ML20041G187

Monthly Operating Repts for Nov 1981

ML20041G187
Person / Time
Site:	Surry
Issue date:	12/08/1981
From:	Jones V, Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20041G184	List: ML20041G183 ML20041G187
References
NUDOCS 8203190372
Download: ML20041G187 (45)

Text

._.

• s VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 81-11 NOVEMBER, 1981

( t *'

APPROVED BY: S vV\.

STATION MANAGER

[

V f

I l

l 8203190372 811214 PDR ADOCK 05000280 R pon

[

e CONTEh'TS Section M

Operating Data Report - Unit il I Operating Data Report - Unit #2 2 Unit Shutdowns and Power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #2 5 Load Reductions Due to Invironmental Restrictions - Unit il 6 load Reductions Due to Environmental Restrictions - Unit #2 7 Average Daily Unit Power Level - Unit #1 8 Aversge Daily Unit Power Level - Unit #2 9 Susanary of Operating Experience 10 Amendments to Facility License or Technical Specifications 13 Facility Changes Requiring NRC Approval 14 Facility Changes That Did Not Require NRC Approval 14 Tests and Experiments Requiring NRC Approval 17 Tests and Experiments That Did Not Require NRC Approval 17 Other Changes, Tests and Experiments 18 Chemistry Report 19 Description of All Instances Where Thermal Discharge Limits l Were Exceeded 20

! Fuel Handling 21 Procedure Revisions That Changed the Operating Mode DescribM in the FSAR 24 Description of Periodic Tests Which Were Hot Completed Within the Time Limits Specified in Technical Specifications 25 Inservice Inspection 26 Reportable Occurances Pertaining to Any Outage or Power Reductions 28 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance -

29 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 31

~

-is.-

5 5ect on Page, Mair.tenance of Safety Related Systems During Outage or Reduced Power Perieds - Unit #1 - Electrical Maintenance 34 Mair:tenance of Saf sty Relate 1 Systems During Outage or Reduced Power Periocs - Unit #2 - Electrical Maintenance ,

36 Maintenance of Saf ety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance , 40 Maintenance of Safety Related Systeins During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance f 42 Health Physics Sumary 4L i i '

Procedure Deviations reviewed by Stetion Nuclear Safety and Operating Committee after Time Limits Specified in T. S. 45 l

w k

4

(

, h to 3

\

k.

\ '

P i.

\

\

.j. .

o l

\

OPL'5ATING DATA REPORT

~

DOCKET NO. 50~280 DATE 08 DEC 81 COA!PLETED By Vivian H. Jones 1

2ELEP90NE 804-357-3184 UTCRATil.G STATUS

1. Ul.IT llA4E OURRY Ul!IT 1

2. REPORTING PETCOD 110181 TO 113081

3. LICEJJED THERVA! POJER (WT) 2441 l~~~~~~ ~~~~~~l '

4. NA4 CPI.AZE RATINC (GROSS W E) 847.5 l NOTES t -

5. DESIGH E!ECTRICA!. RATING (NET WE) 788

6. VI,XEMUY DE?ENDARTE CAPACITY (GROSS MWE) 811

7. .\'AXIXUM DS?ENDARTE CAPACITY (NET WE) 775

3. IF CHANGE 5 OCCUR IV CAPACITY RATINGS N/A tITC4S 3 THROUGH 1) SINCE LAST REFORT, GIVE REASONS

9. P0di7 TEVE: TO WHICH RESTRICTED, IF Ally N/A tliET :fe'E)

10. REAS003 FOR RESTRICTIQUS. IF Ally N/A

, THIS MONTH YR-TO-DATE CU.VULATIVE

11. 500RS I.V REPORTING PERIOD 720.0 8016.0 78384.0

12. NU%3E3 CF HOURS REACTOR iiAS CRITICAI. 671.5 3011.3 45549.8

13. REACTOR RESERVE SHUTDOVu HOURS 0.0 0.0 3731.5

14. NOURS GEt/ERATJR JN-LINE ,

663.9 2941.4 44610.2

15. UNIT HESER'/E 3HUTDOW!I '100RS ' 0.0 0.0 3736.2

16. G40SS THERVAL,6flERGY GEllERATED (WR) 1593943.6 6871969.4 103261370.4

17. GROSS ELECTRIC 45 ErlERGY GENERATED (WH) 499320.0 2186300.0 33488043.0

18. NET ETECTRICAL. ENEMY GENERATED (.WH) e73478.0 2064659.0 31764583.0

19. UNIT SERVICE ' FACTOR 92 2 e/o 36.7 */* 56.9 e/o

20. UNIT AVAILABILITY FACTOR 92.2 e/o 36.7 e/o 61.7 */*

21. UNIT CAFACITY FACTOR (USING VDC NET) 84.9 */o 33.2 e/o 52.3 */*

22. UNIT CAPACITY FACZ' OR (USING DER NET) 83.5 */* 32.7 */* 51.4 */o

23. UNIT FORCED OUTAGE RATE 7.7 e/o 5.7 */* 25.2 e/o

24. S!!UTDOVNS SCHEDULED OVER REXT 6 M01/THS SPRING 4AINT.~02-19-82-10 DAYS (TYPE,DATE.AUD DURATION OF EACH)

25. IF SilUT DCJN AT END OF REPORT PERIOD, t.STL4 ATE DATE OF STASTUP

25. UNITS Ih TFST SEATUS, '

FORECAST ACHIEVED (PRIOR TO COvVERCIA!. OPERATIOll)

INITIAi CRITICALITY LGITIAL ELECTRICITI COVMERCIAT.,.0PERATION -

g- 'a l *

~

CPERATING DATA REPORT 2 *Currcctcd C:py for November Report DOCRET 70. 50-281 DATE 17 DEC 81 CCA'PLETED Sy Vi7ian H. Jones TELEPH0lin 804-357-3184 OPERATIt.G aTATUa

1. CialT HAVE SURRY UTlIT 2

2. REPORTIhG PERIOD 110181 TO 113081

~

3. LICENJED THERVAL POWER (.WT) 2441 l -l

4. !.'AVEPLA2E RATING (GR0a5 WE) 847.5 lNOTEd l

5. DEdIGil ELitfRICAL RATIt!G (NET WE) 788 S. FAXTi!UM DEPENDABLE CAPACITY (GRoad WE) 811

7. VAXNUN DEPENDABLE CAPACITY (NET .WE) 775

9. IF CdnNGEd CCCUR IN CAPACITY RATINGd N/A (ITD!d 3 THROUGH 7) SINCE LA07 REPOEi, GIVE REA30Na

3. PGWER LEVEL TO WHICH REOTRICTED. IF AVY N/A (NET WE)

10. REA50lla FOR REOTRICTIOU3, IF AhT N/A THId MONTH YR-TO-DATE CUNULATIVE

11. EOUR3 IS REPORTING PERIOD 720.0 8016.0 75264.0

12. NUVBER OF HOURS REACTOR WA3 CRITICAL 144.4 7009.2 44793.2

13. REACTOR RiaERVE SHUTDOL71 HOURa 0.0 0.0 0.0

- 14. HOURJ GE?lERATOR ON-LINE 144.4 6968.8 44105.4 1E 71.IT RL'aERVE JHUTD0k11 HOUR 3 0.0 0.0 0.0

16. CAOSS THE0!AL ENERGY GENERATED (WV) 347730.0 16837196.9 103291857.4'

17. GROSA ELECTRICAL ENERGY GE!/ERATED (.WH) 112325.0 5436745.G 33675739.0

18. NE7 ELECTRICAL EllERGY GENERATED (.WH) 106122.0 5149007.0 31927495.0

19. UNIT aEhVICE FACTOR 20.1 =/* 86.9 =/o 58.6 e/o

20. UNIT AVAILABILI27 FACTOR 20.1 eje 86,9 eje $8,6 eje

21. Ut<IT CAPACITY FACTOR (USING VPC NET) 19.0 =/e 82.9 e/e S4.7 e/e

22. UtiIT CAPACI27 FACTOR (USING DER NET) 18.7 e/e 81.5 e/e 53.8 e/e

23. Ui.IT PuhCED CUTAGE RATE , 0.0 0.0 p

24. aHDTlW,3 6C4EDULED OVER NTXT 6 A!ONTHS REFUELIlio ~ 11~06 42 DA!3 (2XPs.DATE, AtlD DURATION OF EAC11)

25. IV allVT DWN AT END OF REPORT PERIOD.

EcTI4 ATE DATE OF STARTUP

25. UtiIIa I!i tea 7 STATUa FORECAST ACHIEVED (PRIOR TO CO.v.VERCIAL OPERATION)

I!!ITIAL CRITICALI"'Y INITIAL ELECTRICI27 COUERCIAL OPERATIO!!

