ML19257C061
| ML19257C061 | |
| Person / Time | |
|---|---|
| Issue date: | 11/21/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0244, ACRS-SL-244, NUDOCS 8001240054 | |
| Download: ML19257C061 (3) | |
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NUCLEAR REGULATORY COMMISSION c
ADVISORY COMMITYEE ON REACTOR SAFEGUARDS 4;
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WASHINGTON, D. C. 20555 f
Novecber 21, 1979 Honorable Joseph M. Hendrie Chairman U.S. Nuclear Regulatory Comission Washington, DC 20555
SUBJECT:
'IWO-HUNDRED-THIRTY-FIF'Di MEETING OF 'niE ADVISCRY C04MITTEE CN REAC'IUt SAFEGUARIS, NOVEMBER 8-10, 1979 IN WASHINGTON, DC Dear Dr. Hendrie.
The Advisory Comittee on Reactor Safeguards held its 235th meeting in Washington, DC, on November 8-10, 1979. Items considered at this meeting are stmarized briefly below:
t e Committee continued its evaluation of the March 28, 1979 accident at Three Mile Island Nuclear Station Unit 2 (TMI-2) and the implications of this accident. We Committee menbers also exchanged preliminary views regarding the effectiveness of the nuclear regulatory process.
We Committee responded to a request from Cmmissioner Bradford for a clarification of the August 13, 1979 ACRS Reprt on Short-term Lessons Learned from TMI-2.
Copies of this response have been provided to you and the other Commissioners.
We Comittee discussed proposed replies to requests frm Commissionor Ahearne and Commissioner Bradford regarding follow-up and implementation of ACRS reccmendations and NRC regulations which may need to be addressed promptly in order to ensure public health and safety. Further discussion of these matters is planned during the 236th ACRS Meetiq.
Se Comittee reviewed the NRC Staff's report, Investigation into the March 28, 1979 Three Mile Island Accident (NUR&-0600). A copy of the Committee's report om this matter has been sent to you.
We Comittee met with members of the NRC Staff to discuss the NRC response to the report of the President's Comission on tree Mile Island, recent regulatory activities related to calculated clad-swellig during a postula-ted I4CA transient, requirements for the combination of dynamic loads in the analysis of nuclear power plant structures and piping, the NRC Staff's proposed schedule for the resolution of currently unresolved safety issues, and systens interactions resultig fran postulated steam line breaks out-side containment.
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Honorable Joseph M. Hendrie November 21. 1979 he Comittee concurred in the regulatory position of Regulatory Guide 1.141 (Rev.1), Containment Isolation Provisions for Fluid Systems, with the condition that the implementation section of this Guide be revised consistent with the 7MI-2 Lessons Learned Task Force reccminda:lons (NUREG-0578).
In addition, the Coramittee agreed with the NRC Staff's plan to issue Proposed Regulatory Guide 1.97 (Rev. 2), Instrumentation for Light-Wa*er-Cooled Nuclear Power Plants to Assess Plant and Envirens Conditions Iwing and Following an Accident, for public comment. We Executive Director for Operations has been informed of these determina-tions.
Dr. Milton S. Plesset and Dr. J. Carson Mark were nominated to be ACRS Chairman and Vice-Chairman, respectively for CY 1980.
Since the last reprt of ACRS activities, the following subcommittee meetings have been held:
Radiobiological Effects and Site Evaluation in Washigton, DC on October 16-17, 1979 Emergency Core Coolirs Systems, in Washington, IE on October 17-18, 1979 Iacrosse Boiling Water Reactor, in Washington, DC on October 26, 1979 tree Mile Island Unit 2, Accident Investigation, in Washington, CC on October 31, 1979 Waste Management, in Washington, DC on October 31, 1979 Sequoyah Nuclear Plant, in Washirgton, DC on November 5,1979 Metal Components, in Washington, DC on November 5, 1979 tree Mile Island Unit 2, Accident Implications, in Washirgton, DC on November 5, 1979 Reactor Safety Research, in Washington, CC on Novenber 6-7, 1979 Reliability arxl Probabilistic Assessment, in Washington, DC on November 6-7, 1979 Regulatory Activities, in Washington, DC on November 7,1979 Procedures and Administration, in Washington, DC on November 7,1979 1797 112
Honorable Joseph M. Hendrie November 21, 1979 The following itens are tentatively scheduled for consideration during the 236th ACRS Meeting, December 6-8, 1979:
Review of Regulatory Processes and Procedures - effectiveness of program Discussion of Recommendations of the President's Commission on the tree Mile Island Accident - Safety Implications and Recommendations Relating to ACRS Review of B ree Mile Island Unit 2 Lessons Learned Final Report Resolution of Unresolved Safety Issues Discussion of NRC " Pause" in Licensing of Nuclear Power Plants Discussion of Systems Interactions resulting from Rupture of High-Pressure, High-Temperature Piping and Components NRC Rules ard Regulations - Proposed Changes Follow-Up ard Implementation of ACRS Recommendations Sincerely yours, 6$
Max W. Carbon Chairman 1797 113