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INFORMATION REPORT SECY-06-0176 August 8, 2006
Contact: U. Shoop, OEDO Office of Nuclear Reactor Regulation (NRR) Ninth NRC/ASME Symposium on Valves, Pumps, and Inservice Testing From July 17-19, 2006, the NRC and the American Society of Mechanical Engineers (ASME) jointly sponsored the subject Symposium in Washington, DC. This Symposium is held every two years to exchange information on technical, programmatic, and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Over 200 individuals from the U.S. and other countries participated in the Symposium representing nuclear power plant licensees, consultants, valve and pump vendors, and regulators. The Director, Division of Component Integrity (DCI), Office of Nuclear Reactor Regulation (NRR) provided the NRC keynote address. During the Symposium, NRC staff members presented several papers on valve and pump performance, risk-informed programs, plant operating experience, and new reactor licensing. The Symposium also included an interactive session where an NRC staff panel discussed established regulatory positions related to valves, pumps, and inservice testing. Advanced Fracture Methods Workshop From July 18-20, 2006, NRR staff members attended the Advanced Fracture Methods for Light Water Reactor Components Workshop in Baltimore, Maryland. This workshop provided insights on the following: (a) current activities in fracture mechanics in modeling and testing techniques in U.S., Europe, and Japan; (b) updated information on radiation embrittlement processes; and (c) techniques for using probabilistic fracture mechanics for reactor pressure vessel pressurized thermal shock to other applications. Brief for United Kingdom Senior Inspectors On July 24, 2006, the Division of Inspection and Regional Support (DIRS) staff provided a brief on the Reactor Oversight Process (ROP) to senior staff members of United Kingdom's Health and Safety Executive/Nuclear Installation Inspectorate. Discussions were held on the various improvements made to the ROP to address lessons learned from the 2002 Davis-Besse boric acid event and how the ROP was improved to enhance the treatment of cross-cutting and safety culture issues. Nuclear Energy Institute and the Westinghouse Owners Group Meeting On July 25, 2006, the staff held a public meeting to discuss the status of Technical Specification Task Force (TSTF) Traveler TSTF-409. Attendees included members of the Nuclear Energy Institute (NEI), the Westinghouse Owners Group, and the NRC staff. Discussions were focused on the resolution of industry comments on the TSTF-409 Notice for Comment, which was published in the Federal Register on April 10, 2006, [71 FR 18380]. TSTF-409 allows licensees to increase the completion time for an inoperable containment spray system train using a risk-informed approach. Robinson Simulator Scenario Based Testing On July 27-28, 2006, two NRC staff members visited the H.B. Robinson site to observe and gather information relevant to Simulator Scenario Based Testing (SBT) in preparation for an upcoming fall national simulator workshop. The NRC and the NEI Operator Licensing Focus Group is working to resolve an outstanding NRC issue with the industry's SBT approach and related simulator documentation of the simulator's performance. While on site, a demonstration of a proposed pressurized water reactor SBT package was observed and discussed. Pilgrim and Vermont Yankee Nuclear Power Station License Renewal Application Public Meetings On July 19-20, 2006, the staff conducted two separate public meetings - one at Plymouth, MA and another at Brattleboro, VT, to report the status of the aging management program audits for Pilgrim and Vermont Yankee, respectively. The staff presented information about the audit process, and provided a copy of the staff questions and licensee responses that were asked during the audit process and publically documented at the completion of the audit. Meeting on Infrastructure Development Schedules On July 24, 2006, the NRC staff met with representatives from NEI and industry in a public meeting to discuss schedules associated with the Standard Review Plan (SRP) Update and Associated Regulatory Guides, New Reactor Licensing Rulemaking, and Combined License (COL) Regulatory Guide (DG-1145). NEI and industry requested schedules for these infrastructure activities in order to establish the level of resources needed to review these documents to support new reactor license applications. Additional discussion about the SRP update and COL regulatory guide schedules will be held as part of the September COL regulatory guide workshop. Meeting on Draft Proposed Rule for Security Assessments for New Reactors On July 25, 2006, staff from NRR, the Office of Nuclear Security and Incident Response and the Office of the General Counsel conducted the subject public meeting. Following a staff presentation on the draft proposed rule and guidance plans, the staff responded to questions on specific aspects of the draft proposed rule language. Office of Nuclear Regulatory Research (RES) 14th International Conference on Nuclear Engineering (ICONE 14) On July 16-20, 2006, RES staff attended the subject conference and participated in workshops on computational fluid dynamics for gas-cooled reactors, sessions on advanced reactor designs, two-phase flow, and safety code assessment. The staff presented papers on rod bundle heat transfer model assessment, and presented a summary of the development of the TRACE code for new and advanced reactors. In addition, the staff conducted informal discussions with representatives from around the world on current and past research programs to leverage international cooperation. Public Meeting on Proposed Revisions to Regulatory Guide (RG) 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities" Public Meeting On July 20, 2006, RES staff conducted the subject meeting to: (1) share with the public the proposed staff changes to RG 1.200, and (2) provide the schedule for issuing Revision 1 of RG 1.200 for use. The proposed changes to the RG resulted from lessons learned from the pilot applications of the RG, revisions to the ASME probabilistic risk assessment (PRA) standard, revisions to the Nuclear Energy