ML20062H499
| ML20062H499 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/30/1982 |
| From: | Baskin K SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-SSINS-6820 IEB-81-02, IEB-81-2, NUDOCS 8208160072 | |
| Download: ML20062H499 (2) | |
Text
"'
Bulletin Reply 81-02
-o Docket Nos. 50-361/362
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- Cn Southern California Edison Company fE 7.,,
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k TELEPHONE July 30,1982
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mn mm SAFE F Y, AND LICE NSING U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Attention:
Mr. R. H. Engelken, Director Gentlemen:
Subject:
IE Bulletin 81-02, Supplement No.1 Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3
Reference:
A.
Letter, SCE to NRC dated July 7,1981, subject:
Letter, SCE to NRC dated November 13, 1981, same subject Contrary to the request contained in the subject bulletin, SCE's earlier response to this bulletin (Reference B) was inadvertently not signed under oath or affirmation.
Hence, the information is reiterated below (with a modification status update) and signed appropriately.
IE Bulletin 81-02 requested that construction permit holders review their facilities design and ascertain whether any of the valves specifically identified within the bulletin (all 3 or 4 inches in size) were used in safety related systems or as PORV block valves. The Reference A letter provided the SCE response, indicated that two of the subject valves were utilized at San Onofre Units 2 and 3, and stated that the recommended corrective action had been completed.
Subsequently, the NRC issued the subject supplement to Bulletin 81-02 which expanded the scope of suspect Westinghouse EMD gate valves to include valves 6 to 18 inches in size, and requested CP holders to determine the extent of use of these valves in safety related systems.
Upon investigation, SCE has determined that none of the subject valves have been I
installed in safety related systems.
However, three of the subject valves are l
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F208160072 820730 PDR ADOCK 05000361 0
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- s Mr. R. H. Engelken, Director July 30,1982 maintained as spares and could ultimately be installed in a safety related capacity. Therefore, SCE instructed the S023 A/E to have the valve vendor provide for the necessary actuator modifications so the valves will meet the specified service requirements.
The valves were subsequently returned to the vendor where the appropriate modifications are currently being completed.
However, the suspect valves remain under control of established SCE Non-Conformance Control Procedures to ensure they are not utilized until those modifications have been effected.
J Should you have any questions or require additional clarification, please contact me.
Subscribed on this 30thday of July
, 1982.
Very truly yours, By
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K.~ P. Baskin Manager of Nuclear Engineering, Safety, and Licensing Subscribed and sworn to before me o
this # 4 day of (p/ /.
, 1982 j
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AGNES CRABTREE
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- yyfyy, NGTARY FURtC CALIFDWNIA Notagy Public ;n and for the County i
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gg of Los Angeles, State of California 77;;__
cc: Director, Office of Inspection and Enforcement, NRC Washington, D.C.
20555 A. Chaffee, USNRC Site Inspector, S023