ML20052C829
| ML20052C829 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Byron, Waterford, Clinton, 05000000 |
| Issue date: | 03/19/1982 |
| From: | Shewman P, Shewmon P Advisory Committee on Reactor Safeguards |
| To: | Palladino N NRC COMMISSION (OCM) |
| References | |
| ACRS-SL-0272, ACRS-SL-272, NUDOCS 8205050600 | |
| Download: ML20052C829 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 5
- E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 s****/
March 19,1982 A
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O239 Honorable Nunzio J. Palladino C
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Subj ect: TWO-HUNDRED-SIXTY-THIRD MEETING OF THE ADVISORY COMM 'TEEIONJEACTOR SAFEGUARDS, MARCH 4-6, 1982
Dear Dr. Palladino:
The Advisory Committee on Reactor Safeguards held its 263rd meeting in Washington, DC on March 4-6, 1982.
Items considered at this meeting are summarized below:
263rd ACRS Meeting The Committee met with representatives of the NRC Staff and the Illinois Power Company to review the request for a full power Operating License for the Clinton Power Station Unit 1.
The status of the Mark III Containment Program was also discussed.
The Committee met with representative of the NRC Staff and the Commonwealth Edison Company to review the request for a full power Operating License for the Byron Station Units 1 and 2.
The Committee met with representatives of the NRC Staff and Louisiana Power and Light Company to complete its review of the request for a full power Operating License for the Waterford Steam Electric Station Unit 3 (Waterford-3).
The Committee met with representatives of the NRC Staff and the Power Authority of the State of New York (PASNY) to review the PASNY proposal to perform a systems interactions study of the Indian Point Nuclear Generating Station Unit 3.
The Committee met with members of the NRC Staff to discuss its review of the NRC's Contract Review Panel recommendations for the selection of a contractor to develop a methodology for predicting Long-Term Performance of Materials Used for High-Level Waste Packaging.
The Committee discussed the status of its consideration of the proposed Licensee Event Report (LER) Rulemaking.
ACRS reports regarding the items noted above have been provided to you.
The Committee approved a memorandum to the EDO containing ACRS recommendations regarding Revision 3 to Proposed Regulatory Guide 1.28, Quality Assurance Program Requirements (Design and Construction) (Task No. 002-5). A copy has been provided to you.
DESIGNATED ORIGINAL 8205050600 820319
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[-O PDR Itified By
Honorable Nunzio J. Palladino March 19, 1982 The Committee was briefed by members of the NRC Staff regarding improved quality assurance program requirements at nuclear power plants.
The Committee discussed the five-year program planned by NRC for development of environmental qualification criteria for safety-related equipment. The ACRS was briefed by representatives of the NRC Staff regarding proposed requirements in IEEE 323-1974 for qualification of electrical equipment. Additional ACRS review of this matter is planned.
ACRS Subcommittee Activity Since the last report of ACRS activities, the following subcommittee meetings have been held:
Qualification Program for Safety-Related Equipment, in Washington, DC on February 10, 1982 Reactor Radiological Effects, in Washington, DC on February 11, 1982 Metal Components and Waste Management Program in joint session, in Washington, DC on February 12, 1982 Zimmer Nuclear Station, in Cincinnati, OH on Fesidary 18, 1982 Byron Station Units 1 and 2, in Rockford, IL on February 25-26, 1982 Clinton Station Units 1 and 2, in Decatur, It on February 25-26, 1982' Safety Philosophy, Technology, and Criteria, in Washington, DC on February 26, 1982 Regulatory Activities, in Washington, DC on March 3,1982 Waterford Steam Electric Station Unit 3, in Washington, DC on March 3,1982 Reactor Operation, in Washington, DC on March 3, 1982 Future Schedule The following items are tentatively scheduled for consideration during the 264th ACRS meeting, April 1-3, 1982:
ACRS comments on the proposed NRC Long-Range Research Program Plan Discussion with the NRC Staff regarding reactor pressure vessel liquid level indication l
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Honorable Nunzio J. Palladino March 19, 1982 Briefing by the NRC Staff regarding the incorporation of the Fire Protection Rule,10 CFR Part 50.48, Appendix A in the new NRC Standard Review Plan ACRS comments regarding proposed changes in seismic design methodology ACRS comments regarding NUREG-0799 (Draft), Criteria for Preparation of Emergency Operating Procedures Sincerely, P. Shewmon Chairman
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