05000361/LER-1982-042, Forwards LER 82-042/01T-0.Detailed Event Analysis Submitted

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Forwards LER 82-042/01T-0.Detailed Event Analysis Submitted
ML20062M939
Person / Time
Site: San Onofre Southern California Edison icon.png
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
ML20062M941 List:
References
NUDOCS 8208200251
Download: ML20062M939 (2)


LER-2082-042, Forwards LER 82-042/01T-0.Detailed Event Analysis Submitted
Event date:
Report date:
3612082042R00 - NRC Website

text

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4 ee ffED Southern California Edison CompaNj? !m p

$AN ONOFRE NUCLE AR CENER A TING S T A TION SW p o. som taa 3 %N C LEMENTE. C A LIFORNI A 92672 *yr ,

H. B. R AY ' ELE'"Oht

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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 14-day Follow Up Report Licensee Event Report No.82-042 San Onofre Nuclear Generating Station, Unit 2

Reference:

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

Prompt Report dated August 3, 1982 On August 4,1982 the referenced letter was telecopied to the Region V office to confirm the prompt notification by telephone on August 3, 1982 of a reportable occurrence involving the Auxiliary Feedwater System l (AFWS).

Pursuant to Appendix A Technical Specification 6.9.1.12b to Operating License NPF-10 for San Onof re Unit 2, this submittal provides the required follow-up report and completed Licensee Event Report (LER) for this occurrence.

On August 3, 1982 while in Mode 3, engineering review of' data generated on July 21 and July 29, 1982, during operability checks of valves within

( the AFWS, indicated valve stroke times apparently in excess of those which would be consistent with the system response times prescribed in Table 3.3-5, item 9, of the Technical Specifications. Consequently, two l trains of the AFWS were declared inoperable, and plant cool down was

-initiated in accordance with Action Statement 3.7.1.2b'.

i l pgangio gg, e .m - gg

l pe I Mr. R. H. Engelken August 12, 1982 The data gathered on July 21 and 29, 1982 was documented in Station Procedure S023-3-3.30, Revision 1, which prescribes the requirements for quarterly test of these and other valves as part of the valve inservice inspection Program. Sta tion Procedure S023-3-3.30 did not include response time acceptance criteris as specified in the Technical Specifications as do Station Procedures S023-11-3.1, 3.2, 3.3 and 3.4 which dro typically utilized to document response time testing in accordance with the Technical Specifications. On August 3, 1982, when based on review of completed tests documented on Station Procedure S023-3-3.30, it became apparent that observed valve streke times were not consistent with the system response times prescribed in Table 3.3-5, item 9, a prompt notification was made to the NRC as stated in the referenced letter. Acceptable system response times had previously been demonstrated, as was indicated in the referenced letter.

Our further review of this matter has led to the possibility that the valve response times determined on July 21 and 29, 1982 and documented on Station Procedure SO23-3-3.30 may have been consistent with the system response times prescribed in the Technical Specifications since the measured stroke time was based on a stroke distance of 24" 21" whereas the valve manuf acturer's specification calls for a valve stroke distance of If" for it to be fully open.

The limit switches were reset and the valve stroke times ratested satisfactorily. The ISI test procedure for valves S023-V-3.50, and the Operator Survel l iance Test S023-3-3.30, have been revised to include acceptance criteria for valve stroke times ccasistent with Technical Specification Table 3.3-5. No additional corrective measures are required. LER 82-042 addresses this event and is enclosed.

I f thera are any questions concerning the above. please contact me.

SincereIy, H%y l1Yu%

Enclosure:

LER 82-042 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 Office of Management Information and Program Control Institute of Nuclear Power Operations