05000311/LER-1980-014, Forwards LER 80-014/03L-0

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Forwards LER 80-014/03L-0
ML18082A907
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/12/1980
From: Librizzi F
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18082A908 List:
References
NUDOCS 8008180485
Download: ML18082A907 (3)


LER-1980-014, Forwards LER 80-014/03L-0
Event date:
Report date:
3111980014R00 - NRC Website

text

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C~ PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 Mr. Boyce H. Grier Director of USNRC August 12, 1980 Off ice of Inspection and Enforcement Region 1 631 Park Avenue Kirig of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 80-14/03L Pursuant to the requirements of Salem Generating StaLion Unit No.* 2 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 80-14/03L.

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

Sincerely yours,

- ff ['_j~,;_ ~: -kA F. P. llbtl;~r 0 -*-'

General Manager -

Electric Production CC:

Director, Office of Inspection and Enforcement (30 copies)

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

-~95~-2~001(200Ml2-78

Report Number:

Report Date:

80-14/03L 8/12/80 Occurrence Date:

7/14/80 Facility:

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

Reactor Coolant Pumps Out of Service for Greater than One Hour CONDITIONS PRIOR 'I*O OCCURRENCE:

Mode 3 Prior to Initial Criticality DESCRIPTION OF OCCURRENCE:

At th~ completion of hot no flow rod drop test, we were unable to restart a Reactor Coolant Pump because pressure could not be main-tained in the Volume Control Tank.

Action Statement 3.4.1.1 was entered_ at 1402 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.33461e-4 months <br /> which requires with Keff less than 1.0, operation may proceed provided at least one reactor coolant loop is in operation with an associated Reactor Coolant or Residual Heat Removal Pump.*

(* -

The asterisk allows all Reactor Coolant Pumps and Residual Heat Removal Pumps may be de-energized for up to one hour, provjded no.operations are permitted which could cause dilution of the Reactor Coolant System boron concentration.

. DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Equipment Failure ANALYSIS OF OCCURRENCE:

At a previous time, the Volume Control Tank relief valve had lifted and the disk became cocked in a partially open position.

When the valve was disassembled, no apparent reason c*ould be found for the disk bei~g cocked and it was decided to replace the internals.

CORRECTIVE ACTION

The valve was removed from the system, inspected and a new disk stem installed.

The valve was tested satisfactorily and reinstalled with the Action Statement being terminated at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> with a Reactor Coolant Pump being started.

LER 80-14/03L FAILURE DATA:

Relief Valve Crosby Valve, Inc.

Model 3L4J0-25 Special Prepared By M. J. Murphy SORC Meeting No.

61-80 2 -

Manager