ML20133E657

Notification of 970121-23 Meetings W/Westinghouse Electric Corporation to Discuss Insights & Important Assumptions That Will Be Included in AP600 PRA

ML20133E657
Person / Time
Site:	05200003
Issue date:	01/09/1997
From:	Joseph Sebrosky NRC (Affiliation Not Assigned)
To:	Quay T NRC (Affiliation Not Assigned)
References
NUDOCS 9701130097
Download: ML20133E657 (4)

Text

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January 9,1997 v

MEMORANDUM TO: mTheodore R. Quay, Director

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Standardization Project Directorate t

Di. vision of Reactor Program Management, NRR i , ,

FROM: - Joseph M.' Sebrosky, Project Manager original signed by:

. s Standardization Project Directorate Division of Reactor Program Management, NRR

SUBJECT:

~' NOTICE,0F. MEETING WITH WESTINGHOUSE TO DISCUSS THE AP600 INSIGHTS THAT WILL BE INCLUDED IN THE PROBABILISTIC RISK l '

ASSESSMENT (PRA)

DATE AND TIME: January 21,1997'- 1 p.m. - 5 p.m.

January 22; 1997 - 8:30 a.m. - 4 p.m.

January 23, 1997 - 8:30 a.m. - 12:30 p.m. (optional)

LOCATION: , Westinghouse Electric Corporation Westinghouse Energy Center Monroeville, Pennsylvania PURPOSE: To discuss the insights and important assumptions that will be included in AP600 PRA. In addition, the PRA modeling of steam generator tube rupture events will be discussed. See attach-ment for a proposed agenda.

PARTICIPANTS *: EG WESTINGHOUSE J. Flack C. Haag N. Saltos T. Bueter, et.al H. Li J. Sebrosky Docket No.52-003

Attachment:

'As stated cc w/ attachment:

See next page

'* Meetings between the NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff Meeting Open to the Public," 59 Federal Reaister 48344,9/20/94.

However, portions of this meeting may be closed to protect Westinghouse proprietary information. Members of the public who wish to attend should contact me at (301) 415-1132. QN DISTRIBUTION:

See next page i

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130025 DOCUMENT NAME: A:PRA INST.NOT (IA AP600 DISK)

TJ seeshse e espy of this sleemsnent. lsitsees in the ben: "C' = copy without ettechenent/encienne *E' = Copy wtan ettschment/ enclosure 'N' = No copy 0FFICE PM:PDST:DRPM D:PDST:DRPM l l l NAME JMSebrosky TRQuay 'M7 ETE 01/9/97 01/4/977t'b 9701130097 970109 "EICI AL; RECORD COPY I " " _'l " @ ' - _ ._- .

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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 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 Mr. John C. Butler 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-50 19901 Germantown Road Germantown, MD 20874

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WESTINGHOUSE /NRC AP600 PRA MEETING

PROPOSED AGENDA f January 21. 1996 I. Discussion of assumptions, features, and insights associated with the following systems:

i e Normal Residual Heat Removal System e Passive Residual Heat Removal System (Other systems associated 4

with the Passive Core Cooling System may also be discussed)

January 22. 1996 I. Discussion of assumptions, features, and insights associated with the l

! following systems:

l e Protection and Safety Monitoring System l l

e Diverse Actuation System e Plant Control System l II. Discussion of the PRA modeling of steam generator tube rupture events.

III. Summary and Conclusion 1

Attachnent

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DISTRIBUTION: Memorandum to Theodore R. Quay. Dated: January 9. 1997 Docket File PUBLIC PDST R/F FMiraglia/AThadani, 0-12 G18 RPZimmerman, 0-12 G18 i BSheron, 0-12 G18 I TMartin l DMatthews i TJKenyon l DTJackson WCHuffman JMSebrosky l WDean, 0-17 G21 JMoore, 0-15 B18 l EJordan, T-4 D18 l ACRS (11)

. JFlack, 0-10 E4 l NSaltos, 0-10 E4 HLi, 0-8 H3 PMNS (e-mail)

OPA (e-mail)  ;

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