ML19317D541

Forwards Guidance Re NRC 760511 Request for Submittal of Proposed Tech Specs for Fire Protection Sys & Intended Date for Meeting Section B of App a, Administrative Procedures, Controls & Fire Brigade. W/O Encl

ML19317D541
Person / Time
Site:	Oconee
Issue date:	09/28/1976
From:	Goller K Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 7912060791
Download: ML19317D541 (2)

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4 SEP 2 8 376 Occket Hos. Sll M dnd 50-287 Duke Power Cot!pany

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ATTH:

• ir. William O. Parker, Jr.

Vice President Steam Production Post Office Box 2178 422 South Church Street Charlotte, north Carolina 28242 Gentlemen:

RE: OCONEE NUCLEAR STATION In our letter dated pay 11, 1976, we reouested that you conouct an examination of your facility to compare its existinq fire protection provisions with the guidelines in the Standard Reviaw Plan 9.5.1, " Fire Protection," dated !ay 1,1975, untch included ? ranch Technical Position APCSB 9.5-1.

Ve are enclosing a cocy of Appendix A to Granch Technical Position APCSB 9.5-1, " Guidelines for Fire Protection For Nuclear Power Plants Docketed Prior to July 1,1976" (Enclosure 1). This doctment presents certain acceptanle alternatives for operating plants to the positions given in APCSB 9.5-1.

We are sending t5is to yce for your information because we will be using Appendix A in our evaluation of your plant.

Af ter reviewing the licensee subnittals made to data in res;mnse to our letter, we believe your initial reseense nay not aceauately cresent tne results of your fire hazards analysis. He stress that in order to begin 1 reevaluation of tbc fire protection progra? of your facility, ycu must Mrfom a fire hazards analysis with the assistance and technical cirstion of a qualified fire protection engineer.

In order for us to evaluate your fire hazards analysis w require that you submit the results in sufficient detail.

To provide further guidance, we are enclosing a copy of "Sucplementary Guidance on Infomation Needed l

For Fire Protection Program Evaluation" (Enclosure 2).

This occueent indicates the type of infomation thet will enable us to evaluate the total fire hazards analysis for your facility.

This type of information

?.ay or may not ce incluced in the cetaileo point-by-noint ecacarison with l

Stanqard Review Plan 3.5.1 ce:encing upon how you cresent that infor-'ations, r~g (f--/d A*w < ' /

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Cuke Power Company SEP 2 81976 In addition, we request at this tirae that ycu pro;ose Technical Specifications for your cresent fire protection systems and inform us of tre date you inteed to.-ect Section u of Apoendix A " Administrative Precedures, Controls and Fire irigade". Your r.resently scheduled snooittal snould incluce tne information indicated by Enclosure 2 and proposed Technical Specifications for the fire protection syste~s of your facility.

Sincerely, Original Signed By Karl R. G 'hr Karl R. Coller, Assistant Directcr for Operatino Scactors Division of Operating Reactors

Enclosures:

1.

Appendix A to Branch Technical DISTRIBUTION Position APCSB 9.5-1 Docket (3) 2.

Supolcmentary Guicanco NRC POR(3)

Local PDR cc w/ encl:

ORB #1 Reading VStello "r. Willian L. Porter TJCarter Ote.e Pcwer Conpsny ASchwencer P. O. Box 2173 SMSheppard 422 South Church Street DNeighbors Charlotto, North Carolina 23242 TWantach OELD

'!r. Trey B. Conner 0I&E(3)

WButler Conner a Knotts DEisenhut 1747 Pennsylvania Avenue, !!. i!.

Washincton, D. C.

20006 VBenaraya TBAbernathy JRBuchanan econce Public Licrary ACRS(16) 201 South Spring Street

'4alnalla, South Carolina.!9631 ORB #1 ORB #1 ORB #1 'I

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TWambach DNeighbors ASchw neer KRGoller k28/h6 hh/76 9_/

/76 9/.2h/76 Form ABC-318 (Re. 9-$3) ABCM 0240

1. u. s. aovanmuswy reentime orriens so?4.sse-see l

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