATTACK AT THE E LBOW.

IT WAS DETERMINED PRUDENT TO ISOLATE THE HEAT EXCHANGER AND REPAI R THE LEAK.

ST. LUCIE-1 05000335 120380 AT NORMAL FULL POWER CONTAINMENT RADIATION CHANNEL MD FAILED HIGH.

CHAN ENGNRD SAFETY FEATR INSTR SYS 80-068/03L-0 123180 NEL MD IMMEDIATELY BYPASSED AND TROUBLESHOOTING COMMENCED. WHEN IT MAS INSTRUMENTATION + CONTROLS 033731 30-DAY DETERMINED DETECTOR HAD FAILED, CHANNEL MD RADIATION WAS TRIPPED PER T.S SENSOR / DETECTOR / ELEMENT

. 3.3.2.1 THIS OCCURRED LESS THAN 10 HOURS AFTER CHANNEL HAD FAILED.

COMPONENT FAILURE NO SAFETY LIMITS WERE EXCEEDED. PREVIOUS LER'S OF THIS NATURE ARE 80-37 INSTRUMENT 78-04 AND 76-05.

VICTOREEN INSTRUMENT DIV.

RADIATION DETECTOR IS IN A HIGH RADIATION FIELD DURING NORMAL PLANT OPER ATION AND CANNOT BE REPLACED WITHOUT A PLANT OUTAGE.

DETECTOR WILL BE R EPLACED DURING AN UPCOMING PLANT OUTAGE.

REPLACEMENT DETECTOR OBTAINED AND CALIBRATED. CHANNEL MD CIS RADIATION WILL BE MAINTAINED IN ACCORDAN CE WITH T.S.

3.3.2.1 UNTIL DETECTOR REPLACED.

ST. LUCIE-1 05000335 121880 DURING NORMAL OPERATION. A LEAK TEST SURVEILLANCE ON CONTAINMENT PERSONN REACTOR CONTAINMENT SYSTEMS A0-062/03L-0 011681 EL AIR LOCK OUTER DOOR INTERSPACE WAS MISSED WHILE AUTOMATIC TESTER FOR PENETRATIONS.PRIMRY CONTAINMNT 033729 30-DAY REPAIR.

CONTAINMENT ENTRY WAS MADE BUT TEST NOT PERFORMED UNTIL ENTRY PERSONNEL ACCESS PERSONNEL EXITED CONTAINMENT CONTRARY TO T/S 4.6.1.3.

CONTAINMENT INTEG PERSONNEL ER"ao RITY MAINTAINED. HINTH OCCURRENCE OF MISSED SURVEILLANCE, SECOND THIS T LICENSED & if JIOR OPERATORS YPE.

ITEI1 NOT APPLICABLE LEAK TESTS BEING PERFORMED MANUALLY WITH A PORTABLE TESTER BUT ENTRY PER SONNEL NOT AWARE MANUAL TEST NECESSARY. TEST PERFORMED SATISFACTORILY W-ITHIN 1 1/2 HOURS OF ENTRY AND CLEARANCE TAG PLACED ON OUTER DOOR TO PRE VENT A REOCCURRENCE. AUTOMATIC TESTER REPAIRED AND FUNCTIONAL.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY

'PAGE 84 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION ST. LUCIE-1 05000335 122680 DG?ING NORMAL FULL POWER OPERATION, A 10% STEAM BYPASS VALVE (PCV-8005).

TURBINE BYPASS SYS + CONT 80-069/03L-0 012681 FAltED OPEN CAUSING REACTOR POWER TO INCREASE TO 101.5%, 103.5% AS MEAS INSTRUMENTATION + CONTROLS 033732 30-DAY URED FY NUCLEAR, DELTA T,

& CALORIMETRIC POWER RESPECTIVELY. TURBINE LO OTHER AD WAS DECREASED 1 THE VALVE WAS CLOSED LOCALLY BY FAILING THE POSITIONE COMPONENT FAILURE R.

THIS CAUSED TC TO MOMENTARILY RISE TO 542.2 DEG. F.

WHICH IS ABOVE T INSTRUMENT HE TECH. SPEC. 3.2.5 LIMIT OF 542 DEG. F.

THIS IS THE FIRST OCCURRENCE-ROCHESTER INSTRU. SYSTEMS INC.

OF THIS TYPE, AND THE SEVENTH INVOLVING TC GREATER THAN 542 DEG.

F.

THE VALVE OPENED DUE TO THE FAILURE OF A VOLTAGE TO CURRENT CONVERTER IN THE STEAM BYPASS CONTROLLER CABINET.

THE VALVE WAS ISOLATED AND THE PL ANT WAS STABILIZED WITH NO FURTHER PROBLEMS. THE CONVERT 0R WAS REPLACED AND TESTED. THE VALVE WAS THEN RETURNED TO SERVICE.

ST. LUC 1E-1 05000335 123180 DURING NORMAL OPERATION, AT 100% POWER. THE V0tUME CONTROL TANK (VCT) WA CHEM, VOL CONT + LIQ POISN SYS 80-071/03L-0 012931 S INADVERTENTLY DILUTED, LEADING TO REACTOR COOLANT SYSTEM DILUTION.

IN VALVES 033747 30-DAY DICATED REACTOR POWER INCREASED OVER ABOUT 15 MINUTES, PEAKING AT 102%.

OTHER TC ALSO INCREASED DURING THE TRANSIENT REACHING 542.5 DEG. F.

(THE STEA COMPONENT FAILURE DY STATE LIMIT IS 542 DEG.

F.).

ACTION PER TECH. SPEC. 3.2.5 WAS TAKEN MECHANICAL AND PCWER AND TC WERE REDUCED. THIS IS THE FIRST EVENT OF THIS TYPE.

CROSBY VALVE & GAGE CO.

WHILE ADDING MAKEUP AND ADJUSTING BORON CONCENTRATION IN THE VCT, A RELI EF VALVE (V2173, CROSBY, STYLE JR-WR-5) ON THE ACID PUMP DISCHARGE FAILE D. RETURNING BORIC ACID TO THE SOURCE TANK.

FLOW INDICATION, UPSTREAM F ROM THE RELIEF, WAS NORMAL.

THE RELIEF VALVE WAS EXERCISED AND LATER RE PAIRED.

ST. LUCIE-1 05000335 012381 DURING NORMAL FULL POWER OPERATION, OUR RE-EVALUATION OF PLANT MASONRY W SYSTEM CODE NOT APPLICABLE 81-003/01T-0 020681 ALLS SHOWED THAT SEVERAL MALLS DID HOT MEET THE CRITERIA 0F IE BULLETIN COMPONENT CODE NOT APPLICABLE 036142 2-WEEK 80-11, 14 WALLS WERE MISSING THE CLIP ANGLES REQUIRED BY THE DESIGN, 3 SUBCOMPONENT NOT APPLICABLE WALLS REQUIRED CLIP ANGLE REINFORCEMENT, 3 WALLS REQUIRED REINFORCEMENT, DESIGN / FABRICATION ERROR AND ONE WALL REQUIRED ADDING CLIP ANGLES THAT WERE NOT INCLUDED IN THE CONSTRUCTION / INSTALLATION ORIGINAL DESIGN.

