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INFORMATION REPORT SECY-07-0087 June 4 , 2007
Contact: U. Shoop, OEDO Office of Nuclear Reactor Regulation (NRR) Regulatory Information Exchange Meeting with Swiss Regulatory Authority, HSK During May 2-4, 2007, staff from NRR, Office of Nuclear Regulatory Research (RES) and Office of New Reactors (NRO) conducted a series of information exchange meetings with Dr. Ulrich Schmocker, head of the Swiss Nuclear Regulatory authority (HSK) and his senior staff. The topics discussed included: evaluation of seismic hazards in safety assessment; applications of probabilistic safety assessment including risk informed regulation; licensing of new reactors; ageing and materials degradation; and license renewal. In addition, Dr. Schmocker presented the HSK Integrated Management System (HSKIMS) and his experience in using the system over the past 7 years. Meeting with Electric Power Research Institute Regarding Steam Generator Issues During May 2 - 3, 2007, staff participated in a public meeting with representatives of Nuclear Energy Institute and the Electric Power Research Institute (EPRI) at EPRI facilities in Charlotte, NC. The topics covered during this meeting included steam generator (SG) tube inspection sampling plans for satisfying technical specification requirements, tools for assessing SG tube integrity, process for qualifying SG tube inspection techniques, and a number of SG technical issues (e.g., impact of operating leakage on the amount of accident induced leakage, divider plate weld cracking, etc). In addition to the formal discussions, EPRI provided a tour of their non-destructive evaluation and performance demonstration laboratories. The staff will continue interactions with the industry on SG technical issues. Meeting with Michigan Power Company Regarding Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on PWR Sump Performance" On May 8, 2007, staff participated in a public meeting with representatives of Indiana Michigan Power Company regarding current activities to address Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors," at D.C. Cook. The licensee representatives described their actions to date as well as their proposed strategy to resolve outstanding technical issues such as chemical effects and downstream effects. The staff provided feedback on various technical aspects of the proposed strategy for issue resolution. Meeting with the Industry on Pressurizer Dissimilar Metal Welds Advanced Fracture Mechanics Analyses On May 8, 2007, staff from NRR and RES, along with a RES contractor, met with representatives of EPRI, Dominion Engineering (EPRI's contractor), and members of EPRI's expert panel. This meeting was held to discuss industry's advanced fracture mechanics program which is being undertaken to address concerns with the potential for significant primary water stress corrosion cracking in pressurizer dissimilar metal nozzle butt welds. The meeting participants discussed the industry's progress to date, responses to technical concerns provided in the staff's April 4, 2007, letter to the Nuclear Energy Institute, and the industry's proposed sensitivity study matrix of analysis cases. The industry provided responses to all the technical concerns in the April 4, letter and the staff will evaluate the industry's response. Reactor Oversight Process (ROP) Public Meeting on Seabrook License Appeal On May, 9, 2007, staff conducted a public meeting on a ROP performance indicator Frequently Asked Question (FAQ), related to the licensee's appeal of FAQ 67.3 for the emergency diesel generator "B" high jacket water temperature at Seabrook. Davis-Besse Nuclear Power Station - 10 CFR 2.206 Petition By letter dated April 30, 2007, the Union of Concerned Scientists submitted a 10 CFR 2.206 petition request to the NRC concerning a recently-docketed technical report prepared by the licensee's consultants in support of an insurance claim related to Davis-Besse's 2002 reactor vessel head corrosion. The petition requested the NRC (1) to immediately order the shutdown of Davis-Besse, (2) to shutdown of all pressurized water reactors in the United States if the report was subsequently validated by the NRC, and (3) to revoke Davis-Besse's operating license if the NRC determines that inaccurate information was submitted by the licensee. On May 3, 2007, the NRC's petition review board (PRB) informed the petitioner by telephone that the request to immediately shut down Davis-Besse was denied because the NRC did not believe that an immediate safety concern existed. The NRC staff further informed the petitioner that the PRB had not yet made an initial assessment on the two other items in the petition request. The PRB will meet on May 9, 2007, to address the remaining requests of the petition. Operator Licensing Examinations at Reed College During the weeks of April 29 and May 6, 2007, staff conducted operator licensing examinations at Reed College in Portland Oregon. The staff administered examinations to more than twenty applicants applying for licenses to operate the school's 250 Kilowatt TRIGA® reactor. The twenty applicants represent approximately twenty percent of the operator licensing examinations to be administered at research and test reactors for the fiscal year. Office of Nuclear Material Safety and Safeguards (NMSS) Issuance of "RIS 2007-09, Examples of Recurring Requests for Additional Information (RAIs) for 10 CFR Part 71 and Part 72 Applications" During a meeting with industry representatives at the Licensing Process Conference in February 2005, the point was made that it might be possible to reduce the number of recurring Requests for Additional Information (RAIs) questions, asked in conjunction with a licensing action, if the staff could identify, and send out to licensees, a list of examples of RAIs that NRC repeatedly has had to address for multiple applicants. On May 4, 2007, the staff issued "RIS 2007-09, Examples of