05000311/LER-1981-009, Forwards LER 81-009/03L-0

Forwards LER 81-009/03L-0

ML18086A586
Person / Time
Site:	Salem
Issue date:	05/22/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18086A587	List: 05000311/LER-1981-009, Forwards LER 81-009/03L-0 05000311/LER-1981-009-03, /03L-0:on 810423,during Plant Cooldown,Inadvertent Safety Injection Occurred.Caused by Valve 24MS10 Opening, Causing Dilution of Boron Injection Tank to Below Min Limits.Situation Corrected within Allowed Limits
References
NUDOCS 8106020393
Download: ML18086A586 (3)

LER-1981-009, Forwards LER 81-009/03L-0

Event date:
Report date:
3111981009R00 - NRC Website

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e PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Mr. Boyce H. Grier Director of USNRC May 22, 1981 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 81-09/03L 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 81-09/03L.

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

Sincerely yours,

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/!~c-~µ R. A. Uderit:-2 General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

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

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(:~ *-PS~G Public Service.Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Mr. Boyce H. Grier Director of USNRC May 22, 1981 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 Bl-09/03L 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 Bl-09/03L.

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

Sincerely yours, d~'P R. A. Uderi~z General Manager -

Nuclear Production

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Director, Office of Inspection and Enforcement (30 copies)

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

CC:

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The Energy People 95-2001 {350M! 4-8

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Report Number:

Report Date:

Occurrence Date:

81-09/03L May 22, 19.81 4/23/81 Facility:

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

Boron Injection Tank -

Out of Specification CONDITIONS PRIOR TO OCCURRENCE:

Mode 2 -

Rx Power 0% -

Unit Load -

O MW DESCRIPTION OF OCCURRENCE:

At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> on April 23, 1981, during cooldown operation, valve 24MS10 opened, causing alarm "24 S/G STM. PRESS. 100 PSI LO" to initiate Safety Injection.

This Safety Injection caused an unusual event to be declared at 0358 hour0.00414 days <br />0.0994 hours <br />5.919312e-4 weeks <br />1.36219e-4 months <br />s*and placed the Boron Injection Tank out of specification.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Apparent Equipment Failure -

Inadvertent opening of valve 24MS10.

Investigation of valve 24MS10 could find no apparent reason for its opening.

ANALYSIS OF OCCURRENCE:

The inadvertent opening of valve 24MS10 caused the boron concentration to drop below the minimum of 20,000 ppm in the Boron Injection Tank.

IAW Technical Specification 3.5.4.1 with the Boron Injection Tank inoperable, restore the tank to operable status withine one hour or be in hot standby and borated to a shutdown margin equivalent to 1% ~K/K at 200°F within the next six hours; restore the tank to operable status within the next seven days or be in hot shutdown within the next twelve hours.

CORRECTIVE ACTION

The Boron Injection Tank was borated and the unit was in hot shut-down IAW Technical Specification 3.5.4.1 within allowed limits.

FAILURE DATA:

Not Applicable Prepared by J. J.. Espey Manager~lem ?erating Station SORC Meeting No. 81-41

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