e

, 2-OPEliATIt!G DATA hE?OR l DOCEET l10. 50-281 DATE OB DEC 81 COVP!JTED SY Vivian H. Jones rEEEPi!DNF 804-357-3184 CFERATZl.G ST.4:US

1. blaIT ./K C SURRY U!!IT 2

2. llEFORTII.G PEEIUD 110181 TO 113081

3. i,1CEASF: THEnMAi, POWER (WT) 2441 \~~~~~~~~~ ~l

4. l:p'E??, ATE RATING (GROSS WE) 847.5 l NOTES l S. DESIGU Ei,TERICAL RATII;G (NET .WE) 788

5. YAXI10.V DEPEllDABi,E CAPACITY (GROSS INE) 811

7. XAXI.4la Li?EilDASTE CAPACITY (NET WE) 775

9. I? ldANGES OCCUR I'l CAPACITY RATINGS N/A (ITEVS 3 IdROUGH 7) SIUCE' i,AST REF0Z' GIVE REASONS

9. ?GiER l EVE.~, TO WfiICH RESTRICTED. IF ANY .7/A

(?iET WE)

10. REASallS FOR RESTRICTIONS. IF ANY N/A THIS MONTH YR-TO-DATE CU4UE,ATIVE

11. EDURS IN REPDETING PERIOD 720.0 8016.0 75264.0

12. liU4BER OF HOURS REACTOR WAS CRITICAi, 144.4 7009.2 44793.2

13. 1EA:ZOR RESERVE SHUTD0aN HOURS 0.0 0.0 0.0

14. EOURS GENERATOR ON-EJNE 144.4 6968.8 44105.4

15. UliIT RESERVE SilVTDS!N HOURS 0.0 0.0 0.0

16. C2OSS THERVAi, ENERGY GENERATED (.WE) 347730.0 16837196.9 103291857.9

17. GROSS Ei.ECTRICAL ENERGY GENERATED (.WH) 112325.0 5436745.0 336*i5739.0

10. NET ETECTEICAi, EhERGY GE!!ERATED (MJH) 106122.0 5149007.0 31927495.0

19. Ul;IT SERVICE FACTOR 20.1 e/e 36.9 e/e 58.6 e/e

20. Ut;IT AVAIi,ABIllTY FACTOR 20.1, ele 86.9 e/o 58.6 */*

21. Ul,IT CAPACITY FACTOR (USING .VDC NET) 19.0 ele 82.9 e/o 54.7 */o

22. UNIT CAPA:ITY FACTOR (USING DER RET) 18.7 e/o 81.5 e/o 53.8 e/o

23. Ui;IT FCECED QUTAGE RATE 0.0 e/o 0.0 ele 20.9 */o

24. SHUTD M S SCHEDUTED OVER ?! EXT 6 VONTHS 'PRING VAINT.-05-07-82-10 DAYS (TYPE.DATE.AND DURATION OF EACH)

25. IF SilUT DOJN AT END OF REPORT PERIOD. DEC. 22. 1981 ESTIcfATE: DATE OF STARTUP

26. Ut.ITS I!v TEST STATUS FORECAST AC!!IEVED (FEIOR TO C04VERCIAi, OPERATION)

INITIni, CRITICALITY INITIAL ELECTRICITY COV.VERCIAL QPERATION b

e UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-280

• UNIT N AME _Surry One DATE 08-81 NOVEMBER, 1981 COMPLETED BY Vivian H. Jones REPORT MONTil TELEPHONE (804) 357-3181i ext. 477 1

.$ E 3 . EI Licensee , .r, E a 1. Cause A Correceive No. Date -h 5g i .2 s E Event uT k'iu Auien t.

! F c$ E 5 j5g Report er i# G Prevent Recurrence 6

81-19 11-25-81 F 17.2 H 3 Momentary loss of power to VB-1-1 with Ch 3 OPAT and Lo Tave in trip for Instrument department testing caused

.l. OPAT reactor trip and high steam line

! flow coincident with to Tave St.

Returned electrical system to normal a' prior to reactor startup.

81-20 11-26-81 F 2.6 H # Anti-motoring trip one minute after generator output breakers were closed.

Had instrument department calibrate sensor for anti-motcring trip.

I . 2 3 4 F: Forced Reasois: Method: Exhibii G . Instructions S: Scheduled A Equipment Failure (Explain) - I-Manual for Preparation of Data ILMaintenance of Test 2 Manual Scram. Enity Sheets for Licensee C. Refueling 3 Automatic Scram. Event Repurs ILLR) File INURI G-D Regulatory Restriction 4-Other ( Explain) 01611 E Operator Training & l.icense Examination F Administrative 5 G-Operational Error (Explain) Eshibit I . Same Soorte t'8/77) ll-Othe r (E xplam)

~ -

4 -

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-280 .

UNIT N AME _SURRY ONE DATE 12-08-81 REPORT MONTil NOVEMBER, 1981 COMPLETED Sy _Vivian H. Jones TELEPHONE (804) 357-3184 ext. 477 "i

No. Date o

i

.!'E 3g 3

@ jjy Ek Licensee Event E

sT

% h

o. 3 Cause & Corrective Action to H g3 E 5 g5g 6

Report ,, ,#G fu Prevent Recurrence 81-20 11-26-81 F 4.3 H 3 Anti-motoring trip two minutes after generator output breakers were closed.

Had instrument department calibrate sensor for anti-motoring trip.

Had electrical lead lifted from sensor i for anti-motoring to prevent another i trip.

81-22 11-29-81 F 32.0 A 3 Lost "A" RCP on instantaneous overcurrent causirig a loss of reactor coolant flow reactor trip. The motor on the "A" RCP will be replaced prlor

. to startup.

I 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions S. Scheduled A Equipment Failure (Explain) - 1 -Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C.Pefueling 3 Automatic Scram. Event Report (LER) File INUREG-D Regulatory Restriction 4 Other (Explain) 01611 E Operator Training & Ucense Examination F Adnunistrative 5 G. Operational Error (Explain) Eshibit I - Same Source 19/77) ll-Othe r (Explain) e

s DOCKET NO.50-28i .-

UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Surry Two DATE 12-08-81 REPORT MONTil NOVEMBER, 1981 COMPLETED BY Vivian H. Jones TELEP110NE _804)

( 357-3184 ext. 477 w.

g e r. 5 ui z o .E _:- = y e ;;; Licensee E

% g4 Cause & Corrective No. Date g 3g g ,g g 5 Event uy a. 3 Action to

• 5 Repor # 97 0 u Prevent Recurrence c3 5 j di g 6

81-16 11-07-81 S 575.6 c 3 Reactor trip on turbine trip caused by high level in the 6th Point Feed Water Heater due to ruptured tubes.

The tubes will be plugged prior to unit startup after refueling.

i I

• 2 3 . 4 F: Forced Reason: Method: Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) - l-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Shecis for 1.icensee C. Refueling 3 Automatic Scram. Event Repore (LER) File (NUREG-D Regulatory Restriction 4 Other (Explaini 0161)

E Operator Training & Ucense Examination l F Administrative 5 l G. Operational Error (Explain) E shibii ! - Same Source t'8/77 I It Other (Explain) l

LOAD EDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS i

UNIT NO.1 MONTH: November. 1981 e

e DATE TIIE HOURS LOAD. MW REDUCTIONS MW MWH REASON i 9

None du ing this re porting period.

S MONTHLY TOTAL

LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTHi Nov'embe r , 1981 4

l '

l 5

DATE I TUfE HOURS LOAD, MW REDUCTIONS, !L' MWH _ REASON NONE DUR ING THIS REPORTING PERIOD.

l MONTHLY TOTAL .

