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Draft Safety Evaluation Report Related to "Justification for Not Including Postulated Breaks in Larg

November 13, 2000

MEMORANDUM TO:	William D. Travers Executive Director for Operations /RA/
FROM:	John T. Larkins, Executive Director Advisory Committee on Reactor Safeguards
SUBJECT:	DRAFT SAFETY EVALUATION REPORT RELATED TO "JUSTIFICATION FOR NOT INCLUDING POSTULATED BREAKS IN LARGE-BORE REACTOR COOLANT SYSTEM PIPING IN THE LICENSING BASIS FOR EXISTING AND REPLACEMENT ONCE-THROUGH STEAM GENERATORS" (BAW-2374, REV. 0, JULY 2000)

During the 477^th meeting of the Advisory Committee on Reactor Safeguards, November 2-4, 2000, the Committee considered the draft safety evaluation report and decided not to review it.

References:

U.S. Nuclear Regulatory Commission Draft Safety Evaluation Report Related to "Justification for Not Including Postulated Breaks in Large-Bore Reactor Coolant System Piping in the Licensing Basis for Existing and Replacement Once-through Steam Generators" (BAW-2374, Rev. 0, July 2000), dated October 27, 2000.

cc:	A. Vietti-Cook, SECY J. Craig, OEDO I. Schoenfeld, OEDO S. Collins, NRR W. Bateman, NRR R. Barrett, NRR S. Bailey, NRR

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