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Topical Report BAW-2374, “Justification for Not Including Postulated Breaks in Large-Bore Reactor Co

July 17, 2000

MEMORANDUM TO:	William D. Travers
	Executive Director for Operations
	/RA/
FROM:	John T. Larkins, Executive Director
	Advisory Committee on Reactor Safeguards

SUBJECT:

TOPICAL REPORT BAW-2374, "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"

During the 474^th meeting of the Advisory Committee on Reactor Safeguards, July 12-14, 2000, the Committee considered the subject document and decided that it would like the opportunity to review this matter after the staff prepares the safety evaluation.

Reference:

Letter dated July 7, 2000, from David J. Firth, B&W Owners Group, to Document Control Desk, U.S. Nuclear Regulatory Commission, Subject: Submittal of Topical Report BAW-2374, "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."

cc:	A. Vietti-Cook, SECY J. Craig, OEDO G. Millman, OEDO S. Collins, NRR S. Bajwa, NRR S. Bailey, NRR

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