CONSIDERING IE BULLETIN 79-14, THIS IS THE SECOND EVEN ITEM NOT APPLICABLE T OF THIS TYPE.

EVALUATIONS WERE PERFORMED TO JUSTIFY OPERATIONS, PRIORITIES WERE ASSIGN ED AND ALL IMMEDIATELY REQUIRED MODIFICATIONS WERE COMPLETED BY 2/5/81 ALL WALLS, THE FAILURE OF WHICH UNDER POSTULATED LOADS AND LOAD COMBINA TION COULD AFFECT SAFETY RELATED SYS, WERE REPAIRED. DETAILS ON FINDINGS 8 CORRECTIVE ACTION WILL BE INCLUDED IN OUR FINAL REPORT BULLETIN 80-11 ST. LUCIE-1 05006335 012781 DURING NORMAL FULL POWER OPERATION, NOTIFICATION WAS RECEIVED FROM GE (S OTHR INST SYS REQD FOR SAFETY 81-005/09T-0 020381 ERVICE ADVISORY BULLETIN S.A. 721-PSL-152.2) THAT THEIR TYPE HFA RELAY C CIRCUIT CLOSERS / INTERRUPTERS 036143 2-WEEK OIL SPOOLS COULD CRACK 8 FAIL IN SUCH A MANNER AS TO PREVENT RELAY OPER.

CONTACTOR SINCE THESE RELAYS ARE UTILIZED IN SOME SAFEGUARD SYS THIS DEFECT IS BE

. DESIGN / FABRICATION ERROR ING REPORTED PER 10 CFR 21 8 TS 6.9.1.8.I.

AN INSPECTION OF ALL TYPE HFA MANUFACTURING RELAY COIL SPOOLS IN PLANT HAS REVEALED NO OBSERVABLE CRACKS OF TYPE ID GENERAL ELECTRIC CD.

ENIIFIED BY GE AS BEING POTENTIALLY HAZARDOUS, FIRST RELAY LER.

SINCE THE MECHANISMS FOR THE CREATION AND GROWTH OF THE CRACKS ARE UNKND WN, ALL OF THE REL AYS WILL BE REPLACED AS RECOMMENDED BY GE.

IN THE INT ERIM UNTIL ALL RELAYS CAN BE REPLACED, ALL SAFETY RELATED HFA RELAYS WIL L BE INSPECTED ON A QUARTERLY BASIS.

ANY RELAY SPOOLS SHOWING HEW OR.GR

^

OWING CRACKS CHARACTERISTIC OF IMPENDING FAILURE WILL BE REPLACED.

i MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 85 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SURRY-1 05000280 012281 DURING THE PERIORMANCE OF PT-26.1. RADIATION MONITORING EQUIPMENT TEST, PRCSS + EFF RADIOL MONITOR SYS 81-002/03L-0 021981 WITH THE UNIT DEFUELED. THE RADIATIOM ALARM SETPOINT FOR THE COMPONENT C INSTRUMENTATION + CONTROLS 036221 30-DAY 00 LING SYSTEM WA5 FOUND TO BE GREATER THAN TWICE BACKGROUND AS LISTED IN COMPUTATION MODULE TECH. SPEC.

3.7.

TABLE 3.7-5.

THIS IS REPORTABLE IN ACCORDANCE WITH TE OTHER CH. SPEC. 6.6.2.B(4).

SINCE THE ACTIVITY LEVELS WERE WITHIN ALLOWABLE L NOT APPLICABLE IMITS, THE HEALTH AND SAFETY OF THE PUBt.IC WERE NOT AFFECTED.

VICTOREEN INSTRUMENT DIV.

THE IMPROPER SETPOINT WAS ATTRIBUTED TO REDUCED BACKGROUND DUE TO PLANT BEING SHUTDOWN AND DEFUELED. THE ACTIVITY LEVELS IN THE CC SYSTEM WERE VERIFIED TO BE WITHIN ALLOWABLE LIMITS AND THE SETPOINT FOR t10NITOR. RM-CC-105, WAS RESET.

SURRY-1 05000280 012981 DURING THE PERFORMANCE OF PT-26.1, RADIATION MONITORIN6 EQUIPMENT TEST, PRCFS + EFF RADIOL MONI'OR SYS 81-003/03L-0 021981 WITH THE UNIT I DEFUELED AND UNIT 2 AT 100% POWER. THE RADIATION ALARM S INSTRUMENTATION + CONTROLS 036222 30-DAY ETPOINT FOR THE COMPONENT COOLING SYSTEM WAS FOUND TG BE GREATER THAN TW COMPdTATION NODULE ICE BACKGROUND AS LISTED IN TECH. SPEC.

3.7, TABLE 3.7-5.

THIS IS REPOR OTHER TABLE IN ACCORDANCE WITH TECH. SPEC. 6.6.2.B.(4).

SINCE THE ACTIVITY LE NOT APPLICABLE VELS WERE WITHIN ALLOWABLE LIMITS, THE HEALTH AND SAFETY OF THE PUBLIC W VICTOREEN INSTRUMENT DIV.

ERE NOT AFFECTED.

THE IMPROPER SETPOINT WAS ATTRIBUTED TO A DECREASE IN BACKGROUND RADIATI ON LEVELS. THE ACTIVITY LEVELS IN THE CC SYSTEM WERE VERIFIED TO BE WIT HIN ALLOWABLE LIMITS AND THE SETPOINT FOR MONITOR, RM-CC-105 AND 106 WER E PESET.

SURRY-7 05000281 122080 DURING THE PERIOD FROM 1600 TO 1700 DN 12/20/80, THE CONDENSER'S COOLING ULTIM TE HEAT SINK FACILITIES 80-000/04X-0 010581 WATER OUTLET TEMP EXCEEDED THE MAXIMUM AVERAGE RATE OF CHANGE OF 3F/HR HEAT EXCHANGERS 033754 OTHER PERMITTED BY TECHNICAL SPECIFICATION 4.14.A.3.

AVG. RATE OF CHANGE WAS CONDENSER 8F/HR.

HOWEVER, THE DURATION OF EACH STEP WAS ONLY 15 MIN. 50 THE MAX.

DESIGM/ FABRICATION ERROR CHANGE IN COOLING WATER TEMP. WAS CHLY 5F.

DESILM OTHER WATERBOX OUTLET VALVES WERE THROTTLED DUE TO STATION VACUUM PRIMING PROB LEMS.

OPERATION AT REDUCED STATION DISCHARGE COOLING MATER FLOWS AND CO LD RIVER WATER MAGNIFY THE EFFECT OF WATERBOX VALVE OPERATION. NO DETRI MENTAL EFFECT ON RIVER WATER ENVIRONMENT.

SURRY-2 05000281 123180 ELECTRICAL PENETRATION E-4 THROUGH THE FIRE WALL BETWEEN 03 EQUIPMENT RO FIRE PROTECTION SYS + CONT 80-049/03L-0 012981 OM AND 02 TURBINE BASEMENT HAD BEEN FOUND OPENED AND THERE WAS NO FIRE W COMPONENT CODE NOT APPLICABLE 033687 30-DAY ATCH ON EITHER SIDE OF THE WALL.

