05000219/LER-1983-009, Forwards LER 83-009/01T-0.Detailed Event Analysis Encl

Forwards LER 83-009/01T-0.Detailed Event Analysis Encl

ML20069G255
Person / Time
Site:	Oyster Creek
Issue date:	03/15/1983
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20069G259	List: 05000219/LER-1983-009, Forwards LER 83-009/01T-0.Detailed Event Analysis Encl
References
NUDOCS 8303250090
Download: ML20069G255 (3)

LER-1983-009, Forwards LER 83-009/01T-0.Detailed Event Analysis Encl

Event date:
Report date:
2191983009R00 - NRC Website

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OPU Nuclear Q

gf P.O. Box 388 Forked River, New Jersey 08731 609-69.3-6000 Writer's Direct Dial Number:

March 15, 1983 Mr. Ronald C. Haynes, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Haynes:

Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/83-09/01T This letter forwards three copies of a Licensee Event Report (LER) to report Reportable Occurrence No. 50-219/83-09/0lT in compliance with paragraph 6.9.2.a.2 of the Technical Specifications.

Very truly yours, f

Peter B. Fiedler Vice President and Director Oyster Creek PBF:jal Enclosure s cc: Dire ctor (40 copies)

Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Dire ctor (3)

Of fice of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.

20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 8303250090 830315 PDR ADOCK 05000 s

o, b

GPU Nuclear is a part of the General Public Utilities System

OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/83-09/01T Report Date March 15, 1983 f

Occurrence Date February 22, 1983 Identification of Occurrence The results of local leak rate testing has identified that Main Steam Isolation Valves (MSIV) NSO4A and NSO4B failed to meet acceptance criteria.

This constitutes operation of the unit or af fected systems when any parameter or operation subject to a limiting condition is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specifications, paragraph 4.5.F.d.

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

Conditions Prior to Occurrence The reactor was in the cold shutdown condition at the time the occurrence was identified. The reactor was in various operating modes prior to the occur re nce.

Description of Occurrence On Febnaary 16, 1983, while conducting Local Leak Rate testing, analysis identified the following valves with leakage in excess of the acceptance crituria of 11.9SCFH @ 20 psig. The results of the Leak Rate Test Program for those valves are as follows:

De scription Valve Date of Test Leakage @ 20 psig.

Main Steam Isolation NSO4A 2-14-83 15.03 SCFH

, Main Steam Isolation NSO4B 2-14-83 15.95 SCFH Apparent Cause of Occurrence The cause of this occurrence is believed to be leakage through the valve packing.

Reportable Occurrence Page 2 Report No. 50-219/83-09/0lT Analysis of Occurrence The analysis of this occurrence is in progress. An update of this LER will be submitted upon the completion of the leak rate test program.

Corrective Action

Valve packing replacement is planned for the MSIVs during the current refueling / maintenance outage.

NOTE:

Any other valve (s) or penetration (s) identified in the Local Leak Rate Test Program that do not meet their acceptance criteria will be included in the update of this LER.