05000272/LER-1982-030, Forwards LER 82-030/03L-0.Detailed Event Analysis Encl

Forwards LER 82-030/03L-0.Detailed Event Analysis Encl

ML20053C980
Person / Time
Site:	Salem
Issue date:	05/19/1982
From:	Frahm R, Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20053C981	List: 05000272/LER-1982-030, Forwards LER 82-030/03L-0.Detailed Event Analysis Encl
References
NUDOCS 8206030245
Download: ML20053C980 (3)

LER-2082-030, Forwards LER 82-030/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2722082030R00 - NRC Website

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'O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 19, 1982 Mr. R. C. Haynes Regional Administrator l USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-030/03L Pursuant to the requirements of Salem Generating Station Unit No. 1, Technical Specifications, Section 6.9.1.9.d, we are submitting Licensee Event Report for Reportable Occurrence 82-030/03L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, l/ f )t/ sWe w J H. J. Midura General Manager -

Salem Operations RF:ks CC: Distribution 8206030245 820519 DR ADOCK 05000 g%

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Report Number: 82-030/03L Report Date: 05-19-82 Occurrence Date: 04-19-82 Facility: Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Containment Type B and C Leak Rate Test - Out of Specification.

This report was initiated by Incident Report 82-118.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 5 - Rx Power 0% - Unit Load 0 MWe DESCRIPTION OF OCCURRENCE:

During the period of January 2, 1982 to April 19, 1982, while conducting scheduled leak rate testing of containment Type B and C systems, it was discovered that Valve LWR 81 leakage rate was greater than the maximum range of the volumetric test equipment (2000 sccm). The actual leakage rate could not be ascertained, and it was not possible to verify that the total leakage did not exceed the Specification limit of 0.60 La for Type B and C systems. Action Statement 3.6.1.2 was therefore entered, retroactive to previous plant operation in Modes 1 through 4.

This occurrence constituted an abnormal degradation of the Primary Water Recovery System in accordance with Technical Specification 6.9.1.9.d.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The range of the test equipment available was insufficient for the necessary leak rate measurements.

ANALYSIS OF OCCURRENCE:

Technical Specification 3.6.1.2 requires:

With the measured combined leakage rate of all penetrations subject to Types B and C tests exceeding 0.60 La, restore the leakage rate to within the limit prior to increasing the Reactor Coolant System temperature above 200 F.

Technical Specification 3.6.1.2 is not applicable in Mode 5; however, leakage rates obtained from leak testing in that mode may be assumed to be present in all modes of operation.

s . ..

LER 82-030/03L CORRECTIVE ACTION:

Valve LWR 81 was reworked, and on March 14, 1982, the measured leakage rate was within the range of the test equipment. The total rate for Type B and C components was within specification, and Action Statement 3.6.1.2 was terminated, while still in Mode 5.

New test equipment with the proper range will be purchased for the next containment leak rate testing. A Supplemental Report,will be submitted upon completion.

FAILURE DATA:

Aloyco, Inc.

3 inch Swing Check Valve Model 376 SP Prepared By R. Frahm / h. M M Genefal Manager SORC Meeting No. 82-51