ML20058L362

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Forwards Comparison of Existing Fire Protection Provisions to Guidelines Contained in SRP 9.5.1
ML20058L362
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/10/1976
From: Mayer L
NORTHERN STATES POWER CO.
To: Stello V
Office of Nuclear Reactor Regulation
Shared Package
ML20058L365 List:
References
NUDOCS 9105160398
Download: ML20058L362 (3)


Text

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NORTHERN STATES POWER COMPANY M IN N E A PO LI S. M IN N E SOTA S S401

\ 4 December 10, 1976

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-2 Mr Victor Stello, Director 8- D E C i s ISl>f , ,,

Division of Operating Reactors % ,~, '?fy ,

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' O[g yO 076 ig, U S Nuclear Regulatory Comission$ a'a'i w *" ' -

"' g Washington, DC 20555 .

Dear Mr Stello:

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MONTICELLO NUCLEAR GENERATING PIANT Docket No. 50-263 License No. DPR-22 Comparison of Existing Fire Protection Provisions to the Guideliner Contained in Standard Review Plan 9.5.1 Your letter of May 11, 1976 requested that we ccxnpare the existing fire pro-tection provisions at the Monticello Nuclear Generating Plant with the recom-mendations contained in Standard Review Plan 9.5.1, " Fire Protection System",

and its companion document Branch Technical Position APCSB 9.5-1, " Guidelines for Fire Protection for Nuclear Power Plants". Appendix A to Branch Technical Position APCSB 9.5-1, " Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1,1976", was forwarded to us in a letter dated September 30, 1976 from Mr K R Goller, Assistant Director for Operating Reactors, USNRC.

Appendix A to APCSB 9.5-1 contained a small number of acceptable alternatives to the recommendations contained in APCSB 9.5-1 which operating plants could employ.

A preliminary comparison of the Monticello plant to the recomendations con-tained in Standard Review Plan 9.5.1 and Appendix A to APCSB 9.5-1 has been completed. The results of this comparison are provided in the attached table which contains the following information.

a. ESP assigned recomendation reference numbers
b. Corresponding paragraph references to the acceptance critaria contained in Standard Review Plan 9.5.1
c. Brief statement of each recomendation
d. Present plant equipment status and operating practices l

Action needed to comply with NRC recomendations in e.

those cases where the recocunendation or an equivalent I

course of action is not followed.

gO5160398761210 1 ADOCK 05000263 i CF i

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NORTHERN OTATEC POWER CO M P*ANY  ;

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3 Mr. Victor Stello a Page 2 December 10, 1976  !

Mr Go11er's letter dated September 30, 1976 requested that we conduct a fire hasards analysis based on specific guidance contained in Enclosure (2) to his letter, " Supplementary Guidance on Information Needed for Fire Protection ,

Program Evaluation". The results of this analysis will be submitted to you  :

in March of next year. While we did not originally intend to perform an analysis of this scope, it now appears that the results of the analysis will be useful in making decisions regarding the number and type of equipment and procedural changes needed to comply with the recommendations contained in Standard Review Plan 9.5.1. In these cases we have indicated in the attached l table that resolution of the item will be made following completion of the ,

fire hazards analy .s.

Yours very truly, o

L 0 Mayer, PE  ;

Manager of Nuclear Support Services ,

LOM/DMM/ deb l

ec: J G Keppler G Charnoff MPCA Attn: J W Ferman  ;

Attachment i

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u.S. NUCLL AR RE GULAToRY CoMMISSloN DOCKET NUMBE R i h FonM 1'J5 30 - z. 6 3 '

< >. w rats NUueER NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL FROM: ATE F CUMENT TO: My Stello Northern States Pwer Co 12-10-76

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  • Hinneapolis, Mn l L 0 Mayer DATE RE CEIVED 12-15 76 ONoToRIZED PHoP SNPUT FORM NUMBER OF COPIES RECEIVEo MLE TTE R IonlG4N AL E UNC LASS 4 F IE D ICC OCoPY DE SC RIPTION ENCLOSURE
  • Ltr re our 5-11-76 ltr. . . .trans the follow: Comparison of Existing Fire Protection  !

Provisions to the Guidelines Contained j in Standard Review Plan 9.5.1.........

l PLANT NAME: MontiCello DISTRIBITIION OF FIRE PROTECTION INFO PER 'rg.c u pm-<rn - 1.pLp G E D S.SHEPPARD 9-22-76 FOR OPERATING REACTORS g

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SAFETY FOR ACTION /INFORMATION 12-15-76 ehf BRANCH CHIEF: %s em aan (I)

PROJECT MANAGER: $co Jw LIC. ASST: Dag s INTE RN AL DISTRIBUTION l f' M J?- VTT r 3 l NRC PDR I & E (2)

OELD l BENAROYA EISENH1'T - -

EUTLER (5) j WAMBACH <

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EXTERNAL DISTRIBUTION ~

CONTRO_L NUMBER LPDR :/Pfee tte,J/o. 4n TIC: MA NS_lC e $

AcRS 16 16 CyS -

r. :=/SENT W-M 6 CAT A / 2- /f. ~7 eo 2. 6 9 5 NRCFORM 195(2 76) ,

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