05000361/LER-1982-155, Forwards LER 82-155/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-155/03L-0.Detailed Event Analysis Submitted

ML20028D913
Person / Time
Site:	San Onofre
Issue date:	01/05/1983
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20028D914	List: 05000361/LER-1982-155, Forwards LER 82-155/03L-0.Detailed Event Analysis Submitted 05000361/LER-1982-155-03, /03L-0:on 821206,two Fire Spray Sys in Cable Spreading Room Declared Inoperable in Order to Repair Leaking Valve.Caused by Minor Leakage Due to Damaged Seating Surfaces of Manual Shutoff Valve SA2301MU121.Valve Replaced
References
NUDOCS 8301200084
Download: ML20028D913 (2)

LER-1982-155, Forwards LER 82-155/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982155R00 - NRC Website

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Southern California Edison Company 003 Jag,g dE [7

S AN ONOFRE NUCLE AR GENER A TING S T A TION P.O. B O X 128 2

SAN CLEMENTE, C ALIFORNI A 92672

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H. B. R AY TELEPHONE January 5,1983

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s U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement

' Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention:

Mr. R. H. Engelken, Regional Administrator

Dear Sir:

Su bject:

Docket No. 50-361 30-Day Report Licensee Event Report No.82-155 San Onofre Nuclear Generating Station, Unit 2 Pursuant to Section 6.9.1.13.b of Appendix A Technical Specification to Operating License NPF-10 for San Onofre Unit 2, this submittal provides the required 30-day written report and copy of Licensee Event Report (LER) for an occurrt..ce involving the fire water spray system.

Limiting Condition for Operation (LCO) 3.7.8.2 requires the fire water spray system to be operable in all modes. On December 6,1982, at 1200, while in Mode 1, two of the four fire water spray systems in the Cable Spreading Room of the Control Building were removed from service to permit repair of a six inch manual shutoff valve, SA230lMU121, which had been observed to be leaking.

In accordance with Action Statement 'a' associated with 1.C0 3.7.8.2, a continuous fire watch was established within one hour and required back-up fire suppression equipment was made availa bl e.

The observed minor leakage was caused by damaged seating surfaces of the valve. The valve was replaced at 2152 on December 6,1982; the fire water spray systems were declared operable and LC0 3.7.8.2 satisfied.

No further corrective action is planned to prevent recurrence of this event as it was an isolated incident.

The enclosed LER 82-155 addresses this event.

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Mr. R. H. Engelken January 5,1983 Public health and safety were not affected.

If there are any questions regarding the above, please contact me.

Sincerely, He 1%/fW%

Enclosure: LER 82-155 cc:

A.E. Chaffee (USNRC Resident Inspector, San Onofre, Units 2 and 3)

R.J. Pate (USNRC Resident Inspector, San Onofre, Units 2 and 3)

U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Office of Management Information and Program Control (MIPC)

Institute of Nuclear Power Operations (INP0) f b