DOCKET NO 50-280 UNIT SURRY I DATE 12-1-81 COVPLETED BY Vivian H. Jones AVERAGE DAILY UNIT POWER LEVEL M09TH: NOVEMBER 81 AVERAGE DAILY POWER LEVEL AVERAGE DAILE POWER LEVEL DAY (NWE-NET) DAY (NWE-NET) 1 731.3 16 728.8 2 729.9 17 732.2 3 706.8 18 733.8 4 728.0 19 732.7 5 728.5 20 730.8 6 728.0 21 728.7 7 723.1 22 730.9 8 724.7 23 730.0 ,

9 723.9 24 730.0 10 728.7 25 410.3 11 728.7 26 108.9 12 731.3 27 576.6 13 729.3 28 691.3 14 729.8 29 462.5 15 729.0 30 0.0 DAILY UVIT POWER LEVEL FORY INSTRUCTIONS

• ON THIS F0lilY, LIST THE AVERAGE DAILY UNIT POWER LEVEL IN MWE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ANG MONTV. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 =/= LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SIEH CASES, THE AVERAGE DAILY UJIT EDWER CUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

DOCKET NO 50-281 UNIT SURRY II DATE 12-1-81 COVPLETED BY Vivian H. Jones I l

AVERAGE DAILY UNIT POWER LEVEL MONTH: NOVEMBER 81 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MJE-NET) DAY (MWE-NET) 1 743.8 16 0.0 2 744.5 17 0.0 3 741.3 18 0.0 4 743.6 19 0.0 5 740.8 20 0.0 6 704.7 21 0.0 7 3.0 22 0.0 8 0.0 23 0.0 9 0.0 24 0.0 10 0.0 25 0.0 11 0.0 26 0.0 12 0.0 27 0.0 13 0.0 28 0.0 14 0.0 29 0.0 15 0.0 30 0.0 DAILY UNIT POWER LEVEL FORV INSTRUCTIONS ON THIS FORY, LIST THE AVERAGE DAILY UNIT POWER LEVEL 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 THE NET ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE POWER EXCEEDS THE 100 */* LINE (OR THE RESTRICTED POVER LEVEL LINE). IN SLCH CASES, THE' AVERAGE DAILY UNIT POWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

, SLMIARY OF OPERATING EXPERIENCE N0VEMBER, 1981 Listed below in chronological sequence by unit it a suzz)ry of operating experiences for this month which required load reduction:t or resulted in sign-ificant non-load related incidents.

UNIT ONE November 1 This reporting period begins with the unit at 100% power.

November 3 At 0510, the Control Room Operator (CRO) noticed a loss of approximately 10 MWe concurrent with a slight decrease in condenser vacuum. The CR0 notified the Shift Supervisor and an investigation began to determine the cause. At 0850, a power decrease was started due to a continuing decrease in condenser vacuum. The pcwer decrease was terminated at 0918 with power at 90%/650 MWe. The vacuum loss problem was traced to a leaking non-return valve (NRV) in the 6th point extraction steam line to the flash evaporator which had been shutdown at 0435 After isolating this line, condenser vacuum returned to normal. At 1140, a power increase began at 3% per hour. The unit reached 100% power at 1600.

November 13 Commenced ramp down at 2210 due to low pH (7.5) in the feedwater going to the S/G's. The chemists resampled after the ammonia injection pump had been placed in service and found the pH had returned to an acceptable level at 2216 and the ramp down was terminated. A power increase began at 2218 and reactor power was 100% at 2222.

November 15 At 2235, experienced a drop in Tave due to FCV-Il3A failing to open when the instrument air line broke. Reduced turbine power to 740 MWe and commenced a dilution to compensate for the inadvertant boration. Isolated FCV-113A, recovered Tave and returned power to 100% at 2247 November 20 Commenced the S/G moisture carryover test at 2015 November 21 The S/G moisture carryover test was complete at 0040.

November 25 At 1331, a reactor trip occurred on an Overpower AT signal followed by a safety injection (SI) on a high steam line flow coincident with low Tave. The reactor trip was a result of a mementary loss of power to Vital Bus 1-I, which caused a Ch 1 OPAT trip sigr.al, while Ch 3 OPAT was in trip for testing by the instrument department. This satisfied the two out of three trip signal matrix and initiated the reactor trip. The SI was caused by a high steam line flow signal, which was a result of the combined flow from the S/G code safety valves and the flow to the reheater section of the moisture separator-reheaters (MSR's) coincident witha Lo Tave signal. The Lo Tave signal was a result of a momentary loss of power to VB l-1, which caused a Ch-1 to Tave signal, while Ch 3 1.o Tave was in trip for testing by the instrument department. This satisfied the two out of three Lo Tave matrix for locking out the steam dumps and providing a signal to the Hi Steam Line flow matrix. The Hi Steam Line Flow signal was apparently

1

SUMMARY

OF OPERATING EXPERIENCE NOVEMBE R, 1981 November 25 real. The S/G code safeties lifted because the Lo Tave (continued) signal had locked out the steam dumps to the main condenser and the MS flow to the reheater section of the MSR's continued following the turbine trip because the flow control valves were manually Jacked open. The momentar) loss of power to VB 1-I was a result of the delay time between the opening of 15H8, the IH bus normal supply breaker from the F Transfer Bus, and the closing of 15H3, the supply breaker from the No. 1 Emergency Diesel Generator. The loss of power to the F Transfer Bus was caused by an error in the testing of the newly installed under voltage and underfrequency relays on the 2J 416ov Bus. Stabilized conditions and reset Si at 1341. Closed breaker 15F1 and returned the electrical system to normal at 1359 November 26 The reactor was taken critical at 0435. The main turbine-generator was synchronized to the line at 0640 and tripped on an anti-motoring signal at 0641. The reactor was taken critical at 0714. The generator was synchronized to the line at 0916 and tripped at 0918 on an anti-motoring signal.

The reactor was taken critical at 1010. The anti-motoring trip was defeated at 1312 by lifting the electrical leads and the generator was synchronized to the line at 1337 Stopped power increase at 36% at 1500. Started 3% per hour power increase at 1620.

November 27 The "A" High Pressure Drain Pump tripped at 0755 Stopped o.

power increase to stabilize plant conditions. Plant conditions

< stabilized and 3% per hour power increase began at 0845 Returned anti-motoring sensor to operable condition at 1459 l The unit reached 100% power at 2027 November 29 The reactor tripped at 1602 on a loss of reactor coolant flow signal. The loss of reactor coolant flow signal resulted f rom the electrical trip of the "A" reactor coolant pump (RCP) motor on an instantaneous over current condition. At 1924, af ter veri fying unit was at CSD boron concentration, commenced a cooldown to cold shutdown (CSD).

November 30 The unit reached CSD condition at 0637 This reporting period ends with the unti at CSD for repair of the "A" RCP motor.

. ~

- - - . , - w., ,.,e -,---a wg- - - - - - - - - - ,

SUMMARY

OF OPERATING EXPERIENCE NOVEMBER, 1981 UNIT TWO November i This reporting period begins with the unit at 100% power.

November 6 Started unit rampdwon for refueling outage at 1954 at a rate of 150 MWe per hour.

November 7 Turbine trip - reactor trip at 32% reactor power due to high water level in the "6B" feedwater heater at 0026. The main turbine was relatched and a turbine overspeed test completed at 0305 The turbine tripped on overspeed at 1970 rpm. The cooldown conmenced at 0351 af ter verification of cold shut-down (CSD) boron concentration. Secured cooldown at 0440 at 505 F to check lift setpoints on the secondary safety valves on the "A" and "B" S/G's. The safety valve lift ~ test was completed and cooldown started at 1118. The primary system (RCS) temperature and pressure were <350 F/450 psig at 1730 and the Residual Heat Removal System (RHR) was placed in service at 2234.

November 8 The RCS reached CSD condition (<200 F) at 0130.

November 16 The reactor vessel head was removed at 1240. All full length control rods (RCC's) were unlatched at 2300.

November 17 The reactor vessel upper internals were removed at 0234. The off/ load of fuel began at 0605 -

November 19 The reactor was defueled at 2340.

November 20 The fuel insert shuffle in the Spent Fuel Pit began at 0116.

November 21 The fuel insert shuffle was completed at 1154.

November 24 Sludge lancing of all S/G's was complete at 2325 November 26 The core reload began at 1849 November 29 The fuel reload was complete at 0401. The reactor vessel upper internals were installed at 2330.

November 30 All full length RCC's were latched and verified at 1046. The reactor vessel head was set at 1800. This reporting period ends with the unit at CSD with preparations in progress for bolting the reactor vessel head.

'. -13 e

AME!D!ENTS TO FACILITT LICDISE OR TECHNICAL SPECIFICATIONS NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

a f-

+

J i

' I

1 i

e i

i

, a i

F l

I i

i

. . _ _ . , _ _ . . . , - - _ _ . . . __r__, ., _ _ _ _ . - . . , _ . _ . - _ _ . __ _ _ - . . . _ .. --

, FACILITY Cl!ANGES REQUIRING

, NRC APPROVAL NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

FACILITY CHA!K;ES TliAT DID NOT REQUIRE NRC APPROVAL NOVEMBER, 1981 UNIT D/C 77-45 Steam Generator Replacement Project 1&2 This design change replaced the steam generator lower assemblies and associated equipment, as well as modifications and temporary changes that were required to facilitate removal and installation.

