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{{Adams
#REDIRECT [[05000530/LER-1992-005-02, :on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility]]
| number = ML17306B427
| issue date = 04/24/1993
| title = LER 92-005-01:on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility
| author name = Bradish T
| author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
| addressee name =
| addressee affiliation =
| docket = 05000530
| license number =
| contact person =
| document report number = LER-92-005-02, LER-92-5-2, NUDOCS 9305050208
| package number = ML17306B426
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 16
}}
 
=Text=
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, FACILITYNAME (I)                                                                        eT                                                f4 0
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MSSV        Set    oints        Out      of Tolerance REPORT DATE {7)                                    OTHER FACIUTIEB OIVOLVED(6)
EVENT DATE (6)                        LER NUMBER (6)
                                                                                                                        - FACILITYNAMES                    DOCKET NUMBER(S)
MONTH    "DAY                              NUMBER        er  NUMBER MONTH        DAY N A                      0  5    0    0  0 1    023 92 92                            005                0    1    0 4 2 4 9 3                                          N A THIS REPORT IS SVBMIITEDPURSUANT TO THE REQUIREMENTS OF 10 CFR $ t (Check one or moro ot the fooovrkro) (11) 0  5    0    0    0 OPERATINQ MODE (6)                                                              20A05(c)                          50,73(a)(2) {lv)                                73.71(b) 20A02(b) 5046(c)<<)                          50.73(a)(2)(v)                                  73.71(c) 20AOS(a)<<){l)
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OTHER (Spectiy ln Abstract below srrrlln Text NRC Forin 3ddA) 20AOS(a}<</(lv)                          50.73(a)(2)(ll) -                50.73(a)(2)(vli){B) 20AOS(a)<<)(v)                          50.73(a) (IIII)                    50.73(a)(2)(x)
UCENSEE COHTACT FOR TIES LER {12)
TELEPHONE NUMBER NAME Thomas R.            Bradish, Nuclear                    Re    ulator Affairs,                      Mana    er                          602 393                      5421 COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANUFAC.                                                                                        MANUFAC CAUSE SYSTEM          COMPONENT            TURER            To NPRDS ../+~i:,p~~'::        >ps', ip CAUSE SYSTEM      COMPONENT          TURER BVPPLEMENTALREPORT EXPECTED                (I6)                                                                  MONTH      DAY  YEAR EXPECTED SUB LBSSION DATE <<5) 1( YES  (llyes, conrptete EXPECTED SUBMISSION DATE)                                        No                                                                    07 31            9 3 ABSTRACT ((brit to fdoo specea    I e., spproxbnstely Iitteen stools space typewritten(ines) (16)
On    October 23, 1992, while Unit 3 was in Mode 6 (REFUELING) wi.th the Reactor Coolant System at approximately 95 degrees Fahrenheit and at atmospheric pressure, an APS engineering evaluation of ASME surveillance testing results determined that eleven (11) of the twenty (20) Main Steam Safety Valves (MSSV) as-found relief settings were out of the tolerance limits specified in Technical Specification 3.7.1.1. The testing and adjustments were performed during the period of October 10 through October 23, 1992, while Unit 3 was in a scheduled refueling outage.
The MSSVs have been the subject of setpoint drift. The cause of the event is being investigated in accordance with the APS Incident Investigation Program.
The results of this investigation and any corrective action to prevent recurrence will be included in a supplement to this LER which is expected to be submitted by July 31, 1993. This supplement will also include the results of the investigation identified in LER 528/92-004-01. As immediate corrective action, the MSSVs were disassembled, inspected, reworked (as required),
reassembled,                retested,              and      their        lift setpoints              were readjusted.
Previous similar events were reported in MSSV and PSV LERs 528/88-014-01, 528/89-007-02, 528/89-010-00, 529/89-002-00, 529/89-007-00, 529/90-004-01, 529/91-005-01, 530/91-001-01, and 528/92-004-01.
9305050208 930424 PDR        ADOCK 05000530 S                                        PDR
 
                        ) UCENSEE, F YENT;QEP9QT(lFR),/PE(CglPINUAQPN FACUTY NAME                                  DOCKET NUMBER            Wl NUMBER                *. PACE SEOUENTlAL
 
