ML20028B031

Forwards Supplemental LER 82-030/03X-1.Detailed Event Analysis Encl

ML20028B031
Person / Time
Site:	Salem
Issue date:	11/03/1982
From:	Heller R, Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20028B032	List: ML20028B031 ML20028B041
References
NUDOCS 8211290389
Download: ML20028B031 (3)

Text

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O 40 PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station November 3, 1982 Mr. R. C. Haynes Regional Administrator i

USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 Dear Mr. Haynes LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-030/03X-1 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1.9.d, we are submitting supplemental Licensee Event Report for j Reportable Occurrence 82-030/03X-1.

Sincerely yours, g h[$b- '

H. J. Midura General Manager -

[ Salem Operations RH:kshj[

i l CC: Distribution 8211290309 821103 PDR ADOCK 05000272

'S PDR 6Ag The Energy People l vam aw n et

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Report Number: 82-030/03X-1 Report Date: 11-03-82 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:

1 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 secm). 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.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

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

ANALYSIS OF OCCURRENCE:

r The limitations on containment leakage ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure.

Technical Specification 3.6.1.2 requires:

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

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LER 82-030/03X-1 .

NNALYSIS OF OCCURRENCE: (continued)

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

This occurrence constituted an abnormal degradation of contain-ment Type B and C Systems and is reportable in accordance with Technical Specification 6.9.1.9.d.

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. A new volumetric leak rate tester was purchased for the next containment leak rate testing.

FAILURE DATA:

Aloyco, Inc.

3 inch Swing check Valve Model 376 SP Prepafed By R. Heller / }&h:

Geherhl Mhnager Salem Operations SORC Meeting No.82-98B i

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