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INFORMATION REPORT SECY-05-0133 July 26, 2005
Contact: T. Kim, OEDO Office of Nuclear Reactor Regulation (NRR) NRC Information Notice (IN) 2005-18: Summary of Fitness-For-Duty Program Performance Reports For Calendar Years 2001, 2002 and 2003 On July 15, 2005, NRC staff issued the subject IN to report on lessons learned by licensees from their fitness-for-duty (FFD) program performance reports for calendar years 2001, 2002 and 2003. As required by 10 CFR 26.71(d), NRC licensees have submitted their semi-annual FFD program performance reports to the NRC. In the past, the NRC summarized and analyzed this performance data and published an annual report, NUREG/CR-5758, “Fitness for Duty in the Nuclear Power Industry—Annual Summary of Program Performance Reports.” This IN provides similar FFD program performance data information for the years 2001, 2002 and 2003. The IN requires no specific action nor written response; however, licensees are expected to review the information for applicability to their facilities and consider taking actions, as appropriate. Nine Mile Point - Amended License Renewal Application On July 15, 2005, Constellation Energy Group submitted an amended license renewal application for Nine Mile Point Nuclear Station, Units 1 and 2. The amended application is an enhancement to the original license renewal application and completes the applicant’s recovery plan addressing quality issues with the original submittal. The applicant identified 14 additional plant systems, that were not identified in the original license renewal application, to be within the scope of license renewal. The staff will establish a revised review schedule beyond the standard 22 months, provided that the staff finds the enhanced submittal satisfactory for further detailed review. NRC Bulletin 2005-02: Emergency Preparedness (EP) and Response Actions for Security-Based Events On July 18, 2005, NRC staff issued the subject Bulletin to request information from power reactor licensees regarding actions taken or planned to be taken in the following areas: 1) security-based emergency classification levels and emergency action levels (EALs), emergency response organization augmentation for security-based events, and a security-based EP drill and exercise program, and 2) accelerated NRC notifications and onsite protective measures. If actions regarding the topics covered in this bulletin have not been taken, the addressees are requested to provide a schedule detailing expected completion dates for all pending activities. The bulletin requires addressees to provide a written response to the NRC in 30 days. NRC IN 2005-19: Effect of Plant Configuration Changes on the Emergency Plan On July 18, 2005, NRC staff issued the subject IN to inform addressees of recent inspection findings where licensees failed to properly evaluate the effect of plant configuration changes (procedures, equipment, and facilities) on their emergency plans. The IN discusses the expectation that licensees effectively manage configuration changes and evaluate any potential impact on implementing the emergency plan and, if necessary, the need to develop and implement compensatory measures. The IN requires no specific action nor written response; however, licensees are expected to review the information for applicability to their facilities and consider taking actions, as appropriate. Proposed Generic Letter on Hemyc/MT Fire Barriers On July 18, 2005, NRC staff forwarded to the Office of Federal Register a proposed Generic Letter (GL) entitled "Impact of Potentially Degraded Hemyc and MT Fire Barriers on Compliance with Approved Fire Protection Programs," for publication. The proposed GL requests power reactor licensees to evaluate their facilities to confirm compliance with the applicable regulatory requirements in light of the information provided in this GL and, if appropriate, take additional actions. Specifically, although “Hemyc” and “MT” fire barriers in nuclear power plants may be relied on to protect electrical and instrumentation cables and equipment that provide safe shutdown capability during a fire, recent NRC testing has revealed that both materials failed to provide the protective function intended for compliance with existing regulations, for the configurations tested using the acceptance criteria in GL 86-10, Supplement 1, "Fire Endurance Test Acceptance Criteria for Fire Barrier Systems Used To Separate Redundant Safe Shutdown Trains Within the Same Fire Area." The proposed GL was published in the Federal Register (70 FR 42596) for public comment. The comment period expires on September 23, 2005. NRC IN 2005-20: Electrical Distribution System Failures Affecting Security Equipment On July 19, 2005, NRC staff issued the subject IN to inform addressees about the adverse impact of electrical distribution system failures on plant security systems. This IN specifically provides four examples of recent failures of electrical distribution systems at the following nuclear power plants, Palo Verde, Millstone, Watts Bar, and Turkey Point, that had adversely affected the respective plant’s security systems. The IN requires no specific action nor written response; however, licensees are expected to review the information for applicability to their facilities and consider taking actions, as appropriate. Construction Inspection Program Public Meeting On July 20, 2005, NRR staff held a public meeting with the Nuclear Energy Institute and the industry to discuss issues related to the Construction Inspection Program. The focus of the discussion was on the necessary documentation to demonstrate that the inspections, tests, analyses, and acceptance criteria have been completed. Public Meeting on Mitigating System Performance Index and Reactor Oversight process On July 20, 2005, NRR staff together with staff from the Offices of Nuclear Regulatory Research (RES) and the Regions hosted a public meeting on the implementation of the Mitigating Systems Performance Index (MSPI). The purpose of the meeting was to discuss the results