ML13324A673
| ML13324A673 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/02/1985 |
| From: | Medford M SOUTHERN CALIFORNIA EDISON CO. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8507160610 | |
| Download: ML13324A673 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M. 0. MED FORD TELEPHONE MANAGER, NUCLEAR LICENSING (818) 302-1749 July 2, 1985 Director, Office of Nuclear Reactor Regulation Attention:
Mr. J. A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Additional Information Relating to Generic Letter 83-28 San Onofre Nuclear Generating Station Unit 1
Reference:
March 11, 1985 letter from J. A. Zwolinski, NRC, to K. P. Baskin, SCE, regarding Generic Letter 83-28 The referenced letter requested additional information relative to our response to Generic Letter 83-28 Items 2.2.2 and 4.5.3.
Item 2.2.2 requires all nuclear utilities to establish, implement and maintain a continuing program to insure that vendor information is (1) complete, current and controlled throughout the life of their plants, and (2) appropriately referenced or incorporated in plant instructions and procedures. Our response to this item was provided by our letters of November 28, 1983 and May 31, 1984. Our response was based on an industry consensus developed by the Nuclear Utility Task Action Committee (NUTAC) formed through INPO.
The referenced letter indicates that the NRC staff has concluded the NUTAC program fails to address the concern about establishing and maintaining an interface between all safety-related equipment vendors and the utility. (Accordingly, additional information has been requested to address this concern).
The Vendor Equipment Technical Information Program (VETIP) as defined in the March 1984 NUTAC document is considered an adequate resolution to the concerns identified in Item 2.2.2. SCE has implemented the program as described therein.
In regards to Item 4.5.3, it is our understanding that the NRC staff has completed their review of the portions of WCAP-10271 and Supplement 1 relating to Reactor Protection System (RPS) analog channels, and issued their safety evaluation by letter dated in February 21, 1985. Upon completion of the staff's review of the remainder of the WCAP items relating to actuation 8507160610 850702V PDR ADOCK 05000206 P
Mr. 3.
July 2, 1985 logic and reactor trip breakers a plant specific response for San Onofre Unit 1 will be provided. We have received the Westinghouse Owners Group (WOG) guidelines for preparation of submittals requesting revisions to the RPS technical specifications which were transmitted to the NRC by letter dated May 16, 1985. The extent to which the recommendations of WCAP-10271 will be integrated into the testing, maintenance and inspection procedures at San Onofre Unit 1 is currently being evaluated. Subsequent to this evaluation, a Technical Specification change will be prepared utilizing the applicable guidelines established by WOG. It is expected that this change will be submitted to you by September of this year.
If you have any questions or desire additional information, please let me know.
Very truly yours, M. 0. Medford Manager, Nuclear Licensing MT:4345F bcc: (see attached sheet)