Text

Monthly Operating Rept for Dec 1978
	ML18113A793
Person / Time
Site:	Surry
Issue date:	01/04/1979
From:	Costello O; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18113A791	List: ML18113A790; ML18113A793;
References
	NUDOCS 7901190055
	Download: ML18113A793 (42)
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VIRGINIA ELECTRIC AND POWER COJVIANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO;* 78-12 DECEMBER, 1978 APPROVED:

L:) 32, til'J~AGER 7901190055

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CONTENTS Section

Operating Data Report - Unit #1 1:

Operating Data Reprot - Unit #2 2 Unit Shutdo~1s and Power Reductions - Unit #1 3 Unit Shutdm~1s and Power Reductions Unit 112 Load Reductions Due to Environmental Restrictions 5 Unit Ill Load Jleductions Due to Environmental Restrictions 6 Unit 112 Average Daily Unit Power Level - Unit Ill 7 Average. Daily Unit Power Level - Unit 1!2 8 Summary of Operating Experience 9 ArJendments to Facility License or Technical Specifications

11 Facility Changes Requiring NRG Approval. 12 Facility Changes That Did Not Require NRG Approval 12 Tests and Experiments Requiring NRG Approval 14 Tests and Experiments That Did Not Require NRC Approval 14 Other Changes, Tests and Experiments 15 Chemistry Report 16 Description of All Instances Where Thermal Discharge .Limits 17

were Exceeded Fuel Handling 18 Procedure Revisions That Changed the Operating Mode Described In 21 The FSAR Description of Periodic Tests 1'n1ich Were Not Completed Within The 22 Time Limits Specified In Technical Specifications Inservice Inspection 23 Reportable Occurrences Pertaining to Any Outage or Power Reductions 24 Maintenance of Safety Related Systems During Outage or Reduced Power 25 Periods - Unit #1 - Mechanical Maintenance Maintenance of Safety Related Systems During Cu.tage or Reduced Power 28 Periods - Unit #2 - Mechanical Maintenance

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Section Haintenance of Safety Related Systems During Outage or Reduced i30 Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Relkted Systems During Outag~ or Reduced 32 Pc:wer Period:.; - unit {.!2 - Electrical 1-hintenance Haintenarice qf Safety Related Systems During Outc;geor_ Reduced 34 Power. P~riods - Unit {fl - Instrument N,,_intenance Haintenance of Safety Related Systems During Outage or Reduced 36 *.

Power *Periods ....: Unit 112 - Instrument Haintenance Health Physics Summary 38 Procedure Deviations reviewed by Station Nuclear Safety and 39 Operating CoIDiilittee after Time Limits.Specified in T.S.

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DOCKET NO. 50-280 D.4TE 04 JAN 7~

COMPLETED BY O.J. COSTELLO TELE?HONE ~04-357-3184 OPERATING STATUS

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1. UNIT NAME SURRY UNIT 1

2. REPORTING PERIOD 0001 12-1.-7-8 TO 2400- 12-31-78

3. LICSNSED THERMAL POWER <UWT) i441 ,-------------~----------,

-4. NrAHEPLATE _RATING \GROSS MWE) ~47.5 !NOTES I

5. DESIGN ELECTRICAL RATING (NET MWE) ~22 I I E. MAXIMUM D5PENDABLE CAPACITY (GROSS MWE) 911 I I

7. MAXI~U0 DEPENDABLE CAPACITY lNET ~WE) 775 l _____________ :.__'_ ________ I

8. IF CHARGES OCCUR IN CAPACITY RATINGS NIA (ITE,~iS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS 9~ POWER LEVEL TO WHICH RESTRICTED. IF ANY NIA

\NET M'ilE)

10. REASONS FOR RESTRICTIONS~ IF ANY NIA THIS MONTH XR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.0 9760.0 52824.0

12. iVUNBER OF HOURS REACTOR i./AS CH.ITICAL 259.9 6393.0 3 5-6 g ':' * ?

13. REACTOR RESERVE SHUTDOW~ HOURS 0. 0 :) . 0 o. *o

14. HOURS GENERATOR ON-LINE 250.8 6293.7 34858.9

15. UNIT RESERVE S!iUTDOtiN FIOURS 0. 0. 0. 0 0.0

16. GROSS THERMAL ENERGY GEOERATED (MWH) 583881.:) 15214957.0 80355953.0

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 187570.0 !~94771.J.0.0 26307583.G

19. VET ELECTRICAL ENERGY GENERATED (MWH) 178035.0 4704155.0 24971719.0 1~. UNIT SE0VICE FACTOR 33.7 ojo 71. 8 o I?.. 6E.O olo

20. UNIT AVAILABILITY FACTOR 33.7 olo 71. B ojo c6.0 o/o'

21. UNIT CAPACITY ?ACTOR (USING MDC ~ET) 30.9 olo E9.3 o/o 61.0 olo

22. UNIT CAPACITY FACTOR (USING DER NET) 29.1 o/o 65.3 o/o .; 5 7. 5 o/ o

23. UNIT FORCED OUTAGE RATK f) 5 . 6 o/o 7. 2 o/o 16.3 o/o

24. SHUTDOWNS SCHEDULED QT/ER NEXT 6 MONTHS (TYPE.DATe.AND DURATION OF EACH) NONE

25. IF SHUT DOWN AT END OF REPORT PERIOD *.

1-2 79 ESTIMATE DATE OF STARTUP

26. UNITS IN TEST STATUS . FORECAST ACHIEVED

. (PRIOR TO COMMERCIAL OPERATION)

INI'1.'IAL CRIT_ICA1..ITY IRITIAL ELECTRICITY.

COM!1ERCI AL OPEH.ATION

.. REPORT DOCK.ET NO. S0-2S1 D.4l'E 04 J.4ll 79 e

COMPL~T°E,'D BY O.J. COSTELI.iO TELEPHONE 004-357-31~4 OPE RATING STATUS

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1. UNIT NAL'1E SlJRRY UtlIT 2

2. R~PORTING PERIOD 0001 12017? TO 2~00 123178

3. LICENSED THERMAL PO~E? (MWT) 2441 ,~------~----------------,

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4. NA~EPLATE RAT:NG :GROSS MWE) 947.5 I :VOTES I

5. DESIGN SLECTRICAL RATING (NET MW~) 822 I I

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE) 811 I l 7.