THIS IS CONTRARY TO TECH SPECS 3.21-G, SUBCOMPONENT NOT APPLICABLE AND REPORTABLE AS PER TECH SPEC 6.6.2.b(3)

PERSONNEL ERROR CONSTRUCTION PERSONNEL ITEM NOT APPLICABLE FIRE STOP WAS REMOVED TO RUN A WELDING LEAD'THROUGH THE ELECTRICAL PENET RATION.

AFTER DETECTION, A FIRE WATCH WAS POSTED AND THE FIRE MARSHALL NOTIFIED. MAINTENANCE ORDER MAS SUBMITTED TO REPAIR THE FIRE STOP.

HEA LTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

c

i f

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 86 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM /CCMPONENT/

DOCKET NO./

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COMPONENT SLBCODE/CAUSE CODE / LER NO./

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION l

SURRY-2 05000281 011481 WITH THE UNIT AT FULL POWER, "C" SAFETY INJECTION ACCUMULATOR WAS FOUND EMERG CORE COOLING SYS + CONT 81-006/03L-0 021381 TO HAVE A BORON CONCENTRATION OF 1943 PPM, 7 PPM BELOW THE REQUIRED LIMI UALVES 036144 30-DAY T OF 1950 PPM.

THIS IS CONTRARY TO T.S.-3.3.A.2 AND IS REPORTABLE PER T CHECK ECHNICAL SPECIFICATION -6.6.2.B(2).

SINCE "C" ACCUMULATOR BORON CONCENT COMPONENT FAILURE RATION WAS INCREASED ABOVE 1950 PPM WITHIN THE 4 HOUR TECHNICAL SPECIFIC 1

MECHANICAL ATION LIMITATION (55 MIN.), THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT ROCKWELL-INTERNATIONAL AFFECTED.

THE CAUSE OF THE REDUCED CONCENTRATION WAS LEAKAGE THROUGH CHECK VALVE 1

-SI-144.

THE CORRECTIVE ACTION WAS TO ISOLATE THIS VALVE WITH FUTURE PL ANS TO REPAIR THE VALVE DURING AN OUTAGE OF SUFFICIENT DURATION.

SURRY-2 05000281 011481 WITH UNIT NO. 2 AT 100% POWER, PT-27 (HEAT TRACING) REVEALED THAT AMP RE OTHER ENGNRD SAFETY FEATR SYS 81-007/03L-0 021381 ADINGS FOR PANELS 8 AND 9, CIRCUITS 20C, WERE BELOW THE ACCEPTANCE CRITE HEATERS ELECTRIC 036145 30-DAY RIA STIPULATED IN THE PT, THEREFORE. THE DIT RECIRC WERE DECLARED INOPER SUBCOMPONENT NOT APPLICABLE ATIVE.

THIS EVENT IS CONTRARY TO TECHNICAL SPECIFICATION 3.3.A.3 BUT PE COMPONENT FAILURE RMITTED BY TECH. SPEC. 3.3.B.10.

THIS EVENT IS REPORTABLE PER TECH. SPE ELECTRICAL C. 6.6.6.2.B(2).

THE HEALTH AND 3AFETY OF THE PUBLIC WERE NOT AFFECTED.

THERMON MFG.

THE LOSS OF HEAT TRACING WAS DUE TO EXCESSIVE TEMPERATURES BREAKING DOWN THE INSULATION. THE DEFECTIVE HEAT TRACING WAS REPLACED AND TESTED WIT HIN 2 HRS.

A DESIGN CHANGE HAS BEEN INITIATED TO CHANGE THE MANNER BY W HICH THESE BORATED LINES ARE HEAT TRACED.

SURRY-2 05000281 011881 WITH UNIT 2 AT 100 PERCENT POWER, ONE OF TWO REQUIRED FLOW PATHS TO THE FEEDWATER SYSTEMS + CONTROLS 81-012/03L-0 021781 CORE BECAME UNAVAILABLE AND BIT RECIRC WAS TERMINATED DUE TO THE LOSS OF PUMPS 036147 30-DAY BORIC ACID TRANSFER PUMP.1-CH-P-2D.

THIS IS CONTRARY TO TECHNICAL SPEC CENTRIFUGAL IFICATION 3.2.B.4 AND 3.3.A.3, AND IS REPORTABLE PER TECH. SPEC. 6.6.2.B COMPONENT FAILURE

.(2).

THE REDUNDANT TRANSFER PUMP WAS PLACED IN SERVICE WITHIN 6 MINUTE MECHANICAL S; THEREFORE, THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED.

GOULDS PUMPS INC.

PUMP'S OIL SEAL FAILED, THEREBY CAUSING BEARING FAILURE AND SUBSEQUENT L OSS OF PUMP.

TRANSFER PUMP 1-CH-P-2C WAS PLACED IN SERVICE. TRANSFER P UMP 1-CH-P-2D WAS REPAIRED, TESTED, AND RE1URNED TO SERVICE.

SURRY-2 05000281 011981 A FIRE NATCH HAD BEEN ESTAR WHEN FUEL OIL PUMP HOUSE CO2 SYS WAS MADE IN FIRE PROTECTION SYS + CONT 81-011/03L-0 021381 OPER FOR DESIGN CHANGE MODIF. AT 0700 IT WAS DISCOVERED THAT A FIRE WATC COMPONENT CODE NOT APPLICABLE 036146 30-DAY H WAS NOT BEING MAINTAINED. OPERATIONS PERSONNEL HAD MADE PERIODIC INSPE SUBCOMPONENT NOT APPLICABLE CTIONS OF THE AREA.

THE POSITION MAS UNMANNED FOR ONLY 1 1/2 HRS. MANUA PERSONNEL ERROR L FIRE SUPPRESSION WAS AVAILABLE. A FIRE WATCH WAS IMMED RE-ESTABLISHED.

MAINTENANCE & REPAIR PERSONNEL THEREFORE, HEALTH & SAFETY OF PUBLIC WERE NOT AFFECTED.

THIS EVENT IS ITEM NOT APPLICABLE

, CONTRARY TO T.S. 3.21.D.3.A 8 IS REPORTABLE PER T.S. 6.6.2.B.(2).

Q THE ASSIGNED FIRE WATCM HAD LEFT THEIR POST WITHOUT BEING PROPERLY RELIE VED.

A FIRE WATCH WAS IMMEDIATELY RE-ESTABLISHED, AND APPROPRIATE DISCI PLINARY ACTION WAS TAKEN AGAINST THE MISSING FIRE WATCH.

e MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 87 PROCESSED DURING MARCH, 198t FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION SURRY-2 0S000281 011981 WITH UNIT TWO OPERATING STEADY-STATE AT 100% POWER, AN IMPROPERLY SEALED FIRE PR0stCTION SYS + CON' 81-013/03L-0 021381 FIRE BARRIER PENETRATION WAS DISCOVERED DURING A Q.C. DEPARTMENT WALKD0 COMPONENT CODE NOT APPLIfABLE 036148 30-DAY WN OF THE PLANT.

