ML19310A900
| ML19310A900 | |
| Person / Time | |
|---|---|
| Issue date: | 04/22/1980 |
| From: | Plesset M Advisory Committee on Reactor Safeguards |
| To: | Ahearne J NRC COMMISSION (OCM) |
| References | |
| FOIA-80-505 ACRS-SL-0248, ACRS-SL-248, NUDOCS 8006300661 | |
| Download: ML19310A900 (3) | |
Text
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- ( - ',j NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS p
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WASHINGTON, D. C. 20555
% ~...= f April 22, 1980 Honorable John F. Ahearne Chairman U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
TWO-HUNDRED-FORTIETH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, APRIL 10-12, 1980
Dear Dr. Ahearne:
The Advisory Committee on Reactor Safeguards held its 240th meeting in Washington, DC on April 10-12, 1980.
Items considered at this meeting are summarized below:
The Committee met with members of the NRC Staff to review NUREG-0660, Draft 3 of the NRC Action Plan Developed as a Result of the TMI-2 Accident.
The Committee met with members of the NRC Staff and with representatives of the nuclear power industry to discuss resolution of the generic issue, Anticipated Transients Without Scram (ATWS).
The Committee discussed the Reorganization Plan No. 1 of 1980 as it affects ACRS activities.
The Committee met with members of the NRC Staff and representatives of Offshore Power Systems to discuss the proposed core ladle design for the Floating Nuclear Plant.
The Committee has sent you separate reports on the matters noted above.
The Committee met with the NRC Staff and with representatives of the Babcock and Wilcox Company (B&W) to discuss the transient response and vulnerability of B&W nua. lear steam sucoly systems.
The Committee has pro-vided an initial report regarding B&" Plants under construction and plans to continue consideration of NUREG-0667, Transient Response of Babcock and Wilcox Designed Reactors during its 241st meeting.
The Committee discussed a propos,ed reply regarding clarification of the Cacember 11, 1979 ACRS report on the pause in licensing. Additional dis-cussion is planned during the ?.41st meeting.
Members of the NRC Staff br'ie/ed the Committee on the reorganization of the Office of Nuclear Reactor Regulation and the stat is of the low-power test program at the Seauoyah Nuclear Power Plant Unit '.
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Honorable John F. Ahearne April 22, 1980 The Committee met with members of the NRC Staff to discuss the proposed Muclear Data Link between operating nuclear power plants and the NRC's Operations Center in Bethesda.
The Committee plans to continue considera-tion of this matter during its 241st m'eeting.
The Committee endorsed proposed changes to Regulatory Guides on Qualifica-tions of Insoection, Examination and Testing Personnel for Nuclear Power Plants and Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants. The Acting Executive Director for Operations has been advised of this action.
The Conmittee met with you and Comraissioners Bradford and Gilinsky to discuss matters related to the NRC Action Plans and recovery operations at TMI-2.
Since the last report of ACRS activities, the following Subcommittee meetings have been held:
ECCS, in Washington, DC on March 25, 1980 ATUS, in Washington, DC on March 26, 1980 Decay Heat Removal Systens, in Washington, DC on March 26, 1980 HRC Action Plans, in Bethesda, MD on April 1-2, 1980 B&W Water Reactors, in Washington, DC on April 8,1980 TMI-2 Accident Implications, in Washington, DC on April 9,1980 Regulatory Activities, in Washington, DC on April 9,1980 Power and Electrical Systeas, in Washington, DC on April 9,1980 Reactor Safety Research, in Washington, DC on April 9,1980 The following items are tentatively scheduled for consideration during the 241st ACRS lieeting, May 1-3, 1980:
- Nuclear Data Link -- installation and use of NDL systems
- NUREG-0660, NRC Action Plans -- application to near-term construction permits
- NUREG-0667, Transient Response of B&W-Designed Reactors -- ACRS comments
- Shippingport Light-Water Breeder Reactor -- extension of core life i
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Honorab!2 John F. Ahearne April 22, 1980 i
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- Feasibility of molten core retention -- ACRS comments
- ACRS Report on the NRC Bulletins and Orders Task Force report --
clarification of ACRS report
- Proposed NRC Rule (10CFR Part 50) on Emergency Planning -- ACRS comments.
Sincerely yours, 4
Milton S. Plesset Chai rman i
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