ML20104A532

Forwards Monthly Operating Rept for Feb 1979

ML20104A532
Person / Time
Site:	Oyster Creek
Issue date:	03/15/1979
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7903260216
Download: ML20104A532 (1)

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.gz Jersey Central Power & Ught Compar

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Ma$ son Aver.ue at Punen Bows Road

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March 15. 1979 Mr. Boyce H. Grier, Director Office of Inspection and Erforcement Region i United States Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pennsylvania 19406 f

Subject:

Oyster Creek Station t Docket No. 50-219 l Monthly Operatino Data Enclosed are ten copies of the monthly operating data (Gray Rook l

l Information) regarding our Oyster Creek Nuclear Generating Station.

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Very truly yours, N

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Donald A. Ross, Manager l

Generating Stations-Nuclear 1-C5 Enclosures l

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Mr. William G. Mcdonald, Director (2 copies)

Office of Management Information and Program Control United States Nuclear Regulatory Comission Washington, DC 20555 Director of Regulatory Operat ions (1 copy)

United States Nuclear Regulatory Comission Washington, DC 20555 l

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OPERAT1r'b STi.Tur UrJ11. Hi. rte...O f 01 EP C RFEF DOCf O rJUtil:FP.. 50-21 O UTILJTY DAT A PREr'r. rep It Y... C. ri. hCC L.il r2 2 i s

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50-219 tfNil sitt!IDOWNS AND PowlR REDUCTIONS DOCKET NO.

UNIT NAME Oyster Creek #1 pggg % rch 12, 1979 COMP!III'I) HY C. M. McClain Ril'ORI MONill February 1979

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3 elA CH RELAYX "C" feedwater pump t ripped when the breaker cubicle door was closed, shaking the "C" differential relay.

The scram occurred from a low water 4-level af ter the purnp t rip.

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Oyster Creek Station #1 nocket No. 50-219 OPI'RATIC'S S'.3E~-O' - FEmi 1979

%e unit was opersting at full load at the boginning of this report period.

On February 6,1979, "C" feed ater pt: p trip;ed k5e. the breaker cubicle door was closed, shaking the "C" differential relay. A reactor scram cccurred at 11:15 a.m. frcm Icv water level following the fwdeater p.rp trip. All systes functiencd nonrally. D e unit was return u to service at 3:41 a.m. on February 7.

On February 9, power level was reduced frco rated load to approxir.stely 351 when condenser vacuum rapidly decreased. Steam jet air ejector IC1 was shutdown and IC2 was started. Ioad was ircreased to rated.

On February 13, power was reduced to appr:xi::utely 65% to insert control rod 34-

'39 and replace a leaking scram pilot solenoid valve. Power was increased to rated follcwing withirawal of rod 34-39.

'No (2) re;ortable occurrences were identified during the ren@:

m 79-2 cccurred on February 6 when ene (1) reacter high pressure saitch for, isolation condenser initiation tripped abcVe tr.e allcwable setpoint curing routine i

surveillance test m 79-3 ccc-arred en February 26, 1979 when the dry. ell to torus differential O

V prenst.re drcpped Irlow the technical specificaticn li.it for 10 minutes during a i

reactor building closed cooling water tgrature t.rarsient.

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h Docket No. 50-219 CO!GJrrIVE INSTIEMl?Tr "AltinNANCE W OASL ITI G IVR 'IllE FOT1110F FEBRUARY 1979 Itcsu il DIullrent P.ilfunction Corrective Action 1

APlot Ch. 6 t'pocale spiking causing half-Dypsssctl 12-41B in APIN ser.res drawer aryl aux, drawer 2

CIO 34-39 rcrari solenoid air Icak Ik!;uilt scram pilot valves with acw pirts and testcd-3 APlot 01. 4 Ital bicck frun faulty diode Implace.1 dicde ard conlucted APIo1 surveillance test & cal.

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!;101 l'rt.nt Panel ICit neter out of s}tc Mjuntnl trip rtxlulo and retud !C any for 10-1 on zero psition 5

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lu:f re twp Al' t rann Icaking water at IC3 Tightenal tucking on root vol',

6 Core : pray :yn I Alaenn did not flash Peplaced "B" acktruledge butti 7

Als; l'rient Patiel l'otential fataty livlicationn Mjustal 7ero ard set alann on recorder aid checked rccite. valves e

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CO!UULTIVE 111L'I'!CCAI. M\\ltmnt'EE Of G\\SL ITIMS IVR ' HIE 10m1 OF RIHUNU 1979 Iten #

11]ui stent K21 function Corrective Action t

1 Service Water Puny #1 13reaker trip unable to reclose Changul undcivoltage coil and perfontr.1 PM on breaker l

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.Dockst No. 50-219 colstrrIVE PJrim1CA1. Fntm1:WCE of Out, ITIFS IVR ' DIE FOml OF FmMmRY 1979

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1' 12;ui inent Fblfunctioi corrective tction Iton 5 l

1 CRD 46-27 IKT Nipple on fill connection R3noved connector T. retapped Icaking arourtl threals c

2 Core Spray Systen V-20-41 leaking tdjusted packi:yy to stop leakage 3

Condensate Transfer' V-11-41 leaking Tightened tranne 'alts as necessary Isolation to Isol. Cond.

to stop leak

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4 Fire Protection Systan Packing leak on the pond pwp '

Repacked the pmp as ncessary at the fire inp house to stop leak 5.

CRD accunulator '14-11 V-Ill valve tralfunction Replaced valve bonnet with a rebuilt spare 6

1-1 RIYXW lu'p Te ak frun inlyurd seal Replaced seals

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Oyster Creek Station #1 Docket Nc. 50-219 REFUELING INFORMATION - FEBRUARY 1979 Name of facility: Dyster Creek Station #1 Scheduled date for next refueling shutdown: Septender 15, 1979 Scheduled date for restart following refueling: November 10, 1979 Will refueling or resamption of operation thereaf ter require a Technical Specification change or other license amendnent?

i No Technical Specification change relative to the re#ueling is lg anticipated.

Scheduled date(s) fo.r submitting proposed licensing action and supporting information:

1.

July 1979 - Cycle Irdependent General Electric fuel design information and safety analysis for future use.

2.

No submittal is scheduled for the use of Exxon fuel.

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

1.

General Electric Fuel Assemblies - Fuel design and perfornance analysis methods have been acproved by NRC.

New operating ll procedures, if necessary, 4'11 be submitted at a later date.

I 2.

Exxon Fuel Assemblies - No major changes nave been made, nor are r

I there any ant cipated.

i The number of fuel assemblies,a) in the core

- 560 (b) in the spent fuel storage pool - 620 The present licensed spent feel 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:

1,500 The projected date of the last refueling that can be discharged to the spent fuel pool assu.ning the present licensed capacity:

The Fall 1986 Outage.

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