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NRC Seal NRC NEWS
U. S. NUCLEAR REGULATORY COMMISSION
Office of Public Affairs Telephone: 301/415-8200
Washington, DC 20555-001 E-mail: opa@nrc.gov
Web Site: http://www.nrc.gov/OPA

No. 00-124 August 9, 2000

NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS TO MEET IN ROCKVILLE, MARYLAND, AUGUST 29 - SEPTEMBER 1

The Nuclear Regulatory Commission's Advisory Committee on Reactor Safeguards has scheduled a meeting from August 29 - September 1 in Rockville, Maryland, to discuss operating events at Indian Point Unit 2 Nuclear Power Plant among other nuclear power plant issues.

The meeting, most of which will be open to the public, will be held in Room T-2B3 of the agency's Two White Flint North building, at 11545 Rockville Pike, starting at 8:30 each day.

On the opening day, the committee will hold discussions with representatives of the NRC staff and the Nuclear Energy Institute (NEI) regarding the proposed agency framework document for risk-informing the technical requirements of Part 50 (relating to nuclear power plants) of the Commission's regulations. Other issues to be discussed include the causes and significance of design basis issues for nuclear power plants and proposed final Regulatory Guide (DG-193) endorsing the NEI's document on design bases. The Committee will also hold discussions with the NRC staff and Westinghouse officials on issues identified during the pre-application review for the AP-1000 advanced nuclear reactor.

On August 30, the committee will discuss performance-based regulatory initiatives, the contents of the proposed Standard Review Plan on License Renewal, "Generic Aging Lessons Learned Report," and an associated Regulatory Guide and NEI guidance documents. In addition, the committee will hear presentations by and hold discussions with NRC staff and Consolidated Edison regarding events that occurred at the Indian Point Unit 2 Nuclear Power Plant in New York and associated staff findings, conclusions, and recommendations resulting from evaluations of the February 15 steam generator tube rupture event there and the August 31, 1999, event involving reactor trip and loss of all off-site power. Lastly, the committee will discuss a Siemens Corporation code for application to analysis of transients and small-break loss-of-coolant accidents.

On August 31, the committee will discuss the responses from the NRC Executive Director for Operations to comments and recommendations included in recent ACRS reports and letters, as well the recommendations of the ACRS Planning and Procedures Subcommittee on items proposed for consideration by the full Committee. Additional topics of discussion will include the format and content of the ACRS' annual report to the Commission on the NRC Safety Research Program, and an upcoming October 6 session with NRC Commissioners.

On the final day of the meeting, the committee will continue its discussion of proposed ACRS reports.

Those who wish to make oral or written statements, or seek additional information on the meeting or changes to the agenda should contact Howard Larson, at 301-415-6805.

A detailed agenda and other aspects of the meeting are described in today's edition of the Federal Register. ACRS meeting notices, transcripts and letters are available on the internet, at http://www.nrc.gov/ACRSACNW.

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