05000219/LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl

Forwards LER 82-004/03L-0.Detailed Event Analysis Encl

ML20041D452
Person / Time
Site:	Oyster Creek
Issue date:	02/22/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20041D454	List: 05000219/LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl 05000219/LER-1982-004-03, /03L-0:on 820121,reactor Bldg Closed Cooling Water Drywell Isolation Valve V-5-167 Failed to Fully Close.Caused by Lack of Stem/Stem Nut Lubrication &/Or Packing Problem. Stem,Stem Nut & Bearing Lubricated & Valve Repacked
References
NUDOCS 8203050330
Download: ML20041D452 (3)

LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2191982004R00 - NRC Website

text

_ _ _ _

4 GPU Nuclear Ng g{

P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number:

February 22, 1982 a

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' N Mr. Ronald C. Haynes, Adminstrator N

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United States Nuclear Regulatory Cmmission d g[,n g"

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631 Park Avenue

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King of Prussia, Pennsylvania 19406

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Dear Mr. Haynes:

l/: ~g SURIECT: Oyster Creek Nuclear Generating Station

' '~J Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/82-04/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/82-04/3L in cmpliance with paragraph 6.9.2.b.2 of the Technical 3pecifications.

Very truly yours, Peter B. iN Vice President - Director Oyster Creek PBF:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforcement United StaMs Nuclear Regulatory Ccmnission Washington, D.C.

20555 Director (3)

Office of Managment Information and Program Control United States Nuclear Regulatory Camtission Washington, D. C. 20555 i

NRC Resident Inspector (1)

Oyster Creek Nuclear Generating Station Forked River, N. J.

F203050330 020222 PDR ADOCK 05000219 r is a part of the General Public Utilities System V

S PDR

OYSTER CREEX NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee L' vent Report Reportable Occurrence No. 50-219/82-04/3L Report Date February 22, 1982 Occurrence Date January 21, 1982 Identification of Occurrence During surveillance testing, Reactor Building Closed Cooling Water Drywell Isolation Valve V-5-167 failed to close. This failure has been determined to affect Drywell Isolation as specified in Technical Specifications 3.5.A.3, Table 3.5.2.

This event is considered to be a reportable occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.2.

Conditions Prior to Occurrence The plant was in the shutdown condition.

Rx coolant tmperature was <212 F.

Description of Occurrence On Thursday, January 21, 1982, while performing surveillance testing on RBCCW Drywell Isolation Valve, V-5-167, the valve position indication failed to indicate full closed upon initiation of a closure signal.

Apparent Cause of Occurrence Upon investigation, current traces were taken which indicated higher than normal motor operator running currents especially during certain portions of the valve stroke. The stmVstem nut were lubricated and the valve was repacked. Current traces were repeated and were normal. Based on these findings the apparent cause of the occurrence was a lack of lubrication and/or a valve packing problem.

Analysis of Occurrence The RBOCW Systen supplies cooling water to cmponents located within the drywell.

There are two containment isolation valves located on the RBCCW return line.

Although V-5-167 failed to isolate, the second isolation valve, V-5-166 tested satisfactorily during the surveillance and would have isolated the penetration.

Since the redundant valve was operable, the safety significance of the event is considered minimal.

Reportable Occurrence Page 2 j

Report No. 50-219/82-04/3L I-

Corrective Action

4 The Sten Nut, Stem and the bearing of the valve motor operator were lubricated and the valve was repacked. The valve was subsequmtly surveilled satisfactorily.

Currmt vs. time recordings were taken during valve operation which indicated the cause of the occurrmce had been eliminated by the corrective acticos which had been taken. Lubricatico checks of similar Limitorque operators will be incorporated into the P.M. program.

In order to further reduce the chance of a future occurrmee, the setting on the torque switch in the limitorque operator was changed from 1.0 to 1.5.

Failure Data Manufacturer: Limitorque Operator i

Model:

SMB-000 1

i 4

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