ML19290A153
| ML19290A153 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/19/1979 |
| From: | Carbon M Advisory Committee on Reactor Safeguards |
| To: | Hendrie J NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0237, ACRS-SL-237, NUDOCS 7910170443 | |
| Download: ML19290A153 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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y April 19, 1979 Honorable Joseph M. Hendrie Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
'IWO-HUNDRED 'IWENTY-EIGHTH MEETIN3 OF 'IHE ADVISORY COMMITI'EE CN REAC'IOR SAFEGUARDS, APRIL 5-7, 1979 AND SPECIAL ACRS MEETING, APRIL 16-17, 1979 IN WASHING'"ON, DC
Dear Dr. Hendrie:
The Advisory Committee on Reactor Safeguards held its 228th meeting in Washington, DC, on April 5-7, 1979.
Items considered at this meeting are summarized briefly below:
Projects The Committee began its review of the application for a Construction Permit for the Palo Verde Nuclear Generating Station Units 4 and 5.
The Committee began its review of the application for an Operating License for the Sequoyah Nuclear Power Plant Units 1 and 2.
Additional consideration will be given to the above matters at a sub-sequent meeting.
The Committee began its investigation of the accident at the Three Mile Island Nuclear Station Unit 2.
An interim report on this matter was sent to you on April 7, 1979, and further evaluation is planned.
Miscellaneous
'Ihe Committee concurred in the regulatory position of Regulatory Guide 1.140 (Rev.1), Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants.
The Committee was briefed by personnel from the Department of Energy (DOE) on the status and safety aspects of the propose! Tokomak Fusion
. Test Reactor and other DOE sponsored controlled thermonuclear fusion projects.
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?:21:;,w.m.2 w.w.cMuscu sen.n.:a.u 6..:Ar.uu-ta.z;w.a. ch w.T. ;.R... _...... y Honorable Joseph M. Hendrie April 19, 1979 h e Committee met with the NRC Commissioners and discussed the following matters: the combination of dynamic loads as a design basis for nuclear power plants; seismic design of piping for nuclear power plants; release of primary coolant and apparent core damage at Three Mile Island Nuclear Station Unit 2; timing and scope of the ACRS Annual Report on the NRC Safety Research Program; the use of probabilistic cssessment in the licensing process; support of ACRS consultants in NRC hearings; and the ACRS use of foreign travel funds.
A Special Meeting of the ACRS was held in Washington, DC on April 16-17, 1979, to inquire further into the accident at the % ree Mile Island Nuclear Station, the effects of this accident on other Babcock and Wilcox Plants, and the effects on other pressurized water reactors. W e Com-mittee met briefly with the Commissioners to discuss the status of this review and to provide verbal recommendations regarding this matter.
Subcommittee Meetings and Site Visits Since the last report of Committee activities, the following subcommittee meetings and site visits have been held:
Sequoyah Nuclear Power Plant, in Washington, DC on March 12, 1979 Fort St. Vrain Nuclear Generating Station (site visit), on March 15, 1979 Emergency Core Cooling Systems, in Los Angeles, CA on March 19-20, 1979 Licensee Event Reports, in Washington, DC on March 23-24, 1979 Nuclear Powered Surface Ship (site visit), in Norfolk, VA, on March 26, 1979 Palo Verde Nuclear Generating Station, in Phoenix, AZ on March 29,'1979 Power and Electrical Systems, in Phoenix, AZ on March 30, 1979 Regulatory Activities, in Washington, DC on April 4, 1979 Three Mile Island Nuclear Station, in Washington, DC on April 4, 1979 2223 339
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Honorable Joseph M. Hendrie April 19, 1979 Future Schedule
'Ihe 229th meeting of the ACRS will be held in Washington, DC on May 10-12, 1979. 'Ihe following matters are tentatively scheduled for discussion:
Millstone Nuclear Power Station Unit 2 - Increase in operating power Combination of Dyarmic Loads - use as a regulatory requirement Anticipated Transients Without Scram - Proposed alternative for resolution
'Ihree Mil 6 Island Nuclear Station Unit 2 - evaluation of recent accident Palo Verde Nuclear Generating Station Units 4 and 5 - construction Sequoyah Nuclear Power Plant Units 1 and 2 - cperation Sincerely, Max W. Carbon Chairman 2223 340 9