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Home NRC Library Document Collections Advisory Committee on Reactor Safeguards Letter Reports 2000

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
   /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 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.

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

Page Last Reviewed/Updated Monday, July 25, 2016