ML20039F405

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Forwards Revision 3 to BAW-10104, Small Break ECCS Evaluation of B&W 205.FA NSS Using Dec 1976 ECCS Evaluation Model. Mixture Level Remains Above Core Throughout Transient.No Cladding Temp Excursion Occurs
ML20039F405
Person / Time
Site: 05000561
Issue date: 12/23/1977
From: Taylor J
BABCOCK & WILCOX CO.
To: Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML111090060 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201120423
Download: ML20039F405 (1)


Text

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Babcock &Wilcox go, o m.,au,, o,,,,

P.o. Box 1260, Lynchburg, Va. 24505 Telephone:(804) 384-5111 December 23, 1977,,.(

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([I\\f Mr. S. A. Varga, Chief lk G4kl370 28A

  • LWR Branch No. 4 4

u.g Division of Project Management Office of Nuclear Reactor Regulation L.

d U.S. Nuclear Regulatory Comission Washington, D.C.

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Dear Mr. Varga:

Attached are the results of a worst-case small break ECCS evaluation of the B&W 205 Fuel Assembly plant as requested in your letter of May 10, 1977.

This analysis was performed with B&W's December 1976 Small Break ECCS Evaluation Model.

The results of this analysis shows that the mixture level remains above the core throughout the transient and therefore no cladding temperature excursion occurs. The results in BAW-10074A, thus, remain valid and are conservati ve.

This submittal completes the responses to all questions asked by the Staff on BAW-10102.

A prompt review and approval of this analysis and the large break analysis submitted on September 30, 1977 is requested.

Formal approval of BAW-10102 is requested following approval of the above analyses.

If you have questions concerning this response, please contact me or Henry Bailey (Ext. 2678) of my staff.

Very truly yours, g,;u t.$

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James H. Taylor t

Manager, Licensing JHT/dsv cc: R.B. Borsum (w/o attach)

T.H. Novak - NRC 780240212 8201120423 810403 PDR FOIA MADDEN 80-515 PDR l

The Babcock & Wilecx Cemoany / Established 1867,

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