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INFORMATION REPORT SECY-05-0161 September 6, 2005
Contact: T. Kim, OEDO Office of Nuclear Reactor Regulation (NRR) Oconee - Issuance of License Amendment to Allow Continued Operation On August 23, 2005, NRR issued an operating license amendment for all three units of Oconee Nuclear Station to allow continued operation of the plant for an additional 96 hours with one of the two Keowee hydro units out-of-service. Since the Keowee hydro units provide the onsite emergency power system (similar to emergency diesel generators at other nuclear stations) for all three units of Oconee Nuclear Station, the technical specifications included in the Oconee operating licenses require shutdown of all three units if one of the hydro units are found to be inoperable for more than 72 hours. On August 20, the second Keowee hydro unit experienced electrical generator malfunction during routine testing. While continuing with troubleshooting and repair efforts, the licensee requested an emergency license amendment on August 21 permitting a one-time extension of 96 hours to continue its troubleshooting and repair efforts beyond the 72 hours allowed by the technical specifications. The licensee was able to restore the hydro unit back in operable status on August 25, prior to the expiration of the additional time permitted by the license amendment. The NRR staff's safety evaluation report for this license amendment is publicly available on the Agency Document Access and Management System under accession number ML052410071. Palo Verde - Equipment Problem Resulting in Plant Shutdown On August 22, 2005, the licensee shut down Palo Verde Unit 2, as required by the station technical specifications, upon its determination that all four channels of the Core Protection Calculator (CPC) system were inoperable. The licensee identified a vulnerability in the software platform used for the CPC system that could prevent the system from performing its safety function if redundant analog input failures occur simultaneously. The licensee is evaluating software modifications to remove this vulnerability. NRR staff is evaluating potential generic implications. To date, Palo Verde Unit 2 is the only U. S. nuclear power plant utilizing this software platform in a safety-related application. Regulatory Issue Summary (RIS) 2005-19: Preparation and Scheduling of Operator Licensing Examinations On August 24, 2005, NRR issued the subject RIS to inform power reactor licensees of the NRC staff's need for updated information on projected site-specific operator licensing examination schedules and the estimated numbers of applicants planning to take operator licensing examinations and the NRC's generic fundamentals examinations. This RIS requires no action or written response on the part of addressees. Actions to collect and transmit the information noted in the RIS are strictly voluntary. Draft Proposed Rule Language for Revision of 10 CFR Part 52 Available on NRC Website On August 25, 2005, NRR staff posted the subject draft rule language for revision of 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants," on the NRC's rulemaking Web site at http://ruleforum.llnl.gov/cgi-bin/rulemake?source=draft_p52&st=risk. The staff is posting draft rule language on the Web site to inform stakeholders of the current status of the Part 52 update rulemaking in advance of submittal of the proposed rulemaking package to the Commission, due by October 31, 2005. This information will aid stakeholders who may begin preparing early site permit or combined license applications in the near future and will inform all stakeholders of the staff's proposals regarding changes to Part 52 and related regulations. Oyster Creek - Public Meeting on License Renewal Review Process On August 24, 2005, NRR staff, together with representatives from the Offices of Public Affairs, General Counsel, Nuclear Security and Incident Response, and Region I, conducted a public meeting in Lacey, New Jersey, regarding the license renewal application for the Oyster Creek Nuclear Generating Station, which was received on July 22, 2005. The purpose of the meeting was to inform the public on the NRC's license renewal review process and to answer questions. About 150 people attended the meeting, including State and local officials, licensee representatives, and members of the public and the media. A number of questions were raised regarding the scope of the license renewal review and public's ability to participate in the NRC's license renewal review process. Office of Nuclear Material Safety and Safeguards (NMSS) Public Meeting with DOE Regarding the Savannah River Site On August 17-18, 2005, Division of Waste Management and Environmental Protection staff met with representatives of the Department of Energy (DOE) at the North Augusta Community Center in North Augusta, GA. The purpose of this meeting was to discuss NRC’s requests for additional information regarding DOE’s draft Incidental Waste Determination for Salt Waste Disposal at the Savannah River Site (SRS). Representatives of the SRS Citizens Advisory Board, the South Carolina Department of Health and Environmental Control, the Environmental Protection Agency, and the National Academy of Sciences also attended the meeting. Onsite Review of USEC Inc.’s Integrated Safety Analysis for the American Centrifuge Plant On August 15-17, 2005, Division of Fuel Cycle Safety and Safeguards staff conducted an onsite review of USEC Inc.’s (USEC’s) Integrated Safety Analysis (ISA) for the proposed American Centrifuge Plant (ACP) to be built and operated in Piketon, OH. The staff conducted walk-downs of some of the existing facilities at the Portsmouth Gaseous Diffusion Plant site that are relevant to the ACP and met with technical staff from USEC. USEC agreed to address issues raised by NRC staff during the review in its ISA Summary. USEC will submit its revised ISA Summary and corresponding changes to the license application to NRC for review. Office of Nuclear Regulatory Research (RES) Meeting of the International Cooperative Group and Research Program for Proactive Materials Degradation Management On August 16 - 19, 2005, RES staff and contractors from Pacific Northwest National Laboratory held the first formal meeting with representatives from several nations to plan an International Cooperative Group and Research Program focused on Proactive Materials Degradation Management (PMDM). This planning meeting was held in conjunction with the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Participants represented utilities, regulators, manufacturers, universities, and research laboratories from Belgium, Canada, Czech Republic, Finland, France, Germany, Japan, Korea, Spain, Sweden, Switzerland, United Kingdom, and United States. At this meeting, the staff provided background information on the NRC's efforts to identify components susceptible to possible future degradation. In addition, industry presented their proactive degradation assessment work. Finally, the staff discussed a detailed plan to coordinate an international agreement to conduct a cooperative PMDM program. A second meeting is planned to be held with potential participants later this year. 