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INFORMATION REPORT SECY-04-0009 January 28, 2004
Contact: M. Markley, OEDO Office of Nuclear Reactor Regulation Conference Call with Senior Staff Members for Vermont Senators Jeffords and Leahy On January 15, 2004, NRC staff from NRR, Region I, and the Office of Congressional Affairs held a conference call with senior staff members for Vermont Senators Jeffords and Leahy to discuss issues related to extended power uprates (EPUs). The call was requested, in part, due to requests from the Senators' constituents for an independent safety assessment (ISA) of Vermont Yankee (VY) (similar to the Maine Yankee ISA), due to public concerns regarding Entergy's EPU amendment request dated September 10, 2003. The NRC staff discussed the EPU review process, the status of the NRC's review of the VY EPU amendment request, including the containment overpressure issue, and the independence in various NRC activities and processes. The Senators' staff advised NRC representatives that formal correspondence relating to the VY EPU application will follow. LaSalle County Station Unit 1 Steam Dryer Cracking During refueling outage inspection activities on January 18, 2004, LaSalle identified cracking on a lower guide rod follower bracket at the base of the steam dryer. The licensee plans to make repairs. Additionally, three indications of possible cracking at the top of the barrel were found. The licensee stated that these may be scratches and General Electric has recommended power brushing the indications. No apparent moisture carryover problems, which has been associated with dryer cracking in the past, were noted during the past cycle of LaSalle Unit 1. The licensee is completing its steam dryer inspections and continuing to evaluate indications and potential damage. NRC staff is continuing to monitor inspection activities and licensee actions. LaSalle Unit 1 is a BWR-5 and received a 5% power uprate on May 9, 2000, as compared to Quad Cities and Dresden units which are BWR-3s and were approved for 17% extended power uprates. Exelon Early Site Permit (ESP) Application Proceeding The NRC received a petition from several organizations dated January 12, 2004, to intervene in the Exelon early site permit (ESP) application proceeding. In accordance with 10 CFR Part 52, a hearing is mandatory for an ESP, and a petition to intervene is a first step in admitting parties as litigants in that hearing. The organizations cited in the petition, which represent 16 individuals who live within 50 miles of the proposed ESP site (at Clinton), are the Environmental Law and Policy Center, Blue Ridge Environmental Defense League, Nuclear Information and Resource Service, Nuclear Energy Information Service, and Public Citizen. The petition asserts three aspects the petitioners believe are within the scope of the proceeding with regard to which they wish to intervene. In accordance with the hearing process set forth in 10 CFR Part 2, a Licensing Board appointed by the Commission will determine whether the petitioners have standing (individuals cited in the petition are affected by the proposed action) and whether at least one aspect cited in the petition is within the scope of the proceeding. The NRC Office of the General Counsel, with support as needed from the NRC staff, will develop the NRC's response to the petition, regarding whether the petitioners have standing and the aspects asserted in the petition are within the scope of the proceeding. Public Meetings on the Draft Supplemental Environmental Impact Statement in Support of License Renewal for Dresden Nuclear Power Station, Units 2 and 3 On January 14, 2004, the NRC staff conducted two meetings to solicit public comments on the draft supplemental environmental impact statement (SEIS) issued on December 2, 2003, in support of license renewal for the Dresden Nuclear Power Station, Units 2 and 3. The draft SEIS is a plant-specific supplement to the "Generic Environmental Impact Statement for License Renewal of Nuclear Power Plants" (NUREG-1437). Approximately 70 people attended the meetings, including representatives of the NRC staff, State and local governments, Exelon, news media, and members of the public. Seven individuals spoke at the meetings. The public comment period on the draft SEIS ends on February 24, 2004. Issuance of License Renewal Safety Evaluation Report for H. B. Robinson Steam Electric Plant, Unit 2 On January 20, 2004, the NRC staff issued the Safety Evaluation Report (SER) associated with the license renewal application for the H. B. Robinson Steam Electric Plant, Unit 2. The staff plans to present the results of its evaluation to the Advisory Committee on Reactor Safeguards (ACRS) in March 2004. License Renewal Pre-Application Meeting for the Point Beach Nuclear Plant, Units 1 and 2 On January 20, 2003, the staff held a public meeting with representatives from the Nuclear Management Company to discuss their upcoming license renewal application for Point Beach Nuclear Plant, Units 1 and 2. The most significant topic discussed at the meeting was pressurized thermal shock (PTS). The licensee discussed its exemption request under staff review for the use of a revised PTS calculation methodology based on the Babcock & Wilcox (B&W) proposed "Master Curve." The licensee stated that it would rely on the approval of this methodology for the PTS calculations of the Point Beach reactor vessels for license renewal. The licensee plans to submit its license renewal application on February 27, 2004. Meeting on 10 CFR Part 52 Combined License (COL) Issues On January 15, 2004, a public senior management meeting was held with the Nuclear Energy Institute (NEI) to discuss 10 CFR Part 52 combined license (COL) issues. Participants at the meeting included the Directors of NRR and RES. NEI requested the meeting with NRC senior managers to share information on priorities, schedules, and challenges in new plant licensing under 10 CFR Part 52. NEI discussed the 23 generic COL issues that have been identified. The staff indicated that discussions have begun on many of the COL generic issues but noted that some resource challenges exist for increased interactions on COL issues. The staff stated that it is currently planning for one COL application in FY 2006 and suggested that additional early site permits and COL applications could be a challenge. The staff emphasized its need to know industry's plans relative to COL applications as soon as possible. Emergency Preparedness Counterpart Meeting On January 20-23, 