9.

MAXIMUM DEP8NDABtE CAPACITY (NET MWE)

IF CHAYGZS_OCCUR IN CAPACITY RATINGS 775 N/A '-----------~------------'

(ITEMS~ THROUGH 7) SINCE LAST REPORt. GIVE REASONS

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY N/A UlET MYE)

10. REASONS FOR RESTRICTIONS. IF ANY N/A THIS MONTH YR-TO-DATE CUMULATIVE 11 .. 80URS IN REPORTING PERIOD 744.0 9760.0 49704.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 724.2 7267.7 336130.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0. ;') 0.0

14. HOURS GENERATOR ON-LINE 722.1 *72413.L~ 3 31 77. 3 .

15. UNIT RESERVE SHUTDm!N HOURS 0. 0 0. 0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 1747175.0 17525943.0 77236177.0 17: GROSS ELECTRICAL ENERGY GENERATED- (MWH) 567125.0 5657145.0 2 s 2 2. 4 5 3 9

0 1e. NET ELECTRICAL EJERGY GENERATED (MWa) 539749.0 5371967.0 23925084.0

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UNIT SERVICE FACTOR 97.1 o/o '!. 2. 7 o/o 6 6. 7 ojo

20. UNIT AVAILABILITY FACTOR 97.1 o / o e2. 7 o/o 6 6. 7 o / o

21. UNIT CAPACITY FACTOR (USING MDC NET) 93.4 o/o 79.1 o/o 62.1 o / o

22. UNIT CAPACITY FACTOR (USING DER NET) 39.1 o/o 74.6 .

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23. UNIT FORCED OUTAGE RATE 2.9 o / o 2. 2 o/o .2.1 . 4 0 /.., 0

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS STE At'>'f GENERATOR REP LAC ENE NT (TYPE.DATE.AND DURATION OF EACH) 6 NONTHS 1-25-79

25. IF SHUT DOwN AT SND OF REPORT PERIOD.

ESTIMATE DATE OF STARTUP

26. UNITS IO TEST STATUS lPRIOR TO COMMERCIAL OPERATION)

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INITIAL CRITICALITY

. - FORECAST ACEilEVED T:iIT I AL ELEC*TRIC.IT Y COMMERCIAt OPERATION

f)OCKETNO. . 50-280 UNiT smsnJOWNS AND rm*vJER rrnpUC."TIONS Surry 1

uNITNAME

... * - DATE Jan.-4, 1979 COl\iPLETE!J,BY S. Steve1.1.s REPORT MONTii DECEMBER 1978 iELE! i!ONE (804) 357-3104

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-- --- I -l 12-8-78 s 15.4 A 3 Rampdown to repack "B" and "C" Hain 78-7 Feed Regulating valves. Repacked valve::;,

While return;Lng to 100% power, reactor t-ripped by_ turbine trip on Hi-Hi level in "C" steam generator caused by mal-function of "C" Hain Feed Regulating valveo Adjust~d stroke of valves.

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I 78-8 12-12-78 F D 1 78-04 7/03L-0 1 Primary t:o Secondary leakage on "C" steam.generator exceeded 0.3 gpm limitation. Shut Clown at end of reporting period. Inspected steam generators and plugged :;.eaking tubes.

1 3 F: forced itcason: Methot!: Exhibit G- Hnslrni:tlons

- S: Scheduled A-Eqiii'pnienl Failure {Explain) I ~Manual for Prcpic:aliun of Data D-Mai11l1:1rnm:e oi Test 2-Munu:il Scram. Entry Sheets for Uc.:cnsee C*Rcfudii1g _ J-Aulomallc Scram. J~venl Hcpo11 (LEIU Fik (NUltEG*

. D-Hcg11lat'ory-Rcs1rlc1!on 4-0lhcr (Explain) 0161.)

E-Opc1alor Tial11i11g & License Er.amlnatfon F-/\d1ninistraii*1e

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DOCKET NO~ . ...,5_0_-*_ 2_81_,,.....,_ __

UN ff SHUtDOWNS AND POWER RlEPUCTIONS

UNIT NAME Surry 2 .

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iuwoar MONTH DECEHBER 1978 lELEi l!ONE (804) 357-3184 licensee Cause & Corr eel Ive

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Rcpotl # Prcvc111 Hc~1a1cni:e 78-8 12-2-78 F 21.9 A l 8 GPH Primary leakage via 2-CH-314 I valve packins. Repacked valve.

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3 4 F: forced Heaso11: . Method: Exhibit G - !11slmctlo11s S: S.ch<!dulct! {\*Eq!iirim;ent Failure (Exp!aln} I *Manual for Prepa!a!lmi of Dara IJ-Mafo!Ciiam:e i>i Tes! 2-?lifanu:ii Scrnm. Entry ~heels for Lh:ensee C-Rcfoclhlg .. .... 3-Autonli.ll!c Scram. ,Evcul ltq1urt (LEIO Fik (NUIU.:G- *I-f,

. D*Hcglllalory Hcs1rli:1!011 E*Opi!rato1 Tiai11i11g & License Examlna!lon 4-0lhcr (Explain) *0161) ,,

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LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: DECmIBER, 197~

f-i I l REASON DATE TIME HOURS LOAD, HH. REDUCTIONSl NI HWH

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None duri h.g this reporti ng eriod.

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I HOt{THLY TOTAL

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e e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT N0.2 MONTH: DECEMBER. 1978

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DATE TIME HOURS LOAD, HW REDUCTIONS 2 HH HWH REASON None duri1g this reporting- eriad.

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' MONTHLY TOTAL 0

DOJi.Ji.ET NO 50-2~0

UNIT SURRY 1 DATE 1-1-79 COMPLETSD BY 0 J COSTELLO lj_Qfl.'l.Jl. : DECE,:JBER 197?