Institute (NEI) Self-Assessment Process, and the need to support other risk-informed activities. Publication of Draft Regulatory Guide DG-1144, "Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors" On July 21, 2006, the subject DG was issued for public comment. The DG describes a method that the staff considers acceptable for use in determining the fatigue life of ASME pressure boundary components with consideration of the light-water reactor (LWR) environment. This DG will support reviews of applications for new nuclear reactor construction permits or operating licenses, and is publicly available on the NRC's web site at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/power-reactors/draft-index.html. The technical basis for this DG is presented in NUREG/CR-6909, "Effect of LWR Coolant Environments on the Fatigue Life of Reactors Materials," also available for public comment at http://www.nrc.gov/reading-rm/doc-collections/nuregs/docs4comment.html. Technical Exchange and Cooperative Arrangement Between the NRC and the Institut de Radioprotection et de Sûreté Nucléaire (IRSN) in the Field of Reactor Safety Research On July 26, 2006, the Executive Director for Operations (EDO) signed the subject Arrangement. This Arrangement defines the terms and conditions by which the NRC and IRSN will continue their cooperation, and is a renewal of the Arrangement that was signed on December 13, 2000. Under this broad Arrangement, the NRC and IRSN will exchange technical information and cooperate in the field of reactor safety research that includes many areas that are pertinent to both current and future reactor designs. This renewed Arrangement will remain in effect for an additional five years. Office of Administration (ADM) Facilities Management Contract On July 27, 2006, a small business set-aside, competitive contract no. NRC-10-06-430 was awarded to WW Contractors, Incorporated. WW is also a HUBZone firm. The contractor will provide all necessary supervision, labor, materials and equipment to efficiently and safely operate and maintain the facilities, equipment, and systems described in the Statement of Work for NRC's Headquarters buildings. The period of performance is 5 years (a base year plus two 1-year options and two 1-year award terms). The total estimated cost is $9,979,389.82. Information System Security Services On July 28, 2006, a competitive Delivery Order no. DR-33-06-236 was awarded to Mar, Incorporated under the General Service Administration's Federal Supply Schedule. The contractor will provide information system security services for the entire agency. The total estimated cost is $41,118,236. The period of performance is five years, including four one-year options. Award for Technical Assistance On July 31, 2006, a GSA/Federal Supply Schedule Delivery Order no. DR-04-06-071 was awarded to Information Systems Laboratories, Incorporated. Technical assistance is required under this delivery order for "TRACE Applicability Evaluation for Economic and Simplified Boiling Water Reactor (ESBWR)." The contractor will evaluate and demonstrate the applicability of the TRACE code for simulating an ESBWR loss-of-coolant accident (LOCA). The period of performance for this order is twelve (12) months. The total estimated cost is $583,857. Office of Information Services (OIS) Freedom of Information Act (FOIA) and Privacy Act Requests Received During the Period of July 21 through July 27, 2006:
Office of Human Resources (HR)
Office of the Secretary (SECY)
Federal Register Notices Issued
Region II (RII) Browns Ferry Management Meeting On July 25, 2006, RII held a management meeting with representatives from Tennessee Valley Authority at the Regional Office. The purpose of the meeting was to discuss the Browns Ferry Units 2 and 3 operating performance. Vogtle Regulatory Conference On July 26, 2006, RII conducted a regulatory conference with representatives from Southern Nuclear Operating Company, Inc. at the Regional Office. The purpose of the meeting was to discuss the risk significance of a preliminary White finding involving a critique of a full-scale exercise that did not identify a weakness. Region IV (RIV) Senior Management Change at Grand Gulf Nuclear Station On July 25, 2006, Entergy Operations, Inc., announced that effective August 14, Russ Brian, General Manager of Plant Operations at the Grand Gulf Nuclear Station will transition to the interim role of Site Vice President. George Williams, the current Site Vice President for Grand Gulf Nuclear Station, has announced he will leave Entergy in mid-August and assume new responsibilities as a Senior Vice President of Utility Operations, for Commonwealth Edison Company, a Chicago-based unit of Exelon. Diablo Canyon Power Plant Annual Assessment Public Meeting On July 25, 2006, the staff conducted a public meeting in San Luis Obispo, California, to discuss Diablo Canyon's safety performance for 2005. Approximately 40 people attended the presentation, including representatives of Mothers for Peace, several members of the local community, and Senator Feinstein's regional representative. Questions and comments received from the public were primarily focused in the areas of plant and independent spent fuel storage installation (ISFSI) security, offsite emergency response, and the 9th Circuit Court of Appeals decision involving the Diablo Canyon ISFSI. NRC Town Hall Meeting in San Luis Obispo, California On July 25, 2006, the staff conducted a town hall public meeting in San Luis Obispo, California, to discuss issues important to the community involving the Diablo Canyon Power Plant. Approximately 75 people attended the meeting, including representatives of Mothers for Peace, a San Luis Obispo County Board Supervisor, members of both the press and television media, several members of the local community, members of a pro-nuclear group from Virginia and Senator Feinstein's regional representative. Questions and comments received from the public were primarily focused on the NRC's response to the 9th Circuit Court of Appeals ruling on the Diablo Canyon ISFSI, ISFSI construction, emergency response, and security for the power plant and spent fuel storage. Office of Congressional Affairs (OCA)
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