05000219/LER-1980-048, Forwards LER 80-048/03L-0

Forwards LER 80-048/03L-0

ML19345A967
Person / Time
Site:	Oyster Creek
Issue date:	11/18/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345A968	List: 05000219/LER-1980-048, Forwards LER 80-048/03L-0 05000219/LER-1980-048-03, /03L-0:on 801029,during Functional Testing,Snubber 23-7 Failed to Lock Up in Tension Direction.Cause Unknown. Snubber Replaced
References
NUDOCS 8011250500
Download: ML19345A967 (3)

LER-1980-048, Forwards LER 80-048/03L-0

Event date:
Report date:
2191980048R00 - NRC Website

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November 18, 1980

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Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I United States Nuclear Regulatory Comission 641 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SUBJECT: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/80-48/3L This letter forwards three copies of a Licensee Event Report to report Reportable Occurrence No. 50-219/80-48/3L in ccmpliance with paragraph 6.9.2.b.2 of the Techr.fcal Specifications.

Very truly yours,

/

/iCM'l van R. Finfrock, Q

Vice President Ge atic IRF:dh Enclosures cc: Mr. John G. Davis, Acting Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D.C.

20555 Mr. William G. Mcdonald, Director (3 copies)

Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 i

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OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-48/3L Report Date November 1 8, 1980 l

Occurrence Date October 29, 1980 Identification of Occurrence A hydraulic snubber failed to lock up in the tension direction during its functicnal testing.

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 at steady state power.

Major Plant Parameters:

Power:

Reactor 1783 MWt Generator 590 MWe 4

Flow:

Recirculation 14.5 x 10 GPM Feedwater 6.597 x 106 lb/hr Description of Occurrence On October 29, during the functional testing of hydraulic snubbers installed on engineered safety related systems, snubber no. 23-7 (serici number F93501) located on Containment Spray System II failed to lock up in the tension di ection.

During the performance of this test, no hydraulic fluid leakage from the assembly was detected, and further inspection showed the poppets, seals, relief valve balls and spring, and the socket head screws to contain no apparent physical or structural damage.

Apparent Cause of Occurrence Unknown Inspection of the components in the valve block assembly revealed no apparent

.iefects or evidence of abnonnal operating conditions. One of the pressure relief valve balls was found to have a slight bit of tarnish on it, yet this had no effect on the manner in which the ball contacted its seat or its spring, and direct measurement determined that the ball was not out of round.

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I Reportable Occurrence Page 2 Report No. 50-219/80-48/3L Analysis of Occurrence Snubbers are installed to limit piping movement during transient and seismic events. Since this snubber failed its test in the tension direction, it would have been inoperable during a downward oipe movement. The saftey implications would have been minimized, however, due to the fact that a rigid pipe support (which would restrict downward pipe movement) is located within 6 feet of the snubber.

In the event of a seismic occurrence, the presence of this rigid pipe l

support would have minimized the consequences associated with the loss of operation of the snubber.

Corrective Action

The snubber was replaced with an operable spare. The functional testing of additional snubbers will be performed in accordance with the Technical Specifica-tions, paragraph 4.5.Q.4.

In order to help determine the cause of the failure of a snubber, it is possible that a more complete method for disassembly and inspection is needed. The snubber testing and rebuilding procedures will be reviewed for possible refinement of both testing and rebuilding operations.

Also, an investigation into the feasibility of replacing hydraulic snubbers with mechanical snubbers on an as needed basis will be performed.

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