AVERAGE DAILY PO'/IER LEVEL AVERA.GE DAILY ?0',!ER LEVEL DA:Y \!-f'tl E NET) DAY (N'i/E-NET) 1 736.9 17 IJ

0 2 747.7 19 0.0 3 737.8 19 0.0 4 746.5 20 o.o t> 749.2 21 0.0 6 748.6 22 u. 0 7 750.4 23 0.0

13 664.6 24 0.0 9 I 76.9 25 0.0 10 710.0 26 0.0 11 731.3 27 lJ

0 12 18.3 28 0.0 13 0 * :J 29 0.0 14 0.0 30 0. 0

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15 0.0 31 0. 0 16 0.0 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS ON THIS .FORM. LIST THE AVERAGE DAILY UNIT POJER ~EVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR jHE NtT ELECTRICAL Rr1TI}IG OF THE UNIT. THERE MAY BE OCCASI.'JNS 'tlHEN THE DAILY AVERAGE .POWER EXCEEDS THE 100 ~/ 0 ~INE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVSRAGE DAILY UNIT POWER OUTPUT SHEET .SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

DOCK2.'T NO so-2°1 UNIT SUH.RY II

DATE 1-1-79 COMPLETl?D BY D J COSTELLO

}10 .'l'J:.fi.: DEC ~:~*!BE l?. 197g AVERAGE DAILY PO~lEF( LEVEL AVERAGE DAILY Po;.; ER LEV~:,

DAY 'u"J;.; E- NET) UAY U1YE-NET) 1 752.9 17 749.0 2 647.5 18 747. 3 3 25.4 1°9 7 53. 1 4 E82.0 20 758.4 5 755.2 21 758 0 6 755.6 22 757.5 7 757.3 23 756.3 8 756.3 24 750.2 9 753.8 25 750.4 10 755.4 26 752.8 11 756.9 27 756.2 12 747.8 28 7 51. 5 13 755.2 29 .750.1 14 751.7 30 7 51. 6 15 749.5 31 75*3. 4 16 749.8 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS ON THIS FORM. LIST THE AVERAGk DAILY UNIT POWER LEVEL 1N MWE-NET FOR EACH DAY IN THE .REPORTING MONTH. THESt FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT. THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POYER EXCEEDS TEE 100 °/ LIUE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGg 0

DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPAREN~ ANOMALY:

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. I ~ill-frt~RY OF OPERATING EXPERIENCE~

DECEHJ3ER, 1978 Listed below in chronological sequence by unit is a sununary of operating experiences for this month which.required load reductions or resulted in signi!-

ficant non-load related incidents.

UNIT 1 December 1 This report period begins with the unit at 100/; p9wer. At 0735 power was reduced to 97/~ to *facilitate removing "A" High Pressure Drain Pump for repacking~ At 0810 power was returned to 100%.

Operation with the "A" High Pressure Drain Pump out for repacking and the "B" High Pressure Drain Pump inoperable with a motor prob-lem caused an approximate 40 HWe reduction in unit output. At 1550 11 A11 High Pressure Drain Pump was returned to service.

December 8 At 1855, commenced unit rampdown to approximately 100 MWe to allow repacking "B" and "C" Main Fe~d Regulating Valves. At 2220, stopped rampdown at 100 MWe, 17% reactor power.

December 9 At 0416, the *reactor tripped on turbine trip caused by Hi-Hi Level in "c 11 Steam Generator. Hi-Hi Level was the result of a malfunction df c Main Feed Regulating Va.lve. At 0550 reactor was critical. At 0735 11 11 reactor tripped by turbine trip on Hi-Hi Level in "C" Stearn Generator *.

Hi-Hi Level was the result of malfunction of 11 C11 Main Feed Regulating Valve. At 08L' reactor was critical. At 1025, with unit critical and turbine latched but not on.the line, received rod urgent failure alarm.

At 1144 while instrument technicians were attempting .to resolve the problem with the rod control system, rods F-:10 .and x,.:.,10 droppedo. The

')'."eactor and turbine were manually tripped. Instrument Technicians resolved the problem with the rod control system, and at 1715 the reactor was critical. At 1940 the turbine generator was on the line and power increase COillillenced. At 2252, secured ramp at 600 :t-me due to secondary chemistry transient caused by condenser inleakage. At 2345, commenced slow ramp to 675 MWe. At 0650 unit at 670 MWe.

December 10 - At 0700 commenced ramp to 100% power. At 0921 reactor power was at 100% *.

December 11 - At 2140 commenced unit shutdovm due to. 11 C11 Steam Generator primary to secondary leakage in excess-of allowable limit.

December 12 - At 0214 the generator was off the line. At 0243 the reactor was shutdown and at 0825 the unit was at less than 350°F.

December 31 - This reporting period ends with the unit still .shutdown for.steam generator tube inspeittion and .repair.

UNIT 2 December 1 This reporting period begins with the unit at 100% power.

December 2 At 1625, commenced unit shutdown due to excessive primary leakage on 2-CH-314 (Letdown Line Hanual Isolation Valve) packing. At 2325 the generator was taken off the line. At 2335 the reactor was shutdown.

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-MMARt OF OPERATING* EXPERIENCE *

. (CONTINUED)

UNIT 2 December 3 At 1925 after repairs to 2-CH-314 were completed, the reactor was taken critical. At _2119 the generator was placed on the line.

December 4 At 0200 the power increase was stopped at* 71% power on request of the system operator. At 0500 commenced raising power.* At 0730 the unit was at 100% power.

December 31 This reporting period ends with the unit at 100% power.

AMEHDHENTS T~ACILITY LICENSE OR TECHNICAL SICIFICATIOUS DECEMBER, 1978 None during this reporting period.

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FACILITY CHANGES REQUIRrnG NRC APPROVAL DECEMBER, 1978 None during this reporting period.

FACILITY CHAHGES THAT DID. NOT REQUIRE NRC APPROVAL DECEMBER, 1978 Design Change Unit DC-76 Steam Generator Blowdown 1,2 Description - This modification reduced the blowdown water to a sufficiently low temperature and pressure to enable processing the water by a demineralizer system.

Summary of Safety Evaluation This design change meets or exceeds t~~ safety specifications of the previous system.

Conclusion This modification neither constitutes an unreviewed safety question nor alters the basis for any Technical Specification.

2. DC-77- RCS Overpressure Hitigat_ing System 1.

Description - The containment instrument air system header to the power operated relief valves (PORV), was modified with the addition of a solenoid valve and a backup high pressure air supply in the line to each relief valve. Two existing RCS transmitters have been used to provide high pressure alarms and to control the PORV's. Two keylock switches were installed in the main control board ver.tical section to permit administrative control of the system at the appropriate point during cooldown or heatup.

