ML20138E453
| ML20138E453 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 04/30/1997 |
| From: | Diane Jackson NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9705020208 | |
| Download: ML20138E453 (4) | |
Text
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April 30, 1997 APPLICANT: Westinghouse Electric Corporation FACILITY:
AP600 1
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS WESTINGHOUSE AP600 FIRE PROTECTION l
ANALYSIS The-subject meeting was held at the Nuclear Regulatory Commission (NRC) office in Rockville, Maryland, on April 21, 1997, between representatives of Westing-house Electric Corporation (Westinghouse) and the Nuclear Regulatory Commis-sion staff. The purpose of the meeting was to discuss the status of the review of standard safety analysis report (SSAR) Section 9.5.1 and 9A. is a list of meeting participants.
The April 7, 1997, meeting handout (Attachment 2), listing the staff's currently. identified review issues, was used as a guide for discussion.
Staff j
and Westinghouse activities on the issues were discussed. Number 9, regarding the use of the FIVE methodology, was not discussed at this meeting.
It will be discussed at a future meeting. Number-10, regarding the necessary 8-hour battery-powered emergency lighting, was resolved.
SSAR Section 7 currently describes that the emergency lighting is powered by the 72-hour batteries.
The staff also discussed a new concern with Westinghouse. Westinghouse use, gypsum walls, rather than concrete walls in some areas. This is contrary to the branch technical position, and Westinghouse has not provided adequate justification for the staff to approve the deviation.
The staff will formalize its review issues in a letter. The staff informed Westinghouse that the staff's letter is expected to be issued by May 2, 1997.
The next meeting was tentatively scheduled for May 5,1997, in Rockville, Maryland.
original signed by:
Diane T. Jackson, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 gg hh
Attachment:
As stated cc w/ attachment:
See next page DISTRIBUTION:
Docket File PDST R/F SCollins/FMiraglia, 0-12 G18 PUBLIC RZimmerman, 0-12 G18 TMartin, 0-12 G18 MSlosson TQuay DJackson i
TKenyon WHuffman JSebrosky
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JMoore, 0-15 B18 WDean, E00 ACRS (11)
O O
l Econnell, 0-8 D1 JHolmes, 0-8 D1 TMarsh, 0-8 D1 V
SWest, 0-8 D1 DOCUMENT NAME:- A:SFP4 7.MIM 03 4 Ta,seelve a copy of this clocumeest,lassate in the ben: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure
- N* = No copy 0FFICE PM:PDST:DRPM H SPLB:DSSf 3 l D:PDST:DRPM l
NAME DTJackson:sg TV SWest W TRQuay 4IM DATE 4 / 96/97 0
4 /30 /97 A/30/97 9705020208 970430 PDR ADOCK 05200003 F
. ~.
Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross g
Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute Westinghouse Electric Corporation 1776 Eye Street, N.W.
Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz 11921 Rockville, Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.
U.S. Department of Energy Eckert Seamans Cherin & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Modro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 Mr. Charles Thompson, Nuclear Engineer AP600 Certification NE-Su 19901 Germantown Road Germantown, MD 20874 i
WESTINGHOUSE /NRC AP600 MEETING FIRE PROTECTION APRIL 21, 1997 MEETING PARTICIPANTS ED CONNELL NRR/DSSA/SPLB JEFF HOLMES NRR/DSSA/SPLB DIANE JACKSON NRR/DRPM/PDST TAD MARSH NRR/DSSA/SPLB TED QUAY
- NRR/DRPM/PDST STEVE WEST NRR/DSSA/SPLB j
ED CUMMINS WESTINGHOUSE i
t DON HUTCHINGS WESTINGHOUSE JIM WINTERS WESTINGHOUSE
- PART-TIME
i
.c l
AP 600 Fire Protection Issues Identified Thus Far l
1.
Consideration of Fire as a Design Basis Event, without consideration of an independent single active component failure, consistent with other OBEs.
2.
The passive safe shutdown capability is not a normal shutdown method (See GL 86-10, 5.1.2).
The fire protection criteria for alternative / dedicated shutdown methods specified in Appendix R i
Section III.G.3 has not been met.
l i
i 3.
The consideration of hose stations as a " fixed fire suppression system" l
1s incorrect (See GL 83-33).
4.
Class II hose stations do not provide an effective hose stream. The use l
of the seismically designed standpipe for non-seismic fires does I
not meet the minimum performance criteria specified in NFPA 14.
)
d.
The reactor coolant pumps are not provided with an oil collection system as required by Appendix R Section 111.0.
6.
Location of fire pumps in the turbine building.
Availability of fire pumps following a turbine blade failure or a major lube oil fire in the turbine building.
7.
Use of technically obsolete equivalent fire severity methodology for determining adequacy of fire barriers in non-safety related areas.
8.
Equivalent fire rating of structural barriers / labyrinths.
l 9.
Fire risk assessment using a modified FIVE methodology, h
Main control room and remote shutdown area are not provided with 8-hour battery powered emergency lighting as required by Appendix R Section III.J.
l l
l l
.