05000272/LER-1981-048, Forwards LER 81-048/03L-0.Detailed Event Analysis Encl

Forwards LER 81-048/03L-0.Detailed Event Analysis Encl

ML20004E768
Person / Time
Site:	Salem
Issue date:	06/08/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20004E769	List: 05000272/LER-1981-048, Forwards LER 81-048/03L-0.Detailed Event Analysis Encl 05000272/LER-1981-048-03, /03L-0:on 810514,Tech Spec Limit Containment Air Lock Leakage Rate Exceeded Design Pressure During Sp.Caused by Outer Door Seal Not Holding Pressure.Seals Repaired & Tested
References
NUDOCS 8106150225
Download: ML20004E768 (2)

LER-1981-048, Forwards LER 81-048/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2721981048R00 - NRC Website

text

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PSEG Publ.c S: vice Electnc and Gas Cornpany 80 Park P!aza Newark, N.J. 07101 Phone 201/:30 70')e; Q

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June 8, 1981 y

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p Mr. Boyce H. Grier co*'55 s

Director of USNRC Office of Inspection and Enforcement q'

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Region 1

( -[to 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-48/03L Pursuant to the requiremencs of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 81-48/03L.

This report is required within thirty (30) days of the occurrence.

Sincerely yours, A

p l

R.

A. Uderitz General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control (3 copies)

Tne Enerov Pso; i 8106150 235

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Report Number:

81-48/03L R9 port Date:

June 8,1981 Occurrence Date:

5/14/81 Facility:

Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Containment Air Lock Inoperable CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 99% - Unit Load 1100 MWe.

DESCRIPTION OF OCCURRENCE:

While performing Surveillance Procedure SP (0) 4.6.1.3 on the Elevation 100' Containment Air Lock, it was determined that the l

leakage rate exceeded tha limit of 0.05 La at the design pressure of 47.0 psig as required by Technical Specification 3.6.1.3b.

At 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br />, Action Statement 3.6.1.3 was entered.

The Action l

Statement for-Technical Specification 3.6.1.3 requires that with an air lock inoperable, restore the air lock to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

This occurrence constituted operation in a degraded mode IAW Technical Specification 6.9.1.9b.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The outer door seal would not hold pressure.

ANALYSIS OF OCCURRENCE:

Upon investigation, it was determined that the outer door seal had come out of its channel and, therefore, could not maintain pressure.

CORRECTIVE ACTION

The seals on the outer door were repaired and tested satisfactorily.

The Action Statement was terminated at 2136 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.12748e-4 months <br /> on May 14, 1981.

FAILURE DATA:

Containment Personnel Air Lock Chicago Bridge and Iron Company b

Prepared By J. J. Espey Manager - Saled Gene' rating Station

~

SORC Meeting No.

81-45