ML20141E868

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Informs That Staff Determined That Discrepancies Exist Between AP600 FP Configuration Described in App a of AP600 Ssar & FP Configuration Assessed in Internal Fire Analysis. List of Discrepancies Encl
ML20141E868
Person / Time
Site: 05200003
Issue date: 06/27/1997
From: Slosson M
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9707010189
Download: ML20141E868 (4)


Text

1 c . June 27, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis i Nuclear ~and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

INTERNAL FIRE ANALYSIS RELATED TO THE AP600 REACTOR DESIGN

Dear Mr. Liparulo:

In a letter dated December 6,1996, the Nuclear Regulatory Commission sent you i a list of potential critical path issues in the design certification process for-the AP600. One of the issues, Key Issue #12, involves the acceptability of Westinghouse's approach'for fire protection. Based on its ongoing review l of Chapter 57, Internal Fire Analysis, Revision 9, dated April 11, 1997, of the AP600 probabilistic risk assessment, the staff has determined that

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discrepancies exist between the AP600 fire protection configuration described in Appendix 9A of the AP600 standard safety analysis report (SSAR) and the fire protection configuration assessed in the Internal Fire Analysis.

j Enclosed are examples of discrepancies identified by the staff. The list is

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not intended to be a comprehensive list of all discrepancies contained in the-analysis. The staff cannot expend additional resources on the review of the

Internal Fire Analysis until We'stinghouse revises the analysis and the SSAR, I

as appropriate, to reflect the actual AP600 fire protection design.

l If the staff develops additional fire protection issues, it will discuss them

. with Westinghouse and will prepare additional technical positions, as needed.

1 If you have any questions regarding this matter, you may contact Diane Jackson I

at (301) 415-8548.

Sincerely,-

l original siped by:

Marylee M. Slosson, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 )

Enclosure:

As stated }

cc w/ enclosure: See next page

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DISTRIBUTION:

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NAME MCunningham* TRQuay* MMSlossbo DATE 06/y)/97 V 06/17/97 06/19/97 06/p//97' @

0FFICIAL RECORD COPY 9707010189 970627 '"

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Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor, Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 Eye Street, N.W.

P.O. Box 355 Suite 300 Pittsburgh, PA 15230- Washington, DC 20006-3706 Mr. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Licensing Doc-Search Associates Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. S. M. Modro GE Nuclear Energy Nuclear Systems Analysis Technologies 175 Curtner Avenue, M/C 165 Lockheed Idaho Technologies Company San Jose, CA 95125 Post Office Box 1625 Idaho Falls, !D 83415 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Sterling Franks 175 Curtner Avenue, MC-781 U.S. Department of Energy San Jose, CA 95125 NE-50 19901 Germantown Road Barton Z. Cowan, Esq.

Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Frank A. Ross Pittsburgh, PA 15219 U.S. Department of Energy, NE-42 Office of LWR Safety and Technology Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Charles Thompson, Nuclear Engineer Palo Alto, CA 94303 AP600 Certification NE-50 l 19901 Germantoun Road Germantown, MD 20874 I

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TECHNICTL POSITION

' BY THE OFFICE OF NUCLEAR REACTOR REGULATION

' FIRE PROTECTION ISSUES RELATED TO THE DESIGN OF THE WESTINGHOUSE AP600 ADVANCED LIGHT WATER REACTOR 4

1.0 INTRODUCTION

Based on its review, the staff has determined that significant discrepan-i cies exist in the AP600 fire protection configuration described in.

Appendix 9A of the AP600 standard safety analysis report (SSAR), Revi-sion 11, dated February 28, 1997, and the fire protection configuration ,

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~ assessed in Chapter.57, Internal Fire Analysis, Revision 9,. dated- l

, April 11, 1997, of the. AP600 probabilistic risk assessment. Listed below l l are selected examples of the discrepancies identified by the staff during l its' review. The listing is not a comprehensive listing of all discrepan-

j. cies contained in the analysis.

l 2.0 DISCREPANCIES k

, 2.1 The Internal Fire Analysis, Table 57-2b, indicates that Fire Area I 1240 AF 01, Non-1E Electrical Penetration Room is provided with pre-action sprinkler protection. _ Appendix 9A of the SSAR, Table 9A-3, identifies the Non-1E Penetration Room as Fire Area 1200 AF 04, with only

. smoke detection and hose stations provided. There is no fire area identified as 1240 AF 01 in Appendix 9A of the SSAR.

2.2 The Internal Fire Analysis, Table 57-2b, indicates that Fire Area 4031 AF 02, Containment Access Corridor, is provided with wet piping sprinkler protection. -Appendix 9A of the SSAR, Fire Area 4031 AF 02, is identified as the area containing.the non-class 1E. batteries and battery charging equipment. The. fire protection provided in this area consists of fire '

l detectors, hose stations, and portable fire extinguishers. The access corridor ~1s identified in Appendix 9A as being located in Fire Area 4031 AF 05, and is provided with fire detectors, hose stations, and portable fire extinguishers.

1 2.3 The Internal Fire Analysis indicates that Fire Area'1202 AF 05, is the Division C electrical equipment room. Appendix 9A of the SSAR indicates that the Division C electrical equipment room is Fire Area 1202 AF 03.

Appendix 9A indicates that Fire Area 1202 AF 05 is a stairwell, i

3.0 TECHNICAL POSITION The applicant should revise the Internal Fire Analysis and the SSAR, as appropriate, to reflect the actual fire protection design of the AP600 and resubmit it for staff review.

Enclosure

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4 DISTRIBUTION: Letter .to Mr. Nicholas J. Linarulo. Dated: June 27. 1997 Docket-File '

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