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)
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 477th 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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