05000272/LER-1981-054, Forwards LER 81-054/01T-0.Detailed Event Analysis Encl

Forwards LER 81-054/01T-0.Detailed Event Analysis Encl

ML20004E715
Person / Time
Site:	Salem
Issue date:	06/04/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20004E716	List: 05000272/LER-1981-054, Forwards LER 81-054/01T-0.Detailed Event Analysis Encl 05000272/LER-1981-054-01, /01T-0:on 810521,vendor Advised That Regulatory Requirements Could Be Violated by Failure of Vol Control Tank Level Control Sys & Subsequent Loss of Suction to Centrifugal Charging Pump W/Failure of Remaining Pump
References
NUDOCS 8106150100
Download: ML20004E715 (3)

LER-1981-054, Forwards LER 81-054/01T-0.Detailed Event Analysis Encl

Event date:
Report date:
2721981054R00 - NRC Website

text

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0 C PSEG' Public Service Electric and Gas Cornpany 80 Fark Plaza Newark, N.J. 07101 Phone 201/430-7000 June 4, 1981 gS\\F ;

Mr. Boyce H. Grier

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Director of USNRC j

p w Office of Inspection and Enforcement Region 1 v-\\

631 Park Avenue

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f King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-54/0lT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 81-54/01T.

This report is required within fourteen (14) days of the occurrence.

Sincerely yours, f A,d M :

R.

A. Uderit-General Man % 3r -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (40 copies)

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

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• 2 819615e100

Raport Numbar:

81-54/OlT i

Report Date:

June 4, 1981 Occurrence Date:

5/21/81 Facility:

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

Volume Control Tank Level Control System CONDITIONS PRIOR TO OCCURRENCE:

Not Applicable DESCRIPTION OF OCCURRENCE:

We have been informed by Westinghouse of a postulated plant operating condition which could result in a violation of current regulatory requirements regarding control and protection system interaction criteria.

Westinghouse had previously notified the Office of Nuclear Reactor Regulation on May 21, 1981 under 10CFR21.

Tr.e postulated situation involves a failure in the volume control tank level control system and a subsequent loss of suction to an operating centrifugal charging pump coupled with a single random failure of the remaining centrifugal charging pump.

The initial control system failure leads to diversion of letdown flow and loss of makeup to the VCT.

Continued charging flow during this conditien could lead to draining of the VCT and loss of suction with consequential pump damage if the operator does not terminate the event.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

This occurrence resulted from a Westinghouse analysis which concluded that regalatory requirements might not be met with respect to system I

interaction criteria.

l ANALYSIS OF OCCURRENCE:

l The Westinghouse analysis indicates that approximately ten minutes are ava;1able to the operator to terminate the assumed event prior to pump loss of suction.

It is further concluded that, in the-absence of automatic letdown isolation or re-alignment of the normal letdown path, core uncovery would not occur until after approxi-mately two days.

Westinghouse has concluded that this item is not considered to involve serious safety implications.

7t should also be noted that the Salem design includes an intermediate-head safet; injection system which could be used as a backup to the high-head centrifugal charging pumps.

It is our conclusion that the Salem design is adequate with respect to the operator's ability to recognize and terminate such an event, and that no serious safety implications exist.

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LER 81-54/03L June 4, 1981 CORRECIVE ACTION:

In accordance with the recommendations of Westinghouse, we have reviewed the plant procedures and find them adequate with respect In to prompt and proper operator response during such an event.

addition, all licensed operators will be informed of the' potential problem and this information will be included in the Licensed Operator Requalification Program.

FAILURE DATA:

Not Applicable

^^*[d Prepared By J.

J.

Espey Manager - Salem Generatiftf3 Station SORC Meeting No.

81-45 l

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