ML19317G501
| ML19317G501 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/30/1976 |
| From: | Boyd R Office of Nuclear Reactor Regulation |
| To: | Rodgers J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8003180787 | |
| Download: ML19317G501 (3) | |
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SEP 3 01976 Dockac No. 50-302 T1orida Power Corporacion ATTN: Mr. J. T. Rodgers Assistant Vice President and Nuclear Probec Manager W 0. Box'14042 Sc. Petersburg, Florida 33733 Gentl'emen:
FIRE PROTECTION EVALUATION By my letter dated May 3,1976, you were sent a copy of revised Standard Review Plan Section 9.5.1, " Fire Protection," dated May 1, 1976. This revised SRP 9.5.1 contained new guide: lines for the NRC staff evaluations of fire protection in our review of nuclear power plant construction pennit applications. docketed after July 1,1976.
The letter stated (1) that to the extent reasonalle and practicable the guidelines in the revised SRP 9.5.1,will be used by the staff in evaluating fire protection provisions of operating plants, appli-cations currently under review for construction permits and operating licenses, and future applications for operating licenses for plants now under construction; and (2) that you would be kept informed of our progress as we developed more definitive criteria or acceptable alternatives for the application of the SRP 9.5.1 guidelines to the review of these plants.
l is Appendix A to Branch Technical Positiert APCSB 9.5-1,
" Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1,.1976,".which gives alternative guidance and criteria acceptable to the staff to be utilized in a. re-evaluation of the-fire protection provisions of the Crystal :d.ver Unic 3.
We request that' you conduct a re-evaluation of the fire protection program of your nuclear power plant and compare, in detail, the fire protection provisions currently _ proposed for your facility (ies) witti the guidelines in Appendix A to Branch Technical Position APCSB 9.5-1.
. In_ order to begin such a re-evaluation, it is necessary that you per-form a fire hazards analysis of your facility with the assistance
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SEP a 01976 and;the technical direction from a qualified fire protection engineer.
-In order for us to evaluate'your fire hazards analysis, we require
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that you submit the results of your fire hazards analysis -in the form described in Enclosure 2, " Supplementary Guidance on Infonnation Needed for Fire Protection Program Evaluation."
Your-re-evaluation should:
1.
Identify the guidelines in Appendix A which are presently met and' discuss _how this is done;_
.;. ~~ Identify the guidelines-forThich modificat'ibns, procedural changes, or' enhanced training of personnel are underway or planned,such that the guidelines will be met, and the date you intend to meet Section B of Appendix A, " Administrative
. Procedures, Controls and Fire Brigade;"
3.
Indicate which of the guidelines you do not now meet or'do not intend to meet in the future. For such items, you should pro-vide a basis for your position; and 4.
Provide proposed revisions to the Technical Specifications in 1
the area of-fire protection systems.
Please' respond within 20 days of receipt of thi.s letter to inform us when you will submit thc requested information, forty (40) copies of which will be required for staff review.-
- This request,for generic information was approved by GA0 under a blanket clearance number B-180225~(R0072). This clearance expires July 31 ~ 1977.
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Sincerely, oger G. B d, Director Division of Project Manigen. -.
Office-of Nuclear Reactor Regulatiori
Enclosures:
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Appendix A'to Branch Technic'l Position APCSS 9.5-1 2.
"Suoplementary Guidance on Infonnation Needed for Fire
$ Protection Program Evaluation" cc: See:next page.
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a cc: Mr. S. A. Brandimore Vice President and General Counsel P. O. Box 14042 St. Petersburg, Florida 33733 S
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