ML19313A261

Forwards Rept Farley Nuclear Plant Fire Protection Program Reevaluation in Response to 760930 Request.Present Fire Protection Sys Design Has Undergone Extensive NRC Review During OL Review Stage & Found Acceptable

ML19313A261
Person / Time
Site:	Farley
Issue date:	09/15/1977
From:	Clayton F ALABAMA POWER CO.
To:	Boyd R Office of Nuclear Reactor Regulation
References
TAC-8671, NUDOCS 8712220036
Download: ML19313A261 (2)

Text

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C Alabama Power Company .

600 North 18th Street l 1

Pcst(fee Box 2341

- Birmingnam, Alabama 35291 - ]

Tetec*ione 20E 323-5341 j

acwma AlabamaPower j Senior %ce P esident the Southem eteCinC SYStem i

i September 15, 1977 i Docket Nos. 50-348 and~50-364 [,(,.

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aus s.ww A Mr. Roger S. Boyd, Director Division of Project Management

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U. S. Nuclear Regulatory Commission ,

Washington, D. C. 20555 -

JOSEPH M. FARLEY NUCIIAR PLANT .

FIRE PROTECTION PROGRAM REEVALUATION

Dear Mr. Boyd:

In your letter of September 30, 1976 you requested that the'existing I fire protection provisions currently proposed at the Joseph M. Farley Nuclear Plant, Units 1 and 2, be reevaluated and compared with the guide-lines in Appendix A to Branch Technical Position APCSB 9.5-1. Specific information necessary for NRC staff evaluation was also identified in your j

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letter.

In our letter of November 8,1976 we advised you that Alabama Power Company had initiated a reevaluation of the fire protection provisions of the Farley Nuclear Plant and that when this reevaluation was completed a report would be submitted to the NRC. Please find enclosed forty (40) copies of the report entitled "Farley Nuclear Plant Fire Protection Program

• Reevaluation" which responds to the information requested in your September ,

30, 1976 letter.

The present fire protection system design of Farley Nuclear Plant has i undergone extensive review by the NRC during the Operating License review stage and found to be acceptable. It is our position that the present fire  :

protection system design provides adequate means to protect the health and  !

safety of the public. However, this report identifies some proposed design ,

modifications which, in our opinion, would allow the design of the plant to e

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Page Two i Mr. Roger S. Boyd l September 15, 1977 l 1

I meet the intent of the guidelines in Appendix A to Branch Technical Position APCSB 9.5-1. Detail design of the proposed modifications vill be initiated when the report has been reviewed and approved by the NRC staff.

Should you have any questions, please advise.

1 1

Yours truly, F. L. Clay n, Jr. 1 FLCjr/JRC:peg Enclosure cc: Mr. R. A. Thomas Mr. G. F. Trowbridge 3

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