SUMMARY

OF SAFETY ANALYSIS The modification required NRC review and approval for this large and complex project. Safety implications were described in the VEPC0 Steam Generator Replacement Submitted and in the NRC Safety Evaluation Report and E ,si ronmental Statement.

D/C 79-83 Fire Protection Breathing Air System 1&2 This design change provides a Breathing Air Charging System for the station as a result of requirements from the NRC Fire Protection Safety Evaluation Report dated Sep'tember 19, 1979 The system has the capability to provide breathing air l

for a minimum of 10 men for a six-hour period at a use rate of three cyclinders of air per man hour.

SUMMARY

OF SAFETY ANALYSIS

~

This addition enhances the fire suppression capability of the fire brigade. The personnel involved with the operation of the high pressure air system will have the proper training and will observe normal safety precautions and operating procedures.

D/C 80-53 insert Check Valve Replacement Bearings I&2 This design change provided a method for replacing teflon insert check valve bearings with stainless steel bearings. The teflon bearings were not qualified for the estimated total integrated radiation dose due to the valve locations. The overexposure I

of these valve bearings could have resulted in failure of the valve to operate properly. ,

1 -

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL NOVEMBER, 1981 UNIT D/C 80-53 Insert Check Valve Replacement Bearings (continued) I&2

SUMMARY

OF SAFETY ANALYSIS The Service Water System and Component Cooling Water System capability and operation readiness is not affected. There are no safety implications created by this design change. This modification increases the reliability of the check valve to operate af ter an accident.

D/C 81-22 Installing Malfunction Alarm On Radiation Monitoring System 1&2 This design change provides an audible alarm in the event of a loss of power to the Radiation Monitoring System. The annunciator will alert the operator immediately upon a loss of power to this system.

SUMMARY

OF SAFETY ANALYSIS This modification does not effect the automatic action of the radiation monitor and it will improve the safe operation of the system.

D/C 81-39 Fire Protection For Temporary Clean Change 1&2 This design change connects the fire protection piping to the sprinklers in the temporary clean change trailer located adjacent to the auxiliarf building.

SUMMARY

OF SAFETY ANALYSIS This modification reduces fire hazards in the temporary clean change trailer an.d does not lessen the capabilities of the rest of the fire protection system.

D/C 81-48 Unit #1 Auxiliary Feedwater System Cavitating Venture Flange 1&2 Modification This design change replaced 3" 600 psi carbon steel slip on type flanges with 3" 600 psi stainless steel weld neck type flanges. This design change eliminates a mismatched flange condition and any thermal expansion problems at the gasket seating surfaces.

SUMMARY

OF SAFETY ANALYSIS This modification enhances the integrity of the Auxiliary Feed System and should reduce the occurance of leaks due to failed gaskets at the flanges.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL NOVEMBER 1981 UNIT D/C 81-115 Emergency Egress Lighting 8 Hour Rating 1&2 This design change upgrades in certain areas existing emergency lighting circuits frnm a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to a minimum 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rating by adding additional battery packs to existing circuits.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect station operations or the operation of any station system.

/

n

, TESTS AND D: PERI!!E TS REOUXRING

. NRC APPROVAL.

NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL NOVEMBE R, 1981 NONE DURING THIS REPORTING PERIOD.

4

l t

. ', OTHER CHANGES, TESTS AND EXPERIMENTS NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

l i .

f l

I l

l 1

u

'I p' 9' ~ -

SURRY PO G ST/. TION

. CHO!ISTRY REPORT Nov , 19 2 T. S . 6. 6. 3.d x

PRI.%RY COOLANT UNIT NO. 1 UNIT NO. 2 (B) (?)

ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGI

-1 y-1 '

Gross Radioact., UCi/ml 1.6h (c) 5.2h (c) 1.2k (c) 8.7k-1(a) 9.9b-4 1.0 >

(a) (a)

Suspended Solids, ppm 1.50 .10 .14 .1 .1 1 E-1 E-1 E-1 L-1 L_3 Gross Tritium, UCi/ml 2.05 1.34 1.85 1.23 2.51 5.2h.2 p2(c) E-1(c) E-1(a) E -3 E -1 Iodine-131, uCi/ml 5.0f(a) (c) 9.05 7.95 7.73 3.07 1.48

~ ~

1.1392 .8858 .7011 1.6255 .9259 1.2914 Hydrogen, cc/kg (d) (d) (

49.3 12.8 29.5 41.5 2.5 18.3 Lithiu=, ppm 1.40 .94 1.16 .30 .21 .27 B2ron-10, ppa + (d) (d) (d) 404.2 149.5 222.1 416.5 4.9 393.6 Oxygen-16, ppm .000 .000 .000 3.9 h .000 1.2(d' Chleride, ppe (d)

-<.05 <.05 <.05 .09 (5) ~< .05 4.05 pH G 25'c 6.64 5.69 6.45 7.73 4.48 5.50 l + Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, PODNDS (E)

T. S . 4.13 . A. 6 ,-

Phosphate - Boron 1297 Sulfate - Chromate .30

~ 500 NaOH Chlorine l Rs= arks: (A) Reflects Unit trin (B) Unit shut down for refueline 11-7-81 (c) High values due to suspected fuel failures (d) Unit at shutdown condition (e) These levels of chemicals should represent no major adverse environmental impact (f) Dip sample l

(cavity open) 11-20-81 @ 1335 0 saturated thereafter.

7 I

l 1

DESCRIPTION OF ALL INSTANCES WHERE THERMAL DISCHARGE LIMITS WERE EXCEEDED NOVEMBER, 1981 I

l Due to the impairment of the circulating water system on the l following days, the thermal discharge limits were exceeded as noted.

November 1, 1981

• Exceeded 15 F AT across station.

2, 1981 o November

• Exceeded 15 o F AT across station.

November 3, 1981

• Exceeded 15 F AT across station, November 4, 1981 Exceeded 15 F AT across station.

November 5, 1981 Exceeded 15 F AT scross station.

November 6, 1981 Exceeded 15 F AT across station.

November 9, 1981 November 10, 1981

• Exceeded 15lF AT across station.

• Exceeded 15 F AT across station.

November 11, 1981

• Exceeded 15 F AT across station.

November 12, 1981

• Exceeded 17.5 F AT across station.

November 13, 1981 Exceeded 17.5 F AT across station.

November 14, 1981

• Exceeded 17.5,,F AT across station.

November 15, 1981

• Exceeded 17 5 F AT across station.

November 16, 1981

• Exceeded 17.5,,F AT across station.

November 17, 1981

• Exceeded 17 5 F AT across station.

November 20, 1981 6 F AT across station.

November 21, 1981 ** Exceeded Exceeded1515,F AT across station.

November 22, 1981 F AT across station.

November 23, 1981

• Exceeded 15lF AT across station.

November 24, 1981 November 25, 1981 *** Exceeded Exceeded15 15lF AT across station.

Exceeded 15 F AT across station.

November 27, 1981

• Exceeded 17.5 F AT across station.

November 28, 1981 Exceeded 17.5 F AT across station.

November 29, 1981

• Exceeded 17.5 F AT across statior

• Indicates dates where station AT was 15.0 F or less across station for something during the day.

The AT excursions were allowable under Technical Specification 4.14.B.2.

There' were no reported instances of adverse environmental impacg The temperature change at the station discharge exceeded 3 F per hour:

on November 7, 1981 due to a Unit Two reactor trip; on November 25, 1981 due to a reactor trip on Unit One; and on November 29, 1981 due to a reactor trip on Unit One.

These events were allowable in accordance with Technical Specification 4.14. Therewerenoreportedinstancesofadverseenvironmentagimpact.

The temperature change at the station discharge exceeded 3 F per hour on

! November 26, 1981 due to a rapid increase in power following Unit One Startup.

This event was reported IAW T.S.-4.14.C.1. There was no adverse environmental impact.

