ML20149G425

Notification of 941020 Meeting W/W in Rockville,Md to Discuss W Rev & Update of Level 2 PRA for AP600 Reactor Design.W/Agenda

ML20149G425
Person / Time
Site:	05200003
Issue date:	10/17/1994
From:	Mike Franovich Office of Nuclear Reactor Regulation
To:	Miraglia F, Russell W, Thadani A NRC
References
NUDOCS 9410210070
Download: ML20149G425 (5)

Text

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October 17, 1994 MEMORANDUM T0: W. Russell J. Zwolinski M. Virgilio F. Miraglia J. Roe B. Boger A. Thadani E. Adensam C. Thomas R. Zimmerman B. Grimes J. Calvo D. Crutchfield B. D. Liaw R. Spessard W. Travers B. Sheron V. McCree, ED0 F. Gillespie G. Lainas J. Caldwell S. Varga G. Holaha Operations Center THRU: R. W. Borchardt, Director Standardizatien Project Di ctorate Associate Directorate for Advanced Reactors and License Renewal-Office of Nuclear Reactor Regulation , ' ,

FROM:

MichaelX.Franovich,ProjectManagerpg,/

Standardization Project Directorate '

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v $ v/ b;1 Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation

SUBJECT:

DAILY HIGHLIGHT - F'RTHC( ING MEETING WITH WESTIL3H0VSE T0  !

DISCUSS THE PROBABILISTIC RI5K ASSESSMENT (FRA) FOR THE {

AP600 DESIGN l l

DATE & TIME: October 20, 1994, 1 - 5 p.m. l LOCATION: U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Room 6-B-11 PURPOSE: To discuss Westinghouse's revision and update of the Level 2 PRA for the AP600 design. A meeting agenda is enclosed.

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9410210070 941017 '

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October 17, 1994 I

PARTICIPANTS *: NRR Westinahouse M. Franovich J. Scobel A. El-Bassioni C. Haag N. Saltos B. McIntyre, et al l M. Pohida f R. Palla M. Snodderly J. Monninger Docket No.52-003

Attachment:

As stated cc: See next page ,

• Meetings between 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 the "Open Meetings and Statement of NRC Staff Policy," 43 Federal Reaister 20858, June 28,1978. 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) 504-1121.

DISTRIBUTION:

Docket J11e PDST R/F RBorchardt PDR RArchitzel KShembarger TKenyon FHasselberg JMoore, 0-15 B18 PMagnanelli AChaffee, OEAB AEI-Bassioni, 0-10 E4 EJordan, T-4 D18 WDean, 0-17 G21 OPA NRR Mailroom 0-12 G18 EButcher, 0-10 E2 AGody, 0-12 E4 NSaltos, 0-10 E4 MFranovich Receptionist, OWFN MPohida RPalla ACRS (11)

MSnodderly JMonninger 0FC: LA;? DSTAADAR PM:PDST:ADAR - SC:PDSI9ADAR ynie twin p ;+ -

l NAME: PM@hanelli MFranovich:sp RArchitzel DATE: 10/fl/94 10//f/94 10//7/94 0FFICIAL RECORD COPY:

DOCUMENT NAME: PRAMTG3.N0T i

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• PARTICIPANTS *: NRR Westinahouse M. Franovich J. Scobel  !

A. El-Bassioni C. Haag N. Saltos B. McIntyre, et al M. Pohida R. Palla M. Snodderly J. Monninger Docket No.52-003

Attachment:

As stated cc: See next page

• Meetings between 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 the "Open Meetings and Statement of NRC Staff Policy," 43 Federal Reaister 20858, June 28,1978. 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) 504-1121.

i 1

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Westinghouse Electric Corporation Docket No.52-003 i

cc: Mr. Nicholas J. Liparuio Mr. Victor G. Snell, Director Nuclear Safety and Regulatory Analysis Safety and Licensing Nuclear and Advanced Technology Division AECL Technologies Westinghouse Electric Corporation 9210 Corporate Boulevard P.O. Box 355 Suite 410  ;

Pittsburgh, Pennsylvania 15230 Rockville, Maryland 20850 [

Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Program '

Westinghouse Electric Corporation Nuclear Energy Institute -

Energy Systems Business Unit 1776 Eye Street, N.W.

Box 355 Suite 300 Pittsburgh, Pennsylvania 15230 Washington, D.C. 20006-3706 i

Mr. John C. Butler STS, Inc.

Advanced Plant Safety & Licensing Ms. Lynn Connor i Westinghouse Electric Corporation Suite 610 Energy Systems Business Unit 3 Metro Center  ;

Box 355 Bethesda, Maryland 20814  ;

Pittsburgh, Pennsylvania 15230  !

Mr. Patrick W. Marriott, Manager  !

Mr. M. D. Beaumont Advanced Plant Technologies- l Nuclear and Advanced Technology Division GE Nuclear Energy Westinghouse Electric Corporation 175 Curtner Avenue, M/C 781  ;

One Montrose Metro San Jose, California 95125-  !

11921 Rockville Pike i Suit < 350 Mr. John E. Leatherman, Manager l Ror' ille, Maryland 20852 SBWR Design Certification GE Nuclear Energy, M/C 781  ;

Mr. . Sterling Franks San Jose, California 95125 t U.S. Department of Energy i NE-42 Barton Z. Cowan, Esq.

Washington, D.C. 20585 Eckert Seamans Cherin & Mellott '

600 Grant Street 42nd Floor Mr. S. M. Modro Pittsburgh, Pennsylvania 15219 EG&G Idaho Inc.

Post Office Box 1625 Idaho Falls, Idaho 83415  !

Mr. Steve Goldberg  !

Budget Examiner 725 17th Street, N.W.

Room 8002 Washington, D.C. 20503 Mr. Frank A. Ross i U.S. Department of Energy, NE-42 l Office of LWR Safety and Technology i 19901 Germantown Road l Germantown, Maryland 20874 i l

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Agenda for AP600 Revision 1 PRA Overview October 20,1994, Rockville, MD

• Introduction and Summary of Changes Made to PRA in Revision 1 RAIs Addressed by Revision 1

• AP600 Containment Event Tree Structure Accident Classes (Plant Damage States)

CET Top Events Release Categories

• Assignment of Nodal Split Fractions to Containment Event Tree Systems Nodes (Fault Tree Linking)

Phenomenological Nodes (Decomposition Event Trees)

In-Vessel Retention of Core Debris Thermally-Induced Failures of the RCS Pressure Boundary In-Vessel Steam Explosion Ex-Vessel Debris Coolability Hydrogen Deflagration and Detonation Containment Failure Nodes (Containment Failure Probability Distribution)

• Results of the Containment Event Tree Quantification Base Results In-Vessel Retention Sensitivity

• MAAP4 Analyses and Fission Product Release Fractions

\fAAP4 Model Analyses and Results

• Offsite Dose Analyses Assumptions Results

• Overall Results and Conclusions Attachment