ML20028D587

Forwards LER 82-089/03L-0.Detailed Event Analysis Encl

ML20028D587
Person / Time
Site:	Salem
Issue date:	01/05/1983
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20028D593	List: ML20028D587 ML20028D596
References
NUDOCS 8301190305
Download: ML20028D587 (3)

Text

n O PSIEG Public Service Electric and Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 5, 1983 Mr. R. C. Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-089/03L Pursuant to the requirements of Salem Generating Station Unit No. 1, Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 82-089/03L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, l/ff;[ww H. J. Midura General Manager -

Salem Operations FD:ks CC: Distribution l

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8301190305 930105 PDR ADOCK 05000272 S PDR The Energy Peor'e p#

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t Report Number: 82-089/03L Report Date: 01-05-83 Occurrence Date: 12-13-82 Facility: Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

No. 12 Residual Heat Removal Pump - Inoperable.

This report was initiated by Incident Report 82-512.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 6 - Rx Power 0% - Unit Load 0 MWe.

DESCRIPTION OF OCCURRENCE:

At 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, December 13, 1982, due to excessive leakage from the mechanical seal, No. 12 Residual Heat Removal (RHR)

Pump was declared inoperable and Action Statement 3.9.8.2.a was entered. No. 11 RHR Pump was started to provide RHR flow.

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

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE: a The apparent cause was mechanical seal failure.

ANALYSIS OF OCCURRENCE:

The requirements that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during

the refueling mode and (2) sufficient coolant circulation is maintained throu?gh the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR loops operable when there is less than 23 feet of water above the core ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

J

LER 82-089/03L i ANALYSIS OF OCCURRENCE: (cont'd)

Technical Specification 3.9.8.2.a requires:

Two independent Residual Heat Removal (RHR) loops shall be operable in Mode 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet. With less than the required RHR loops operable, immediately initiate corrective action to return the required RHR loops to operable status as soon as possible.

CORRECTIVE ACTION:

The mechanical seal in No. 12 RHR Pump was replaced and Surveillance Test 4.0.5.p was satisf actorily performed. At 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, December 16, 1982, Action Statement 3.9.8.2.a was terminated.

FAILURE DATA:

Durametallic Corp.

Mechanical Seal Drawing No. 2 D-9 0183 Prepared By F. Dickey //Nt4A[W General Msnager -

Salem Operations SORC Meeting No. 83-02 i

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