ML19290C070
| ML19290C070 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/27/1979 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| REF-GTECI-A-24, REF-GTECI-IS, TASK-A-24, TASK-OR NUDOCS 8001090118 | |
| Download: ML19290C070 (2) | |
Text
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DCrutchfield VStello Vice President, Nuclear Projects RSBoyd RSatterfield Arizona Nuclear Power Project DFRoss P. O. Box 21666 DBVassallo Phoenix, Arizona 85036 RLBaer DTibbitts
Dear P.r Van Brunt:
JLee (w/cy of incoming) t Your letter to me dated February 23, 1979 was one of several letters that I recently received concerning Combustion Engineering, Inc. topical report,
" Qualification of Class IE Instrumentation" (CENPD-255). Yuur letter, as well as the others, expressed the concern that our review of this topical report would not be performed on a schedule ccmpatible with Combustion Engineering's equipent qualification programs.
In addition, your letter requested the status of your August 28, 1978 submittal of inforcation on the qualification of balance-of-plant equipment.
In response to ycur con-cern, I would like to discuss (1) our overall plan for reviewing the imple-mentation of Institute of Electrical and Electronics Engineers (IEEE) Stan-dard 323-1974, " Qualifying Class IE Equipnent of fiuclear Fower Cenerating Stations," (2) how we intend to proceed in our review of CEhPD-255, and (3) the status of your August 29, 1978 subraittal.
Recognizing that IEEE Standard 323-1974 represented a departure from the previous standard on equipment qualification, the staff developed Task Action Plan A-24, " Qualification of Class IE Safety-Related Equipment" to handle the generic aspects of the implementation of this standard.
The purpose of this plan was to review and evaluate qualification rethods, test plans, and test procedures for Class IE equipment presented in vendors' topical reports. The review of the topical reports was to be followd with an audit of qualification reports during the operating license review of each application.
1730 336 Cur progress to date on Task Action Plan A-24 has been limited. Topical reports have been received from three nuclear steam supply system vendors, Westinghouse, Combustion Engineering. ard Babcock & nilcox. The Babcock &
Wilcox report was not received until just recently, February 1,1979.
The first topical report that we~ reviewed was WCAP-8537, "Vethodology for Qualifying Westinghouse PWR-SD Provided NSSS Safety Related Equipment."
This report was reviewed first because the first operating license appli-cation that requires implementation of IEEE Standard 323-1974 enploys a Westinghouse nuclear steam supply systera. Our review of WCAP-8587 has lead us to conclude that we will not be able to write a generic evalua-tion of a qualification topical until we have reviewed detailed informatien on the implementation of the methodology on applications which reference WCAP-8587. Therefore, for the first several plants that reference that topical report, we plan to eview in detail the rethods used to cualify or.ic s >
,unaams >
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hr. E. E. Van Brunt, Jr. MAR 2 71979
- e expect that as a result of the equiprient on a plant specific basis.
r our plant specific reviews, we will require mocifications to the topical report. When adequate information has been incorporated into WCAP-8587 as a result of these plant reviews, we will issue a safety evaluation.
In concert with the acceptance review of the CESSAR System 80 final design approval submittal, the staff has completed a preliminary review of CENPD-255. The staff has found the discussion of qualification methodology to be much too general to support a detailed review. This matter was discussed with Combustion Engineering in a meeting on the CESSAR System 80 design on February 12, 1979. Subsequently, Combustion Engineering indicated that they are revising CENPD-255 and that a revision containing a portion of the information we require will be completed in July 1979.
We expect that they will submit the revised report shortly thereafter. As soon as we receive the report and have detemined that sufficient infor-mation has been provided for us to initiate our review we will develop a review schedule. We will continue to keep you informed by sending you notices of meetings and meeting surnaries dealing with this topical report.
Your August 28, 1978 submittal was in response to our gene:-ic letter dated September 14, 1977 to you on environmental qualification of balance-of-plant electrical components. To date, this information has not been reviewed and there are no plans to perform this review until the submittal of the Final Safety Analysis Report for the Palo Verde Nuclear Cenerating Station, Units 1, 2 and 3.
However, if members of your technical staff have any particular questions regarding environmental qualification, a meeting can be arranged to discuss these questions.
I trust you will find this information useful.
1730 337 Sincerely, Gr5.-r--d by H. 7 Mn Harold R. Denton, Director Offi e f Nu le r Reactor Regulation T
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