NUMBER
                                                                                'EVSlON N NUMBER Palo Verde Unit  3 osoloo 530 92              0  05      0  1  0 2 OF 0 9 DESCRIPTION OF WHAT OCCURRED:
A. Initial Conditions:
On  October 23, 1992, Palo Verde Unit    3 was  in Mo'de 6 (REFUELING) withi the Reactor  Co@lant System (RCS).(AB) -at:approximately, 95 degrees- Fahrenheit and at'tmosphericvpressure during a scheduled refueling outage.
B. Reportable Event Description (Including Dates and Approximate Times of Major Occurrences):
Event  Classification:    Condition Prohibited by the Plant's Technical Specifications.
Palo Verde Unit 3 is a two-loop pressurized water reactor (PWR).
Each loop has a vertical U-tube steam generator (SG)(AB) with two outlet main steam lines (SB) per steam generator. Overpressure protection for the shell side of the steam generators and the main steam lines up to the inlet of the turbine (TRB) stop valve (SHV)(TA) $ s provided by twenty flanged, spring loaded, direct acting, ASME Code Main Steam Safety Valves (MSSV)(RV)(SB)-which have open bonnets and discharge to the atmosphere.          The MSSVs are mounted on each of the main steam lines upstream of the Main Steam Isolation Valves (MSIV)(ISV)(SB) but outside the Containment (CTMT)(NH). The opening pressure of the MSSVs is set in accordance with ASME Code and Technical Specification (TS) 3.7.1.1 requirements. The MSSVs are set to  lift  sequentially at 1250, 1290, and 1315 pounds per square inch gauge (psig).
The MSSVs are    required by TS 4.7.1.1 and the ASME Code to be tested once per five, years. This testing is being conducted at less than the five year interval in accordance with the corrective action for the previous out-of-tolerance relief settings in Units 1, 2, and 3 as reported in LERs 528/88-014-01, 528/89-010-00, 529/89-002-00, 529/89-007-00, 529/90-004-01, 529/91-005-01, 530/91-001-01, and 528/92-004-01. An enhanced preventive maintenance and testing program has been implemented wherein the MSSVs are removed for testing and sent to an offsite testing facility (Westinghouse Test Facility). The MSSVs are tested in accordance with approved procedures under elevated steam pressure conditions. Each MSSV is tested to determine its as-found              lift setpoint. Following this testing, the MSSVs are 'disassembled, inspected, reworked (as required), reassembled, retested, and their  lift setpoints are readjusted.
 
h,'
lL.lGENSEE.FVEtg';REPORT) {LER)jan%)Pt'QPPP)gUAT10N FAClQlY NAME                                      OOCKET NUMBER
                                                                " '      * ', LKR NUMBER
                                                                              , SEOUENTIAL ., REVISION
                                                                                  'NUMBER'.'UMBER PAOE Palo Verde Unit      3 060005309                      005          01      0 3 OF 0 9 On  September 19, 1992; Unit 3 was shut down for a planned refueling outage'uring the r'efueling outage,'he MSSVs were removed and sent to the offsite testing facility for scheduled testing. On October, 23, 1992, APS Engineering personnel                  .
(utility, non-licensed) completed a review of data obtained for
                  . the MSSV testing conducted at the offsite testing facility from October-10 'through 'October 23, 1992. Based upon a review of the
                *
                    -a'ctual test results .ele'ven (ll) of twenty (20) MSSVs as-found relief settings-were out of tolerance. None of the MSSV 'as-found relief settings were below specification; eleven (11) were above specification. The maximum deviation from the setpoint for the as-found settings was 3.35 percent high. The as-found settings for seven (7) valves were greater than one percent but less than two percent high, two (2) valves were greater than two percent but less than three percent high, and two (2) valves were greater than three percent high. Setpoint and as-found data for these valves has been tabulated in Section V. of this report.
Since eleven'of the twenty MSSV as-found relief settings were outside the TS limit,    it is assumed that one or more of these valves were outside the TS limit during operation. Therefore,                      it is assumed that the OPERABILITY requirements and the associated ACTIONS were not met for TS 3.7.1.1.
Status of structures, systems, or components that were inoperable at'he start of the event that contributed to the event:
Other than the MSSVs described in Section I.B, no structures, systems, or components were inoperable which contributed to the event.
D.      Cause  of  each component or system      failure, if known:
Not applicable - no component or system failures were involved E ~      Failure mode, mechanism, and effect of each failed component, if known:                                /
Not applicable - no component        failures  were involved.
For failures of components with multiple functions,              list of systems or secondary functions that were also affected:
Not applicable - no component        failures  were involved.
 