Summa~i of Safety Evaluation No margin of safety defined in .. the basis for any Technical Speci-fication has been reduced, no potential accident or malfunction dif-ferent fron those previously evaluated have been created, and no consequences of accidents previously postulated have been increased in magnitude.

Conclusion This design change neither constitutes an unreviewed safety question nor alters the basis of. any existing Technical Specifications.

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FACILITY CHANGES THAT NOT H.EQUIRE NH.C APPROVAL (CONTINUED)

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3. DC-77 Domestic Water Backflow Prevention 1,2 Description - In order to comply with State (Virginia) water works regulations air gap, vacuum breaker, and reduced pressure backflow preventers were installed in'the domestic water system at appropriate postions.

Summary of Safety Analysis The installation of this design ch~nge has no refl~ction oti the Safety Analysis Report or the Technical Specification.

Conclusion This design change does not. constitute or create an unreviewed safety question.

4. _p_c- 7 8_

Waste Oil Storage Fae i l ity 1, 2 Description - This design change provides for a sump, a sump pump with accompanying equipment to collect and transfer waste oil to a storage tank ~ Provisions have been included to reduce the probability of oil spillage which would ultimately seep into the river with the instaliation of a dike surrounding the tank.

Summary of Safety Evaluation No modification to or category 1 systems have been incorporated into this design change and safety aspects have been addressed with respect to fire and oil spill measures.

Conclusion This design. change does not constitute an un'reviewed safety question antl the subject is not addressed in Technical Specification.

TESTS AND EXPERTNENTS REQUIRING NRC APPROVAL DECEMBER, 19 78 There were none during this reporting period.

TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL DECEMBER, 1978 ST-31 Service Water Subsystems Data Acquisition TP.st . Unit The results of this test are still being analyzed at this time,* 1,2 however, indications are that it was completea successfully and any results to the contrary will be reported l!n the.next monthly report. Test was conducted December 28, 1978.

ST-35 Inside Recirculation Spray Pump 1 Test was conducted on December 30, 1978. This test to check*

the amperage bn the recirculation spray pump motors after pump maintenance proved satisfar;:tory.

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OTHER Cl:ll1.NGES, TESTS fu'JD EXPERIMENTS There were none during this reporting period.

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SURRY POWER STATTON CHL1JSTRY REPORT .e DECEHE ER , 19_2~

T.S.6.6.A.11 l

PRIHARY COOLAl.'-ff Ai"JALYSIS UNIT NO. 1 UNIT NO. 2 l!

MAXIMUM MINIMUM AVERAGE MAXIMUM MJ;NINUM AVERAGE 'I

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Gross Radioact., µCi/ml S. 77E-l 9.07E-3 1. S3K-l 2.07E-l 9.04E-3 8.3SE-2 iI

- -i Suspended Solids, ppm I

o. 3. 0.2 0.2 0.2 0.1 0.1 '

Gross Tritium, µCi/ml 1. 61E-l 8.SOE-2 1. 23E-l l.04E-l 4.0SE-2 7.90E-2 II lI

Iodine-131, µCi/ml 6.38E-l 7.09E-3 7.19E-2 6. 79E-4 l.32E-4 3. 69E--4 I f

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I-13.l/I-133 0.6822 ___I 0. 4 796 O.S904 0.1436 O.OSS6 t 0.0884 I !

I - i L.=-ydrogen, cc/kg t~7 . 4.8 27 .1 14 7 .1 21.1 30. 3 !

l l J_,ithium,

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2.lS I 0.13 1.08 Io. 38 0.2-1 0.30 II

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l II P.oron-10, ppm + 333.8 r 99.2 2 ;39 . s 116 .. 8 21. 6 f O:cyg~n-16, ppm

4.7 .000 1.14 .000 .000 .000 I

i Chloride, ppm .OS .OS .OS .OS .OS .o.s l

G' l\ pH*@ /.5 °C 7.02 S.39 6.22 7.38 6 .. S6 7.14

+ Borori-10 Total Boron x 0.196 NON-RADIOACTIVE_CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Phosphate Boron 656

-*---0.0 Sulfate 1112 Chromate .06 .. '

SO% NaOH 1400 Chlorine 0.0 Remarks:~__:U~n~i~t:_:::l~s~h~u~t=do~.w~m::........:f~~o~r:..__::m=a=i~n=t~e1~1a=1=1c=e.:.....::l=2--~1~2--~7-8_*_to_l_2_-_3~1--_7_8_ _~~-------~-~~

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. DESCRTPTION OF ALL INSTAHCES WHERF.

Tif-AL--IllSCHARGE LitIITS WE~

DECEMBER, 1978 Due to impairment of the criculating water system on the following days the thermal discharge limits were exceeded as noted.

December 1, 1978

Exceeded 17.5°F 6T across station December 2, 1978

Exceeded 15°F 6T across station December 4, 1978

Exceeded 15°F t.T across station December 5, 1978 *,._ Exceeded 15°F 6T across station December 6, 1978 Exceeded 15°F 6T across station Decer.1ber 7, 1978

Exceeded 17.5°F 6T across station De.cember 8, 1978 *1': Exceeded 17.5°F !:.T across s*tation December 9, 1978 Exceeded 15°F 6T across station December 10, .1978 *>'> Exceeded 17.5°F 6T across station December 11, 1978 Exceeded 15°F 6T across station Indicates dates when station 6T was < l.5°F across the station for some-

time during the day.

These 6T excursions were allowable under Technical Specifications 4.14.B.2.

There were no reported instances of significant adverse environmental impact.

On December 27, 1978, the temperature change at the station diE?charge exceeded 3°F per. hour while per:f:orming, Special Test ST-31. On December 31, 1978, the temperature chan:ge at the station discharge again exceeded 3°F per hour. These changes occurred* while increasing flow through Unit No~ *1 curidenser i:..r,aterboxes and were reported as required by Tech. Spec. 4.14.B.1.

FUEL HA!WLIUG DECEMBER, 1978 One shipment of new fuel for the upcoming refueling on Unit 2 was received December 21, 1978.

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UNIT NO. 1 HANDLING DECEMBER, 1978

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DATE NO OF ANSI NO. NEW OR SPENT FUEL SHIPPED/RECEIVED ASSEMBLIES PER SHIPMENT .INITIAL ENRICIDIBNT SHIPPING CASK ACTIVITY LEVI.