THIS IS CONTRARY TO TECHNICAL SPECIFICATI0M 3.21.G.1 A SUBCOMPOW"NT NOT APPLICABLE ND IS REPORTABLE AS PER TECH. SPEC. 6.6.2.B.(3).

ALL OTHER FIRE PROTECT PERSONNEL ERROR ION SYSTEMS REMAINED OPERABLE, THEREFORE, THE HEALTH AND SAFETY OF THE P CONSTRUCTION PERSONNEL

. UBLIC WERE NOT AFFECTED.

ITEM NOT APPLICABLE THE FIRE BARRIER PENETRATION HAD BEEN PACKED WITH IMPROPER MATERIAL. A FIRE WATCH WAS ESTABLISHED UNTIL THE PENETRATION COULD BE PROPERLY SEALE D.

SURRY-2 0S000281 011981 ON JAMUARY 19, 1981. WITH UNIT NO. 2 AT 100% POWER, A POSITIVE PRESSURE CONT ROOM HABITBLTY SY3 + CONT 81-016/03L-0 021881 0F GREATER THAN 0.0S INCHES 9F WATER, COULD NOT BE MAINTAINED IN THE CON OTHER COMPONENTS 036223 30-DAY TROL ROOM.

THIS IS CONTRARY TO TECH. SPEC. -3.19.A AND IS REPORTABLE PE SUBCOMPONENT NOT APPLICABLE R T.S.-6.6.2.B(2).

THE CONTROL ROOM EMERGENCY VENTILATION SYSTEM MAS OP COMPONENT FAILURE ERABLE, THEREFORE, THE HEALTH AND SAFETY OF THE PUBLIC WERE NOT AFFECTED MECHANICAL OTHER THE SEALS ON THE DOORS TO THE CONTROL ROOM COMPLEX WERE DETERIORATED, T HE DEFECTIVE DOORS WERE REPAIRED.

VHREE MILE ISLAND-1 0S000289 011781 WHILE IN THE LONG-TERM COLD SHUTDOWN CONDIriON, DURING A LIMITED PLANT H REAC COOL CLEANUP SYS + CONT 81-001/03L-0 021881 EATUP, 2 LEAKS WERE FOUND IN THE 1" BYPASS AROUND MU-V17.

THIS EVENT'IS PIPES. FITTINGS 036253 30-DAY REPORTABLE PER 6.9.2.B(4).

THE LEAKAGE WAS REDUCED WHEN THE SYSTEM PRE LESS THAN 4 INCHES SSURE WAS RETURNED TO ATMOSPHERIC PRESSURE.

COMPONENT FAILURE CORROSION j

OTHER l

THE LEAK ON THE FLOW INSTRUMENT IS THOUGHT TO BE DUE TO A LOCALIZED PITT ING ATTACK.

THE LEAK ON THE SOCKET WELD IS DUE TO AN INITIAL ROOT WELD DEFECT WHICH APPEARS TO HAVE PROPAGATED DUE TO CYCLIC FATIGUE.

THE DAMA GED COMPONENTS WERE REMOVED FROM THE SYSTEM AND ARE BEING REPLACED. AF OLLOWUP LER WILL BE ISSUED.

l THREC MILE ISLAND-2 0S000320 121780 ON 12/17/80 DURING PERFORMANCF OF SURVEILLANCE PROCEDURE 4303-M10, AIR I OTHR INST SYS PEQD FOR SAFETY 80-OS7/03L-0 011681 NTAKE TUNNEL CHLORINE MONITOR WAS FOUND TO BE INOPERABLE IN THAT WHEN PR l

INSTRUMENTATION + CONTROLS 333688 30-DAY OBE WAS EXPOSED TO CHLORINE VAPORS MONITOR DID NOT RESPOND. THIS IS NOT SENSOR / DETECTOR / ELEMENT A VIOL ATION OF TECH. SPECS.

THIS REPORT IS SUBMITTED UNDER SECTION 6.9 t

COMPCNENT FAILURE

.1.9(B) BECAUSE ACTION STATEMENT OF SECTION 3.3.3.7 WAS ENTERED INADVERT OTHER ENTLY.

THIS EVENT HAD NO EFFECT ON PLANT, ITS OPERATION, OR HEALTH AND FISCHER 8 PORTER CO.

SAFETY OF THE PUBLIC.

CAUSE OF EVENT WAS THAT PROBE HAD BECOME DIRTY.

THIS REDUCED ITS SENSIT-IVITY TO DETErT CHLORINE AT REQUIRED LEVEL.

PROBE WAS REMOVED FROM SERV ICE, CLEANED, AND THEN RETURNED TO SERVICE. SURVEILLANCE PROCEDURE IS B EING MODIFIED TO INCREASE CLEANING FREQUENCY OF PROBE TO ONCE PER 31 DAY S.

1

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACIIITY PAGE 88 PROCESSED DURING MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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REPORT DATE/

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION THREE MILE ISLAND-2 0$000320 122680 AT 1320 HRS ON 12/26/80, "A" EMERGENCY DIESEL GEN.(EDG) DF-X-1A WAS STAR EMERG GENERATOR SYS + C0NTROLS 80-059/03L-0 012681 TED DURING A TRAINING EXERCISE. EDG STARTED BUT TRIPPED AFTER APPROX. 9 RELAYS 033733 30-DAY SEC.

THIS EVENT WAS NOT A VIOL. OF ANY T/S.

THIS EVENT IS REPORTABLE TIME DELAY, PNEt!MATIC UNDER T/S 6.9.1.9(B) DUE TO ENTRY INTO ACTION STATEMENT OF SPEC. 3.8.1.1 COMPONENT FAILURE BY EQUIP. FAILURE. THIS EVENT IS SIMILAR TO S.R.80-003, LER'S 80-09 I

ELECTRICAL AND 80-028.

TH.S EVENT HAD NO EFFECT ON PLANT, ITS OPERATION, OR HEALTH I-T-E CIRCUIT BREAKER AND SAFETY OF THE PUBLIC.

UPON FURTHER INVESTIGATION IT WAS DETERMINED THAT CAUSE OF EDG TRIP WAS RESULT OF A FAILURE IN ALARM DELAY RELAY, T3B-LOW LUBE DIL PRESSURE, IN EDG STARTING CIRCUITRY. RELAY AND COIL WERE REPLACED. COMPONENT MANUFA CTURER WILL BE CONTACTED TO DETERMINE IF THERE IS A HISTORY OF TP*S TYPE OF FAILURE.

TROJAN-1 05000344 101680 SPECIAL REPORT.

A LIMITING CONDITION FOR OPERATION (LCO) 0F THE TROJAN FIRE PROTECTION SYS + CONT 80-000/13X-0 101680 TECHhICAL $?ECIFICATIONS REQUIRES A SPECIAL REPORT BE SUBMITTED IN THE E PUMPS 033756 OTHER VENT OF IHOPERABILITY OF THE FIRE SUPPRESSION SYSTEM. SYSTEM OPERABILIT OTHER Y WILL NOT BE MET DURING A PLANNED FIAINTENANCE OVERHAUL OF THE DIESEL-DR COMPONENT FAILURE IVEN FIRE PUMP.