2004, the Division of Inspection Program Management staff hosted the Annual Emergency Preparedness (EP) counterpart meeting where NRC Headquarters and regional EP staff discussed issues of mutual interest. Because of the large number of topics and increased interest in the meeting, consideration is being given to increasing the meeting frequency to semi-annually or quarterly. Topics discussed during the EP counterpart meeting included the Reactor Oversight Process, Alert and Notification Systems, and updates on various topics such as potassium iodide (KI), U.S. Federal Emergency Management Agency (FEMA), and evaluation of dose/consequences during exercises. A portion of the meeting on January 21, 2004, was open to the public and was attended by Nuclear Energy Institute and licensees representatives. A series of topics was discussed, including emergency preparedness performance indicators, the significance determination process, and security issues. Office of Nuclear Material Safety and Safeguards Third Part of DOE Yucca Mountain Project Office Evaluation On January 12-16, 2003, staff from the Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses (CNWRA) performed the third part of a three-part evaluation of the Department of Energy's (DOE's) Yucca Mountain Project Office activities in Las Vegas, Nevada. During the three evaluation periods, staff independently verified technical information presented in high-risk-significant analysis model reports (AMRs); assessed DOE's processes for developing and controlling AMRs; and evaluated the effectiveness of DOE's corrective action process in eliminating recurring problems. The NRC staff plans to use these evaluations in determining DOE's ability to submit a high-quality, technically adequate license application, using its existing policies, procedures, methods, and practices. A final report discussing the evaluation effort will be issued and made publicly available. Meeting with BNFL Fuel Solutions Regarding Transport of VSC-24 Canisters in the Model No. TS125 Cask On January 15, 2004, Spent Fuel Project Office staff met with BNFL Fuel Solutions (BFS) to discuss the transport of VSC-24 spent fuel canisters in the Model No. TS125 Cask (NRC Certificate of Compliance No. 9276). The VSC-24 canister is part of a storage system that is currently approved under 10 CFR Part 72 (Certificate of Compliance No. 72-1007). BFS plans to request approval for shipment of the canisters, taking credit for fuel burnup and submit an application for package approval to NRC in December 2004. Meeting with Transnuclear, Inc. and Nuclear Management Company Regarding Transport of TN-40 Storage Casks On January 15, 2004, Spent Fuel Project Office staff met with Transnuclear, Inc. (TN) and Nuclear Management Company to discuss the possibility of certifying for transportation the TN-40 casks which are currently licensed only for storage of spent fuel at the Prairie Island nuclear power plant. The discussion focused on the proposed approaches by TN for qualifying the TN-40 casks for transport. Office of Nuclear Regulatory Research Public Meeting on Mitigating Systems Performance Index Pilot Program On January 21, 2004, at a public meeting to discuss technical and implementation issues with the Mitigating Systems Performance Index (MSPI) pilot, RES and NRR staff presented final results regarding the MSPI probabilistic risk assessment (PRA) adequacy issue, as well as comparisons between MSPI predicted results and those from the current Reactor Oversight Process (ROP). The meeting was attended by participants from NRC regional offices, industry representatives (e.g., Nuclear Energy Institute, Institute of Nuclear Power Operatins), and pilot plant licensees. The purpose of the MSPI is to monitor the performance of six systems based on their ability to perform risk-significant functions. These include the emergency AC power, high pressure injection, residual heat removal, and cooling water support systems for both pressurized water reactors (PWRs) and boiling water reactors (BWRs), and the auxiliary feedwater system for PWRs and heat removal systems for BWRs. The index, which approximates the change in core damage frequency, is comprised of two elements - system unavailability and system reliability. Plant-specific PRA models will be used to calculate the contribution of component failures and maintenance unavailability to the index. Technical Exchange Meeting with Framatome-ANP on the Teleperm XS Digital Safety Platform On January 16, 2004, RES staff participated in a technical exchange meeting with Framatome-ANP (FANP) on the Teleperm XS (TXS) digital safety platform. TXS has been generically approved for safety-related applications at power reactors in the United States. The meeting supports ongoing research on the three generically qualified digital safety platforms. FANP detailed technical information that will assist RES in developing guidance for performing future plant-specific reviews. RES plans to hold future discussions with FANP on these matters. Office of Administration Acquisition Training for NRC Project Managers On January 22, 2004, Division of Contracts conducted the Source Evaluation Panel Procedures Workshop as one of the twelve workshops offered under the NRC's Acquisition Certification Training Program. Chief Information Officer Conference on Platform for Privacy Preferences (P3P) On January 21, OCIO staff attended a P3P conference for Federal government agencies sponsored by the Center for Democracy and Technology and the American Council for Technology. The conference focused on methods for meeting new OMB requirements for Web site privacy issued under Section 208 of the E-Government Act. The requirements fall into two categories: (1) submission of an annual privacy impact assessment and (2) creation and maintenance of a machine-readable privacy statement in agreement with the natural language privacy statement that is already available at NRC's Public Web Site. Freedom of Information Act and Privacy Act Requests received during the period of January 16 through January 22, 2004:
Office of Human Resources
Office of Public Affairs Media Interest New delays in efforts to restart the troubled Davis-Besse nuclear plant in Ohio. NRC initiates special inspection at Kewaunee concerning nuclear plant safety pump problems that led to an unscheduled plant shutdown. An NRC-sponsored public meeting in Mississippi on Entergy's application for an early site permit at Grand Gulf. OPA assisted NRR staff in an interview with the Chicago Tribune on plant aging issues.