. . . - ~ - - ._ ._

i

. , FlfEL HAl'DLING NOVEMBER, 1981 Unit Two was refueled during this reporting period. Sixty-eight (68) new fuel assemolles and sixty-four (64) new BPRA's were inserted.

a T

a l

a N

4 l

l i

t l'

a 1

+,-.--r r,------_t,,,-.--,- ..--..-,-.....,,..m_ - , ,._ _ . . .__,._.,_.g_ . , , y. ,-. , , -, . , _ 7, ,_,,,,, . . , _ _ _ . , _ . . 79, _ . . ,

FUEL HANDLING UNIT ONE NOVEMBER, 1981 DATE NO. OF ANSI NO. NEW OR SPEhi FUEL SHIPPED / RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LE7E ,

I NONE DURING THIS REPORTING PERIOD.

l l

l

FUEL HANDLING UNIT TWO NOVEMBER, 1981 DATE NO. OF ANSI NO. NEW OR SPENT FUEL SHZPPED/ RECEIVED ASSEMELIES PER SHIPMENT INITIAL ENRIC1DiENT SHIPPING CASK ACTIVITY LEVE NONE DURING .THIS REPORT 1NG PERIOD.

l e

. _ __.__ _ ..___.. . __ . _ _ _ _ _ _ . - _ . . . _ . _ _ _ _ _ _ _ . _ _ = _ . _ . . _ _ . . .

t 24-

, , PROCEDURE REVISIONS THAT CHANGED THE OPERATING !! ODE DESCRIBED IN THE FSAR

! NOVEMBER, 1981 l

.I 1

'I i NONE DURING THIS REPORTING PERIOD, a

h i

a T

4 4

t i

l 4

f i

I

)

1

+

--.rv., , ,_- .- ,-n _

y . - , . . ,_ - , - _ _, , , , , - . ~ , - , , . . . . - . . . , , _ , . ..-mm_,.,, . . . . _ _ , . - .,_ , . . _, . _. .-.,__- . - -mm_ o

. DESCRIPTIOi; OF PERIODIC TESTS WEICH WERE NOT COMPLETED WITHIN THE TDIE LIMITS SPECIFIED IN TECIC;ICAL SPECIFICATIONS NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

e G

.. , _ . _ . _ . . - - . _ _ , y

INSERVICE INSPECTION NOVEMB ER , 1981 UNIT ONE No inservice inspection work was conducted.

UNIT TWO The Westinghouse program for inservice inspection is still in progress.

No reportable or major indications have been reported. There have been minor indications that have been corrected by mechanical maintenance. During the course of the inspections.

An inspection of ASME Class 3 supports and hangars was performed. Minor indications were noted and will be corrected by mechanical maintenance as scheduling permits.

o An eddy current examination was performed on ID water box. There were no reportable indications noted.

An ultrasonic inspection was performed on 10 low point welds in the' containment spray system and 10 low point weld on the recirculation spray #

system. No reportable indications were noted.

An eddy current examination was performed on 100% of the tubing in 2-RS-E-1 A '

and approximately 15% in B, C, and D recirculation spray coolers. No defects were noted. -

An eddy current examination was performed on A and B steam generators. In "A" S/G 560 tubes (16%) were examined and in "B" S/G 568 tubes (17%) were examined.

There were no defects noted in any of the tubes.

l A radiographic examination was performed on the main feed water reduce,rs on A, B, and C steam generators. There were no reportable indications noted.

I i

l l

l l

i i

l t s

/

.i .

OEPf Alif 2 URIT2 m (MA!RTENAME OF SAFE 1T REl.ATED SYST!)ts D91Rin( Ct! TACE OR REDtKED PtniER PER10 DSS RCfSF M D7 STS CatP MARDO S1MMART WKEYRF tl NR D1TinitTM '

11/19/81 CS P!PIM 10-CS-103 'IRStVT 10 EJW 101.17 VEEJlS PERTOMED UT ERM RRE 2 11022ns12 165 11/19181 RS P2PIM to-RS-112 ERSIECT to 1/W 10ERT VElnS OR RS STS PERF0 MED t!T EE N MRI 2 11022051s 165

• 11/30/81 ES RR 2-RS-E-10 PERrQM EDOT Cl!RRERT PERTOMED LT MRI 2 111151631 336 11/30/81 RS RK 2-RS-E-1R 1%RFr]M EDDT CliRRFRT PERF0MED LT ERM RRE 2 111151s38 335 .

• 11/30/81 RS MX 2-RS-E-1A 1%RFOM FDOT CilRRERT PERFOMEO 100 PKK ET RRE 2 111151639 391  %

11/30/81 RS R1 2-MS-E-SC PERF0M KDDT CilRMRT PERTOMED ET RRE 2 111t516%0 13%

i ......

'8 DETT 17TAl, 1129 3

'8 ' 'l , s s

-l 4 a' 'd

.g , ,

f f

,/

' i Q .

+

_ , , .../ /*~

' s-',,

,' i

• i *

/ k' d'# $" '

d

(

.a.

1. , ~ . . '_ ;

., __ . y

.a ' -

, - / ,

4 , .s 9

< ' 4 O w-a '

8 e

' f '

R

• j , ,

. , U_

sr '

,  : / -

/

i

. f ,

/.-

l _-

M9 O l e. a l > <

j  ; ~

lw ' ,' e . ,

l

.* Y

- ' ^ ^ ' - - _L _ _

J

/

. ,,) ~28 REPORTAB'LE OCCURRENCES PERTAINING TO ANY OUTAGE OR POWER REDUCTIONS NOVEMBER, 1981 NONE DURING THIS REPORTING PERICO.

i I

T 4

l i

. i I

r l

l 1

i Maintenance of Safety Related Systems During Outate or Reduced Power Periods i UNIT #1 Mechanical Maintenance l

l l

I i

l l

', Maintenance of Safety Related Systems During

, Outage or Recuced Power Periods UNIT #1 Mechanical Maintenance NOVEMBER, 1981 NONE DURING THis AEPORTING PERIOD. .

I

.i O

-319 t

I l

t

_ Maintenance of Safety Rela,

_ Outage or Reduced Po'

_ UNIT #2 Nechanical Mainte e

f I

i I

I 1

1 I

C1.Virn t'l IIMIT2 (MAlVTERA4CE OF SAFETT EELATED STSTF)tS Dt;314C WTACE OR RKinN'ED IMR PER10ft%)

kFTSt hV'r? Srs t*MT' atARKR0 Sint4 ART VKWRT U Mol 1% %%T4 11/vn/n1 36 MTAKM U-2 13NER DOOR PERS DO ROT DISUGME C0'frLETE 2 Stinnnynn 1 11/U8/81 AW l't9er 2-RM-l*-19 SEAL TEARS RWARRED 11M 00 VERT LEWW 2 111n80610 13 11/opl81 CV VALVE 2-CV-5 BLKK 2-CV-5 CM TK VALVE CLOSTD BLAMt 0FP TLA M E 2 11 ton 190n 3 11/08/A1 V PEPIM iRSTALL MICW EC197 iRSTALLED SIDOLS 2 111nn1901 1 11/08/81 Y PIPIM 1RSTALL CHANWEL MEAT) ORAlf C04T'LFTE 2 111netin?  %

11/on/81 nr 11tESSUR  ?-NC-E-2 OPU PRESSUNilER TO IRSitKT 10 OPEEED*CLtA%ED tiA MANAT 2 110220%31 199 11/n9/e1 V PIPEM INSTALL Siv0tflRCES COtPLETE 2 11Sant%29  %

11/ini.t C4 FIPIM REPAIK WELD REPAlt VELDED SUrickT 1% 2 1110%n901 to 11/in/nt C4 FiftM KWA!R V%LD REPAIR VELIMD SUPivRT 15 2 111060909 7n 11/11/81 St VIPIM REPAIR LTLD -

RFM0VED NATERIAL inn't NT Fire MD M 2 ttins0911  %

11/1%/81 NE VALVE 2-EC-Sn AIR STRA18ER DRAIM VALVE LEAKS LAPPED DOWNET 111 N DT AWI) Pl T 2 111o*n%n% 1 11/14/nt n't 11MP EV-759 DOES WOT PUWP REPLACE PIMP 2 1111' Sal % 7 St/11/at KE DIESEL @C3 Vil,L NOT START IE PREFERRm 1 CtMPl.ETED 2 011851130 15 tt/tR/51 St VALVE 2-51-165 8007 tv BORRET LEM REPKKED VALVE 2 101051111 1716 11/18/81 Si VALVE 2-S1-12% AN PKKlM ANUSTED PKKlM 2 111112306 111 11/19/41 St VALVE 2-S1-090 AM PKKIM ANUSTED PKKitC 2 111112311 til 11/in/At St VALVE 2-31-081 AN PKK!M ANUSTED PKK10C 2 11111111% 1 11/1n/91 51 VALVE 2-51-t%8 AN PKK190 ANUSTED PVKlM 2 111111119 til 11/19/81 51 VALVE 2-51-1%9 AN PKKl3C ANU.5TED PKKiw 2 111112320 n1 e 11/3R/81 St VALVE 2-51-86 AM PKKEM 11/ inlet St VALVE 2-51-93 AN pat'KIM ANUSTED PKKIM ANUSTED PKKIM 2 111112311 2 111112322 tia 3 Y e

