ML19341A453

Monthly Operating Rept for Dec 1980

ML19341A453
Person / Time
Site:	Oyster Creek
Issue date:	01/14/1981
From:	Sklar J JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19341A452	List: ML19341A451 ML19341A453
References
NUDOCS 8101230548
Download: ML19341A453 (9)

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OPERATIC 23S St2fGRY l

DameER 1980 At the _arinn47 h of the ut.w. Ling period, t6e Oyster Creek Nuclear Generating Statien was rem 45 to power M11e5r4M repairs to the Feedwater Systen. Icad j was maintained at approximately 99% rapac4ty (643 We) through r*--he 12 until limited by cx:ndensata d=4nar=14 er differential pressure. 'Ita ultimate cause of the differential pressure limitation was the irab4if ty of the New Radwaste l Systen to m-:a== liquid and solid waste as designed.

l narw+ar 12, load was rMv ad approximately 250 se to rerove "C" Feedwater Cn l Beater String frcm service for =4*anance on the IC3 heater relief valve. "C" string was back in service after 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and load was ircreased to condersate d=4nar=14'ar differential pressure limits at 637 We on racamhal 14. "A" CRD nar=ahar puup was out of service for electrical and --han4e=1 ~4n+ananca frem 18 thi=+ n=--har 24. Frcun narwhar 19 through the end of the reporting period, load was steadily A - 4M due to emdensata d=4naralirer differential pressure limitations. Cn naramhan 31, the SCRAM Dung volune Continucus w:nitoring Systen Funcrienal Testing as directed by I E Bulletin 81-17 Sqplanent 4 was satisfactorily c:smpletai. C:: replete evaluation of the test results is not fully er mluded.

ters were 9 Reportable Cccurrences and 1 Ncn-Routine Divi. mtal Cperatig Report idenei#4ad durW C+:uaz:

R.O. 480-55 was 4 dan +4'4ed en nar=haz 3 when Core Spray High Drywell Pressum SwiP+en RV46B, C, and D were fcund to have settims less ccnservative than Tae-kn4 r=1 S W #4r= tion requirements.

R.O. 980-56 was 4 dan *4 4'4 ed en naewnbar 4 when Steam Line High Flow Sensors RE22 C and G were found to have setti:x;s less consrrvative tPan Tech Spec requirements.

R.O. 480-57 was iden+4 *4 ed cn C+:2-r 5 when Coe=4nmant Spray High Drywell Pressure Sensors 1P15A,-B, C and D were found to have settims less conservative than Tech Spec requirements.

R.O.980-58 was identified en nar==hal 11 when 2 annkham en Core Spray  !

piping were found to be izrpar=hle. l R.O. 480-59 occurred en n==+=n- 15 when monthly tests on the Diesel Generator, Staticn and Fire niaaal Batteries were not p=a.h.=1.

R.O. 480-60 was 4da*4 84 ed on C+:2 -l 11 when Isolaticri Condenser candannate Retz:rn Line Break Sensor was found to have a setting less conservative than Tech Spec requia. Li.

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- R.O. 480-61 was iden*4 #4 ari on December 12 when Core Spray %Eha_rs 19/11, 19/12 and 19/13 failed functional testing in u urassion.

4 1 R.O. 480-62 occurred on Decenber 18 when "A" CRD Pung was irx:perable.

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R.O. 480-63 was 4da*4 *4ad on Decenber 17 when Reactor Triple Icw Water  !

Imvel Sensor RE18A was found to have a setting less conservative than Tech Spec requirenents.

NRECR 980-13 ocentred on C+:2 +r 6 when 2 Diluticn Puaps were shut off due to ext:snely 1cw water level in the intake canal.

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- AVERAGE DAILY POWER LEVEL -

DOCKET ?...... 50-219

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UNIT.......... O.C. ti REPORT DATE... January 14. 1981 COMPILED BY... J.B. SKLAR TELEPHONE..... 609-693-6013 MONTH December 1980 DAY MW DAY MW

1. 441.- 17. 60' 8.

2. 479. 18. 605.

3.- 589. 19. 601.

4. 614. '20. 597.

5. 634. 21. 594.

6. 422. 22. 588.

7. 618. 23. 588.

8. 423. 24. 583.

9. 623.. 25. 583. '

10. 620. 26. 580.

11. 618. 27. 581.

12. 595. 28. 578.

13. 448. 29. 576.

14. 585. 30. 576.

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i i 15. 605. 31. 574.

16. 605.

