ML20199B191
| ML20199B191 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/09/1986 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20199B196 | List: |
| References | |
| NUDOCS 8606170068 | |
| Download: ML20199B191 (2) | |
Text
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b Northern States Power Company 414 Ncollet Mall Minneapohs. Minnesota 55401 Telephone (612) 330-5500 June 9, 1986 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Fire Protection Safe Shutdown Analysis and Compliance with Section III.G and III.0 of 10 CFR 50, Appendix R
Reference:
(1) Letter dated June 30, 1982 from D M Musolf to the Director of the Nuclear Reactor Regulation entitled " Fire Protection Safe Shutdown Analysis and Compliance with Section III.G of 10 CFR, Part 50, Appendix R, Including Request for Relief" Attached you will find 40 copies of a report entitled, " Fire Protection Safe Shutdown Analysis, Compliance with 10 CFR Part 50, Appendix R, Section III.G and III.O."
This report supersedes our previcus submittal on this issue (Reference 1).
The purpose of this report is to provide for the information of the NRC Staff, a revised Fire Protection Safe Shutdown Analysis for our Prairie Island Nuclear Generating Plant which accurately reflects the current configuration of those features necessary to be in compliance with 10 CFR Part 50, Appendix R.
Included in this report are:
- 1. Description of Necessary Functions and Equipment Required for Placing the Reactors in a Safe Shutdown Condition
- 2. Analysis Comparing the Existing Safe Shutdown Equipment to the Requirements of Appendix R,Section III.G.2
- 3. Modification Completed to Comply with the Requirements of Appendix R, Sections III.G.2 and III.0
- 4. NRC Basis of Approval of Exemptions from Certain Requirements of Appendix R, Sections III.G.2 and III.0 8606170068 860609 h
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4 Dirsctor of NRR Juna 9, 1986 Page 2 Northom States Power Company One item of note which differs from the previously submitted report is that those safe shutdown components in Fire Area 37 which did not have 20 feet of separation have been relocated in meeting other NRC requirements and the exemption approved for this fire area is no longer applicable and therefore not described in this revision.
Any corrections or new information which changes the conclusions drawn by this analysis will be reported in the future through changes to the Prairie Island Updated Safety Analysis Report.
Please contact us if you have any questions related to this submittal or or if we can furnish additional information related to this issue.
w.
David Musolf Manager - Nuclear Support ervices DMM/ TAP /le c: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G Charnoff Attachment 1
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