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. .

e UNIT NO . 2 FUEL HAHDI,ING DECmIBER, 1978 e

DATE NO OF ANSI NO. NEW OR SPENT FUEL SHIPPED/RECEIVED ASSEMBLIES PER SHIPMENT INITIAI, ENRICHrillNT SHIPPING CASK ACTIVITY LEVI:~L 12 21 118. . ' 12 LM06FT/3.l .. 2*. 5 mrem/hr.

\ LM06FS/3.l 2.5 mrem/hr.

..

LM06FN/3.l 2.5. mrem/hr.

. ., LM06FR/3.1 2.5 . mrem/hr.

.

'

LM06FG/3.4 2.5 mrem/hr.

. LM06F3/3.4 2.5 mrem/.hr.

LM06FH/3 .1 2.5 mrem/hr.*

LM06FL/3.l 2.5 mrem/hr.

LM06FP/3.l 2.5 mrem/hr.

-1 LM06ET/3.l 2.5 mrem/hr. I

.. -

.. LM06EW/3. l 2.5 mrem/hr.

..

LM06FJ/3.l 2.5 mrem/hr.

..

. ..

- **I

!

I

--

..

.

...

'*

. -:.... **-

----

...

~tf.~'

- -- --- -

~--CC..:R.:::.EIJ..:...'.ISIONS THAT CHANGED -

"' HODE DESCRIBED IN THE F -

DECEMBER, 1978 There were none during this reporting period.

. *"*

,. DESCRI92N OF PERIODIC TESTS WHICH WI~Rh COHPLETED WITHIN THE TIME LINITS SPECIFIED IN TECHNICAL SPECIFICATIONS DECEHBER, 1978 There were none.during this reportin,g period.

~zJ-INSERVICE INSI'ECTIOH

' *~

DECEMBER, 1978 An Eddy Current, Gaging Inspection was performed in Unit Ill A,B, arid C Steam Generators in accordance with VEPCO NDT Procedure 14.1. Eddy current inspections were performed at lOOKHZ and 400KHZ using .650,

.610 and .540 probes.

As a result of the eddy current inspection the following number of tubes were plugged:

A Steam Generator B Steam Generator C Steam Genera tor*

75 69 114 Due to leaks, eight (8). previously plugged tube ends were repair welded in 11 A11 Steam Generator in accordance with.approved Westinghouse procedures.

-*:...24-

_!{.J,RTABLE OCCURRENCES PE1Z°IAINING 'f' ANY OUTAGE OR PO\-lER REDUCTIO, DECEMBER.z 1978 On 12-11-78, a tube leak in Uni-t 1 11 C11 Steam Generator was determined to be of such intensity that unit shutdown was required. LER-78-047/0JL-0

was **submitted covering the details of this event.

/ ',*

Uaintenance of Safety llelated~stems During Outage or *Reduced *Pm1er 'Periods*

UNIT ill Mechanical Maintenance

DEl'f=N.'XH 11 JAN 7g * ?. :119 PM Uf;JT1-UtArNTt:NANCE OF SAFSTY RE[,AT8D SYS1't:MS' DURING OUTAGE 'au REDU1.'E'f) !'OWE[( PE:RIOUS) fr'f.'T S& !IV DT SYS COMP MA!iKNO

SUMMARY

WKPSHF u MR 1'0'I'WNT/.f 1//00/7~ Ff.{ V/l[,V!l n.'v111°P, RE:PACK. Rf1'PACK8/J VA[,VE.' 1 80A1f;150B 3 1?./Q0/7~ HI VALVS FCV-lliAR REPACK VAf,VE RBPllCH.li'D VADVE: i qtl ?00q06 3 1 MS-11q RBPACK. VAI.VE RE:PACl(f.D VALVE.' 1 812051/.22 9 12/13/7D *NS VALVB 12/13/70. SYl. V1iLV& 1-SW-115 RE.'PLACE STEM WITH STAifv'f,fi:SS 1 1/?. R8PiACil'/J STP:M 1 O.J 20fi11'10 7 12/13/7~ E'..! VADV& 1-EW*-131 ii'f,'P[,ACE/J sn:M W.T'l'H S1'A.TNLRSS 2 RE Pf.Ace* VALVE S'l'ISM i ~12061230 7 1'-P.1'*-116 RE:PLACf. .STEM fl!TH STAINLESS 2 Rl'.'PlllCf.D STEM 1 81?.0!01?.SS 7 12/13/7° SI~ VllLVE 12/13/7q E'rl VAf,Vt: 1 .. Elr*-171 R!iPDAC:F. STEM rnrn STAINLESS 2 Re'PLllCr:D S1'b'N 1 8120fi1302 7 fi'T::Ff,ACE 81'1!:/.1 l,T.[TIJ S'l'/J.rN[,f:,'SS 1 1/2 REPMCE 81'/i,'M 1 'l120Gl305 .1 12/13/B s:v . VAlVE 1-BW-1/.1 1 B121J61315 33 12/lli/7° 8\' VAlVE 1-sw-1rio RE:CLACE 81'6?1 WI1'11 8Tt1.UIU:SS 1 1/2 R6'Pf,AC6' S1't:N 1-8!?-170 HE'l'f,ACIS ,'}'J"f,'N W['!'!/ S'l'AJN/.,/*:ss 1 1/2 IN RF:Pl/IC/i,'/J S'fEM 1 ?12131532 2 12/111/7~ f!,{ Vl]T,V E 1?/14/7q 12/11.1f7q 12/1F./7~

Sil Sf{

Cl!.

VAT,VN VA/,V8' v A/,liS 1 *Sf./*17:l h%'"1~1J icv-1111;on ..

lTE.'PLACi!,' 8'/'il'M frl7'1! S1't1INDES8 1 'J./2 IN Rlll'!,AC 11'/J,S'J'BM VALVE DlsC MJ88Jf/(]

BODY TO BONN6"f GASl<.6'1' LlW<.