Recurring Requests for Additional Information (RAIs) for 10 CFR Part 71 and Part 72 Applications." This Regulatory Information Summary is being issued to inform addressees of RAI questions that have been asked repeatedly when reviewing applications and amendments under Parts 71 and 72, so as to illustrate technical areas in which applicants may be able to address issues before submitting applications for NRC review. This list of questions is not exhaustive and does not limit the scope of questions that may be asked by NRC staff, but rather is intended as a guide for applicants to use in an attempt to reduce or eliminate potential RAI questions. Office of Nuclear Regulatory Research (RES) Meeting with Canadian Nuclear Safety Commission on Digital Instrumentation and Control (I&C) Risk Analysis On May 9, 2007, staff met with a representative of the Canadian Nuclear Safety Commission (CNSC) to discuss NRC and CNSC work on reliability modeling of digital systems. The NRC participants provided a briefing on the ongoing RES work on both traditional and dynamic methods for modeling and quantifying digital system reliability. The CNSC participant provided information on planned digital I&C risk research activities at CNSC, which will initially focus on the area of fault coverage. Implementing Agreement with the Health and Safety Executive of Great Britain to Participate in the NRC's Cooperative Severe Accident Research Program (CSARP) On May 8, 2007, the NRC's Executive Director for Operations signed the subject agreement. The CSARP work expands the NRC's and the international community's data and knowledge base in the area of severe accident research and provides insights on severe accident computer code development, assessment, and applications. The NRC uses the MELCOR code to evaluate potential severe-accident scenarios, to address regulatory and licensing issues for operating plants, and to review new designs. This Implementing Agreement includes Great Britain in the international MELCOR user community. The severe accident work performed, the technical information exchanged, and the code assessments and feedback provided help provide quality assurance of NRC's reactor safety codes. The next step is for the signed Implementing Agreement to be sent to Great Britain for countersignature. This Implementing Agreement will become effective upon signature and will remain in effect for a period of five years. Office of Nuclear Security and Incident Response (NSIR) Preliminary Notifications
Office of Administration (ADM) List of Approved Spent Fuel Storage Casks: NAC-MPC Revision 5 (AI13 - Part 72) On May 10, 2007, the NRC published a direct final rule in the Federal Register (72 FR 26535) that amends the entry for the NAC International, Inc., NAC-Multi-Purpose Canister (MPC) cask system in the list of approved spent fuel storage casks (Amendment 5). This action modifies the Certificate of Compliance (CoC) by revising the Technical Specifications (TS) to incorporate changes to the reporting and monitoring requirements to allow for visual inspection of the air inlet and outlet vents instead of thermal monitoring, and to replace all references to backfilling the cask with air to backfilling with inert gas. The rule also revises the CoC description to remove the requirement for tamper-indicating devices on the Vertical Concrete Casks. The direct final rule becomes effective July 24, 2007. On May 10, 2007, the NRC published the companion proposed rule to this direct final rule in the Federal Register (72 FR 26568). The comment period closes June 11, 2007. Contract Awarded to Interpark Holdings, Inc. On May 8, 2007, a contract (NRC-10-07-449) was awarded to Interpark Holdings, Inc. This procurement provides for 22 parking spaces at the Bethesda Gateway facility. The period of performance is June 1, 2007 through May 31, 2008 and four 1-year option periods. The total amount of the award is $92,400 (NRC's portion). Office of Information Services (OIS) Freedom of Information Act (FOIA) and Privacy Act (PA) Requests Received During the Period of May 4 through May 10:
Office of Human Resources (HR)
Office of Public Affairs (OPA) OPA received significant media inquiries on the following: Mercury Spill at Two White Flint: OPA worked with Montgomery County Fire Dept Public Information Officer and followed up with local media. SOAR-CA Study including participation from Peach Bottom and Surry Plants Browns Ferry restart Indian Point license renewal and questions on recent tritium leak at site
Office of the Secretary (SECY)
Commission Correspondence - Letter to Congressman Bart Gordon, dated May 1, 2007, provides the requested Office of the Inspector General report on former Local Public Document Room libraries. Federal Register Notices Issued
Region IV (RIV)
Wolf Creek Generating Station Annual Assessment Meeting On May 3, 2007, Region IV staff conducted a public meeting in Burlington, Kansas, to discuss the Wolf Creek Generating Station's safety performance for 2006. The meeting was attended by approximately 25 people, including state and local officials and a member of the local media. Grand Gulf Nuclear Station Annual Assessment Meeting On May 8, 2007, Region IV staff conducted a public meeting in Port Gibson, Mississippi, to discuss Grand Gulf Nuclear Station's safety performance for 2006. In addition to several members of the public, the meeting was attended by state and local officials as well as the media. Announcement of Diablo Canyon Power Plant Site Vice President On May 8, 2007, Pacific Gas and Electric Company announced that Mr. John Conway will become the new Site Vice President at the Diablo Canyon Power Plant. Mr. Conway will replace Mr. David Oatley who recently retired. Mr. Conway most recently served as Site Vice President of the Monticello Nuclear Plant. Mr. Conway will assume his duties effective May 29, 2007. Office of Congressional Affairs (OCA)
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