PUMP OUTAGE IS EXPECTED TO LAST FROM 10/20/80 TO 11/12/

MECHANICAL 80.

OTHER PREVENTIVE taINTENANCE OF DIESEL ENGINE AS WELL AS THE PUMP.

IN ADDITIO N.

THE PUMP WILL ALSO BE COATED WITH A CORROSION ?NHIBITOR. THE LOCAL F IRE DEPARTMENT WlLL PROVIDE A PUMPER TRUCK AT THE SITE WHILE THE DIESEL DRIVEN PCMP IS OUT OF SERVICE.

TROJAN-1 05000344 121280 DURING HORMAL OPERATION, A BLOWN FUSE WAS FOUND IN THE BREAKER CONTROL P AIR COND. HEAT. COOL VENT SYSTEM 31-001/C3L-O 010981 OWLR CIRCUIT FOR THE VENT SUPPLY FAN TO THE TURBINE-DRIVEN AUXILIARY FEE BLOWERS 036224 30-DAY DWATER PUMP ROOM.

THE TURBINE-DRIVEN PUMP WOULD HAVE OPERATED NORMALLY SUBCOMPONENT N01 APPLICABLE UPON RECEIVING AN AUTO-START SIGNAL AND BACKUP VENTILATION COULD HAVE BE COMPONENT FAILURE EN SUP* LIED BY OPENING THE PUMP RJ0M DOOR UNTIL IHE FAN WAS RETURNED TO ELECTRICAL SERVICE. THE REDUNDANT DIESEL-DRIVEN PUMP WAS OPERAb.E AND AVAILABLE FO OTHER R USE.

THERE WAS NO APPARENT CAUSE FOR THE BLOWN FUSE.

ELECTRICAL FAULT CHECKS WERE PERFORMED ON THE BREAKER CONTROL CIRCUIT WITH NO DEFICIENCIES FOUN D.

A REPLACEMENT FUSE WAS INSTALLED AND THE FAN OPERATIONALLY TESTED SA TISFACTORILY. NO FURTHER CORRECTIVE ACTION IS REQUIRED.

TROJAN-1 05000'344 123180 NC.80-282 WHILE RETURNING THE "B" SERVICE WATER BOOSTER PUMP TO SERVICE AC ONSITE POWER SYS + CONTROLS 80-028/03L-0 012 f r> 1 A MIN 3R FIRE OCCURRED IN 480 VAC ESF MCC B22.

THIS RENDERED CERTAIN C CIRCUIT CLOSERS / INTERRUPTERS 033734 30-DAY ONTAINMENT ISOLATION VALVES IHOPERABLE PER TECH. SPEC.

3.6.3.1, CERTAIN CIRCUIT BREAKER SPRAY VALVES INOPERABLE PER TECH. SPEC. 3.6.2.1 AND THREE OF EIGHT CONT COMPONENT FAILURE AINMENT AIR COOLERS INOPERABLE PER TECH. SPEC.

3.6.2.3.

REDUNDANT CONTA ELECTRICAL INMENT ISOLATION VALVES, SPRAY SYSTEM, AND AIR COOLERS WERE AVAILABLE.

ITE IMPERIAL CORPORATION REPEATED' CYCLING OF PUMP ONTO BUS COUPLED WITH INADEQUATE STAB TO BUS BA R CONTACT AND DUST IN THE MCC CABINET CAUSED A FIRE.

OPERATORS WERE REM INDED OF UNDESIRABILITY OF REPEATED CYCLING OF LOAD BREAKER. AN ENGINEE RING STUDY TO DETERMINE IF THE BREAKERS ARE ADEQUATELY SIZED WILL BE !!AD E.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 89 PROCESSED DURING MARCH, 19.1 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION TROJAN-1 05000344 123180 CONTROL VALVES CONNECTING THE REFUELING WATER STORAGE TANK AND THE SPENT EMERG CORE COOLING SYS + CONT 80-029/03L-0 012931 FUEL PURIFICATION SYSTEM WERE FOUND TO HAVE A DEFICIENCY WHICH COULD PR INSTRUMENTATION + CONTROLS 033735 30-DAY EVENT THEIR SHUTTING. A FAILURE OF.THIS TYPE DURING A SEISflIC EVENT AND OTHER.

SAFETY INJECTION COULD CAUSE AN UNACCEPTABLE LOSS OF WATER FROM THE RMS EXTERNAL CAUSE T.

NOT APPLICABLE ASCO THE CAUSE OF THIS EVENT IS ATTRIBUTED TO CONSTRUCTION / INSTALLATION ERROR S.

AN AC SOLENDID HOUSING WITH A DC SLUG AND CCI! WERE INSTALLED IN A D C CONTROL CIPCUIT.

.g TROJAN-1 05000344 010781 NO. 81-02: REPORTED IN ACCORDANCE WITH 3.6.3.1 - AFTER NORMAL SAMPLING 0 OTHER COOLANT SUBSYS + CONTROL 81-002/03L-0 020381 F THE REACTOR COOLANT SYSTEtt, THE COMMON SAMPLE CONTAINMENT ISOLATION VA UALVES 036149 30-DAY LVE FAILED TO CLOSE FR0t1 THE CONTROL ROOM.

AFTER SEVERAL ATTEMPTS, THE PLUG VALVE CLOSED.

THERE WAS NO EFFECT ON PLANT OR PUBLIC SAFETY SINCE THE S OTHER AMPLE ISOLATION VALVES INSIDE CONTAINMENT WERE OPERAFLE.

HOT APP 8.ICABLE ROCKWELL MANUFACTURING CO.

THE Ct9SE OF THE OCCURRENCE WAS INADEQUATE LUBRICATION OF THE VALVE STEM

. THE VALVE STEM WAS CLEANED, LUBRICATED.AND TESTED SATISFACTORILY.

TROJAN-1 05000344 011281 NO. 81-04:

DURING A PERIODIC OPERATING TEST OF THE "B" CONTAINMENT SPRA AIR COND, HEAT, COOL, VENT SYSTEM 81-004/03L-0 021881 Y PUMP, THE FAN COOLING UNIT FOR THE. PUMP DID NOT AUTOMATICALLY-START.

CIRCUIT CLOSERS / INTERRUPTERS 036254 30-DAY NORMAL BUILDING VENTILATION WAS AVAILABLE FOR COOLING AND THE PUMP COULD CIRCUIT BREAKER HAVE OPERATED FOR AN EXTENDED PERIOD CL TIME.

FSAR 9.4.2 STATES THAT L COMPONENT FAILURE OCAL COOLING FANS BACK-UP BUILDINA VENTILATION.

ELECTRICAL ITE IMPERIAL CORPORATION THERMAL OVERLOADS ON THE FAN UNIT SUPPLY BREAKER (B-2415) WERE TRIPPED.

OVERLOADS WERE RESET AND FANS STARTED. MAINTENANCE INVESTIGATION OF'TH E BREAKER REVEALED NO EXCESSIVE CURRENT FLOWS.