JN[;pgr;1* ANIJ R8PAJ R RBPL.4CE SI'6'N+DISC lltPUAC6'D FJONNF:'l' AllD LOltb'R GAGE*GASKb' Rl'.'NEWt:D GAGE llrlD LOl-II::R f!I,ArmE GASl(J1'T 1 P.1"131!;33 1 8121315115 1 *eoF.271311 1 81? 1/.1101 2fl St:

8

~

e 12/lF!./7~ RC Vt1DVE PCV-1'1SSA 7

12/1Fo/7?, *.nr; VAirn 1-l/C-71 .C WUP l1F./,1Et' UNF: ISOLAY'WN R!IPAC/i.F:D VALVE,' *i 9.12131520 1-Cl/-Ql! VADV[;; IJH'FlCU[,'l' TO OE'8h'A7'1',' REPLAcrm BONN6'T 1 0.070115'.23 1 12/17/7~ Cll VAl,VE Ell PCV .. 11156 V11[,VE DT::AK.S 1'1/RU 13ADDY REPAIRl','U VAlVE IN1'eliNAlS 1 81/.051215

. i2/17/7~ RC VAL.Vb' .

~.\2051215, 611 RE'PDllCW GASKETS LAPP[!,'/J SAT FOR 100 1 j') /17 /7q HC VAJ,V t PCV-14SSC VADVE [,l','/l/(S 2'/IRU 12/17/7Q, RC EG 1-liC-E-111 Rflf.fOVE~Rl\lNS'l'A[,f, 6 INCH llANDHOl.,8 Rl>NOV/i'/J AN!J RB.TN:l'J'A[,[,!W 6IN I/AND 110[, :t P1'.i'121125 12 p

1 CIJ--31'1 REP/;CK VAlVli' RE'MOVED 0[,D PACKING ANU RSPMCb'/J 1 81?131022 i2/17f7q Cl! VA/,Vt:

RB,'PACK V/lf,VS Rt.'PACKE/J VAlVE 1 81J1 'J1D:~2 ?.°o I 12/17/'i~ li'C VALVE 1-RC-45 {.,,:)

REPf,ACl:,'IJ VALVE 1 ~or.,noqoo 51 Cl/' VADVli' 1-Cll-297 [,EA/(S 'l'/llW 1?/1°/n 1'//1°/7~ Cll VAL.VE 1 *Cfl.*300 VALVE [,EAKS THRU REl'lAC t:D VAf,V E RBP[,!1C/','/J V11LV!'.'

1 1

RO!;;i1oqo1

~or.nd802 5<i 51

°'I 12/lq/70. C/f VA£Vll 1-CIJ--2<Jt1 VALVE UiAl<S TllRU inili'N 8/WT TIGHT IJACKJNG LEAK lff,PAC.rnD 'V A&V/:,' 1 eoqo32300

2 17./10./7~ Cl! VA[,V/i,' 1-cu.,3q2 12/l~f7q HI VAWE r:cv .. 111qo h:PACl<.-C!IECK FOR ST/:,'M lo/EAR Rb'f.'[,ACIW S1'l'M AND PACKING RING 1 . ~1.1:!51215 151 Rl\'PACK-CIJEC/( !:'OR ~;,pg,1i WE:A°R RllPLllCEQ STEN AND PACKING RING 1 q1:t251216 151 12 /10./7~ HI VA£Vt:: FCV-1'17'3

.Au.rusn;;o l'AGKlflG 1 ~120P,OQ25 3 12/1q/7a, CH VADVE FCV-112?. V/llVE STICKING 12/1P/7P, Cl! PIPING FE 1122 W1lKS ON/-; DROP E'V8RY I\ SECONDS CHARG~: hex G1ISK8T CTIGHTEN'fi,'D) 1 912l11'15'1 3 Pb'HF'ORN Pl'. 3?A+Pl'. 3°8 VISUA[, JNSP COf.1PU'1'ED VISUAf, INSN:CUON 1 P.1/'121036 1112 12/1 ~/7~ HSS SNU/JBER 12/1a,17q NS VAf,~E 1*NS*-81 R,l!.'PAC/( VAlVll lil.IMOV/l:/j OLD PACKING REl'LACED WITfl :NE 1 qi21111423 7 NE11UVW OLD PACKING RF.l'lACffD ~'IT/I NE 1 Pj 2111111/.lj T MS VAT,VE 1-NS-75 'Rfll'ACK VADV/i,'

e 12/1°/7q 11

. 1'2/1°/7q MS VAlVE PCV-MS-114 i:-'ACK.IF/r; r,r:A/( N04 S'i'OP Bi'PASS HEPACKt:V VAf,VE 1 813 ?1.0733 1'J/ 1°/7~ RC SG 1-RC-E-18 l/b'MOVE'+R/':.!NS2'ALD fi lNCfl llA:VDflOLF: liE:ftiOV E:D Ail!J IN.~']' ALM,'U 1/.11/IDllO LE COVER 1 812121126 llA VADVS PCV .. 1 1155C SO[,E:NOJU ON l'CV-1'155C BDOf./S AI.'? BY Rff PLACISU VALVE ASSYS 1 A1/.1q0230 13 1?/10/?P. /IC

. 12/1'~/7~ VtlDVl.i' PCV-1456 SODF.NOJD ON PCV-1'~56 BWWS AIR BY RF:Pf,ACE/J VALVF,' ASSYS 1 e1nqo231 13 RC

. 1-lJR-P-O ANNUAD PMS NMP .. P.. G*-012 COMt'U'1'il'U ANNl/Af, PNS 1 811271026 455 17/20/7q BR PUMP Ti'f,'MOVl~->f?f,'Pf,ACE SECONDARY M.4/IWAY //f,'MOVW + REP/,ACBU :11/INWAYS 1 Pi?.121130 101 12/20/7~ RC SG 1 .. l/C*E-1C 81212091.3 35 Rr,'NOVE /IND Rli'INS'l'ALD 6 INCFI IJAND/JOLE [(f,'.lfOVC:/J+l//':lNS'I'A[,[,F,'/J f/JlNDl/0[,E COVERS 1 12/21/7° RC SG 11/C-E-1G IJOUY .TO 80.VNJ..:1' LE1IK Rl:.'P[,,jcsu IJONNET GASKE'l' Ai'//) l'ACKIW 1 8121'!1230 72 12/?.1/7A SI MOV MOV*-1°G**A 1 qor-:2201115 129 VALVE LCV11l60/3 SO[,ONOID VAf,VE' LEAKS 8/IU[,Y INS1'Af,(,F,'/) m::r BOLONOl D VALVE 12/22/7q CH 2111)

CliE'Ch. Of'E:RATION AND REPAIR CHANGIW OUT e'N1'1RE COUP 1 811251210 12/?.2/7q IA COi'fPRilSS 1-Iil-C-2A CHb'CK OP/i'RATION AND REPAIR OV.&,'fUl11U£/W CONl'/le'SSUR 1 ~11)51211 10 12/22/7q IA CONPRP.SS 1-IA-C-213 MOV-t'iV-151C IIAS PACKING u:Ak IN81'/lf,f,f,'V NeN P11CKlNG 1 0 121110713 10 12/22/78 Frr VAf,VE 1-~JOV-l*Y-151 12/22/70. Fl./ VALVE f.JOV-FW-151E PACKING LF.AJ;.<; lNSTAU):D NF.Ir PACKING 1 81?1'11007 1?