and follow-up actions from the June 20-21, 2005, MSPI Workshop. Additionally, industry representatives discussed the status of proposed alternatives to the requirements for probabilistic risk analysis (PRA) quality issues related to MSPI implementation. RES staff presented preliminary results from its confirmatory analysis of the industry’s PRA cross-comparison effort, as well as comparisons between the NRC’s Standardized Plant Analysis Risk model results and industry MSPI PRA data. The NRC has also developed an MSPI database to assist the staff in the identification of PRA model “outliers” to support staff inspection activities for MSPI implementation. The MSPI is a more risk-informed performance indicator than the NRC’s current Safety System Unavailability performance indicator used as part of the agency’s Reactor Oversight Process. Industry-wide implementation of the MSPI is scheduled for January 2006. On the following day, the staff hosted the monthly public meeting on the Reactor Oversight Process. Discussion topics included implementation issues associated with the Significant Determination Process, status updates from the Task Forces evaluating the Scrams with Loss of Normal Heat Removal and Reactor Coolant System Leakage Performance Indicators (PIs), update on efforts to improve the safety system functional failure PI, general discussion of security issues (closed session), and PI Frequently Asked Questions (FAQs). Office of Nuclear Material Safety and Safeguards (NMSS) Participation in U.S. - Russian Federation Bilateral Meeting to Discuss Surplus Weapons-Grade Plutonium Disposition Program On July 11-14, 2005, NMSS staff participated in the subject Bilateral Meeting with the Department of Energy (DOE)/National Nuclear Security Administration, and the Nuclear, Industrial and Environmental Regulatory Authority of Russia (Rostekhnadzor) to discuss current efforts and upcoming regulatory/licensing activities related to the Surplus Weapons-Grade Plutonium Disposition Program. DOE is supporting regulatory development activities associated with the Russian Federation Plutonium Disposition Program. Discussion topics included the status of U.S. licensing reviews, the status of mixed-oxide lead test assembly irradiation, and future workshops to be held in Moscow. NRC/DOE Technical Exchange Meeting on High-Level Waste On July 20, 2005, NRC and DOE high-level waste (HLW) staff held the subject meeting in Las Vegas to discuss the extent of technical information necessary to support an NRC safety decision for the potential Yucca Mountain Repository. The technical exchange was open to the public and was held in hearing room facilities constructed in anticipation of hearings on a future license application for a HLW repository. Office of Nuclear Regulatory Research (RES) Meeting of the Proactive Materials Degradation Assessment Expert Panel On July 11-14, 2005, RES staff and contractors from Brookhaven National Laboratory (BNL), held the last formal meeting of the Proactive Materials Degradation Assessment (PMDA)- Phenomena Identification and Ranking Table (PIRT) Expert Panel. The purpose of the PMDA- PIRT is to identify locations and components in light-water reactors (LWRs) that could be susceptible to future materials degradation phenomena. This information will provide a basis for the development of proactive regulatory and industry actions to avoid, mitigate, and/or manage potential future degradation of reactor components. The Panel is comprised of eight internationally recognized experts in materials degradation phenomena of components in nuclear and non-nuclear applications. The experts are from industry, regulatory agencies, and academic institutions in the U.S., France, Sweden, Japan, and Canada. A final draft report which combines the results from both the boiling-water reactor and pressurized-water reactor systems will be developed by November 2005. Office of Administration (ADM) List of Approved Spent Fuel Storage Casks: Standardized NUHOMS -24P, -52B, -61BT, -32PT, -24PHB, and -24PTH Revision; Withdrawal of Direct Final Rule (Amendment 8) (AH72- Part 72) On July 15, 2005, NRC published the subject notice in the Federal Register (70 FR 40879) for the withdrawal of a direct final rule. This action is taken because the NRC staff became aware of changes in the technical specifications associated with the Certificate of Compliance for this cask system. Export and Import of Nuclear Equipment and Material: Nuclear Grade Graphite (AH51 - Part 110) On July 21, 2005, a final rule was published in the Federal Register (70 FR 41937) that removes NRC export licensing requirements for nuclear-grade graphite for non-nuclear end use. This amendment removes nuclear materials which are not of significance from a nuclear proliferation perspective from NRC jurisdiction. The Department of Commerce assumes responsibility for licensing exports of nuclear-grade graphite in a final rule published on July 21, 2005 (70 FR 41952). The final rule became effective July 21, 2005. Contract Award On July 15, 2005, a competitive delivery order, DR-09-05-332, was awarded to Eagle Design & Management, Inc., a small business, under the General Service Administration's Federal Supply Schedule. The contractor will provide design support to the production of the NRC Performance Accountability Report. The total estimated cost is $73,857. The period of performance is 18 months. Office of Information Services (OIS) Freedom of Information Act and Privacy Act Requests Received During the Period of July 15 through July 21, 2005:
Office of Human Resources(HR)
Office of Public Affairs (OPA) The Office of Public Affairs (OPA) received significant media inquiries on the following: Yucca Mountain Licensing Support Network issues. Disabled emergency sirens at Indian Point. Proposed Resolution of Generic Safety Issue (GSI)-189, "Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion During a Severe Accident," through voluntary actions by certain licensees. Other OPA Items: OPA assisted the Chairman’s interview with The Washington Post on the future of nuclear power.
