05000311/LER-1981-051, Forwards LER 81-051/03L-0.Detailed Event Analysis Encl

Forwards LER 81-051/03L-0.Detailed Event Analysis Encl

ML20030B197
Person / Time
Site:	Salem
Issue date:	07/27/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20030B198	List: 05000311/LER-1981-051, Forwards LER 81-051/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-051-03, /03L-0:on 810627,steam Generator 22 Tripped.Safety Injection Caused Dilution of Boron Injection Tank.Tank Was Borated Until Concentration within Allowable Limits
References
NUDOCS 8108060216
Download: ML20030B197 (3)

LER-1981-051, Forwards LER 81-051/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3111981051R00 - NRC Website

text

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GEL 0 PSEG Public Service Electric and Gas Company 80 Park Plata Newark, N.J. 07101 Phone 201/430-7000 July 27, 1981 t\\

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Mr. Boyce H. Grier AUG 05198W hi Director of USNRC iE, Office of Inspection and Enforcement i

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King of Prussia, Pennsylvania 19406 Q(f

Dear Mr. Grier:

LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-51/03L Pursuant to the requirements of Salem Generating Station Unit No. 2 Technical Specifications, Section 6.9.1.9.b, we are submitting Licensee Event Report for Reportable Occurrence 81-51/03L.

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

Sincerely yours, bfCbuk R. A.

Uderit General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

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

$[ /l 8108060216 610727 PDR ADOCK 05000311 S

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The Energy People 95 2001 (400NI) 181

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Report Number:

81-51/03L Report Date:

- July 27, 1981 Occurrence Date:

6-27-81 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.

This report was initiated by Incident Report 81-221.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 30% - Unit Load 260 MWe DESCRIPTION OF OCCURRENCE:

At 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br /> on June 27, 1981, No. 22 steam generator feed pump tripped, causing a low low level in No. 22 steam generator, which tripped the reactor at 0404 hours0.00468 days <br />0.112 hours <br />6.679894e-4 weeks <br />1.53722e-4 months <br />.

At 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br /> a safety injection occurred due to low Tavg on 3 of 4 loops in coincidence with high steam flow on Nos. 21 and 23 steam generators, causing the boron injection tank concentration to decrease to less than 20,000 ppm of boron.

Action statement 3.5.4.1.b was entered at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />, June 27, 1981.

This constituted operation in a degraded mode in accordance with technical specification 6.9.1.9.b.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The boron concentration in the boron injection tank was diluted to less than 20,000 ppm boron due to initiation of safety injection.

ANALYSIS OF OCCURRENCE:

Technical specification 3.5.4.1 requires:

With the boron injection tank inoperable, restore the tank to operable status within one hour or be in hot standby and borated to shutdown margin equivalent to 1% Ak/k at 200*F within the next six ho,urs; restore the tank to operable status within the next 7 days or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

'LER 81-51/03L July 27, 1981

CORRECTIVE ACTION

The boron injection tank war borated to between 20,000 and 22,500 ppm boron from the boric acid storage tank.

Action statement 3.5.4.1.b was terminated at 1622 hours0.0188 days <br />0.451 hours <br />0.00268 weeks <br />6.17171e-4 months <br />, June 27, 1981.

FAILURE DATA:

Not Applicable Prepared By F.

Dickey

AM Manag6r - Salem Generating Station SORC Meeting No.

81-68 l

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