1?./22/70. F'..! VA[,V/i' NOV-E:Y-151F PACK.ING U:11KS lNSTllUE.D Nb'fol PllCKJNG 1 A121'1100P. 15 DISC FiANGE U:AKS ON B [,/JS 1 PUNP . R6'PLAC6'/J /!'LEX GASKS1' 1 ?1/.:tll:l?.32 26 1'//2?/70, SI Pl !'ING SI 0,3 -152

. '*

UEFT=i*ff,'C//

UNITl-NAWTENANCE OT! SAFF:TY R/SiATIW SYS1'EMS WRING OUTAGE OR' Ht:DUC/S'I POWER PERIODS)

RbTSE:lil'DT Si'S CO/.IP N/IR!(NO SUM11AfiY f./KPt:RT! u MU 'J'OTDJ-INT.'*f 12/22/7~ Cf{ VAI,VE MOV-13)D PACKING LP.AK REPlACED PACKING 1 111221on10 7 12h3/7q Cf/ V!:J,VE l/CV-131011 SOLENOID wnr, NOT OPERATE JNSTADT,W NEW SOLE'NOI:J 1 0.12161?.52 25P, 12/7.3/7° C!i VAJ,VE 1-C// 1.tO STb'M S/~l'A!r'ATSD PRON DJllPllR1W 118l'LAC6'/J Sl't:M+DI APJ/ARGM 1 .Pj,217?.000 27 12/77 /7.q Rf/ MO\' NOV-R//-1700 INSPECT A/ID Ri<,'PACK Rf.'PAC/(JW 1 Rl:t?.51?20 171 1//27/70. SI VAI,V e 1*-SI- 0 5 BODY TO BOi>Nlff STU/JS DE'l'ERIOATEIJ Hll'PLACt:D STUD AND GASl<E1' 1 R121 'll ?.27 107 D/2°/78 NS VAJ,V E 1-NS-379 Rt;P11CK l' A!,V/S li'EPACKIW VADVE' 1 R112P.l055 3'1 1?/2~/7° NS VA[,Vf. 1-11S-:tt1C> PAC!WiG [,EAK Rb'PACl<F-:D VAl VE 1 ?11?.S1057 311 12/2°/7q /.IS VA!,Vll 1 NS-209 RL'FACK VA£VE REl'AC KF.D 11 A!,VB: 1 91J.7.P1155 2'1 12/?P./7° MS VAI,VE 1-MS-:tSR llfl'11CK VA[,VE HEl"AC/iSIJ VAWE 1 . P.11?R:,159 311 12/7. 0 /'iq NS VM,VE 1-MS-PO m:PACK. VALVE REP1ICl<ED VADVE 1 R112P.1205 33 17./?~/7g NS VALVE: 1 .. MS .. 266 R8P11C K I SO[, FON DRAIN REl'tiCKr.'IJ VAI,VE 1 ~1.12~~/.:1.0 311 17./2°/70. MS VllI,V E: 1-.'!8*711 Rl'.'PACK VALVE REPACKIW VA£VE 1 gll/81305 4 1?/2°/7q /IS VAL,Vt'; 1-Ms-1113 RP.PACK VALV/\ Rb'PACKE.D I/ A!,V8 1 q11(.814:?0 3ll 17./2q/78 SI V/1[,Vt: 1-Sl-79 BODI' ~l'O BONNE1' S1'/JDS DETE'RIOATED . Cl/ANGf,'D GASKF.T 1 P.12).'1 1126 1?.~

17/? 0 /70. fl./ PIPING 1-Sl-l*E' *1A Sh' LISAl~~./70. RC VAJ,VE 1-HCV-145SC CIIANGE SOL,t.'NOID REPDACED S0[£NOJD 1 B12?.81 1i02 23 N~~

~~-...!~~

12/30/7~ RS PUNP 1-RS-P**lB OPI'ICAT,[,Y Al.lGN PUMP OPI'IC AL[,Y ALIGNb'D PUMP . 1 ~0'!07 l!iOS '137 I 12/31/70. RC SG 1-fiC-E 1B £1/i.'/10V8/INSTALI, PRIM NA1Vf.IAYS COMPD6'1'ED 1 P.121.112115 1120 17./31/70. RC SG 1-RC-E-1C R8MOVE,'/INS1'AL[, PRIM MAfMAYS INSTA!,LED NANl~AYS 1 P.1"111320 3g7 12/28/78 cc PUMP l-CC-P-2B EXCESS SEAL LEA!v\GE REPLACED MECH SEAL 1 81225.1300 26 DEPT. TOTAL

