ML19257C050
| ML19257C050 | |
| Person / Time | |
|---|---|
| Issue date: | 12/18/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0245, ACRS-SL-245, NUDOCS 8001240037 | |
| Download: ML19257C050 (3) | |
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o UNITED STATES 5 /_.
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ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
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WASHINGTON, D. C. 20$55
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December 18, 1979 Honorable John F. Ahearne Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
'IWO-HUNmED-THIRTY-SIXTH MEETING OF ME ADVISGY CCMHITITE CN REACPCR SAFEGUARDS, DECD4BER 6-8,1979
Dear Dr. Ahearne:
We Advisory Committee on Reactor Safeguards held its 236th meeting in Washington, DC on December 6-8, 1979.
Items considered at this meeting are sumarized below:
Se Committee completed its report, A Review of NRC Regulatory Processes and Functions.
We Committee met with members of the NRC Staff and the Tennessee Valley Authority to discuss TVA's request for a license to carry out an enhanced low-power test program in the Secuoyah Nuclear Power Plant Unit I during the NRC pause in licensing.
Se Comittee developed comments and recommendations regarding tM NRC pause in the licensing of nuclear power plants.
Se Committee respnded to your request for its ccmnents regardirg the adequacy of procedures for communication between the Comittee and 'N with respect to the follow-up and implementation of ACRS recommendations.
We Comittee developed a partial respr:nse to the Commission's request for its ccanents regarding the recommendations of the President's Commis-sion en the tree Mile Island Accident with respect to ACRS' activities.
We Comittee respnded to a request from Comissioner Bradford to iden-tify the NRC Regulatory Requirements that the Committee believes need changing and the adequacy of procedures for such reccxr.mendations.
We Comittee responded to a request from Representative Morris K. Udall for its comments regarding the proposed NRC FY-80 Supplenental Reactor Safety Research Budget.
1797 071 4003 goor2
Honorable John F. Ahearne December 18, 1979 We Committee continued its evaluation of the March 28, 1979 accident at tree Mile Island Nuclear Station Unit 2 and the implications of this accident. Comments on the final report of the Lessons Learned Task Force were developed.
Copies of the above reports and letters have been provided to you.
S e Committee met with members of the NRC Staff to discuss an outline of the NRC Staff's Action Plan to implement changes in the regulatory process as recernmended by the President's Commission, the 7MI-2 Lessons Learned Task Force, the ACRS, and others.
W e Committee was briefed by Dr. S. H. Hanauer regarding NRC Staff plans to revise NUREG-0606, Unresolved Safety Issues Dr. Milton S. Plesset and Dr. J. Carson Mark were elected to be ACRS Chairman and Vice-Chairman, respectively, for CY 1980.
Since the last report of ACRS activities, the following subcommittee meet-ings have been held:
General Electric Test Reactor, in San Francisco, CA or Novenber 14, 1979 Extreme External Phenomena, in Los Angeles, CA on November 15-16, 1979 Floating Nuclear Plant, in Los Angeles, CA on November 17, 1979 Advanced Reactors, in Albuquerque, NM on November 29-30, 1979 Reactor Operations, in Washington, DC on December 3,1979 Three Mile Island Accident Implications, in Washington, DC on Decenber 4, 1979 Reliability and Probabilistic Assessment, in Washington, DC on December 5, 1979 Fire Protection, in Washington, DC on December 5,1979 ACRS Procedures, in Washington, DC, on December 5,1979.
We following items are tentatively scheduled for consideration during the 237th ACRS Meeting, January 10-12, 1980:
he ACRS annual report to Congress on the NRC Reactor Safety Research Progran atio Review of the Proposed NRC Action Plan to implement the recommei / / qq j g
'J r c of the President's Commission on 'IMI and others 1797 072
Honorable John F. Ahearne December 18, 1979 Methods to implenent recommendations of the President's Commission to strengthen the ACRS NRC Bulletins and orders resulting frem TMI/Small break LOCA analyses Proposed revision of the NRC siting criteria.
Sincerely yours, Max W. Carbon Gairman 1797 073