ML19345H254

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RO 81-001:on 810415 & 16,two Dilution Pumps Tripped & Reserve Pump Would Not Start.Caused by Component Failure. Flow Switch Jumpered After First Event,Lube Oil Cooler Switch Reset After Second
ML19345H254
Person / Time
Site: Oyster Creek
Issue date: 04/27/1981
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-50-219-81-1, NUDOCS 8105010410
Download: ML19345H254 (4)


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OYSTER CREEK NUCLEAR GENERATING STATION g u gf g 5j yj (609) 693-1951 P.O. BOX 388

  • FORKED RIVER
  • 08731 w.b. ua s - .

April 27, 1981

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@. ~ 4 Mr. Boyce H. Grier, Director Office of Inspection and Enforcanent Region I

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United States Nuclear Regulatory Ccmnissicn 631 Park Avenue p AER.?0 /gg7'2

,3'2 LA King of Prussia, Pennsylvania 19406 u.s,kl,,g g h s J

Dear Mr. Grier:

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SUBJECT:

Oyster Creek Nuclear Generating Station *

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Docket No. 50-219 Nonroutine Envi m mr.ad.al Operating Report No. 50-219/81-1 l

'Ihis letter forwards two copies of Nonrout:l e Envimmental Operating t

Report No. 50-219/81-1 in 714ance with parag2.J 5.6.2 of Appendix B to l the Technical F4 #4 catims.

Very truly yours,

. N-van R. F Jr.

Vice Preside 1t JCP&L ,

Director - Oyster Creek IRF:dh Encla.,sures cc: Director (17 copies)

Office of Nuclear Reactor Regulations United States Nuclear Regulatory Camission Washington, D. C. 20555 Director NBC Resident Ins g-W (1)

Oyster Creek N el a r Generating Station Forked River, N. J.

Ob 3 'l 8105010Y/o

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OYS'IER CREEK NUCLEAR GDERATING STATION Ebzked River, New Jersey 08731 Nontoutine Envitmo.iutal Operating Report No. 50-219/81-1 Report Date

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April 27, 1981 Occtu. ins Date April 15 & 16, 1981 Identification of Occtu.imm Excaading a limiting cx:niition as dafined in the Envircomental Tachnical Speci-fication, Paragraph 2.1.4.3, when within a span of two days, two indivichm1 ~

dilution ptmp trips occurred in which the reserve ptmp oculd not be started within the required 15 minutes. Dur ng each occurrence, the station intake canal tm-reture was below 60.00F.

This event is considered to be a ncteoutine envircnnental operating report as dafined in the Technical Snac4 fica *4rms, Amandix "B", paragraph 5.6.2.

Conditic 1s Pricr to Occtu.rus Steady State Power Ptmp Trip No.1 Dilution Ptmp Flow: 5.20 ES GPM Circulating Water

. Ptmp Flow 3.45 E5 GPM Ptmp Trip No. 2 Dilution Ptmp Flow: 5.20 E5 GPM Circulating Water Ptmp Flow 2.30 E5 GPM l

na= -intion of occuu.ma Dilution Ptmp 1-3 was manually triW at 0109 on April 15, 1981. 'Ihe ptmp i shutdown was necessitated by low gear box oil pressure. An 4-ad< ate attspt i

was made to start Dilution Ptmp 1-1, the reserve ptmp, but this failed due to a faulty seal water flow switch. Ctmpers were plaM around the flow switch and Dilution Ptmp 1-1 was started at 0545. During this occurrence, the total time of insufficient dilution ptrp operaticn was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 36 minutes and the time of ml4ance was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 21 minutes. The following day, April 16, 1981, the seal water suction inlet plugged with grass. Dilution Ptmps 1-1 and 1-2 tripped at 1008. Operators cleaned the inlet and started dilut' m puup 1-1 at 1020. Dilution Ptmp 1-2 was started two minutes later, but an asso-lated transient tripped ptmp 1-1. A pressure switch across the lube oil cxcler was l reset and Dilution Ptmp 1-1 was restarted at 1042. The time of rs-dying di eharge was 5 minutes.

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Ncmroutine Enviu-- --Fa1 Operating Report No. 50-219/81-1 Page 2 Apparent Cause of Occe41ce Ccr.ponent Failure

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Analysis of Occurrence Ccx*4rmia operation of the two dilution puups when the intake water tenperature is below 60.0 F during plant operation will reduce the area of ai.Lition and thereby minimize a build-up in the fish standing stock in the discharge canal.

6 At the time of the pung trips, the reactor l power level was approximately 60% of rated power. 'Ihe heat discharge to the diacharge canal was, therefore, greatly reduced. Failure to operate the dilution punps in accordux:e with Tehnical spe4 fication 2.1.4.3 had minimal, if any, adverse biological effects on aquatic

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organisms.

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Oorrective Action i i

r_n==44=te cxh.loct.ive actica cxmsisted of j == ring the flow switch on Dilution Pung 1-1 and restarting the pmp at 0545 on April 15, 1981. On April 16, 4wn=94 ate corrective-action consisted of resetting the lube oil cooler switch on 1-1 dilution punp and restarting the pmp at 1042.

Mxlifications to the cooling and seal water systems for the dilution pungs are presently in the design evaluation stage.

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U. S. NUCLEA3 REIULATO.;Y COMMIS$10N '

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