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, , OPERATING DATA REPORT u

'o m rP D "D M' I OPERATING STATUS M J a UNIT NAME.. 0YSTER CREEV DOCKET NUMBER.. 50-219 UTILITY DATA PREPARED BY...J.B. SKLAR 609-o?3-6013 REPORTING PERIOD... Decernber 1980-I' LICENSED THERMAL POWER (MWT).. 1930 NAMEPLATE RATING (GROSS MWE).. 650 "

DESIGN ELECTRICAL RATING (NET MWE).. 650

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MAXIMUM DEPENDABLE CAPACITY (GROSS MWE).. 650 MAXIMUN DEPENDABLE CAPACITY (NET MWE).. 620 .

!F CHANGES OCCUR IN CAPACITY RATING SINCE LAST REPORT. GIVE REASON...

NONE POWER LEVEL TO WH.ICH RESTRICTED, IF ANY(NET MWE)... 650' REASON FOR RESTRICTION, IF ANY... -

CONDENSA~E DEMINERALIZER DIFFERENTIAL PRESSURE MONTi4 YEAR CUMULATIVE i

HOURS IN PERIOD 744.0 8784.0 96648.0

{* HOURS RX CRITICAL 744.0 3791.3 72430.6

.s j RX RESERVE SHUTDOWN HRS. 0.0 0.0 468.2 HRS. GEN ON LINE '744.0 3663.5 70Y68.?

UT RESERVE SHUTDCb:N HRI 0.0 0.0 0.0 GROSS T.HERMAL ENERGY 1325000.0 6267321.2 120146480.5 GROSS ELEC ENERGY 451970.0 2045930.0 40929245.0 NET ELEC ENERGY 435087.0 1957645.0 39438658.0

{ UT SERVICE FACTOR 100.0 41 .7 73.4 i

i UT AVAILABILITY FACTOR 100.0 4.1. 7 73.4 I

UT CAPACITY FACTOR MDC .94.3 35.9 67.3 l UT CAPACITY FACTOR DER 90.0 34.3 62.S i

FORCED OUTAGE FACTOR 0.0 10.0 6.6

, THE NEXT SCHEDULED OUTAGE IS TO BEGIN ON SPRING 1981.

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DOCKET No.

50-219 '!

UNIT SilU1 DOWNS AND POWER REDUC 110NS UNIT NAME O.C. Il  !

DATE .Im - rv 14. 1981 l' t

COMPLETED gy J. B. Sklar REroRTMONT1g Decaser 1980 TEl,ErfIONE 609-693-6013 i

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-- E- * '" U Licensee Et 4 Cause & Correct'Ive No. D,etc F

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}M jge Event Repint

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, Action to.

Prevent Recurrence ,

8 12-2-80 F 0.0 B 5 N/A ZZ ZZZZZ Reduction to investigate Condensate Syston vibration. Cause was attributed to problems with the Hot-well Sucker / tamper Station corrected +

by adjustments to the station.

9 12-12-80 F 0.0 D 5 N/A ZZ ZZZZZ Heplaced IC3 Ileater Helief Valve in the "C" Feedwater llenter String.

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.I I 2 3 4 F: Finced Reasim: Methat: Exhibit G Instructhms 5: ScheduleJ A-Equipment Failure (Explain) 1-Manual for riepsestitm of Deta , j B-Maintenance of Test 2-Manual Scram. Entry $heet Ioe 1.icensee 4 c.RcIncling 3 Automatic Sessm. Event RepmI(tER) File

• INUREG-D-Regulatoey Restricthm 4 Other (Explain) 0161)

E4)perator Tsaining & IJcense Examinathm F Administrative $

G4)perational Error (Emplain) Exhibit I - Seine Source 19/77) Il-Other (Emplain) j I

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DECEM3ER SLMMIN OF OASL PECimHICAL PRINID4ANCE r I Cuivasesit or Systm Malfunction Corrective Action _ .

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CRD Systen 'D' CRD Filter is fouled. Replaced filter elment.  ;

CRD Systm 'A' CHD filter is fouled. Replaced filter elenent.

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CRD Systen Icak through scram outlet valve (V-127) Replaced gaskets and seat rings.

for acusm11ator 34-31.

Valves V-15-25 & V-15-26 leak.' Replace packing.

CRD Systen CRD Systen 'A' CRD filter is fouled. Replace filter elenent. 1 CIO Systen CHD filter 'B' is fouled. Also valve Changed filter elenent and j V-15-26 leaks. tightened packing gland on  ;

the valve. 4 i

CRD Systen valve V-111 associated with accumulator Replaced the valve with a new i 22-03 leaks. valve.  ;

CRD Systen CFD Filter 'A' is fouled.

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- Replaced filter elenent. 4 i

valve V-111 associated with acctmulator Replaced the valve with a new  :

CRD Systen valve.

