ML18086A519

Forwards LER 81-005/03L-0.Detailed Event Analysis Encl

ML18086A519
Person / Time
Site:	Salem
Issue date:	05/11/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18086A520	List: ML18086A519 ML18086A523
References
NUDOCS 8105190430
Download: ML18086A519 (3)

Text

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• Pub I ic Service Electric and Gas Company 80 Park Plaza Newark, N .J. 07101 Phone 201 /430-7000 May 11, 1981 Mr. Boyce H. Grier Director of USNRC Off ice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-05/03L Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 81-05/03L. This report is required within thirty (30) days of the occurrence.

Sincerely yours,

~4'/~..w*1 J 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)

The Em-rnv Peonlr*

aio;;190Lfio . 95 2001 13501/.) -1 ti)

Report Number:

Report Date:

Occurrence Date:

81-./03L May 11, 1981 4/13/81 Facility: Salem Generating Station, Unit 2 Public Service Electric.& Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

All Reactor Coolant Pumps and Residual Heat Removal Pumps Out of Service CONDITIONS PRIOR TO OCCURRENCE:

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

At 1823 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.936515e-4 months <br /> on April 13, 1981, Action Statement 3.4.1.1.b.2.b was entered because all Reactor Coolant Pumps and Residual Heat Removal Pumps were de-energized to facilitate the replacement of relief valve 2RH3 in the Residual Heat Removal System. Technical Specifications allow for all Reactor Coolant Pumps and Residual Heat Removal Pumps to be de-energized for up to one hour, provided no operations are permitted which would cause dilution of the Reactor Coolant System boron concentration.

The replacement of valve 2RH3 and the subsequent return to service of the RHR System required 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 22 minutes, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 22 minutes in excess of the time allowed by Technical Specifications for the pumps to be de-energized. The Action Statement was

• terminated at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />.

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

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The time allowed by Technical Specifications for all the pumps to be de-energized was not sufficient for the completion of this task.

ANALYSIS OF OCCURRENCE:

The r~placement of valve 2RH3 was part of Engineering Change Notice 21257, revision 2, which essentially is an installation of the Pres-surized Overpressure Protection System.

Prior to the actual replacement of the valve, its associated piping had to be vented and drained. After replacement, correct system lineup verification had to be performed and finally, the system returned to service. From start to finish, the entire task required 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 22 minutes for completion.

LER 81-05/03L *

• May 11, 1981 PSE&G feels that every effort was made to complete this task in the minimum amount of time consistent with safe work practices and our operating and maintenance procedures.

CORRECTIVE ACTION:

PSE&G feels that this particular occurrence warrants no specific corrective action.

FAILURE DATA:

Not Applicable Prepared By W. J. Steele Manager ~ Sa'iem=Generating Station SORC Meeting No. 81-36