ML19341A453

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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:
References
NUDOCS 8101230548
Download: ML19341A453 (9)
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OPERATIC 23S St2fGRY l

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DameER 1980

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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

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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

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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

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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

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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

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Retz:rn Line Break Sensor was found to have a setting less conservative

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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 -

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DOCKET ?...... 50-219

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UNIT.......... O.C. ti REPORT DATE... January 14. 1981

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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.

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4. 614. '20. 597.
5. 634. 21. 594.
6. 422. 22. 588.
7. 618. 23. 588.
8. 423. 24. 583.
9. 623.. 25. 583. '

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10. 620. 26. 580.
11. 618. 27. 581.
12. 595. 28. 578.

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13. 448. 29. 576.

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14. 585. 30. 576.

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i i 15. 605. 31. 574.

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16. 605.

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, , OPERATING DATA REPORT

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'o m rP D "D M' I OPERATING STATUS M J a

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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

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NAMEPLATE RATING (GROSS MWE).. 650 "

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DESIGN ELECTRICAL RATING (NET MWE).. 650

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

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

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

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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

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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 '!

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

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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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Prevent Recurrence ,

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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.

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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

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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.

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  • CRD Systen Acctmulator 14-35, V-111 valve leaks

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Replaced with a rebuilt valve.

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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 ~

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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.

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

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light) on panel SF. '

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i DECEMER SLMMIN OF OASL INSTRLMNT N. ,

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Equipnent Malfunction Corrective Action ],

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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. ,

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

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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.

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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

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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

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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 ,

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  • 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. ,

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

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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.

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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

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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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