ML19290A168
| ML19290A168 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/01/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0240, ACRS-SL-240, NUDOCS 7910170478 | |
| Download: ML19290A168 (3) | |
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UNITED STATES pf
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NUCLEAR REGULATORY COMMISSION' f. ty J E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
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~,#g August 1, 1979 Honorable Joseph M. Hendrie Chairman U. S. Nuclear Regulatory Commission Washington, DC 20555 7WO-HUNDRED-THIRTY-FIRST MEETING OF 1EE ADVISCRY CCMMITTEE
Subject:
REACTOR SAFEGUARDS, JULY 12-14, 1979 IN WASHINGTON, DC
Dear Dr. Hendrie:
The Advisory Committee on Reactor Safeguards held its 231st meeting in Nashington, DC on July 12-14, 1979.
Items considered at this meeting are summarized below:
Projects The Committee continued its evaluation of the accident at three Mile Island Nuclear Station Unit 2 (TMI-2). and the implications of tais accident for Further evaluation of the accident
.ather operating nuclear power plants.
and its implications is planned.
The Committee reviewed the proposal to use shorter piles under the founda-tions of safety-related structures of the Bailly Generating Station, s-c1=1 1.
A report on this matter was sent to you on July 16, 1979.
Miscellaneous to the FY 1980 budget and The Committee Ieviewed the proposed supplement the proposed FY 1981 budget for the Office of Nuclear Regulatory Research.
In addition, the A report regarding this program has been sent to you. recommendations regarding Committee has provided you with comments and cooperative efforts between DOE and NRC to improve reactor safety, and the NRC requirement for a " user" to sponsor safety research work.
The Committee provided a reply to Mr. M. Rogovin, NRC/IMI Special Inquiry Group, regarding recommendations the Committee made, prior to March 28, A copy of this letter has been sent 1979, relating to non-B & W reactors.
to you.
2223 346 791027o977
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Honorable Joselt M. Hendrie.
Since the last report of ACRS activities, the following subcommittee meetings have been held:
ECCS, in Washington, DC, on June 19-20, 1979 Improved Safety Systems, in Washington, DC, on June 26, 1979 Floating Nuclear Plant, in Washington, DC, on June 27, 1979 Radiological Effects and Site Evaluation, in Washington, DC, on June 27, 1979 Evaluation of Licensee Event Reports, in Washington, DC, on June 28-29, 1979 Lacrosse Boiling Water Reactor, in Washington, DC, on June 30, 1979 Bailly Nuclear Station, in Portage, IN, on Ju.y 9,1979 (Site visit included)
MI-2 Bulletins and Orders, in Washington, DC, on July 9,1979 Reactor Safety Research, in Washington, DC, on July 10, 1979 Metal Components / Combination of Dynamic Loads, in Washington, DC, on July 10-11, 1979 Extreme External Phenomena, in Washington, DC, on July 11, 1979 Advanced Reactors, in Washington, DC, on July 11, 1979 mI-2 Implications, in Washington, DC, on July 11, 1979 The following items are tentatively scheduled for consideration at the 232nd ACRS Meeting, August 9-11, 1979:
mI-2 Accident Investigation - Underlying Causes Evaluation of Licensee Event Reports - period of 1976-1978 Salem Nuclear Generating Station, Unit 2/ Westinghouse Nuclear Plants -
operation 2223 347
Honorable Joseph M. Hendrie NUREG-0395, A Modified Basis for Developnent of Dnergency Response Plans - proposed plans for implementatitn Pipe Cracking in Boiling Water Reactors - impact on BWR safety Anticipated "-.sients Without Scram - proposed plan for resolution Sincerely yours, Max W. Carbon Chairman 2223 348
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