ML20207B708
| ML20207B708 | |
| Person / Time | |
|---|---|
| Issue date: | 12/16/1986 |
| From: | Ward D Advisory Committee on Reactor Safeguards |
| To: | Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR ACRS-R-1230, NUDOCS 8612240087 | |
| Download: ML20207B708 (1) | |
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o,
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December 16, 1986 Mr. Victor Stello, Jr.
Executive Director for Operations U. S. Nuclear Regulatory Commission j
Washington, DC 20555
Dear Mr. Stello:
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SUBJECT:
ACRS COMMENTS ON PROPOSED NRC FINAL REGULATORY GUIDE ENTITLED,
" FORMAT AND CONTENT OF PLANT-SPECIFIC PRESSURIZED THERMAL SHOCK SAFETY ANALYSIS REPORTS FOR PRESSURIZED WATER REACTORS,"
DATED JUNE 1986 During our 320th meeting, December 11-13, 1986, the members of the l
Advisory Committee on Reactor Safeguards heard reports from our Subcom-mittee en Metal Corrponents and from the NRC Staff on the #inal draft of a regulatory guide implementing the recently adopted rule (10 CFR Part j
50.61) concerning reactor vessel pressurized thermal shock (PTS) for pressurized water reactors.
This matter also was considered by our Metal Components Subcommittee on February 27-28, 1986.
As a result of these discussions, we recommend that you issue the final PTS regulatory guide.
However, we would like to review the work performed by the lead licensee using this regulatory guide, when it becomes available.
Sir ? rely, JQ AR Dec'f A. Ward Chairman cc:
E. Beckjord, RES je 4
.