ML20050D547

RO 50-219/82-19/01P:on 820331,results of Leak Rate Testing on Main Steam Isolation Drain Valves Identified Abnormal Degradation of Primary Containment.Cause Unknown.Valve V-1-106 Repaired & Valve V-1-111 Will Be Replaced

ML20050D547
Person / Time
Site:	Oyster Creek
Issue date:	04/01/1982
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RO-50-219-82-19, NUDOCS 8204120305
Download: ML20050D547 (3)

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'IO: Ronald C. Haynes Administrator of Regulatory Operations Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 FRm: G P U Nuclear Oyster Creek Nuclear Generating Station Docket No. 50-219 Forked River, New Jersey 08731 SUILTECT: Reportable Occurrence Report No. 50-219/82-19/0lP

'Ihe following is a preliminary report being subnitted in coupliance with the Technical Specifications, paragraph 6.9.2.a. (3).

REPORT DATE: April 1, 1982 Preliminary Approval:

- YV $24Wf Peter B. Fiedler //

ice-President - Directiof Oyster Creek Director (2)

Office of Management Information and Program Control U.S. Nuclear Regulatory Conmission 4 Washington, D. C. 20555 O  %

NRC Resident Inspector (1) p Oyster Creek Nuclear Cenerating Station d' CE4rg 4 Fbrked River, Nw Jersey 08731 Z 4Pgy - -

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a OYSTER CREEK NUCLEAR GE2ERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/82-19/0lP Report Date April 1, 1982 Occurrenm Date burch 31, 1982 Tdentification of Occurrence It was identified that an abnonnal degradation of the primary containnent existed, based on the results of leak rate testing perforned on the Main Steam isolation drain valves.

'Ihis event is considered to be a reportable occurrence as defined in the Techni-cal Specifications, paragraph 6.9.2.a.3.

Conditions Prior to Occurrence

'Ihe reactor was in the cold shutdown condition at the time the occurrence was identified. Ibwever, the reactor was in various nodes between the time period of January,1980 until the date of identification of the event.

Description of Occurrence On Febrmry 8,1982, while perfonning local leak rate tests on bbin Steam isola-tion drain valves V-1-106 and V-1-107 the results were found to be outside of the acceptable limit pluvided in the test procedure. On burch 18, 1982, the re-naining pair of bhin Steam isolation drain valves (V-1-110 and V-1-lll) were leak tested, and the results of this test were also outside of acceptable limits.

Since V-1-110 and V-1-lll were tested as a pair, it could not be determined which valve was leaking. An additional test was perfonned and valve V-1-111 was deter-mined to be the leaking valve.

In the piping configuration containing these valves, a leak in either V-1-106 or V-1-107 and a leak in V-1-111 provides an abnonnal flow path frcm the reactor vessel to the Condenser hotwells.

_Agurent Cause of Occurrence p Unknown.

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e . ;s 4 b Reportable Occurrence Page 2 Report No. 50-219/82-19/0lP Analysis of Occurrence Since the last time these valves were leak tested was January,1980, it must be assumed that the increasing degradation in prinnry contaiment occurred between that time and March 18, 1982.

Corrective Action Valve V-1-106 was repaired by replacing the valve internals, and it passed the leak rate test after the repairs. Valve V-1-107 was determined not to leak. At the present time, valve V-1-lli is in the process of being replaced.