ML19254F946

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Confirms 791017 Request for Cooperation Re NRC Study of Electrical Design Adequacy of B&W NSSS Utilizing once-through Steam Generators
ML19254F946
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 11/02/1979
From: Reid R
Office of Nuclear Reactor Regulation
To: Moore G
FLORIDA POWER CORP.
References
NUDOCS 7911190494
Download: ML19254F946 (2)


Text

{{#Wiki_filter:f '/DC ~., 0, UNITED STATES y$.., j NUCLEAR REGULATORY COMMISSION ,.i h l WASHWGTON, D. C. 20555 %%,/ November 2, 1979 Docket No. 50-302 Mr. George C. Moore Assistant Vice President - Power Production Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733

Dear Mr. Moore:

On October 17, 1979, Mr. Saul Levine, Mr. Denwood Ross and Mr. Morton Fairtile of the NRC staff contacted you by telephone to discuss the Commission's concern about the design adequacy of Babcock and Wilcox (B&W) Nuclear Steam Supply Systems (NSSS) utilizing once-through steam generators and to solicit Florida Power Corporation's cooperat'on in a study by the NRC Office of Nuclear Regulatory Research of this concern. You expressed a desire to cooperate with the staff in this study, but requested that we prepare this letter to you to formalize our request and to provide more details about the study. We wish to thank you for your cooperation. We plan to send people to the Crystal River Station during the second week in November. They will be at the station for about one month. There will be a maximum of eight NRC or NRC contractor people at the station. Mr. Francis H. Rowsome, Acting Direc^ tor of the Probabilistic Analysis Staff will be the NRC contact for logistics support at the station for these people. His phone number is (301) 492-8393. To support this study we will request, in the near future, certain piping and instrument drawings, electrical layouts, logic drawings and so forth to be sent to our Bethesda, l'aryland offices. Mr. Fairtile, the Crystal River Operating Reactor Project Manager will contact your staff regarding specific needs for drawings'. We estimate this study to be completed in about six months. Crystal River Unit No. 3 was selected as we believe it most closely represents an operating B&W NSSS type of plant. We will rely on B&W for required data specific to the NSSS, which is common to all operating B&W plants. In order to permit verification of engineering and procedural details, we need our analysts to be located at or near the station to have access to as-built drawings, the plant operations staff and procedures so that generation of our fault trees and event trees can proceed in a rapid and accurate manner. Sincerely, d Robert W. Reid, Chief l3bk )bl Operating Reactors Branch #4 Division of Operating Reactors

s Ficrica ?;<eer Corporation cc: f tr. S. A. Brandimore Vice President and General Counsel ~ P. O. Box 14042 St. Petersburg, Florida 33733 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Crystal River Public Library Crystal; River, Florida 32629 Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 0 E -k e '?E % *. C. -hh ' E .'- E j Y e e 1344 162

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