~~\.., .* --...../~~

~~" ~f:-~~

(
Maintenance of Safety Related Systems Durino Outage or Reduc~d Powet Periods UNil' f,12
~~Mechanical Maintenance~~
..
UEl'I'=Hf\1,1/ 11 ,l/iN 7"
~~2:59 FN PliU/1 1 UN.P/'2'" I~~
\MMN'l'ENANl'P, Of SAFE.'TY Rl'.'f;,1'/'f<:f) 81'81'81'.f.'.I /JUU!N(J OUTAGF.' 01\ RISVUCi;'IJ POfJt*:J? /Wlt'lODS)
RE;TSflRVV1' SYS COMP MllRKNO 8Ul*111ARY liKPERF u MR 1'<J1'/Jl.'N:l'/.I l2/'J3/7° Cli VALVE
2-C/J-3111 PACK.rNG LE11K TIEPACK8D VIII.VI!: 103 DE,Pr TOTM, 103 I
N l.D I
-
Maintenance of Safety Related Systems During_
Outage or.Reduced Power Periods UNIT tf l Electrical Maintenance
/
UE!'7'=E:LEC lf Jiili 79 " 2:'1'1 P,'J UN.IT1- . . .
~~.NAJNTF.'NA!ICEOC' SAFETY llF.[,AT/i:D SYS1'W*.1S DUUING OUTAGE 011 RF.DUct:v POIVl-:R T'S/1.WDS)~~
RETSEHVIJT SYS CO/IP f*IARKNO SUNN ARY 1./KPEHI!' u MR 7'0'/'IMN1'.'f
.12/0u/70 Ff.I CON1' FCV-1 11Qq CHECK .C:Ol.ENO.WS nsn:D sAT 1 R:l20~1332 ~
17./1~/70. RS com* [,S~RS-100C UP ALARM S!v LEllKING AHOUND TREADS S'../ITCll OPERM'TONAL 1 012150720 ?O .
1?/1~/70. /i,C: COflT LS-RS-100D LO [,P,'V sr~ /JOE:SN'1' OP LOCAL IND L.ZGHT llE/"1!1/'D MICHO SW.l1'Cll 1 R:t/1S0721 20 12/22/70. Cl/ . COllT 11AKF:llP MODE CON!/0[,LE;R OFF PIX Sll'f 1 ?.070"0500 38'1 11
.12//.2/7P /IC p/.fl' M1'11 1-RC-P-18* BRIDGE l'I CUli'VE OTL Slli\!P£E PI llND OJ[, IS SAJ'ISFAC'l'OTIY 1 8.11131507 200 12/2?./7~ RC PNP M'TR 1-TIC-P lA IJEiIDGE PI CUHVE GIL S1li.f/'Lli,' PI AND OJL SllTISFACTORY 1 0.1113150g 200
12/22/7P RC :.fOTOR 1-RC-P-lC BRIDGE r.r CUHVE OIL St:."4PLE PI Nm OIL SAT.lSFACTORY 1 Rl.1131510 200 12/2F./7~ BS VA[,VE TV-SS-10F.A WHL N01' SHUT FRON COiJTROL ROON AD,JUS1'E/J LIMITS 1 817.1C!0013 157 TJi:.'PT TO.TM, 46L19 I
w f-'
I
.. '
Maintenance of Safety Related Systems During Outage or Reduced Power Periods
(..
-(:-
'*
>
UNIT {f2
~--
. Electrical Maintenance c
Electrical Ma~ntenance UNIT 2 There was none during this reporting period.
\,,__ .*
" .~ .. .. J .** (
' .
Maintenance of Safety Related Systems During Outa 0 e or Reduced Power Periods
~~-~'--~~~~~-
UNIT f,!l Instrument Haintenance
(
. /Jf,Pf=If/S]' I IJ JllN 79
~~2:110 PN~~
. llNl1'l~ * *, . . .
UIAlN1't::fiAllCl!J (jf;' SM'E}'f'/ m~£An'l) llYB2'/1f.!S VUU!f{G OUTAGE' Oft /UtfJUCl!:D l'IJl-lmi PE'lllf)f)S) i I. RSTSERVUT Sl'8 CO/.JP MARkNO SUMNARY lvKPb'RP u UR . T01'lWt/T,"1 12/0q/7". Cl/ .rrit.r FCV-it?.2 CONTRO[,Lf:R is iIUNTING VALVE IS S1'ICKING 1 ~113.011115 1£q 12/00/7".. HI CON1' FCV-11JCJ?. REPAIR CONT/f.0[,S AFTt:I? i1F:C/I REPACK CHECK/I'/) T/JE CONTRVLLE!i FON OPENA1'ION 1 812081330 .7 12/0a/7° fit' CVliT FCV-:1.118~ Rf,'P/ilR CON1'ROLS tlF'I'ER Nl','C/I REPACK . CHc'CKlm THE CONT!Wf,[,ER FOH OPf.RA'I'lON 1 Pt20R1331 7 i2/1?./7q Rii IllST 't'R-1-6611 m:EUS C11l..I/Jflli1'JON OR R&PAIR INSf/il,T,EU NflW /(I'D EJ,El1fl'N7' 1 . 81005163'1 1320 12/15/7~ RC. VALVE PCV*11\55A EXC8SIV f,' nor* VADVE OV8R/IAULF.D AUD S'J'ROKE ATUUS1'P,/) 1 P.07.l023'!2 3774
. 17 17/1°/70. RC INST LI-1-461 PZR a;;ver, TRtlN[O,'.JJ1'TER RtlN 2. 3 SA1' 1 Q17.POIJ.35 D/20/70. Hi. CON1' HGV -Fff-15 SB FITTINGS [,EAKING tlT .lSO[, VALt'E+RF:G TIGlf'l'llN&D F17'1'TNGS 1 ~12B0°1S 22 12/20/79. C:r' CONT PCV-14<:iR AIR [,5111<.. A7' Fn'T!NG 1'0 R/','GULATOEI TIGHnNED FITTING 1 R1./1S0917 .22 12/7.7 /7~ CF/ INST PI1153 DISC PiiHSSIJR/',' GJlllGE Ftl!Lr:D ON C PUMP CAf,IBHA'J'l!:U G1li!GE 1 ?,12130730 11'!
12/27 /B CF/ INST Pl-1152 Rb'P[,ACE GAGE CALiiJ/IATE,'U GAi/GP: 1 ~17.7.10 17 11~
D!-Pl' TOTtl[,
I w
Vl
. I
) .
Maintenance of Safety Relate<;l. Systems During_
~~Outage or.Reduced Power Periods UNIT 112~~

Instrw:;:ient Maintenance
.. Instrument Maintenance
~~. , ' UNIT 2 There was none during this reporting period.~~
~~.... -~~
~~' .. HEALTH PHYSICS~~
. DECEMBER, 1978 There was no single release of radioactivity specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20.
There were 5 individuals who received single radiation exposure spec:..fically associated Fith Unit f.11 Outage, which accounted for more than 10% of the allowable annual values in 10CFR20 .101. .
PROCEDURE DEVIATIONS REVIEWED BY STATION NUCLEAR SAFETY AND O?ERATING COHt1ITTEE AFTER TIHE LIHITS SPECIFIED IN TECHNICAL SPECIFICATIONS
~~DECEMBER, 1978 There were none during this repor'::ing peridd.~~
~~\ .~~

ML18113A793

Text

SUMMARY

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