11/1R/nt St VALVE 2-51-92 Arri P K Kl K ANUSTED PKKEM 2 111111111 111 tt/tn/n1 Si VALVE 2-ST-13% AN PWKl8C CLAWD ANUSTED PVKinG 2 t1ttillsn 11s St/1n/81 St VALVE 2-51-138 AM PKKIM CLARD ANUSTED PWKlM 2 1111111%1 11' 11/in/81 S FLMGK ORFECE FLA M E LEAKS REPl,KfD CAStET 2 111141%nn 1 11/19/81 Si FIPIM REPAIR VtlDS AS PER 1R-33 1-311 INSit%T VEL!nS 2 111n610%0 1%

11/19/8i M VALVE MOV-RH-2100 VALVE MAcfWNEEL rates OFT REIESTALLED 4AWWHEEL 2 11101715n 212 11/13/81 r4 VALVE 2-CH-361 PKKlM LEM A N USTED P VK100 2 111111300 l1%

11/19/81 C4 VALVE K V-1311 AN PKKIM ANUSTED PKKIM 2 111111301 1 39 11/1'/n1 CW val,VE 2-CH-3%1 AN Pk'KIM ANUSTED PKKISC 2 111112301 11%

11/in/Rt CM VALVE 2-CM-3%1 AM PKKlM CLAfD ANUSTED PWKlM 2 1111123n1 115 11/19/81 CV VALVE 2-C#-331 AM PKKTM A NUSTED PKKIsc 2 111112315 11%

St/in/81 St VALVE 2 31-2%% AN PACKinc ANUSTMD PKilK 2 111112319 11%

11/19/et rv VALVE #tT-2201 AN PKKIM ANUST8D PKK!3C 2 11111211F 11%

11/2n/81 C4 VALVE 2- K-355 RFfLKE EVO CORRODED nt1TS OR VALVE RMWED 2 800 NET RVITS 2 11111180e 1%%

11/71/81 R4 Pt9tP 2-RN-P-1A SWALL SEAL LEAKA REPLKED NRti SEAL 2 1111%S100 2%

11/22/81 K4 VALVE NOV-2101 Ol9tAIJTLE AWD IfSPEYY 90R RDT IRSPEt' DESASSBNRfAD VALVE CIAAQED+RMPKKED 2 110291101 61 1:/23/81 4C VALVE W-25514 PERF0 apt ,9fP-C-nC-Ott NTDRUfEST REl# STALL 2 tin 0911%n 177 11/23/nt QC VALVE SV-255tC PERF0lN WP-C-nc-Ott NTDn0 TEST REIESTALL 2 110011%02 '21 11/23/11 C4 110t!' 2-CH-P-SA 1.1 stall, VERT Ric 1RSTAT, LED AMD RLMaVED YEWTinc RfC 2 1111212%G 25 11/?%/81 W l.tSTR F1 .SV-100R RM OVE F1 RESTAllAD RN TTDV 1RDICATJR 2 0010sn11s 11*$a 11/2%/81 CU VALVE KV-rN-2%60R PKKLM LEM TIGNCTERED PKKlM CLAND 2 1090673ng 29 11/2%/81 C4 VALVE RV-2209 iMLET ARU ut/ TEAT FLAME LEARS REPLAr'ED CASKETS 2 109191%16 R%

11/2%/11 455 SMUBnKR PEnFGft AS Sot!ND SNt/BBER 1RSP. PERF0h4ED AS RDUND SRt1BMFR INSP. 2 11nn9090s  %%e 11/2%/81 CM VALVE MnV-CR-2781A RFNnVE VALVE MOV-CH-1281A RPMOVE VALVE TR04 SYSTRW 2 111n5tn%R 111 11126/n1 r4 VALVE ^WV-CH-22814 EfSTAri VALVE MOV-rN-2281A INSTAL!JD KN VALVE 2 Stinssn%s 32n 11/?%/n1 r1 VALVE %0V-r!!-2811R 1,fSTALL VALVE nUV-CH-?)%TR isSTALffD WFW VALVE 2 1110%1n%9 129

'W . * .-

f *:Trpft *#

UNIT 2 (MAERTERANCE tY SAFFTY RKr.ATED SYSTDt3 iMIREM IMITAGE OR Rf2tCED IWKR lYR10M1 GRT.'f Mf *1? 515 t't]41' MARRRf) SIN 4 ART WElthf 11 4R T**1W1 EM 11/2%/81 M' VALVE 2-NC-95 VA!.VE nnM.1F.T !.KAtlM RENNED M9ET CASKET 2 1111%1103 1%1 11/2%/31 0 VALVAE 1Y-CC-2098 EKCESSIVE LAMACE 01. Tons!X'Tm AIID Riv'05KFtTw YAf vh 2 1112 51r.s"9 1%

tt/2F/81 Si FALFE 2-51-6 AOIPT TO 80#.1ET LE M COfPLETp 2 In t%11?'t 1%?2 11/16/31 IT' VALVE 2-T-Et 2-N-t t LEARS nr PRF.YERTEM CLEMM VALVE norr Mf) 994.9FT 2 111111111 111

, 0 '

1n/2R/81 Si VA'.VE 2-31-9 VALVE allL% Nt!T Of'AR C0%rl/TMD 2 19 *91n t s.' %nt 11/2F/91 N VA'.VK 2 =.W-208 1-lN-20e' RM CROSS PN'E!M (JAK REPACE VALVE 2 1911n t We  ??e 11/3n/st WE 1)ltSA L EK-EC-2 IfRFtJRW IWF.YFMTIVE atAINT. ConrLETE 2 nos:11nc.n no 0 11/30/nt 55 R2 2-RS-E-1D CLEM RK Cl/Mm MRE

• 2 110:n t ' 't 1 tt/30/nt Es  !!% 2-RS-E-tC CLEM NK CLEMED M NZ  ? 1102*'1*'?: t r, 11/30/n1 K5 IIK 2-RS-E-tB CLEM RE Cl2ANm M RE  ? 11a?11 an t v.

0 11/30/81 RS 2-RS-E-1A CLEM NR C!EMED M llK

• RK 2 Stn:11nn. 1 ts 11/.10/81 MS VALVE 2-MS-Sn VALVE nFEM OVENAtillM CO Wl/TED 2 191111111 1 I lEIT f2TAL

• 15911 O

• w W

C '

4 *

• 0

. , 34 l

I 1

1 1

Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 Electrical Maintenance O

--- - -- , , q -- - -

S j

Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 ELECTRICAL MAINTENANCE NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD. .

i

)

O

,. ,- ,_ v-+--,r--,-, -

, ,--.,e,, ,,,,r-

1 i

_ Maintenance of Safety

_Outane or Reduced Powe _

UNIT 02 Electrical Maintenance _

l l

I i

+

I I

l I

i

.- _ _ . .~ . .- --- - - , _ . . _ , , ._ , ,- _ - . . _ - . _ . - _ _ , _ , - , - - - - - + - - - . -

DWrs9 t*Y IIMIT2 *

(atA!RTERANCE OF SAH.TT RE*,ATFD STSTEMS 11t1R14C OttTME OR RHwrED IWER PFRIO!nl RAT:2 kV!77 SVT CC"P NARENU SU441RT VKITW U n'.i i+M tr* '

11/08/n1 %E flEATER  !.Gl UIRE Cl!. TE4P

• 11/09/81 W at0V FGIMD TEMP Witt'R NORLE41.15T 13'M 2 t t tnano.~1  %

NOV .W-20%A V0U!.D ROT CU1SM TOR PT 8.5A N019inBl}?t CTCLED SAT 2 819nanyn

• 11/10/81 EE BSEMER 25M% PMS EM 1

NRFOMED NS OR BREAKER 2%II% SAT 1 innynnn11 e 11/11/n1 *E MK!:MkW 2%R2 NS 1 N

• PERF0MED INS 00 2W3 21EMER SAT 1 toq1ntn11 1 11l11/31 %F MRMVR 2%Ils IMS 1 W 11/11/n1 NRFORWED NS OR BREMFR 2%35 SAT 2 1 )nte snym 3 *

'. E MREMkR 2W1 EM S W PERTOMED NS OM 241 BREMtR SAT 11/11/91 W MOV W 206A 1 in92ntG15 1

• INF N-E/C1 M-NOV-E/At + C1 PERFOMED EntS DE MV-W-20GA SAT 2 1n9twn$ n 1 11/11/81 SV NOV W-20sn l'4r N-E/C1 W-MOV-E/At

• C2 PEWOMED NS 04 N0t'-N-20sR SAT

• 2 19An%n%11 2 11/11/81 SE MOV 40V-2RG98 WOULD M0T OrlR ICR PT in.2 WO EW0Bil)t 11/11/91 V'I 2 111080nnn 1 Url' ENDER K11 RITLK E IWORNETT REPEXED Nitt91 2

