05000311/LER-1982-140, Forwards LER 82-140/03L-0.Detailed Event Analysis Encl

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Forwards LER 82-140/03L-0.Detailed Event Analysis Encl
ML20064B696
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/15/1982
From: Midura H
Public Service Enterprise Group
To: Haynes R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20064B699 List:
References
NUDOCS 8301040142
Download: ML20064B696 (3)
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LER-1982-140, Forwards LER 82-140/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
3111982140R00 - NRC Website
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text

.

- O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 15, 1982 Mr.

R.

C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 82-140/03L Pursuant to the requirements of Salem Generating Station I

Unit No.

2, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-140/03L.

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

Sincerely yours, h. f$bh z+ H.

J. Midura l

General Manager -

Salem Operations FD:ks

[

CC:

Distribution 6}Y 4

8301040142 821215 PDR ADOCK 05000311 S

PDR The Energy People 1: n us, u e, m.,

Report Number:

82-140/03L Report Date:

12-15-82 Occurrence Date:

11-21-82 Facility:

Salem Generating Station Unit 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Containment Airlock - Inoperable This report was initiated by incident report 82-480 CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - RX Power 82 % - Unit Load 900 MWe DESCRIPTION OF OCCUBRENCE:

At 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br />, November 21, 1982, while performing surveillance procedure SP(0)4.6.1.3 on the 130' elevation containment airlock, it was determined that the leakage rate exceeded the limit of 0.05 La at the design pressure of 47.0 psig, as required by Technical Specification 3.6.1.3.b.

The air lock was declared inoperable, and Action Statement 3.6.1.3.a was entered.

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

APPARENT CAUSE OF OCCURRENCE:

The cause of the containment air lock leakage was excessive air flow past the inner door seal.

ANALYSIS OF OCCURRENCE:

The containment air lock doors allow for personnel access to the containment building while providing a redundant boundary as part of overall containment integrity.

This barrier prevents the release of radioactive contamination to the environment in the event of a design basis accident.

Since one door remained sealed, providing containment integrity, no risk to the health and safety of the general public existed.

Action Statement 3.6.1.3a Requires:

1.

Maintain at least the operable air lock door closed and either restore the inoperable air lock door 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 lock the operable air lock door closed.

F LER-82-140/03L ANALYSIS OF OCCURRENCE: (cont'd) 2.

Operation may then continue until the performance of the next required overall air lock leakage test provided that the operable air lock door is verified to be locked closed at least once per 31 days.

CORRECTIVE ACTION

The air lock outer door was maintained in a closed position.

The interior door seal was repositioned in the groove and surveillance procedure SP(0)4.6.1.3 was performed satisfactorily.

At 1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br />, November 21, 1982, the air lock was declared operable, and Action Statement 3.6.1.3.a was terminated.

A number of previous problems with air lock operating linkage and door seals have been encountered (See LER's 82-055/03L, 82-056/03L, 82-090/03L, and 82-129/03L).

Efforts are presently underway to correct the problems including improved personnel training, installation of snubbers on the doors, relocation of test air supply isolation valves, revision of the surveillance test to more accurately simulate desired airlock perf ormance, and installation of the Chicago Bridge and Iron Co. recommended latch mechanism modifications.

Final evalutation of the effectiveness of the measures is pending full implementation.

FAILURE DATA:

Chicago Bridge and Iron Co.

Containment Air Lock Door Seal Prepared By P.

Dickey

/t '< % -

J/

Gene'ral Manager -

SORC Meeting No.82-110

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