            ~ " i . q 3 ~i I, r~ FLICENSEE EVENT RPPORT      (LER) /EX'ONTINUATION P
DOCKET NUMBER                                            PAOE FACILITYNAME P"P SEQUENTIAL ";.N'EVISION v'UMBER        4    NUMBER Palo Verde Unit 3 os ooo53092                005            0  1  0  40F09 G.      For a        failure that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the train was returned to service:
Not applicable - no failures were involved which rendered a                        train of a safety system inoperable.
H.      Method        of discovery of each component or system failure or procedural error:
Not applicable - there have been no component or system                      failures or procedural errors identified.
Cause        of Event:
The MSSVs and          Pressurizer Safety Valves (PSV)(RV)(AB) have been subject        to setpoint  drift as reported in LERs 528/88-014-01, 528/89-007-02, 528/89-010-00, 529/89-002-00, 529/89-007-00, 529/90-004-01, 529/91-005-01, 530/91-001-01, and 528/92-004-01.
APS      has implemented an enhanced preventive maintenance and testing program as described in Sections I.B and III.B. The cause of the setpoint drift is being investigated in accordance with the APS Incident Investigation Program. This investigation is expected to be completed by June 30, 1993. The next Unit 2 refueling outage will be the        first  opportunity for APS to retest and reinspect MSSVs that were initially tested and rebuilt in accordance with the enhanced testing program. The results of this investigation will be included in a supplement to this LER which is expected to be submitted by July 31, 1993. This supplement will include the results of the investigation identified in            LER  528/92-004-01.
During the        last Unit 3 refueling outage, the Unit 3 MSSVs were tested in place using the Furmanite Trevitest method described in previous LERs. The MSSVs were removed and tested during this refueling outage as part of the enhanced preventive maintenance and      testing program for MSSVs described in Sections I.B                and  III.B.
Unit        3 is currently in the third refueling outage.
During MSSV disassembly and inspection, although most exhibited seat wear and some of the MSSVs had steam cut seats, no discs were replaced. No galling between the disc holder and disc guide was observed as        it  was in the Unit 1 valves (LER 528/92-004-01).                  No obvious additional information relating to the setpoint drift of these valves was immediately obtained from this testing.
 
I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER                                            PAOE FACILITYNAME
                                                                        >g
                                                                        ?"'?
SEOUENTIAL NUMBER  P REVISION A NUMBER Palo Verde Unit  3 os oo o5 3092            0      0 5      0    1  05pF09 TEXT Safety System Response:
Not applicable - there were no safety system responses                and none were necessary.
K. Failed  Component  Information:
Although there were no failed components associated wi.th this event the following data is provided for information:
MSSVs Manufacturer:      Dresser Valve and Controls Division Dresser Industries, Inc.
Model No:    6" 3707R Consolidated Main Steam          Safety Valves Type 3700 II. ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS OF THIS EVENT:
As  described in Section I.B, the MSSVs are intended to provide overpressure protection for the secondary side from the steam generators and main steam lines up to the turbine stop valves.              The MSSVs ensure that steam generator pressure remains below 110 percent of design pressure and the RCS pressure remains below the acceptance criteria of 120 percent of design pressure for large feedwater line breaks, for Control Element Assembly (ROD)(AA) ejections and 110 percent of design pressure for all other overpressurization events.
APS  Engineering has completed a preliminary review of the as-found condition of the MSSV setpoints and determined that, for the design basis accidents, the MSSVs would have prevented system pressure from exceeding 110 percent of steam generator design pressure (peak analyzed pressure was approximately 108 percent of steam generator design pressure) and the sequential lifting scheme would have ensured that steam generator  integrity would not be compromised. Furthermore, event occurred in which the MSIVs remained open, overpressure protection if an could have been automatically provided by the Steam Bypass Control System (JI). In addition,    it  should be noted that secondary side pressure is monitored by Reactor Operators (utility, licensed) in the Control Room (NA), and manual overpressure protection is provided by remote operation of the Atmospheric Dump Valves (ADV)(PCV)(SB) from the Control  Room.
The Bounding  Anticipated Operational Occurrence for overpressure events at Palo Verde is a Loss Of Condenser (SG) Vacuum (LOCV). The LOCV event is the limiting event for    a decrease      in heat removal by the secondary
 