' 11111n119 11 11/1%/81 RE BREMER 2 51% INS SM 11/1n/81 VS MOV WRFORWED INS 00 BREAKER 2M% SAT 2 inn 2009%2 2 VS-20%A NP VS-E/C1 VS-NOV-E/At

• C2 NRf0R4ED NS 06 MV-VS-20%A SAT 2 1090' sos 2n 1 11/1%/et VS NOV VS-20%R ENP VS~E/Ct VS-NOV-E/A1 + C2 PEWOMED NS OM NOV-VS-010%8 SAT

' 2 LO9*%n571 1 11/15/nt YS NOV VS-200M INP VS-K/C1 VS-NOV-E/A1 + C2 NRF0bVtED NS 0E MV-VS-200R SAT

• 2 1090nn%1% 7 11/15/91 VS NOV VS-2000 INP VS-E/C1 VS-MOV-E/A1 + C2 PERF0MED NS of ADV-VS-2000 2 1090%0511 7 11/1%/31 VS NOV VS-201 NP VS-E/C1 VS-NOV-E/A1 + C2 0 PERF0MED NS 00 NOV-VS-20t 2 1999n05t1 1 11/15/81 VS ar0V V&?nt INF VS-E/C1 VS-MOV-E/At + C2 PERf0MED INS On MV-VS-2n2 SAT 2 in90n0%19 1

• 1'/15/A1 M PtMP 7-RW-P-1M UPNR NOTOR REAt!NG RISM TMP 1St M/At RE REPLACED WPER MMIECS 2 11 t l% 1Vn 20 RREM RR 25M1 NSSW PERFORWED NS DE BWMER 2541 SAT 2 108200910 2 e t1/1 In1 D4 VJW. 2Y-DA-2003 Cl.5 l.I'lli M.1t'llES 11/11/nt  !.h M.ini;R 25NT INS 1G OPERATRO VALVE OFERATO SAT EERf0RWED IMS 06 MREMN 25M9 SAT 2 tong 51720 2 10n280911 S c~M 3

Y' '

11/11/et *h BREMER 25M11 INS SG

• 11/11/81 %E MRE4KER 2%I9 PNS SM PERF0MED INS 00 BREAEER 25M11 SAT 2 10n2en919 3 1 t/11/81 EE BREMI;R 2%I11 PEMOMED E9tS 06 BMMKR 2549 SAT 2 LOS2n09%s 5

• ENS S G PEMOMKD NS 00 BREMER 25/11 SAT 2 1082909%9 5 11/18/11 EE BREMER 2%N% l'tS 1G

• 1t/In/81 CS MOV PERF0MED INS 00 BM 2%M% SAT 2 toe 191033 2n CS-203A INP CS-E/R1 CS-Nov-E/R2

• R3 PEWOMED INS 00 MV-CS-203A SAT 2 1990%0521 3

• tt/In/81 rs at0V CS-203R INP CS-M/Rt CS-NOV-E/R2 + R3 PEWOMED IMS 00 NOV-CS-2038 SAT 2 1090%n%23 3 11/1n/11 CS tt0V CS-203C INF CS-E/Rt CS-40Y-E/R2 + R3

• PElvMED NS DE n0V-CS-20Y SAT 2 1090n057% 3 11/1n/st CS NOV CS-203D NP CS-E/Rt rS-MOV-E/R2 + R3

\t/te/81 C4 1%WOMED NS DE NOV-CS-203D SAT 2 109n%n575 3 8 MOV CN 2289A INS NWOMED NS 0E NOV-CR-22n9A SAT 2 198311106 3 11/19/81 C4 NOV CR 22n9R NS 0 11/19/nt CR NOV NRFOMED Pts 06 M0V-CR-2289R SAT 2 108311701 2 CR 2310 UNS PERYOMED NS 00 NOV-CM-2310 SAT 2 1n8311209 2 6 St/ Inlet CW NOV CR 2313 EM PERFON4WD NS OW NOV-CR-2313 SAT 2 19831111n 1 11/19/81 CII NOV CR 2381 INS 4 11/19/81 NWOMMED NS OM NOV-CR-2381 SAT 2 108311111 2 W.' *t0V 2536 NS ItWOMED NS OR al0V-2536 SAT 2 in901n9ns t

• 11/14/81 VS NOV VS-2004 NP VS-E/C1 VS-at0V-E/At + C2 PERFOMKD INS DE MW-VS-2n0A SAT 2 innon0%t% 1 11/ t *9/81 VS NOV VS-200r INP VS-E/Ct VS-MOV-E/A1 + C2 PEWORWED INS OE MV-v5-2nnt' SAT 2 10nonn%1% 1 11/20/81 6E RREMER 2 5113 DNS 3G NWOMKD NS OM MR 15M3 SAT 2 tonynnn11  %

11/70/91 EE RKEMF R 25M1 INS 1G PERF0MED INS 06 MR 2%M1 SAT 2 10n?80n15  %

11/70/81 *E MREAKER 2%Nn EMS 1N PERF0bFtED N S OR M R 25Ne SAT 2 1012Rn93G  %

11/70/41 'E RREMER 2W1 EMS S W PERFORED INS OR RRK 2W1 SAT 2 1on?ntn30 2 11/70/91 s. E pggggy pq1 g gy$ g w pygropptED NS OM MM 2Wtt SAT 2 SG82ntn31 2 11/70/41 EE PREMER 2%I815 NS t w itNFOMED NS 06 PRK 2%M1% SAT 1 10n28tn1e 3 11/70/91 FE BMMER 2%il16 NS SM PERFDR%KD IMS CW NRK TW16 SAT 2 10n19tn'1 3 11/70/11 EE THMStHR 291-242 INS I M ME-TR-F/2R1 ETRFOMED NS OR RNR 1st-?N1 SAT 1 111111%R  %

11/2l/61 E. 9 MREAhER 2M3 P't3 1 W PESiggwfD INS OR BkN 1%93 SAT 2 inn?*nnnt 1 11/71/nt *W MREAI FR ?M1 EMS 1 W PERIORVEl' IMS ON MkK 2%,*I SAT 2 innpannst 7 in

PFI'Td *,*T llMIT7 _

(MA!1 TEM 49'E OF SAff.TT RELATED STSTFWS IMIR100 Ot!TAGE OR RTivM*FD IWER FFRl*WGS N *.Y :t h V'7? ST9 CMP 4Aht30 SMMRT VKrFRF U *PI 1"1tV2.4 11/71/81 (E BRFAKER 2%!n 19tS S G ltRF0MED INS OR BRV 2%91 SAT 2 2 nn11trt% 1 11/71/81 FE RRE 2%J15 N3 IN MCC-Cif-E/Rt NRFOMED NS 06 DKk 2aJ1% SAT 2 111 \n1e nn  ?

11/71/n1 AE TR1d%0R 2Jt-2J2 NS IN KE-TR-E/2R1 WRFOR4ED EMS 05 ZFMR 141-127 SAT 2 115 titrno n 11/71/11 RM WV WV-M-2 Loo Vitt. MOT OltHATE EtJTTRICA?.LT VALVE RFJ'AIGr0 2 11121181% n 0 11/71/81' 51 40Tt)W 2-SI-P-t a IMS SM NS CMPt.ETE 19 TART 2 108710131 %1 11/72/81~ %8 40NK 2-S!-P-tM NS1G FiS C Mrl.ETE 2 son 21nt3% 1 11/22/81 V BRFAKER 2%!!3 NS t w NRFCINED INS 0E MRR 2%Il1 SAT 2 inntn1n17 2 11/77/81 CI! NOV CN 22814 EMS NS CMPLETE 2 inM 3 t t 7n1 7*. 9 11/ 2/nt h!I VALVE NOV-2101 Dif EDR ROT !ESITCT DETMMUTeRFCORRECTm AFTER Wilt IES 2 111?111n% %I

• 11/77/81 r1 VALVE NOV-CH-2281A Dl%C11ND.T NOV-CH-2281A VALVAE RTTIIRMED W SERVit'E 2 11tn%1111 H.9 11/77/81 CC SOV TV-CC'-209AA RF'90VE LEAKS FRQ4 SOV-tv-CC-20%A plTOMMETFD+RWOW3bt.T4D M9til REPAER 2 111711Gn1 11 11/73/8I ES DIESEL isvNER ROT VOREl72 ERSTALLED RW !J1t!VER COWTNOL SAT 2 0010% ten 1 t *.~%

11/73/81 r4 VALVE NCV-2200C VALVE Vill. NOT STR0tr VALVE STROKES SAT 2 inn 2r.nn nn e117