Office of the Secretary (SECY)
Commission Correspondence
Federal Register Notices Issued
Region I (RI) Meeting to Discuss License Termination Issues for a Complex Decommissioning Site On July 19, 2005, staff from Region I and the Office of Nuclear Material Safety and Safeguard met with representatives of the New Jersey Department of Environmental Protection (NJDEP) at their Trenton, NJ offices. The purpose of the meeting was to discuss NJDEP comments on a draft environmental assessment prepared by NRC on proposed termination of the Heritage Minerals license. The Heritage Minerals site is a complex decommissioning site containing diffuse source material as well as state-regulated naturally-occurring radioactive material. The NRC staff also made a site visit to Heritage following the meeting. Indian Point Siren Outage On July 19, 2005, a radio transmitter for activation of the 156 sirens in the emergency planning zone for Indian Point lost power for approximately six hours. Plant personnel were not aware the transmitter had been operating on backup power supplies for several hours prior to the loss of all power which rendered the transmitter and the siren system inoperable. Entergy has restored the power sources and implemented interim compensatory measures, pending the results of their root cause investigation. The NRC resident inspectors at Indian Point are reviewing this event with support from regional specialists. Haddam Neck Community Decommissioning Advisory Committee Meeting On July 19, 2005, Region I staff participated in the Haddam Neck Community Decommissioning Advisory Committee (CDAC) meeting held in Connecticut. The meeting was open to the public with approximately 15 people in attendance. The NRC staff provided an overview of recent inspection findings and planned inspection activities. The licensee discussed recent site activities regarding safety performance, radiological exposure performance, status of decommissioning, and status of soil cleanup and groundwater monitoring. Commissioner Merrifield Visit to Indian Point On July 20, 2005, Commissioner Merrifield, accompanied by Region I management staff, toured the Indian Point Energy Center. The tour was hosted by Entergy Nuclear Northeast and discussion topics included security, the corrective action process, conduct of operations, the status of emergency preparedness equipment, and the company's progress and challenges associated with site integration. Commissioner Merrifield held a question and answer session with approximately 175 plant employees during his site visit. Region II (RII) Deputy Executive Director for Reactor and Preparedness Programs Visit to Vogtle and Region II Offices On July 19, 2005, the NRC’s Deputy Executive Director for Reactor and Preparedness Programs (DEDR), accompanied by the Regional Administrator, visited the Vogtle Nuclear Plant in Georgia for a site tour and meetings with licensee management and the resident inspectors. On the following day, DEDR visited the Region II offices in Atlanta, Georgia, and met with regional staff. Browns Ferry Nuclear Plant - Management Meeting to Discuss Unit 1 Restart Project Status On July 20, 2005, Region II management met with representatives from the Tennessee Valley Authority in the Regional Office to discuss the status of Browns Ferry Unit 1 Restart Project Status. The Deputy Director of the Office of Nuclear Reactor Regulation also attended the meeting. Region IV (RIV) Public Meeting with Ameren Union Electric Company On July 20, the Region IV Regional Administrator and members of the Region IV staff held a public meeting with representatives of Ameren Union Electric Company (UE), the licensee of the Callaway Nuclear Plant. The purpose of the meeting was to discuss the scope of the upcoming refueling outage at the plant that will include steam generator replacements, the results of the auxiliary feedwater assessment, and the results of recent work climate surveys. Regional Administrator Visit to Fort Calhoun Station On July 22, the Regional Administrator visited the Fort Calhoun Station site for a site tour with the resident inspectors and discussions with licensee managers regarding overall plant performance and outage activities planned for 2006.
Office of Congressional Affairs (OCA)
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