ML20072M809
| ML20072M809 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/22/1983 |
| From: | Ray H SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 83-134, RO-83-022, RO-83-22, NUDOCS 8304010377 | |
| Download: ML20072M809 (2) | |
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S AN ONOFRE NUCLE AR GENER A TING ST A TION P.O. B O M 128 S AN C LEMENT E. C A LIFOR NI A 92672
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m, H. B. R AY YELEPHONE STCITION M AN AGER (7343492 7700 U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region v 1450 Maria ~ Lane, suite 210 Walnut Creek, California 94595-5368 Attention:
Mr.
R.
H.
Engelken, Regional Administrator
Dear Sir:
Subject:
Docket No. 50-361 Prompt Report Licensee Event Report 83-022 San Onofre Nuclear Generating Station, Unit 2 Pursuant to Section 6.S.1.12.i of Appendix A Technical Specifications to Facility Operating License NPF-10 for San Onofre Unit 2, this submittal provides the written confirmation of our March 21, 1983 prompt notificaton to the NRC of a reportable occurrence involving the Component Cooling Water (CCW) System.
Westinghouse Electric Corporation by letter SCE-83-508 dated January 21, 1983 identified an issue of potential safety concern involving valve position indication for certain Westinghouse nanufactured gate valves.
Specifically, the valves indicate
" closed" prior to the valve disc fully isolating flow.
A rev;.ew of the Unit 2 and Unit 3 designs revealed that two such valves are installed in the Unit 2 CCW System.
These valves, 2HV6227 and 2HV6229, route component cooling water to CCW pump 2PO25 (the swing pump), from either CCW Train A or Train B and isolate the other train. An evaluation of the effect of the potentially erroneous position indication of these valves on system performance was concluded on March 21, 1983.
It was concluded that since these valves are used in a safety related application that requires positive indication of valve position and the valves do not have redundant indication, corrective action (a modification) and a prompt report pursuant to the above-identified Technical Specification, were required.
Until this modification is performed the valves will be manually seated by use of the handwheels and verified closed by administrative control.
8304010377 830322 EM PDR ADOCK 05000361 S
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Mr. R. H. Engelken March 22, 1983 A 14-day follow-up report with a copy of Licensee Event Report (LER) No.82-022 will be submitted by April 4, 1983 to address this event.
'If there are any questions, please contact me.
Sincerely, A'
?
cc:
A. E. Chaffee (USNRC Resident Inspector, Units 2 & 3)
R. J. Pate (USNRC Resident Inspector, Units 2 & 3) 1 i
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