ML19319B748
| ML19319B748 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 11/18/1976 |
| From: | Hoyle J NRC OFFICE OF THE SECRETARY (SECY) |
| To: | |
| Shared Package | |
| ML19319B747 | List: |
| References | |
| NUDOCS 8001270209 | |
| Download: ML19319B748 (4) | |
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O reaer 1 aesister netice NUCLEAR REGULATORY CO) MISSION i
ADVISORY COSMITTEE ON REACTOR SAFEGUARDS Notice of Proposed Meetings In order to provide advance information regarding proposed meetings of ACRS Subcocunittees and Working Groups and of the full Coctuittee, the following preliminary schedule is being published. This preliminary schedule reflects the current situation, taking into account additional meetings which have been scheduled and meetings which have been postponed or cancelled since the last list of nroposed meetings published in FR Vol. 41, October 26, 1976, page 46912. Those meetings that are definitely scheduled have had, or will have, an individual notice published in the FR approximately 15 days (or more) prior to the meeting. These Sub-comittee and Working Group meetings for which it is anticipated that there will be a portion or all of the meeting open to the public are indG ad by an asterisk (*).
It is expected that the sessions of the full Com!..:ee meeting designated by an asterisk (*) will be open in whole or in part to the public. Information as to whether a meeting has been firmly scheduled, cancelled, or rescheduled, or whether changes have been made in the agenda for the December 9-11, 1976 ACRS full Committee meeting can be obtained by a prepaid telephone call to the Of fice of the Executive Director of the Committee (telephone 202/634-1,374, Attn: Mary E. Vanderhc it) between 8:15 a.m. and 5:00 p.n., EST.
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- Pressurized Water Reactor Pressure Vessel Blowdown Forces, December 1, 1976, Los Angeles, CA to discuss with the NRC Staff and representatives of the Licensees, as appropriate, the effects of blowdown forces on pressurized water reactor pressure vessels designed by Babcock and Wilcox Electric Corp.
Company, Combustion Engineering, Inc., and Westinghouse / NRC funded research in this area will also be discussed. Notice of this meeting was published in FR Vol. 41, page 50361, November 15, 1976.
- Assessment of Se'ected Light-Water Reactor Safetv Matters, December 3, 1976, Washington, DC to review selected matters related to LWR safety referred to it by NRC. Notice of this meeting was published in FR Vol. 41, November 19, 1976 and also appears elsewhere in this issue.
- Resolution of Generic Items, December 7,1976, Washington, DC to consider the current status and degree of resolution of the generic items identified in the Committee's report dated April 16, 1976. Notice of this meeting appears elsewhere in this issue.
- Regulatory Guides, December 8,1976, Washington, DC to review working papers regarding future Regulatory Guides and proposed cht.nges to existing Guides. Notice of this meeting appears elsewhere in this issue.
- Clinch River Breeder Reactor, December 8,1976, Washington, DC to develop information for concideration by the ACRS in its review of the combined application of the U. 5. Energy Research and Development Administration, the Tennessee Valley Authority, and the Project Management Corporation for a permit to construct this nuclear power plant.
In particular, this meeting will concern aspects of a core disruptive accident and of thermal hydraulics.
Notice of this meeting appears elsewhere in this issue.
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- Reactor Safety Study, December 8,1976, Washington, DC to continue the i
L review of WASH-1400 (NUREG-75/014), "An Assessment of Accident Ricks in U. S. Commercial Nuclear Power Plan;.t."
Notice of this meeting appears
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elsewhere in this issue.
- North Anna Power Station, Units 1 and 2, rescheduled from December 8, j
1976 to January 5, 1977.
- Emergency Core Cooling System, December 20, 1976, Washington, DC to j
discuss technical aspects associated with plenum filling following a i
loss-of-coolant accident.
- Emergency Core Cooling System, December 21, 1976, Washington, DC f
(rescheduled from November 6,1976) to review EXXON Nuclear Company, Inc.
analytical models formulated to meet current ECCS criteria for fuel fabricated by EXXON for pressurized water reactors with ice condensers and for nonjet-pump boiling water reactors, and to review the application of these models to the Donald C. Cook, Unit No. I and the Oyster Creek, Unit No.1 Nuclear Power Plants.
- Davis-Besse Nuclear Power Station, Unit 1, December 21, 1975, Washington, DC to review the application of the Toledo Edison Company for an operating license.
Power
- Donald C. Cook Nuclear / Plant. Unit 1, December 22, 1976, Washington, DC to continue the review of the EXXON Nucicar Company, Inc. fuel reload, the related emergency core cooling syste ' analysis, and other itema to determine if the plant should be allowed to operate at a 100% power level following r(fueling.
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. *Regulatorv Guides, January 5,1977, Washington, DC to review working r
papers regarding future Regulatory Guides and proposed changes to existing Guides.
- North Anna Power Station, Units 1 and 2, January 5,1977, Washington, DC to develop information for consideration by the ACRS in its continuing review of the application of the Virginia Electric and Power Co=pany for a license to operate North Anna Power Station, Units 1 and 2.
- Cherokee Nuclear Station, Units 1, 2, and 3, and Perkins Nuclear Station, Units 1, 2, and 3, January 19, 1977, Charlotte, NC to review the applica-these Units.
tion of the Duke Power Company for a permit to construct
- Seismic Activity, February 8-9, 1977, Washington, DC, to discuss Appendix A to 10 CFR 100 and the derivation of earthquake response spectra.
Full Committee Meetings December 9-11, 1976
- General Electric Standard Safety Analysis Report (GESSAR-238/GESSAR-251) --
Preliminary Design Approval January 6-8, 1977 Agenda to be announced.
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M [7117 John C. Hoyle Date Advisory Committee r
Management Officer
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