34-27 leaks. ,

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'A' CHD ptmp bound aid notor overleated. Replaced tie ptmp rotating elenent, CRD Systen bearings, and seals.

CRD Systen Acctmulator 14-35, V-111 valve leaks Replaced with a rebuilt valve.

past seat. '

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DECDHR SLMWN OF ONIL EIECTRIGL MMNIENANCE ,

l Equipnent M11 function Corrective Action '

'1brus Oxygen Sanple Ptmp Not ptmping }

Deplaced vanes in punp. .

. Main Steam Drain Valve V-1-lli Breaker tripping Heplaced btrken torque switdt ~

Mechanical maintenance required on valve'medustism. !

x Isolation Condenser Vent Switch Icose set screw on switch Tightened set screw.

V-14-5 and V-14-20 (10F) harxile.  ;

CRD Pupp Motor A Shortal out Ikplaced notor.

Condensate Transfer Ptmp fl No off indication (green Repairal loose wire on rear of panel 5F. '

light) on panel SF. '

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i DECEMER SLMMIN OF OASL INSTRLMNT N. ,

l Equipnent Malfunction Corrective Action ],

CRD 34-31 Ibsition 00 shows no green- After trouble shooting and stroking green badtground indication was satisfpcbory.

L CRD 02-27 tb position Indication teaky scran valve discxyvered resulting in the disconnaction of accunulator - job

'crder issued to medi. maint. Indication , I is correct at 00 and green-green. ,

i Reactor Protection Syston - Check for leaks at tubing dianged defectiv hittingsandpressure IE 23 Switches fittings decked at 1000 psi.  ;

Area Radiation Monitor - Reactor Building Erroneous reading Ibadjusted zero offset per tedmical manual. l l

Equipnent Drain Tank Ibczn M N - Cleanup Punp Area Doesn't alarm at desired Readjusted alann per standing orders and } ,

setpoint and no r6r.ase to replaced high alann light bulb indicator.

a high alarm trip check. 1 6

CRD Iow Air Pressure Switch Setpoint change per HIC Reset switdt to trip at 55 psi ca decreasirg l l; pressure. i Drywell/1brus Oxygen Recorder Inoperative . Retightened pointer on recorder string. l I

Standby Gas Treatment Syston II Filter differential

• pressure Replaced 1-10, 11, 12 AP gages with i indicators defective. 0-5" magnehelle gages. l

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Isolation Condensers Temperature Alarm Intermittent alarm Jtmpered alarm per procedure 108. l Shutdown Cooling Trip Alann Alarming for no reason Cleaned dirty contacts on annunciator board. .

Fuel Ibol Invel Alarm Intermittent alarm Recallbrated instrunstation per nenufacturer's bulletin.

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DECENER StMRIN OF OFGL INSTRMNr MMNIDmHCE - Page 2 ,

! Iljulpnent Malfunction Corrective Action IIM Channel 15 Intermittent failures Itplaced cxxinector under vessel ,

upscale. -

APIN Channel 7 Power Supply Defective Itplaced and performed surveillance.

i Aucynented Off Gas Instrumesit Alarming Itplaced alarm asseibly and adjusted i Failure Alarm power stqply. ,

AOG Radiation Monitor IIL III trip point out of Calibrated monitor, i calibration. ,

AIM - Reactor Building Equipnent Trip point out of -

Calibrated monitor. .

Drain Tank Rocm calibration l '

l Off Gas Line Flow Recorder Not driving properly Tightened slide wire, repaired pen  !

mechanima, calibrated. j i

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, mm 9 T' Oyster Creek Station #1 '

, ww e SL C Occket No. 50-219 RE UE!. LNG INFORMATION -

Name of .:acility: Cyster Creek Station #1 Scheduled date for next refueling shutdown: N m L+r 28, 1981 Scheduled date for restart follcwing refueling: May 31, 1982 Will refueling or resumption of operation thereafter require a Technical Specification change or other . license amendment?

No Tach"4"al Spae4 44ca*4mn change relative to the rafnal4g is an*4e4natad.

Scheduled date(s) for sucmit. ting procosed licensing action and supporting in fo rmation:

No sut:r.d.ttals are sc.Miad.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

1) FM Electric fuel adlies - fuel Mir71 & gm.Em- analysis methods have been e v d by the NIC. New operating yu - a res, if necessary, will be subnitted at a later date.

2) Exxon Fuel Assemblies - No major changes have been made nor are there any an*4e4n=ted.

The number of fuel assembiles (a) in the core -

560 (b) in the spent fuel storage pool - 781 I

The present licensed spent fuel pool storage capacity and the size of any Increase. in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

• Present: 1,800 Planned: 2,600 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

The Spring 1987 Outage.

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