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”

July 17, 2000

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."