NSD-NRC-97-5072, Forwards non-proprietary Rev 0 to WCAP-14869, MAAP4/NOTRUMP Benchmarking to Support Use of MAAP4 for AP600 PRA Success Criteria Analyses
| ML20137X738 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 04/16/1997 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20137X744 | List: |
| References | |
| NSD-NRC-97-5072, NUDOCS 9704220151 | |
| Download: ML20137X738 (2) | |
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1 Westinghous6 Energy Systems
$ $ e m m m 30 0355 p
Electric Corporation NSD-NRC-97-5072 1
DCP/NRC0817 Docket No.: STN-52-003 i
April 16,1997 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 A'ITENTION:
T.R. QUAY SUIDECT:
MAAP4/NOTRUMP Benchmarking to Support the Use of MAAP4 for AP600 PRA Success Criteria Analyses - WCAP-14869
Dear Mr. Quay:
t Enclosed is Westinghouse Topical Report WCAP-14869, "MAAP4/NOTRUMP Benchmarking to Support the Use )f MAAP4 for AP600 PRA Success Criteria Analyses." This report documents the benchmarking of MAAP4 against NOTRUMP, the Westinghouse-validated code for AP600 small-break LOCAs. A total of nineteen benchmarking cases were analyzed with both MAAP4 and NOTRUMP. The NOTRUMP input modeling used for the MAAP4 benchmarking is consistent with 1
SSAR plant modeling at the end of 1996. When the SSAR NOTRUMP analyses are completed, differences in the NOTRUMP input modeling will be assessed. The results of the assessment will be transmitted to the staff. This approach has been discussed with the staff in a telecon. It is anticipated that the differences will not impact the results and conclusions of this report.
The benchmarking effort confirms that MAAP4 is an adequate, mui iiol to support the AP600 Probabilistic Risk Assessment (PRA), success criteria in multipe-faiY accident scenarios.
'Ihe NRC technical stafT should review the enclosed t( pical report. Feedback from the staff is essential to maintain momentum on the path to resolviag the PRA success criteria, thermal / hydraulic uncertainty, and PRA long-term cooling issues. Pending feedback fram the ongoing NRC review, and detailed review of support calculations, no future revisions are planned.
Please contact Cynthia L. llaag on (412) 374-4277 if you have any questions concerning this transmittal.
Ac~ / #
a Brian A. McIntyre, h anager Advanced Plant Safety and Licensing Enclosure cc:
W. Iluffman, NRC (2 copies enclosure)
A. Levin, NRC (enclosure)
G. Ilolahan, NRC (w/o enc!osute)
N. J. Liparulo, Westinghouse (w/o enclosure)
NNNI 970422015; O
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