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors On August 15-18, 2005, RES staff participated in the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of the conference was to present current information about materials degradation in nuclear power plants and to discuss prevention and mitigation strategies. The conference focused on degradation of nickel base alloys, stainless steels, pressure vessel and piping steels, zircaloys, and other alloys in the water environments relevant to nuclear power plant components. Publication of Draft Regulatory Guide DG-1128 for Public Comment On August 26, 2005, RES issued the subject draft regulatory guide DG-1128, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants," for public comment. It is publicly available on the NRC's Web site at http://ruleforum.llnl.gov/cgi-bin/library?source=*&library=rg_lib&file=*&st=draftrg. This draft regulatory guide endorses the Institute of Electrical and Electronics Engineers (IEEE) Standard 497-2002, "Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations," with certain clarifying regulatory positions. This proposed regulatory guide is intended for applicants of new nuclear power plants; however, licensees of current operating reactors may voluntarily convert their entire accident monitoring program to the criteria in this proposed revision. Completion of Integrated Chemical Effects Test # 5 On August 25, 2005, the integrated chemical effects Test # 5 was completed as part of the Integrated Chemical Effect Testing (ICET) program to support the resolution of Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," issued on September 13, 2004. RES staff was on hand to witness the completion of Test # 5 at the University of New Mexico, Albuquerque, NM. Test # 5 parameters included 100 percent fiberglass insulation and sodium tetraborate buffer. Sodium tetraborate is a buffering agent that is used in ice condenser containment pH control under accident conditions. Participation in the 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT-18) On August 7-12, representatives from RES and the Offices of Nuclear Reactor Regulation and Nuclear Material Safety and Safeguards participated in the SMiRT-18 Conference held in Beijing, China. SMiRT conferences have been held biennially since 1971 and have become the leading conference on structural safety of nuclear plants and facilities. NRC representatives presented technical papers on ongoing NRC research programs, seismic designs for independent spent fuel storage installations, and also served as chairperson on several conference sessions. The conference sessions included structural/thermal analysis and testing of nuclear structures, spent fuel storage systems and core structures, life extension and license renewal, seismic soil-structure and fluid-structure interaction. SMiRT-18 also included a new session, "Generation IV," on new reactor designs. Office of Nuclear Security and Incident Response (NSIR) Preliminary Notifications
Office of Human Resources (HR)
Office of Public Affairs (OPA) The Office of Public Affairs (OPA) received significant media inquiries on the following: Oyster Creek license renewal application and compliance with the Coastal Zone Management Act. Keowee Hydro Station electrical problems affecting Oconee. New reactor design and licensing. Other OPA Items: OPA supported a FOX News interview with Chairman Diaz on the new reactor licensing process. OPA supported an ABC News interview with the Director - Office of Nuclear Security and Incident Response on research reactor security. OPA supported a public meeting on license renewal at Oyster Creek.
Office of the Secretary (SECY)
Commission Correspondence
Region I (RI) Indian Point - Meeting hosted by the Westchester County Executive on Emergency Sirens On August 24, 2005, Westchester County Executive Andrew Spano hosted a meeting on the Indian Point emergency sirens. The meeting attendees included representatives from: Westchester, Putnam, Rockland, and Orange Counties; the New York Public Services Commission, Entergy (the licensee for the Indian Point Energy Center), the Federal Emergency Management Agency Region II, the New York State Emergency Management Office, Verizon and NRC Region I. The purpose of the meeting was for participants to gain a common understanding of the recent siren problems and the actions being taken to address these issues. Region II (RII) Commissioner Jaczko Visit to Framatome ANP Richland, Inc. On August 23, 2005, Commissioner Jaczko, accompanied by the Regional Administrator, visited the Framatome facility in Richland, Washington for a site tour and meetings with licensee management. Meeting with NRC’s Advisory Committee on Reactor Safeguards (ACRS) On August 24-25, 2005, members of the ACRS Subcommittees on Plant Operations and Fire Protection visited Region II offices and met with Region II management and staff to discuss various regional inspection, enforcement, and operational activities. On the previous day, the members visited the Browns Ferry Nuclear Station for a plant tour and discussions with the licensee management regarding plant status including the restart activities for Unit 1. Visit by Russian Federation’s Rostekhnadzor and Department of Energy (DOE) On August 25, 2005, Mr. Victor Neretin, Division Director of the Office of the Russian Federation’s Rostekhnadzo and representatives of DOE met with the Regional Administrator and staff from the Division of Fuel Facility Inspection to discuss items of mutual interest associated with the proposed MOX [mixed oxide] fuel fabrication facility. The staff briefed the visitors on the NRC’s proposed Fuel Facility Inspection Procedures. Region III (RIII) Point Beach - Public Meeting with Nuclear Management Company (NMC) On August 25, 2005, Region III staff met with NMC representatives in Two Creeks, Wisconsin, to discuss the licensee’s progress in meeting its commitments as documented in the Confirmatory Action Letter (CAL), dated April 21, 2004. NMC representatives provided a detailed overview of results, progress, and challenges in implementing improvements in the corrective action program and plant engineering. A meeting summary will be issued within the next two weeks, and a copy will be publicly available from the Publicly Available Records System (PARS) component of NRC's document system (ADAMS). |
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