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
|MEMORANDUM TO:||William D. Travers|
|Executive Director for Operations|
|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 474th 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.
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