November 13, 2000
|MEMORANDUM TO:||William D. Travers |
Executive Director for Operations
|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.
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