ML20029C534
| ML20029C534 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1994 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Russell W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20029C535 | List: |
| References | |
| TAC-M84799, NUDOCS 9402180041 | |
| Download: ML20029C534 (2) | |
Text
a rWT 31 1994 a
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MEMORANDUM FOR: William T. Russell, Associate Director for Inspection and Technical Assessment Office of Nuclear Reactor Regulation l
l FROM:
Ashok C. Thadani, Director.
l Division of_ Systems Safety and Analysis 1
Office of Nuclear Rea.ctor Regulation
SUBJECT:
WAIVER OF CRGR REVIEW FOR BAW-10166P, " BEACH: BEST ESTIMATE ANALYSIS CORE ~ HEAT TRANSFER"~(TAC NO: M84799)
REFERENCE:
Memorandum from E.L. Jordan (USNRC) to T.E. Murley, "CRGR l
Consideration of Topical Reports," September 29, 1989 i
Enclosed is the safety evaluation report (SER) prepared by the Division of Systems Safety and Analysis in which the staff accepts topical report-BAW-10166P, Revision 4, for referencing in licensing applications. The staff proposes that the Committee to Review Generic Requirements (CRGR). review be waived in accordance with the suggested revised procedures in the above i
referenced memorandum.
Topical Report BAW-10166P, Revision 4, describes the-Babcock and Wilcox (B&W)
I Nuclear Technologies methodology for best-estimate, core heat transfer analysis.
B&W Nuclear Technologies submitted the methodology described in the topical report to support reload design and operation, and licensing actions for PWR nuclear power plants. The report, BAW-10166, Revision 4, describes a special usage of the RELAP5/M002-B&W code for emergency core _ cooling system l
(ECCS) evaluation model reflood heat transfer analysis. 'The previous revision i
of BAW-10166P, Revision 3, was approved for loss-of-coolant accident (LOCA) reflood analysis. Revision 4, describes updates to the reflood fluid flow and i
heat transfer models which improve the post-peak cladding temperature quench front advancement modeling, allow multiple, independent reflood channels to be l
run simultaneously, and permit optional multipliers to be used for sensitivity l
studies. The B&W Nuclear Technologies methods and assumptions described in the topical report are typical of those used in approved codes and reflect the current design basis.
l According to the CRGR charter, the CRGR should review each of the staff's approvals of topical reports. However, the staff believes that CRGR review is not necessary because staff approval of BAW-10166P, Revision 4, does not present a new staff position.
C 44B4 W NRC RLE CENTER CGr
Contact:
L. Lois, SRXB/DSSA/504-3233 003001 y
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W. T. Russell If you agree that a CRGR review is not necessary,-please indicate your agreement by signing below. Otherwise the staff will prepare an appropriate.
CRGR package.
Ashok C. Thadani, Director Division of Systems Safety an'd Analysis Office of Nuclear Reactor Regulation lifff i
j William T.
ussell Approved: CRGR review is not necessary.
l l
Tech. Ed.: R. Sanders Date:
12/14/'93 DISTRIBUTION Central File PDR SRXB R/F AThadani RJones i
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