LICENSEE EXEAT'REPORT JLERl'TSP CONTINUATION FACILITYNAME                                                            'LER NUMBER                  PAOE YEAR p~ SEQUENTIAL Ih REVISION NUMBER F" NUMBER
  =Palo Verde Unit    3
          'h                                    osooo53092                00'5          0    1  D 6 oF 0 9 system. APS Engineering performed a preliminary LOCV analysis to determine    if  the as-found condition for the MSSVs and the PSVs could have resulted in the steam generator pressure or RCS pressure exceeding the limit of 110 percent of design pressure.        The analysis used the as-found MSSV and PSV setpoints.      The assumptions used for this analysis
              , are similar to assumptions used in the previous MSSV setpoint tolerance calculations described in the LERs discussed in Section IV. The peak RCS p'res'sure reached dur'ing"the analysis 'gas'2712 psia, which remained below the limit of 2750 psia. The peak-steam generator pressure reached during the analysis was 1358 psia, which remained below the limit of 1375  psia.
The assumptions made      in this LOCV analysis are similar to the assumptions made in      the Updated FSAR. The analysis in the Updated FSAR estimates that RCS pressure will reach approximately 2742 psia. Three additional assumptions, each supported by either tests or analyses, have been made to limit the RCS peak pressure increase.          These assumptions are summarized below:
: 1)    The High    Pressurizer (AB) Pressure Trip (HPPT) response time was changed to 0.5 seconds from 1.15 seconds'urveillance testing for the three units has shown that the HPPT trip response time is consistently less than 0.3 seconds. An assumed response time of 0.5 seconds is therefore conservative.
: 2)    The surge    line friction form loss factor  was reduced        to 3.0 from 3.9 to  reflect actual Palo Verde design. This change was analytically justified in a calculation    performed by ABB-Combustion Engineering in May 1989.
: 3)    In previous analyses, the PSVs were assumed to open to 70 percent of the nominal area opening at the setpoint pressure. In this analysis, the PSVs are assumed to open to 100 percent (modeled in the CESEC code as 0.99 of the nominal area opening) at the setpoint pressure. This operation of the PSVs is justified based on the test data presented in ABB-Combustion Engineering Topical Report CEN-227 "Summary Report on the Operability of Pressurizer Safety Valves in CE Designed Plants." This report was accepted by the NRC for use at Palo Verde in Supplement 8 of the Safety Evaluation Report (NUREG-0857).
The assumptions    used  for the preliminary analysis are similar to the assumptions    used  in previous MSSV setpoint tolerance calculations described in the LERs discussed in Section IV. If the results of the final analysis are significantly different than the preliminary analysis, the results of the final analysis will be discussed in a supplement to this report. Based on the preliminary results of the
 
LtKENSE~EATIREFIOAV'(L'CR)TEXT CONTIN0ATI5N FACILITYNAME                                  DOCKET NUMBER                                            PACE SEOUENTIAL  REVISION YEAR    -NUMBER    NUMBER Palo Verde Unit    3 o- s  o o o'- 5 3 0 9  20 05            0  1  070FO    9 analyses  described above, there were no safety consequences            or implications resulting from this event.
III. CORRECTIVE ACTION:
5mmediate:    .
Following the testing, the      MSSVs were disassembled,        inspected, reworked (as required), reassembled, retested, and their              lift setpoints were readjusted. Seven (7) original Unit 3 valves were returned to the Unit; thirteen (13) were replaced with pre-tested spares that had been included in the preventive maintenance program.
A  tracking system, using individual serial numbers, has been implemented to facilitate trending test results as the valves are not necessarily returned to the same location.
B. Action to Prevent Recurrence:
The cause  of the setpoint drift is being investigated in accordance with the APS Incident Investigation Program. The investigation is expected to be completed by June 30, 1993 results of this investigation and any corrective action to prevent
                                                                                                'he recurrence will be included in a supplement to this LER which is expected to be submitted by July 31, 1993. The supplement to this LER will include the results of the inspection identified in LER 528/92-004-01. No supplement to LER 528/92-004-01          will be      issued.
APS  has submitted an amendment to the TS      to increase the tolerance on the MSSV setpoints (161-03587-WFC/JST,        dated November 13, 1990).
Due to the tendency toward setpoint drift exhibited by these valves and NRC Information Notice 89-90, in 1991, APS started an enhanced preventive maintenance and testing program for MSSVs.
Starting with the Unit 2 1991 refueling outage, MSSVs have been sent to an offsite test facility so that the valves could be tested, disassembled, inspected, reworked (as required),
reassembled, retested, and have their It lift    setpoints readjusted.
should be noted that the twenty (20) Unit 3 MSSVs were removed during the current Unit 3 outage and shipped to the offsite testing facility.
All twenty (20) Unit 2 MSSVs will be removed and shipped to the offsite testing facility during the current (March 1993) Unit 2 refueling outage. Six (6) of these valves      will be reinstalled in
 