VURKEY POINT-3 05000250 111980 DURING POWER OPERATION. A REACTOR TRIP OCCURRED DUE TO STEAM FLOW /FEECWA CONDNSATE + FEEDWTR SYS + CONT 80-024/03L-0 121930' TER FLOW MISMATCH CONCURRENT WITH tou STEAM GENERATOR WATER LEVEL IN 'A' UALVES 033757 30-DAY STEAM GENERATOR. SUESEQUENT TO REPAIR OF THE APPARENT PROBLEli, FEEDUAT GLOBE ER CONTROL PROBLEMS RESULTED IN TWO ADDITIONAL' REACTOR SHUTDOUNS. REPORT C0t1PONENT FAILURE ABLE PER T.S.

6.9.2.B. PUBLIC HEALTH & SAFETY NOT AFFECTED. AUX FEEDWATE.

MECHANICAL R SYS WAS OPER DUAiau OCCURRENCES. USNRC WAS NOTIFIED IN ACCORDANCE WITH COPES-VULCAN, INC.

10 CFR 50.72 REQUIREMENTS.

THE ROOT CAUSE OF THE SERIES OF EVENTS WAS A BROKEN VALVE STEM IN FCV 478. STEAM GENERATOR

'A' FEEDWATFA FLOW CONTROL VALVE.

THE APPARENT CAU SE OF THE STEtt FAILURE WAS. If1 PROPER LOAD DISTRIBUTION BETWEEN THE STEM A HD PLUG DUE TO THE TAPER ON THE VALVE STET 1.

THE VALVE STEMS ON ALL THRE E VALVES OF BOTH UNIT NO. 3 AND UNIT NO. 4 HAVE BEEN REPLACED.

MAR 26. 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 90 PROCESSED DUkiNG MARCH, 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

9DCKET NO./

EVENT DATE/

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CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYP.

CAUSE DESCRIPTION TURKEY POINT-3 05000250 122980 DURING POWER OPERATION. A DC GROUND WAS EXPERIENCED ON 3B BATTERY BUS.

OTHER ELEC POWER SYS + CONTROL 80-023/03L-0 012881

?NVESTIGATION SHOWED A PROBLEM MITH CONTROL POWER TO 4160 V BREAKER 3AB1 CIRCUIT CLOSERS / INTERRUPTERS 033689 30-DAY U.

FOR 3B HEATER DRAIN PUMP. WHICH PREVENTED BREAKER FROM BEING REMOTELY CIRCUIT BREAKER TRIPPED. THIS IS REPOR1ABLE PURSUANT TO TECH. SPEC. 6.9.2.B IN THAT THI COMPONENT FAILURS S BREAKER WOULD NOT HAVE TRIPPED TO CLEAR 3B 4160 V BUS IN RESPONSE TO A i

ELECTRICAL BUS ! TRIPPING SIGNAL.

BREAKER WAS TRIPPED MANUALLY.

GENERAL ELECTRIC CO.

INVESTIGATION SHOWED SHORTED CONTROL CIRCUIT WIRING BETWEEN 3AB10 AND IT S LOCAL START STATION.

FAILURE WAS CAUSED BY STEAM ENTERING ELECTRICAL BOX AND SHORTING OUT CIRCUIT.

THIS RESULTED IN BURNING OUT TRIP COIL OF FREAKER.

CIRCUIT AND CONDUIT HAVE BEEN #EROUTED AND BREAKER WAS REPLAC FJ WITH A SPARE.

TURKEY POINT-3 05000250 123080 JURING POWER OPERATION. THE 3A BORIC ACID TRANSFER (BAT) PUMP WAS FOUND CHEM. VOL CONT + LIQ POISN sis 80-029/03L-0 012981 TO BE LEAKING WATER 8 WAS REMOVED FROM SERVICE. OPERATION CONTIP"ED PUR PUMPS t13736 30-DAY SUANT TO T.S.

3.6.D.2 FOR APPROXIMATELY 20 HOURS BEFORE THE TWO PUMP REQ CENTRIFUDAL UIREMENT OF T.S.

3.6.B.2 COULD BE MET.

AN ALTERNATE DORATION PATH WAS A COMPONENT FAILURE VAILABLE VIA THE 4A BAT PUMP WHICH WAS OPERABLE. BAT PUMP OUTAGES WERE MECHANICAL PREVIOUSLY REPORTED AS LERS 251-77-2, 251-79-1, 251-79-15. 251-79-16.

CHEMPUMP CORP THE CAUSE OF THE FAILURE WAS FLUID LEAKAGE INTO THE SEALED STATOR ASSEMB LY.

THE PUMP WAS REPAIRED AND RETURNED TO SERVICE WITHIN 20 HOURS.

TURKEY POINT-3 05000250 010181 WHILE PERFORMING THE SURVEILLANCE ON "B" EMERGENCY DIESEL GENERATOR (EDG EMERG GENERATOR SYS + CONTROLS 81-001/03L-0 012981

) TO IMPLEMENT T/S 4.8.1.A.

A LOSS OF VOLTAGE CONTROL WAS EXPERIENCED.

ENGINES. INTERNAL COMBUSTION 036150 30-DAY THE EDG WAS MANUALLY SHUT DOWN. AN INVESTIGATION REVEALED 4AT TWO FUSES SUBCOMPONENT NOT APPLICABLE ASSOCIATED WITH THE 120 VAC SUPPLY AND VOLTAGE REGULATOR 1RANSFORMER HA-COMPONENT FAILURE D FAILED OPEN.

THE FUSES WERE REPLACED. AND THE EDG TESTED AND RETURNED ELECTRICAL TO SERVICE WITHIN 12 HOURS.

THE REDUNDANT "A" EDG WAS AVAILABLE TO SUP SCHOONMAKER. A.G.

PLY ESF EQUIPMENT AS DISCUSSED IN FSAR SECTION 8.

THE CAUSE OF THE FUSE FAILURE COULD NOT BE DETERMINED. HOWEVER. THE CONT ACT BANDS UERE FOUND TO BE LOOSE ON THE FUSE BODY.

THE 2-SIX AMPERE FUS ES WERE REPLACED.

THE ANNUAL SURVEILLANCE ASSOCIATED WITH T/S 4.8.1.C W ILL BE EXPANDED TO INCLUDE CHECKING FUSES ASSOCIATED WITH THE EDGS.

TURKEY POINT-3 05000250 010381 WHILE PERFORMING A PLANNED UNIT SHUTDOWN. THE BORIC ACID FLOMPATH FROM T CHEM. VOL CONT + LIQ POISN SYS 81-002/01T-0 011631 HE BORIC ACID TANKS AS DESCRIBED IN T/S 3.6.B.4 WAS FOUND TO BE OBSTRUCT ELECTRICAL CONDUCTORS 036131 2-WEEK ED.

THE FLOW PATH WAS RE-ESTABLISHED IN 1 HR. 33 MIN PU3LIC HEALTH AN SUBCOMPONENT NOT APPLICABLE D SAFETY WAS NOT AFFECTED.

THE ALTERNATE FLOW PATH FROM THE REFUELING W COMPONENT FAILURE ATER STORAGE TANK WAS OPERABLE THROUGHOUT THIS PERIOD.

REFERENCE FSAR S ELECTRICAL EC.

9.2.2.