• 11/73/81 FK RREAKKR 2%H8 NS t w PERFORMED NS ON BRM 2%Me S4T 2 1382ntn1R  %

t1/23/91 C4 NOV C# 2261A NS MRFORwED IMS 01.WV-CR-2261A SAT  ? 10nitnot; 1 11/23/et (4 FCV CR 42154 NS itRF0MED IMS 02.WV-CR-2215A SAT 2 sne 3 inn t'. 2 A

• 11/73/81 r4 NOV CH 2286A NS TERFORwr0 1995 06 NOV-CR-22n6A SAT 2 108311100 1 1Lf73/81 C4 NOV LCV 21158 EMS PERFOMED NS OR l/T-titSS SAT 2 108311112 2 FERNMED NS of ICV-2ttSD SAT '

11/73/nt C4 NOV I/V 2115D INS 2 10431121%  %

11/73/81 kW MOV RH 1101 745 CLEA!!m GWRED CME.*CTCLED SAT Of'E 2 109010111 21 ccp 11/23/81 W NOV W 20%R IMP N-E/C1 SV-NOV-E/At

• C2 NWOMED NS 0W NOV-N-20%R SAT 2 1n40%0505 2t%

11/73/et M MOV 5 -20%C INP % -E/Ct M -NOV-E/At

• C2 PEMOR4ED NS OR WV-N-10%c SAT 2 in3nW.or. 2tse

1. 1t/73/81 W NOV W-205A NP 5-E/C1 M-NOV-E/At

• C2 ItRFOMED IMS OR NOV-W-tosA SAT 2 toon w.no n t1/73/81 SV 40V W-2054 INP W-E/C1 SV-MOV-E/A1

• C2 NFOMED INS Of NOV-N-2058 ,2 1n'9010509 R tt/73/et EE CFMERATO 00-2 PMS EM 1%RFORvtD P45 06 EfC 2 SAT 2 1107011%9 19

• 11/23/81 SV MOV MOV-SV-20%8 D170MMELT*RW0038YT EDR NE01 DEK00RSCTED*RWORW8CTED M-20%B 2 tt10%17nn 1%%

11/73/81 M NOV .WV-M-20%C DETOMMET*RWOWNET DUR NECM DIK00 RECT @*RWORRETED %-20%C '2 1110%12n9 2C%

11/7%/31 W NOV W 20%A PvP M-E/CS M-MOV-E/At + C2 NRF0MED INS 00 anW-M-10%A S4T 2 1090%n50% 2n%

11/2%/St SV At0V & 20* NP S-E/CE M-MOV-E/At

• C2 PERFORtED ENS OR NOV-N-2n%D SAT 2 innn%D5ni tra t1/7%/81 W MOV SV~~- INP N E/C1 M -at0V-E/At + C2 NRFOR4ED NS OW MOV-N-105C SAT 2 SMo%n$to 17 11/7%/8t W .WV N 20% IWP 5 -E/C1 M -NOV-E/At + C2 NMORMED INS 00 NOV-%-20%D SAT 2 2non%0%11 13

• M DET

• RWOM ECR NTH 1114%12n1 2%

11/7%!8i 40V Mos 0%A DE TOMhWT80 AMD REC 0WN6f7KD sat 2 11/7%/qt W NOV NOV-SV-2n%D DIT

• RWM FOW ND'M DEMONRWTED AND REF'ONMMTm W 2n%D 2 1110%1110 7'n 11/7%/et CS NOV CS-2014 P4S EWRFOMED intS AS FER twtrEtutRE 2 ton 1tnnom 7

• NS PERF0m.tD INS 06 MOV-CM-1269A 2 inesson11 1 11/2%/At C4 NOV CR 2269A 11/7%/11 CM MOV CH 116%8 19t3 PERFORwED CES 00\ NOV-CH-2269M SAT 2 ton 11nat3 2

, 11/7%/n1 * 'l . N01 CN 1210A NS PERF0MED NS DE N0Y-CM-2210A S4T 2 10n11ont% 1

\' 11/25/81 C4 WV CR 2210B NS NWCMED INS 00 $mV-CR-2250R Set 2 10n31941% n 11/75/81 CW MOV 1215R INS TERFOR4ED ENS 04 MOV-CR-2315N SAT 2 10eston11 1 11/7%/e1 ry MOV r;I 2215C is'S I?JtFCMD NS CR WV-C#-2215c SAT 2 ine11nete 1 6 11/7%/nt r4 'M PV Q 27G1R IMS FFRFOMED NS 06.WY-Cll-21G1R SAT 1 ln s1nn7a 1 11/7%/qt rS MOV CS-2n1R INS COWFLTm AS 1%R INS PR(Y!TMIRF 2 in' 19 t'n 2% 2 11/2b/nt C4 NOV CH 2?n6M NS PERNk1tED IMS OR NOV-CN-?7nsn SAT 2 1nn111101 1 CII 22nt/' NS ETRFanFtED lits of NOV-rM-77nro' SAT 1 11/15/91 C4 NOV 2 inn 3111t')

11/75/81 rol Mt1V CN 22n1C l't3 PERFORwfD latS DR lt1Y-rN-??nir SAT 2 1on11110% 5%

11/70/st 44 MOV M-21on (WS NS etNP!JTK 2 10901n186 E 11/71/nt R4 VA!.VE .W V-R?t-2100 l'l9' e RWOM WR M.*141 Mn1nR in MT RFV!N m 03 4R 71117tt11 7 1117%t>'1s %1 ep O

[ I

, s e e a o o o o o o o e . . . -

g i t

', , ' , t ,

y """"-l5 E

a !5 E $#{

cf $

sex::

g..

22 m nenne 5

~

g s

E 5

ag*

R 4 8 .:

E =  :

E 2 atw888Q:k Ek Ek E

- es E k'eagEl k*o

= 2 ggh$h 4 1 =622t I

a N

B ,

LS k

~g B

~t a.

h a R- -

A 5N

$ 5 6IEEE 5

E

= .as

?

• g g:::

o ns t!

I 4 5$$

e. c.

! RElla E utee .

4 S

l =:::a::aa h-6 g

b,.

33333 bo

- . .- -  ?  ? - - - -

. . . 40 Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 Instrument Maintenance a

e o

e 9

9_ _ _ _ __ . -

. , , Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 INSTRUMENT MAINTENANCE NOVEMBER, 1981 NONE DURING TH15 REPORTING PERIOD.

e

. . , , -. r..

Maintenance of Safety Related Systems Durina Outaae or Reduced Power Periods UNIT #2 Instrument Maintenance l

I I

i

e *\ HEALTH PHYSICS

, u ,

NOVEMBER, 1981 There was no single release of radioactivity or radiation exposure specifically assolcated with an outage that accounted for more than 10%

of the allowable annual values in 10CFR20.

l

)

6 r -r- , ,- .w, - - ,.--- - - - --a -, - - . - - , . - , - - - , ,m ,--s- , - ---- ---- - --

, , , PROCEDURE DEVIATIONS REVIE7ED BY STATION NUCLEAR SAFETY AND OPERATING Cod 2!ITTEE AFTER TI!!E LD!ITS SPECIFIED IN TECENICAL SPECIFICATIONS NOVEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

I l .

b =

e

• e .

l*EITalRST

• UNIT 2 (MAIRTERANLT OF SAFLTT REL4Tw SISTDtS DURIM OtfTAGE OR RETMXEO IWER NR1016)

WTT J KVW STS C04P NARRRO SIM4 ART VRlYRF U WW fnTtv3N '

• 11/11/81 RE WlXR EDG-2 TDiP NEXR FOR (JIBE Oil CART FIED ART PROBfDt 2 111041019 3%

1t/13/81 KC TDer !*T TI-% 63 METER 1901 CATES LOV 0FF RN RWRECRM M Pn0012M F0000 2 109092352 011 tt/1k/81 R4 Ins INSERT RET W LLE M RU4K & INSERT 60 MFMLinG RIMM.15 2 111130s52  %

11/23/81 SI 11STR FT-2%3 METER RE@S CAllRR4TIOR CAllRRATKD TRANSW11TTR 2 111n8012n 312 31/23/81 SE INSTR Fl 2962 REPLVE TRMSW11TER RWLKED 24TER 2 111101100  %

• 11/23/81 SE IRSTR F1-2%1 EEPLKE TRANS411TER KFJ'L K ED 34TR 2 1912nt 1nt K%

11/21/81 N W 11CR PS-N -10%/105 M11C!l WILL MT AUTO START \-<RTPLKED IRESSURE %!1CR 2 111221n%%  %*

8 '

UNET TOTAL 5%E%

8 .

O 4 e a

8 2' Las e

9 e e

e

• e e

9 W , #