LICdblSEE EVENT FfPPOAT'(LEH) TEXT 6ONTINOATI6N PAOE FACILITYNAME YEAR
                                                                            '  SEOUENTIAL ~~ REVISION
                                                                            ~ 'UMBER $      - NUMBER Palo Verde Unit    3 osooo53092                  0050            1  0 8 OF 0 9 TEXT Unit  2  following maintenance and testing. The other fourteen (14)
MSSVs  will be  replaced with pre-tested spares that have previously been included in the preventive maintenance program. Seven (7) of the Unit 2 MSSVs had been removed, sent offsite, tested, and placed into the preventive maintenance program during the last Unit 2 refueling outage. All four (4) Unit 2 PSVs are also
                        -. scheduled for shipment: to the offsite testing fa'cility for testing, inspection,iand rework as required.
I'V.
PREVIOUS SIMILAR EVENTS:
MSSV    and PSV LERs 528/88-014-01, 528/89-007-02, 528/89-010-00, 529/89-002-00, 529/89-007-00, 529/90-004-01, 529/91-005-01, 530/91-001-01, and 528/92-004-01 describe events where MSSVs were out of the tolerance limits specified in TS 3.7.1.1 and PSVs were out of the tolerance limits specified in TS 3.4.2.2. Corrective action for these MSSV and PSV events include readjustment of the valves and an administrative reduction of the five year testing interval, as described in Sections I.B  and  III.B.
Previous corrective actions could not have prevented these events because    they would not affect the tendency toward setpoint drift exhibited by the MSSVs and PSVs as described in the previous LERs.
ADDITIONAL INFORMATION The  Unit 3 PSVs were also tested during the current refueling outage and the as-found setpoints were within the required tolerance of TS 3.4.2.2.
The PSVs were tested, disassembled and reworked (as required),
reassembled, retested, and had their        lift  setpoints adjusted in accordance with the preventive maintenance program. No problems were noted. Setpoint and as-found data for these valves has been tabulated below.
Main Steam and Pressurizer Sa et Valve Test Results Se tember 1992 Unit 3 Refuelin Outa e SSV Ta  Numbe        Set  oint Toler  nce      s  ou d    essure              Va  iance PSV0554          1250  psig (1238-1262)    1280  psig                        +2,4 PSV0555          1290      (1278-1302)    1313                              +1.78 PSV0556          1315      (1302-1328)    1320                              +0.38 PSV0557          1315      (1302-1328)    1318                              +0.23 PSV0558          1315      (1302-1328)    1333                              +1.37 PSV0559          1315      (1302-1328)    1324                              +0.68
 
I LlCENSEE EVENT REPORT (LER) TEXT CONTINUATlON DAOE FACILITYNAME
                                                                          '~~+
SEOVEN      REVISION YEAR        NUMBER P4  NVMBER Palo Verde Unit    3 TEXT o  5  o o  o  530  9200501                        0 9oF Main Steam and Pressurizer    S'afet  Valve Test Results          cont Se tember 1992    Unit  3 Refuelin  Outa e MSSV Ta  Number  Set  oint Tolerance          As Found Pressure                Variance PSV0560    1290 psig.(1278;1302).,      1297  psig                      +0.5 PSV0561    1250      , (1238-1262)      1265                            +1.2 PSV0572    1250    c ,(1238-1262)      1257                            +0 5~
PSV0573    1290        (1278-1302)      1297                            +0 5~
PSV0574    1315        (1302-1328)      1359                            +3.35 PSV0575    1315        (1302-1328)      1345                            +2.28 PSV0576    1315        (1302-1328)      1327                            +0.99 PSV0577    1315        (1302-1329)      1338                            +1 75
                                                                                              ~
PSV0578    1290        (1278-1302)      1289                              0.00 PSV0579    1250        (1238-1262)      1291                            +3.28 PSV0691    1315        (1302-1328)      1333                            +1.37 PSV0692    1315        (1302-1328)      1333                            +1.37 PSV0694    1315        (1302-1328)      1341                            +1.98 PSV0695    1315        (1302-1328)      1327                            +0.99 PSV Ta  Number    Set  oint Tolerance          As Found Pressure                Variance PSV0200    2485  psig (2460-2509)      2500  psig                      +0.60 PSV0201    2485        (2460-2509)      2499                            +0.56 PSV0202    2485        (2460-2509)      2504                            +0.76 PSV0203    2485        (2460-2509)      2479                            -0.24
 
t}}

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