SIMILAR OCCURRENCES WERE REPORTED AS A0 251-74-C8. AND LERS CHROMALOX 251-77-11, 251-77-12. AND 251-79-1.

THE APPARENT CAUSE OF THE OBSTRUCTION WAS REDUCED TEMPERATURE RESULTING FROM FAILURE OF ONE CHANNEL OF HEAT TRACING CIRCUIT NO. 21 THE CIRCUIT WAS FOUND TO HAVE 4 OPEN SECTIONS AND A PARTIAL GROUND.

THE ROOT CAUSE COULD NOT BE DETERMINED. THE TEMPERATURE SETPOINT ON THE REMAINING CHA NNEL WAS INCREASED TO RE-ESTABLISH FLOW.

DAT1 AGED CHANNEL WAS REPAIRED.

MAR 26, 1981 LER MONTHLY REPORT SORTED BY FACILITY PAGE 91 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE CODE / LER NO./

REPORT DATE/

EVENT DESCRIPTION /

CAUSE SUBCODE/ MANUFACTURER CONTROL NO.

REPORT TYPE CAUSE DESCRIPTION TURKEY POINT-3 05000250 010581 IN THE COURSE OF IAVESTIGATING POTENTIAL CRACKS DESERVED IN THE LEXAN CO OTHER ENGNRD SAFETY FEATR SYS 81-003/01T-0 0119G1 IL SPOOLS OF GENERAL ELECTRIC CO. TYPE HFA RELAYS, A NEW CGIL ASSEMBLY I RELAYS 036152 2-WEEK N SPARE PARTS STORAGE WAS CONFIRMED TO HAVE A CRACK IN THE SPOOL END PLA CONTROL, GENERAL PURPOSE TE.

THE CONCERN IS THAT A CRACKED SPOOL COULD RESULT IN A BROKEN PIECE DESIGN / FABRICATION ERROR WHICH COULD PREVENT DESIRED CONTACT ACTION.

A COIL INSPECTION PROGRAM W MANUFACTURING AS ESTABLISHED AND IMPLEMENTED. AN EVALUATION PURSUANT TO 10CFR21 REQMT GENERAL ELECTRIC CO.

5 IS IN FROGRESS. A SIMILAR HFA RELAY PROBLEM WAS REP. AS AD 251-75-8.

i NO OPERATICMAL FAILURE OF THIS TYPE RELAY DUE TO COIL SPOOL CRACKS HAS B l

EEN EXPERIENCED. ONE COIL IN SERVICE WAS FOUND CRACKED AND WAS REPLACED

. INSPECTION RESULTS REVEALED POSSIBLE INDICATIONS CN 39 0F THE 184 REL AYS.

A PERIODIC INSPECTION WILL BE IMPLEMENTED PENDING RECEIPT OF NEW C OILS AND/OR RELAYS.

VERMONT YANKEE-1 05000271 122080 WHILE PERFORMING THE TYPE C LEAK RATE TESTING, RCIC -15 WAS FOUND TO HAV REAC CORE ISOL COOL SYS + CONT 80-043/03L-0 011681 E SEAT LEAKAGE OF 1.531 LBM/HR WHICH IS IN EXCESS OF TECHNICAL SPECIFICA VALVES 033690 30-DAY TION, SECTICH 4.7.A.4.

SINCE A SECOND VALVE IN THE LINE PROVIDED CUNTAI CATE NMENT ISOLATION, THERE WERE NO ADVERSE CONSEQUENCES TO THE HEALTH AND SA COMPONENT FAILURE FETY OF THE PUBLIC.

THERE HAS BEEN NO SIMILAR OCCURRENCE REPORTED TO TH MECHANICAL E COMMISSION ON THIS VALVE.

WALWORTH CO.

THE VALVE SEATING SURFACES WERE LAPPED AND THE VALVE WAS SATISFACTORILY RETESTED PRIOR TO PLANT STARTUP PER TECHNICAL SPECIFICATION, SECTION 3.7

.A.4.

THE VALVE FAILURE WILL ALSO BE REPORTED IN ACCORDANCE WITH APPEND IX J, 10 CFR 50, V.B.3.

VERMONT YANKEE-1 05000271 122930 DURING STARTUP AT 24 PERCENT POWER, ROUTINE OPERATOR SURVEILLANCE DISCOV REAC COOL CLEANUP SYS + CONT 80-041/03L-0 012881 ERED WATER LEAKAGE FROM THE 4 INCH. REACTOR WATER CLEANUP LINE 3.

UPON PIPES, FITTINGS 033737 30-DAY CLOSE INSPECTION, TWO AREAS OF WATER WEEPAGE WERE FOUND.

THERE WERE NO 4 TO 6 INCHES CONSEQUENCES TO THE PUBLIC HEALTH AND SAFETY AS A RESULT OF THIS EVENT.

COMPONENT FAILURE SIMILAR OCCURRENCES WERE REPORTED TO THE COMMISSION AS LER 80-37 8 79-0 CORROSION 1.

UNITED STATES STEEL CORP, REACTOR CLEANUP LINE WAS ISOLATED 8 AFFECTED PORTION OF PIPE WAS REPLACE D WITH A LOW CARBON STAINLESS STEEL PIPE.

PIPE MATERIAL FROM REGENERATI VE TO HONREGENERATIVE HEAT EXCHANGER WAS ASTM-A-312, TYPE 304.

A SAMPLE OF THIS PIPE WILL BE SENT TO A LABORATORY FOR ANALYSIS OF THE FAILURE M ODE, AND THE RESULTS PROVIDED IN A SUBSEQUENT REPORT.

VERMONT YANKEE-1 05000271 010681 DURING THE WEEKLY REVIEW OF SURVEILLANCE TESTING DATA, IT WAS DISCOVERED SYSTEM CODE NOT APPLICABLE 81-002/03L-0 020581 THAT QUARTERLY STACK PARTICULATE COMPOSITE AS REQUIRED BY T.S. 4.8.C.3.

COMFONENT CODE NOT APPLICABLE 036153 30-DAY D COULD NOT BE COMPLETED BECAUSE STACK SAMPLE FILTERS FOR THE MONTH OF 0 SUBCOMPONENT NOT APPLICABLE CTOBER WERE MISPLACED. SIHCE PLANT WAS SHUTDOWN AT THAT TIME AND AN ANA PERSONNEL ERROR LYSIS OF DATA FROM REMAINING 1.ACK SAMPLE FILTERS INDICATED NO UNUSUAL A RADIATION PROTECTION PERSONNEL CTIVITY, Il IS CONCLUDED " ARF WERE NO CONSEQUENCES TO HEALTH AND SAFETY ITEM NOT APPLICABLE OF PUBLIC.

'HFRE WERF a0 PR' JICUS OCCURRENCES OF THIS TYPE.

THE STACK SAMPLE rititRS FOR CCTOBER WERE MISPLACED.

APPLICABLE PERSONN EL HAVE BEEN WEINSTRUCTED AS TO THE LOCAIION AND PROPER STORAGE OF THE S TACK SAMPLE FILTERS AFTER THE MONTHLY ANALYSIS IS PERFORMED.

f.

