05000361/LER-1982-069, Forwards LER 82-069/03L-0.Detailed Event Analysis Submitted

Forwards LER 82-069/03L-0.Detailed Event Analysis Submitted

ML20062M572
Person / Time
Site:	San Onofre
Issue date:	08/12/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20062M575	List: 05000361/LER-1982-069, Forwards LER 82-069/03L-0.Detailed Event Analysis Submitted 05000361/LER-1982-069-03, /03L-0:on 820713,while in Mode 4,containment Isolation Valve Declared Inoperable Due to Failure to Meet Surveillance Tech Spec.Caused by Loosening of Limit Switch Due to Vibration.Switch Adjusted & Tightened
References
NUDOCS 8208200145
Download: ML20062M572 (2)

LER-1982-069, Forwards LER 82-069/03L-0.Detailed Event Analysis Submitted

Event date:
Report date:
3611982069R00 - NRC Website

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09"Ga Southern California Edison Company

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S AN ONOFRE NUCLE A R GFNER A TING ST A TION P.O. B O M 128 S A N C L EMEN T E. C A LIFORNf A 92672 H. 8. R AY vrtepwagt uanoN = ANAara August 12, 1982 U. S. Nuclear Regulatory Commission Of fice 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:

Subject:

Docket No. 50-361 30-day Report Licensee Event Report No.82-069 San Onofre Nuclear Generating Station, Unit'2 This submittal is in accordance with the reporting requirements of Section 6.9.1.13b of Appendix A to Facility Operating License NPF-10.

It describes a reportable condition involving Limiting Condition for Operation (LCO) 3.6.3 associated with containment isolation valves.

While in-Mode 4, at 0200 on July 13, 1982,- the quarterly inservice valve testing in accordance with procedure S023-3-3.30 was in progress.

Due to f ailure to meet the rcquired full stroke (open position indication) test in accordance with Technical Specification 4.6.3.3, containment isolation valve 2HV-7805 was declared inoperable. This valve isolates Radiation Monitor RT 7807. As required by the associated Action Statement, the redundant valve 2HV-7810 was maintained operable and the

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penetration isolated by securing 2HV-7805 in the closed position.

Subsequent investigation revealed that the trouble was loosening of the limit switch presumably due to vibration. After adjusting the limit-switch, the valve was declared operable in accordance with S023-3-3.30 at 2020 on July 13, 1982. This event was an isolated occ'Jrrence and further corrective action is not deemed necessary. However, the Independent Safety Er]Ineering Group (ISEG) will monitor this type of limit switch to determine if a irend develops, resulting in further action. Maintenance personnel have also been informed by ISEG to verify that these switches are properly tightened af ter each adjustment.

42 8208200145 820812

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PDR ADOCK 05000361 S

PDR

R. H. Engel ken August 12, 1982 The redundant monitor remained operable throughout the event, therefore plant operation and safety were not affected, if there are any questions regarding the above, please contact me.

Sincerely, HfA

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Enclosure:

LER 82-069 cc:

A. E. Chaf fee (USNRC Resident inspector, San Onof re Unit 2)

U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Of fice of Management Information and Program Control Institute of Nuclear Power Operations