ML20070C665

Forwards LERs 82-094/03L-1 & 82-103/03L-1.Detailed Event Analyses Submitted

ML20070C665
Person / Time
Site:	San Onofre
Issue date:	11/30/1982
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20070C667	List: ML20070C665
References
NUDOCS 8212140265
Download: ML20070C665 (2)

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Southern California Edison Company S AN ONOFRE NUCLE AR GENER ATING S T A TION y SG f

P.O. Box 12 8 /

5 AN C LEMEN T E. C A LIFOR N! A 92672 H. B. R AY

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0!bN' Yg""3 n te.*oN E November 30, 1982 " ' " ' " "

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

Subject:

Docket No. 50-361 30-Day Follow-Up Reports Licensee Event Reports Nos.82-094 and 82-103 San Onofre Nuclear Generating Station, Unit 2

References:

1) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC),

dated September 7, 1982, "30-Day Interim Report -

Licensee Event Report No.82-094"

2) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC), dated September 23,1982, "30-Day Interim Report - Licensee Event Report No.82-103"

3) Letter, H.B. Ray (SCE) to R.H. Engelken (NRC), dated October 15, 1982, " Interim Follow-Up Reports -

Licensee Event Reports Nos.82-094 and 82-103" This letter provides the follow-up to the referenced interim reports which were made in accordance with Section 6.9.1.13b of Appendix A to Facility Operating License NPF-10. The reported events involve Limiting Condition for Operation (LCO) 3.6.3 and its Action Statement b. Final copies of LER's82-094 and 82-103 are enclosed.

As stated in the referenced reports, an engineering investigation has been performed to determine if problems exist with maintenance and/or adjustments of limit / torque switches. Based on this investigation, it has been determined that present Station Maintenance procedures do not adequately address the setting of limit switches, torque switches and position indicators after equipment maintenance. The instructions conteined in the procedures do not adequately identify specific valve characteristics (i.e., stroke distance, torque settings, etc) on an individual basis, but do so generically.

8212140265 021130 PDR ADOCK 05000361 PDR S IE-AQ 62 47

R.H.Eng21kdn Novemb::r 30,.,1982 -

As corrective action, all procedures dealing with the setting of limit switches, torque switches and position indicators have been reviewed and are currently in the process of revision, if needed,. to reflect individual valve characteristics. All revisions are expected to be completed by March 31,1983.

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

Sincerely,

Enclosures:

LER's82-094, 82-103 cc: A. E. Chaffee (USNRC Resident Inspector, San Onofre Unit 2)

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

Office of Management Information and Program Control Institute of Nuclear Power Operations ,

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