Office of the Secretary
Commission Correspondence
Federal Register Notices Issued
Region I Region I Conducts Response Technical Manual Training On January 21 and 22, 2004, NRC Region I conducted two, eight-hour training courses on the NRC Response Technical Manual (RTM). These courses were provided by an NSIR staff member and were attended by approximately 60 persons, including Region I management, four headquarters personnel, the Bureau Director of the Pennsylvania Department of Environmental Protection (DEP), and a DEP staff member. Yankee Rowe Citizen's Advisory Board Meeting On January 21, 2004, a Region I Branch Chief and inspector attended the quarterly meeting of the Yankee Rowe Citizen's Advisory Board in Rowe, MA. The Region I representatives described recent inspection results and planned inspection activities to the Board, as well as the review process for the Yankee Rowe License Termination Plan. The licensee presented the results of recent decommissioning progress, and a representative of the Massachusetts Department of Public Health (MDPH) described the risk evaluation MDPH will prepare for site release. Approximately 45 people attended the meeting, including a representative from a local weekly newspaper. Presentation to American Society of Mechanical Engineers On January 20, 2004, the Region I Deputy Director, Division of Reactor Safety, addressed the Philadelphia Chapter of the American Society of Mechanical Engineers at Villanova University. Approximately 70 engineers and engineering students attended the presentation on NRC licensing of advanced reactors. Region II Southeastern Nuclear Plant Manager's Meeting On January 20, 2004, the Regional Administrator attended the Southeastern Nuclear Plant Manager's Meeting in Orlando, Florida. Florida Power and Light Company - St. Lucie Nuclear Plant On January 21, 2004, the Regional Administrator visited the St. Lucie Nuclear Plant in Jensen Beach, Florida. The purpose of the visit was to tour the facility and meet with licensee management and the resident inspectors. 2004 NRC Regional Security Inspector's Counterpart Meeting On January 20-23, 2004, Region II hosted the 2004 NRC Regional Security Inspector Counterpart Meeting. The meeting included inspector training, briefings on current issues and comments by two representatives from the Office of Nuclear Security and Incident Response. United States Enrichment Corporation - Closed Predecisional Enforcement Conference On January 21, 2004, Region II held a closed Predecisional Enforcement Conference with United States Enrichment Corporation. The purpose of this Predecisional Enforcement Conference was to discuss apparent violations involving the failure to properly control classified information. Region III Special Inspection at Kewaunee Nuclear Power Plant On January 20, 2004, Region III began a special inspection at the Kewaunee Nuclear Power Plant, operated by Nuclear Management Company, to review the circumstances surrounding the partial clogging of heat exchangers for the safety injection pump oil coolers. The plant was shut down January 16 when the heat exchangers were found to be clogged by silt and lake weeds. NRC Oversight Panel Meeting in Oak Harbor, Ohio The NRC Oversight Panel, established under Manual Chapter 0350 to coordinate the agency's activities in response to the reactor vessel head damage at the Davis-Besse Nuclear Power Station, met with FirstEnergy Nuclear Operating Company officials on January 21, 2004, in Oak Harbor, Ohio, to discuss the status of the utility's activities at the plant. The meeting was held in the evening to facilitate attendance by members of the public. Region IV 21st Century Technologies, Inc. - Closed Predecisional Enforcement Conference On January 20, 2004, Region IV conducted a closed predecisional enforcement conference with 21st Century Technologies, Inc. to discuss four apparent violations of NRC requirements involving distribution products that were not specifically authorized by the Company's exempt distribution license. Regional Administrator Visits South Texas Project On January 21, 2003, the Regional Administrator visited the South Texas Project Nuclear Power Plant. The visit included a tour of the plant and observation of material condition and security controls, meetings with licensee managers on current issues, and a discussion of plant performance with the resident inspector. Public Meeting with Nebraska Public Power District On January 22, 2004, the Director, Division of Reactor Projects led a public exit meeting with Nebraska Public Power District officials in Brownville, Nebraska. The purpose of the meeting was to discuss the results of recently completed quarterly inspection of completed actions in the Cooper Nuclear Station Confirmatory Action Letter.
Items of Interest Week Ending January 23, 2004
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