05000311/LER-1981-084, Forwards LER 81-084/03L-0.Detailed Event Analysis Encl

Forwards LER 81-084/03L-0.Detailed Event Analysis Encl

ML20010F270
Person / Time
Site:	Salem
Issue date:	08/28/1981
From:	Midura H Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20010F271	List: 05000311/LER-1981-084, Forwards LER 81-084/03L-0.Detailed Event Analysis Encl 05000311/LER-1981-084-03, /03L-0:on 810810,leak Rate Calculation Indicated RCS Leak to Reactor Coolant Drain Tank.Caused by Packing Leakage on Valve 22RC20.Valve Repacked & Leak Rate Reduced
References
NUDOCS 8109090548
Download: ML20010F270 (3)

LER-1981-084, Forwards LER 81-084/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3111981084R00 - NRC Website

text

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vf A g >ggg o-Public Service tilectric and Gas Cornpany P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 28, 1981 Mr. Boyce !!. Grier k'

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4 Director of USNRC j

g' Office of Inspection and Enforcement J

Region 1 o-SEP 0 81981 m-T 631 Park Avenue

] uma King of Prussia, Pennsylvania 19406 7

Dear Mr. Grier:

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'}l lTN LICENSE NO. DPR-75 DOCKET NO. 50-311 REPORTABLE OCCURRENCE 81-84/03L 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 81-84/03L.

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

Sincerely yours, j.

b lcebtA U II. J. Midura Manager -

Salem Generating Station l

CC:

R. A.

Uderitz General Manager - Nuclear Production Director, Office of Inspection and Enforcement (30 copies)

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

'810 9095N '

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The Energy People

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Report Number:

81-84/03L Report Date:

8-28-81 Occurrence Date:

8-10-81 Facility:

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

Identified Reactor Coolant System Leakage - Greater Than 10 GPM This report is initiated by Incident Report 81-319.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 - Rx Power 70% - Unit Load 730 MWe DESCRIPTION OF OCCURRENCE:

At approximately 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br />, August 10, 1981, a leak rate calculation indicated a Reactor Coolant System leak rate of 11.6 gpm to the reactor coolant drain tank.

An unusual event was declared in accordance with EPI-1.

At 0238 hours0.00275 days <br />0.0661 hours <br />3.935185e-4 weeks <br />9.0559e-5 months <br /> a shutdown was commenced at the rate of 1% per minute, and action statement 3.4.7.2.b was entered.

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

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

The source of the Reactor Coolant System leakage was packing leakage on valve 22RC20.

ANALYSIS OF OCCURRENCE:

Technical specification 3.4.7.2.b requires:

With any identified Reactor Coolant System leakage greater than 10 gpm, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

CORRECTIVE ACTION

The plant was taken off the line at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> and was in mode 3 at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />.

Valve 22RC20 was repccked, and the leak rate was reduced to within specification.

At 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, August 10, 1981, action state-ment 3.4.7.2.b was terminated.

LER'81-84/03L' 2-I FAILURE DATA:

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!l-Prepared By F.

Dickey

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Manager - Salem Generating Station SORC Meeting No.

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