ML19261C519

From kanterella
Jump to navigation Jump to search

Forwards Safety Evaluation Rept for Fire Protection Program. Concludes Program,W/Scheduled Mods,Meets General Design Criterion 3 & Is Therefore Acceptable
ML19261C519
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/27/1979
From: Hanauer S
Office of Nuclear Reactor Regulation
To: Grimes B
Office of Nuclear Reactor Regulation
Shared Package
ML19261C520 List:
References
TAC-52156, NUDOCS 7903230096
Download: ML19261C519 (2)


Text

a THIS DOCUMF.NT Obkh/I

~ ~'

~

q

/

POOR QUAUTY PMES l

DISTRIBUTION;.

(NRirREADING DOCKET FIL L, PS READING FEB 2 71979 ASB READING Docket Hos: 50-346 MEMORANDUM FOR:

B. Grines, Assistant Director for Engineering & Projects Division of Openiting Reactors FRON:

S. H. Hanauer, Assistant Director for Plant Systeras Division of Systems Safety

SUBJECT:

FIRE PRuiu,rION SAFETY EVALUATION REPORT - DAVIS BESSE MUCLEAR STATION, UNIT NO. 1 Plant Name: Davis Besse Nuclear Station, Unit No.1 Docket Humber: 50-346 Licensing Stage: OR Milestone Number: N/A Responsible Branch: 00R 4 Project Manager:

G. Vissing ASB Reviewer:

V. Leung Requested Completion Date: December 30,1978 j

Review Status: Complete The Auxiliary Systems Branch has completed its review of the Davis Bessa Nucleat Station Unit No.1, Fire Protection Program. The Fire Protection Prugram was reviewed in c:cordance with Appendix A to Branch Technical Position AS8 9.5-1.

r

(

Table 1 of the SER presents an acceptable schedule for implementation of improvements under way or planned for the plant fire protection program.

The licensee has coenitted to isolement emergency shutdown procedures and modifications to maittain hc. shutdown capability by February 28 1979, and to assure safe cold shutdown independent of the cable spread-ing room or the control room by October 31,1979. These dates are

{

consistent with the operating license provisions.

i Based on our review, we find that the licensee's firepprotection program with iwrovements alrea# made by the licensee, is adequate thetbeepeetent time and with the scheduled modifications will meet the guidelines of Appendix A to Branch Technical Position 9.5-1, and meets General Design Criterion 3 and is, therefore, acceptable.

7 9 0 3 :2 3 009 L orrec s p-su== A wa e-DATW 9-

.. ~ - -.

NRC FORM 318 (946) NRCM 0240 W un e. ears==meier raiwnne orrics, me -eam

a v

B. Grimes Until the co::nitted fire protection system inaprovements are operational, we consider the existing fire detection and suppression systems; the existing barriers between fire areas; improved administrati~ e procc-v dures for control of combustibles and ignition sourec3; the trained onsite fire brigade; the capability to extinguish fires manually; and the fire protection technical spacificaticas provide adequate protec-tion against a fire that would threaten safe shutdown.

S. H. Hanauer, Assistant Director for Plant Systems Division of Systems Safety

Enclosure:

As stated cc:

R. Mattson R. Boyd W. Pike D. Eisenhut G. Vissing P. Matthews D. Fischer V. Benaroya G. Lainas C. Long R. Serguson V. Leung DSS:ASB,

DSS:)3S, m DSS:ASB DSS:ADPS1 din -

PM[tb[I VBenarppa SHanauer ?

..w...,

2//6/79 2[//79 2/1{/7 N _ 2/J3/794/

..n,

NRC FORM 318 (9 76) NRCM 0240 4 u. s. eova.musut eninnme orrms. 4.n -.a z.