ML20210E171
| ML20210E171 | |
| Person / Time | |
|---|---|
| Issue date: | 06/12/1992 |
| From: | Hasselberg F Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Russell W NRC |
| References | |
| PROJECT-676A NUDOCS 9206180384 | |
| Download: ML20210E171 (4) | |
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UNITED STATES
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,I NUCLEAR REGULATORY COMMISSION o
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June 12, 1992 Project No. 676 MEf10RANDUM FOR:
T. Murley D. Crutchfield G. Holahan F. Miraglia J. Zwolinski B. Grimes W. Russell M. Virgilio F. Congol E
J. Partlow W. Travers J. Roe F. Gillespie E. Butcher A. Chaffee S. Varga C. Rossi W. Bateman G. Lainas J. Richardson L. Plisco J. Calvo A. Thadani M. Slosson B. Boger Operations Center THRU:
Robert C. Pierson, Director Standardization Project Directorate O
Associate Directorate for Advanced Reactors j and License Renewal Office of Nuclear Reactor Regulation FROM:
Frederick W. Hasselberg, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Rentwal Office of Nuclear Reactor Regulation
SUBJECT:
DAILY HIGHLIGHT - NOTICE OF FORTHCOMING HEETING WITH WESTINGHOUSE RELATED TO THE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR)
DATE AND TIME:
June 18, 1992 (9:00 a.m. - 4:00 p.m.)
LOCATION:
U.S. Nuclear Regulatory Commission r
One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Room 1-F-21 PURPOSE:
Presentation by Westinghouse Electric Corporation of AP600 Design Basis Accident (DBA) analytical methodology and computer codes applicable to Chapter 15 of the AP600 SSAR.
R0Jf: Westinghouse proprietary design features of the AP600 will be discussed at this meeting. A meeting agenda is
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armu Tn nrg0p3 CBlIMES 9206180384 920612 PDR PROJ 676A PDR
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. June 12, 1992 PARTICIPANTS *:
tiRC WESTINGHOUSE A. Thadani L. Hockreiter R. Jones A. Sterdes M. Rubin B. McIntyre A. Notafrancesco et al.
F. Hasselberg et al.
Original tbnC4 by Richard W. Borchardt Frederick W. Hasselberg, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosure:
Meeting Agenda cc w/ enclosure:
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 "Open Meeting 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) 504-1141.
w DISTRIBUTION; Central file,
PDST R/F NRC PDR TKenyon RPierson JNWilson RBorchardt FHasselberg GGrant, EDO PShea JMoore, 15818 EJordan, MNBB3701 ETana, PMAS P0' Dell, PTSB ACRS (10) '
Receptionist, 0WfN CMcCracken, 801 RJones, 8E23 MRubin, 8E23 ANotafrancesco, NLN344 0FC:
LA:PDST:DAR PM:PDSTfAR SC:PDSJ:DAR NAME:
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FHas[ erg:tz RBoddardt DATE:
06/}l /92 06////92 06//I/92 0FFICIAL RECORD COPY: DBAC0 DES.RH
WWW E Project No. 676 Westinghouse Electric Corporation AP600 cc:
Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. B. A. McIntyre Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 j
Ms. R. K. Beck Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Daniel F. Giessing U. S. Department of Energy NE-42 Washington, D.C.
20585 Mr. S. M. Modro EG1G Idaho inc.
Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner 725 17th Street, i:.W.
Room 8002 Washington, D.C.
20503 Mr, Mark McCabe U.S. Department of Justice /EAG l
555 4th Street, N.W.
Room 11-809 l
Washington, D.C.
20001
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Enclosure WESTINGHOUSE /NRC NIETING DESIGN BASIS ANALYSIS CODES & MEltlDQQ1AG1 AGD!DA JUNE 18, 1992 CONTAINMENT-ANALYSIS CODES USED IN AP600 ANALYSIS METHODOLOGY RESULTS LARGE BREAK LOCA CODES USED IN AP600 ANALYSIS METHODOLOGY RESULTS
~SMALL BREAK LOCA CODES USED IN AP600 ANALYSIS-
-METHODOLOGY
.RESULTS e.
STEAM GENERATOR TUBE RUPTURE CODES USED IN AP600 ANALYSIS METHODOLOGY RESULTS l
, TRANSIENT' ANALYSIS CODES-USED=IN AP600 ANALYSIS-METHODOLOGY RESULTS
_