~*

LER MONTHLY REPORT SORTED BY FACILITY PAGE 92 MAR 26, 1981 PROCESSED DURING MARCH. 1981 FOR POWER REACTORS FACILITY / SYSTEM / COMPONENT /

DOCKET NO./

EVENT DATE/

COMPONENT SUBCODE/CAUSE C'

/ LER NO./

REPORT DATE/

EVENT DESCRIPTIDH/

CAUSE SUBCODE/MANUFACTUk t CONTROL NO.

REPORT TYPE' CAUSE DESCRIPTION VERMONT YANKEE-1 05000271 010681 DURING THE WEEKLY REVIEW OF SURVEILLANCE TESTING DATA, IT WAS DISCOVERED SYSTEM CODE NOT APPLICABLE 81-003/03L-0 020681 THAT THE SURVEILLANCE FREQUENCY FOR THE MONTHLY DIESEL FUEL OIL QUALITY COMPONENT CODE NOT APPLICABLE 036154 30-DAY ANALYSIS WAS EXCEEDED.

SINCE-THE ANALYSIS WAS IMMEDIATELY AND SUCCESSF SUBCOMPONENT NOT APPLICABLE ULLY DONE AND EACH DELIVERY OF FUEL OIL IS ANALYZED PRIOR TO STORAGE IN THE PLANT TANK. IT IS CONCLUDED THAT THERE WERE NO CONSEQUENCES TO THE H PERSONNEL ERROR RADIATION PROTECTION PERSONNEL EALTH AMD SAFETY OF THE PUBLIC.

OTHER OCCURRENCES WERE REPORTED AS RO 8 0-34/3L. RO 80-05/3L AND RO 79-12/3L.

ITEM NOT APPLICABLE THE ANALYSIS WAS NOT PERFORMED AS SCHEDULED DUE TO PERSONNEL OVERSIGHT.

THE ANALYSIS WAS IMMEDIATELY PERFORMED WITH SATISFACTORY RESULTS. APPL ICABLE PERSONNEL HAVE BEEN REINSTRUCTED IN THE REQUIREMENTS OF THE SURVE ILLANLE TESTING PROGRAM.

YANKEE ROWE 05000029 012281 DURING NORMAL OPERATION IN MODE

1. WHILE PERFORMING MONTHLY SURVEILLANCE REACTOR TRIP SYSTEMS 81-00t/03L-0 022081 0F LOW MAIN COOLANT FLOM SYSTEM "B".

UNDERCURRENT RELAYS 2A AND 4C FAIL-INSTRUMENTATION

  • CONTROLS 036155 50-DAY ED TO DROP OUT WHEN DEENERGIZED. THE SYSTEMS ARE REQUIRED TO BE OPERATI SENSOR / DETECTOR / ELEMENT OMAL PER TECHNICAL SPECIFICATION TABLE 3.3-1.

THIS IS THE FIRST EVENT 0 COMPONENT FAILURE F THIS NATURE.

THE REDUNDANT SYSTEM "A" WAS OPERATIONAL AND WOULD HAVE MECHANICAL PERFORMED AS REQUIRED. THEREFORE THERE WERE NO ADVERSE EFFECTS TO THE P WESTINGHOUSE ELECTRIC CORP.

UCLIC HEALTH OR SAFETY.

THE ROOT CAUSE OF THIS EVENT WAS DUE TO A RESIDUE LUILDUP DN THE RELAY A CTIVATION PLUNGER.

ALL RELAY PLUNGERS IN SYSTEM "B" WERE INSPECTED 1 CL EANED AS NECESSARY.

ALL RELAYS IN SYSTEM "A" WERE INSPECTED & CLEANING WAS MOT REQUIRED. RELAYS ARE UESTINGHOUSE TYPE SC-1 NO. 1876-072.

NO F URTHER ACTIONS ARE DEEMED NECEESSARY AT THIS TIME.

ZION-l 05000295 121680 DURING NORMAL OPERATION. THE GAS DECAY TANK RAD MONITOR ORT-PR02B WAS TA PRCSS + EFF RADIOL MONITOR SYS 80-055/03L-0 011581 KEN OUT OF SERVICE FOR MAINTENANCE. THE SalFT OPERATING PERSONNEL WERE INSTRUMENTATION + CONTROLS 033691 30-DAY IMMEDIATELY NOTIFIED. HOWEVER. SHIFTLY GRAB SAMPLES WERE NOT TAKEN FOR TWO SHIFTS AS REQUIRED BY TECHNICAL SPECIFICATION 3.14,1.C.

hJ RELEASES OTHER OCCURRED DURING THIS TIME AND THE HEALTH AND SAFETY OF THE PUBLIC WERE PERSONNEL ERROR LICENSED 8 SENIOR OPERATORS NOT AFFECTED.

OTHER A FAILED EQUIPMENT SURVEILLANCE WAS NOT STARTED DUE TO AN OVERSIGHT BY T HE SHIFT OPERATING PERSONNEL.

THE PERSONNEL INVOLVED HAVE BEEN RE-INSTR UCTED ON THE NECESSITY OF PERFORMING THE REQUIRED SURVEILLANCE ON FAILED EQUIPMENT. NO FURTHER ACTION IS NECESSARY.

ZION-1 05000295 122680 DURING NORMAL OPERATION, THE GAS DECAY TAKr CUBICLE RAD MONITOR ORT-PR02 GAS RADI0ACT WSTE MANAGMNT SYS 80-056/03L-0 012381 B FAILED TO RESPOND TO ITS INTERNAL CHECK SUURCES OR TO AN EXTERNAL SOUR INSTRUMENTATION + CONTROLS 033692 30-DAY CE.

THE MONITOR WAS TAKEN OUT OF SERVICE AND SHIFTLY GRAB SAMPLES WERE TAKEN AS REQUIRED BY TECHNICAL SPECIFIC & TION 3.14.1.C.

THERE WERC NO SA COMPUTATION MODULE IMPLICATIONS AND THE HEALTH AND SAFETY OF THE GENERAL PUBLIC WERE N FETY OTHER NOT APPLICABLE OT AFFECTED.

NUCLEAR MEASUREMENTS CORP.

THE FAILURE WAS DUE TO BAD ELECTRICAL CONTACTS ON THE PRINTED CIRCUIT B0 ARD (NMC P/N CRM 70).

THESE CONTACTS WERE REPAIRED.

THE MONITCR WAS TH EN FUNCTIONALLY TESTED AND RETURNED TO SERVICE. THIS IS THE FIRST OCCUR RENCE OF THIS TYPE FOR THE MONITOR AND NO FURTHER CORRECTIVE ACTION IS N ECESSARY.

_ __. -., ~ _. _,,.

UNITED STATES NUCLEAR REGULATORY COMMIS$10N I

l W ASHIN G T u'J. D. C. 20555

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U.S. N UC LE A R R E GU LATOR Y OFFICI AL BUSINESS COMMasslON PEN ALTY FOR PRIVATE USE, $300 o

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J 120555064215 2 NJ US NRC SECY PUBLIC DOCUMEN T ROOM BRANCH CHIEF HST LOBB Y WASHINGTON DC 20555 l

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