ML16288A432
| ML16288A432 | |
| Person / Time | |
|---|---|
| Issue date: | 08/15/1989 |
| From: | Banks M, Remick F Advisory Committee on Reactor Safeguards |
| To: | Taylor J NRC/EDO |
| References | |
| D890815 | |
| Download: ML16288A432 (10) | |
Text
D890815 Mr. James M. Taylor, Acting Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Taylor:
SUBJECT:
PROPOSED RESOLUTION OF GENERIC ISSUE 79, UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS DURING NATURAL CONVECTION COOLDOWN During the 352nd meeting of the Advisory Committee on Reactor Safe-guards, August 10-11, 1989, we met with representatives of the NRC staff and discussed the actions proposed by the staff for resolving Generic Issue 79.
The evaluations performed within the framework of Generic Issue 79 have resolved the natural circulation cooldown (NCC) for Babcock & Wilcox nuclear steam supply systems (NSSS). The NCC condition has not been specifically evaluated for Westinghouse and Combustion Engineering PWRs.
However, the RES staff will recommend to NRR that if a licensee with Westinghouse or Combustion Engineering NSSS experiences a significant NCC event, the licensee should be required to provide confirmation that no applicable regulatory design or fracture toughness criteria has been exceeded for the reactor vessel.
Our only recommendation with respect to the resolution of this generic issue is that licensees with Westinghouse and Combustion Engineering NSSS should be informed of this potential evaluation requirement.
Sincerely, Forrest J. Remick Chairman
Reference:
Memorandum dated July 7, 1989 from R. W. Houston, RES, for R. F. Fraley, ACRS,
Subject:
Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown 9 ¸{Ú
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