ML20151H938

Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants

ML20151H938
Person / Time
Site:	Mcguire, Catawba, McGuire, 05000000
Issue date:	07/25/1988
From:	Taylor J BABCOCK & WILCOX CO.
To:	Norberg J Office of Nuclear Reactor Regulation
Shared Package
ML19292J166	List: ML20151H938
References
JHT-88-128, NUDOCS 8808020139
Download: ML20151H938 (1)

Text

7 s

. Babcock & Wilcox Nuclear Power DWon a McDerrnott company 3315 Old Forest Road P C. Box 10935 Lynchburg, VA 24506-0935 (804) 385 2000 Jilt /88128 I

July 25,1988 hir. James A. Norberg, Special Assistant Division of Engineering and System Technology l Office of Nuclear Reactor Regulation U. S. Nuctrar Regulatory Commission Washington, D.C. 20555

Subject:

ECCS hiethodology for Licensing Catawba and hicGuire Reloads

Reference:

J. ii. Taylor to Thcmas E. hiurley, same subject, JIIT/87137 July 13,1987.

1

Dear hir. Norberg:

The reference given above transmitted the draft version of the RSG LOCA Topical Report.

, Enclosed are twenty (20) copies of the completed Babcock & Wilcox proprietary Topical Report BAW 10168P, "RSG LOCA". This report describes the evaluation model that Babcock

& Wilcox will be using to perform loss of coolant accident (LOCA) analysis.

The report is considered proprietary as sworn by me as hianagcr, Dabcock & Wilcox

! Licensing, in my affidavit presented with our July 13, 1987 submittal of the draft topical report anti should be treated as such.

Y ruly yours,

., J l

3 J.11. Taylor hianager, Licensing Services i

cc: w/o attach  !

R. B. Borsum j T. L. Baldwin

• i A. C. Thadani, NRC  !

ht. W. Ilodges, NRC r

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