ML20137Z387

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Summary of 970407 Meeting W/W in Rockville,Md to Provide W Feedback on Status of Review of Ssar Sections 9.5.1,9A & Fire Protection Analysis.List of Meeting Attendees & Meeting Handout Encl
ML20137Z387
Person / Time
Site: 05200003
Issue date: 04/22/1997
From: Diane Jackson
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9704240131
Download: ML20137Z387 (4)


Text

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April 22,1997 APPLICANT: . Westinghouse Electric Corporation FACILITY: AP600

SUBJECT:

SUMARY OF MEETING TO DISCUSS WESTINGHOUSE AP600 FIRE PROTECTION ANALYSIS The subject meeting was held at the Nuclear Regulatory Commission (NRC) office in Rockville, Maryland, on April 7, 1997, between representatives of Westing-house Electric Corporation (Westinghouse) and the NRC staff. The staff requested the meeting to provide Westinghouse feedback on the status of the review of standard safety analysis report Section 9.5.1 and 9A. Attachment 1 is.a list of meeting participants.

Attachment 2 is the NRC meeting handout that lists the major issues currently identified and the staff's technical position development. The staff dis-cussed the status of its concerns with Westinghouse. The staff also informed Westinghouse that an additional reviewer was assigned to assist the review.

Issue 5 on the meeting handout was satisfactorily responded to by Westing-house. Westinghouse explained that because the reactor coolant pumps were

" canned," that they are water-cooled and do not require oil.

The staff suggested that bi-weekly meetings be held to facilitate discussion and expedite the resolution of open issues. The next meeting was tentatively scheduled for April 21, 1997, in Rockville, Maryland.

original signed by:

Diane T. Jackson, Project Manager St.andardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

Attachment:

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Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 i Nuclear and Advanced Technology Division Office of LWR Safety and Technology I Westinghouse Electric Corporation 19901 Germantown Road j 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 l 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 Curtrer Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 4

Mr. Sterling Franks Barton Z. Cowan, Esq.

U.S. Department of Energy Eckert Seamans Cherin & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germaatown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed RcJwell, 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-50 19901 Germantown Road

- Germantown, MD 20874

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WESTINGHOUSE /NRC AP600 MEETING FIRE PROTECTION  ;

APRIL 7, 1997 l

MEETING PARTICIPANTS M ORGANIZATION I

ED CONNELL NRR/DSSA/SPLB JEFF HOLMES NRR/DSSA/SPLB  :

DIANE JACKSON NRR/DRPM/PDST l TAD MARSH NRR/DSSA/SPLB .

1 TED QUAY NRR/DRPM/PDST STEVE WEST NRR/DSSA/SPLB DON HUTCHINGS WESTINGHOUSE

. JIM WINTERS WESTINGHOUSE I

Attachment 1 d

+

AP 600 Fire Protection Issues Identified Thus Far .

1. Consideration of Fire as a Design Basis Event, without consideration of  :

an independent single active component failure, consistent with other  !

DBEs.

i 2. The passive safe shutdown capability is not a normal shutdown method .

(See GL 86-10, 5.1.2). The fire protection criteria for f alternative / dedicated shutdown methods specified in Appendix R Section III.G.3 has not been met.  ;

3. .The consideration of hose stations as a " fixed fire suppression system" i
is 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 not meet the minimum performance criteria specified in NFPA 14.

j M. The reactor coolant pumps are not provided with an oil cuilection system as required by Appendix R Section 111.0.

6. Location of fire pumps in the turbine building. Availabi?ity of fire l 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.
9. Fire risk assessment using a modified FIVE methodology.  ;
10. 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.

Attachment 2

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