ML20028B366
| ML20028B366 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/13/1982 |
| From: | Kingsley O ALABAMA POWER CO., WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| OG-81, NUDOCS 8211300324 | |
| Download: ML20028B366 (3) | |
Text
e Alabama Power Company 600 North 18th Street Post Office Box 26J1 Birmmgham, Alabama 35291 Telephone 205 250-1000 L
AlabamaPower the southem emctrc system November 23, 1982
- 0G-81 Dr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014
Dear Dr. Denton:
Westinghouse Owners Group Program to Optimize Plant Standard Technical Specifications I wish to confirm our meeting on Tuesday, December 14, 1982, the purpose of which is to present a sumary description of the current Westinghouse Owners Group (WOG) program to revise the Standard Technical Specifica-tions (STS). Our intention is to give you an overview of the program's objectives and the methodology being employed to provide a basis for eventual STS revision.
As you know from prior Westinghouse presentations to your staff, the STS optimization program was originally conceived to address industry con-cerns about the current technical specifications and their impact on plant operation and safety. Historically, compliance with high frequency surveillance requirements, for example, has resulted in many spurious system transients and challenges to the plant protection systems as-well as having a significant effect on manpower availability, exposure and equipment reliability.
It is also evident that allowable equipment outage times are somewhat arbitrary and inconsistent with system needs.
To address this concern, the WOG program will consist of a failure proba-bility analysis utilizing fault trees and component failure probabilities to determine equipment sensitivity to surveillance intervals, duration of repair / test outages and coincident logic levels; sensitivity to various equipment design and implementation schemes will also be assessed.
The data used will be taken from the existing Westir.@ouse Reliability Data Bank supplemented, as necessary, with operational data from WOG y60 /
member plants. The result will be recommended changes to the Generic Standard Technical Specification.D D'-
- y. nedW 8211300324 821113 PDR ADOCK 05000364 P
PDR
0G-81 Dr. Harold R. Denton November 23, 1982 Because of its potential for substantive improvement in plant safety and availability, and system reliability, we believe this program to . b2 sufficiently worthwhile to request, through this sumary session, your support and that of your staff. As you may know, we have arranged a subsequent and more detailed working session with NRC staff repre-sentatives through Mr. Brinkman for December 21. At that session we will present the preliminary results of our sensitivity studies on the reactor trip system. Given proper feedback, we then plan to embark on a program of more exhaustive scope which will address the potential for relaxation of current requirements for the Reactor Protection syst".m and ESF instrumentation. Accompanying me for this discussion will be Mr. Skip Copp, Duke Power Company, who is chairman of the Westinghouse Owners Group committee working on this program and Messrs. Pres Rahe and Dan Call of the Westinghouse Nuclear Safety Department and Mr. Rick Muench, also of W:stinghouse, who is the Project Manager for the Westinghouse Owners Group activities. I have attached a proposed agenda for our meeting for your reference. Thank you for your cooperation. I am looking forward to our meeting. Very truly yours, O. D. Kingsle, ., Chairman Westinghouse Owners Group /pab Attachment cc: E. P. Rahe D. W. Call R. A. Muench R. L. Jansen G. A. Copp E. Brinkman D. Eisenhut
e a:>, AGEN0A e INTRODUCTION - MESSRS. KINGSLEY AND RAHE HISTORICAL ACCOUNT OF INSTRUMENTATION TESTING & MAINTENANCE o - MAGNITUDE OF CURRENT TESTING / MAINTENANCE PRACTICE - EQUIPMENT IMPLICATION OF TESTING / MAINTENANCE - OPERATION IMPLICATION OF TESTING / MAINTENANCE e TECHNICAL SPECIFICATION REVISION PROGRAM - PURPOSE - QUANTITATIVE ANALYSIS OF REACTOR PROTECTION RELIABILITY - RECOMMENDATIONS FOR TECHNICAL SPECIFICATION REVIEW BENEFITS TO BE REALIZED BY REVISION OF TECHNICAL SPECIFICATION e f ,}}