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INFORMATION REPORT SECY-07-0072 April 16, 2007
Contact: L. Rakovan, OEDO Office of Nuclear Reactor Regulation (NRR) Staff Issuance of Confirmatory Action Letters Regarding Dissimilar Metal Butt Welds During the period of March 15 through March 29, 2007, the staff issued confirmatory action letters (CALs) to the licensees for Diablo Canyon, Palo Verde, V.C. Summer, Waterford, St. Lucie, Catawba, Beaver Valley, Davis Besse, Comanche Peak, Braidwood, Byron, Three Mile Island, McGuire, San Onofre, Shearon Harris, South Texas Project, Crystal River, Millstone, Oconee, Prairie Island, Arkansas Nuclear One, Callaway, North Anna, Palisades, and Sequoyah. The letters confirm commitments made by the licensees to inspect the pressurizer surge, spray, safety, and relief nozzle welds by December 31, 2007, to implement enhanced reactor coolant system leakage monitoring until the inspections are complete, to repeat butt weld examinations every 4 years until the welds are either removed from service or mitigated, and to report inspection results to the NRC. Audit Conducted at Oconee Nuclear Station During the week of March 26, 2007, NRR staff visited the Oconee Nuclear Station site near Clemson, South Carolina. The purpose of the visit was to audit Duke Energy's sump performance corrective actions for Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors." The audit team conducted numerous meetings with Duke Energy's technical representatives, and will continue to review information provided by the licensee. NRR is developing a report which will document the areas reviewed and open items identified, and will continue to audit selected plants to monitor corrective actions as it works toward the resolution of Generic Safety Issue 191. Meeting with Federal Energy Regulatory Commission On March 28, 2007, representatives of Federal Energy Regulatory Commission (FERC) and NRC staff met at FERC to discuss the scope of the FERC final rule on reliability. Discussions focused on what reliability standards that affect nuclear power plants are to be approved, what modifications have been directed in response to the NRC's December 21, 2006 comments (ML063560130) to FERC's Federal Register Notice and Mandatory Reliability Standards for the Bulk Power System (71 FR64770). The NRC comments were limited to those standards that could have significant planning and operating impacts on either the auxiliary power system or the offsite power system of a nuclear power plant. The NRC staff toured the FERC operations center where FERC monitors electric power market and bulk electric power flows. Boiling Water Reactor Vessel and Internals Project On March 29, 2007, NRC staff met with members of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) to discuss various topical report reviews that are currently being reviewed by the NRC. The subjects discussed included steam dryer integrity evaluation updates, vessel internals inspection guidelines, mitigation activities (water chemistry and mitigation effectiveness of core shroud reinspection data) and preliminary results of testing concerning crack growth and fracture toughness of irradiated stainless steels. The NRC staff provided comments on the subjects presented by the BWRVIP. The BWRVIP will consider the NRC comments in their development of their topical reports, such as the generic steam dryer report, and visual inspection guideline reports. On March 30, 2007, NRC management met with the BWRVIP executive members to discuss the BWRVIP approach to management of materials degradation issues, the status of the BWRVIP topical report reviews and the BWRVIP's future plans and submittals. The NRC will use this information to prioritize and assess future reviews. In addition, the BWRVIP provided the status of the evaluation on the effects of the dissimilar metal weld experience at Duane Arnold. The BWRVIP plans to provide an initial summary of the data collected from all BWR plants concerning the Duane Arnold issue by mid-April. Oyster Creek Nuclear Plant Safety Evaluation Report On March 30, 2007, the staff issued the Safety Evaluation Report (SER) related to the license renewal of the Oyster Creek Generating Station, on schedule. By letter dated July 22, 2005, AmerGen Energy Company, LLC, submitted an application pursuant to 10 CFR Part 54, to renew the operating license for an additional 20 years. The NRC staff has closed all open items and identified no confirmatory items in its review. The staff will add a total of seven new license conditions based on staff review and Advisory Committee on Reactor Safeguards recommendations. Vermont Yankee Nuclear Plant Safety Evaluation Report On March 30, 2007, the staff issued the Safety Evaluation Report (SER) with Confirmatory Items related to the License Renewal of Vermont Yankee Nuclear Power Station. On January 27, 2006, the staff received from Entergy Nuclear Operation, Inc., an application requesting the extension of the operating license for Vermont Yankee Nuclear Power Station for an additional 20 years. The SER has six confirmatory items (regarding the license renewal scoping boundaries for various systems). The staff is scheduled to meet with the Advisory Committee on Reactor Safeguards Subcommittee on June 5, 2007, to discuss the SER with Confirmatory Items. Office of New Reactors (NRO) Regulatory Guide 1.189, "Fire Protection for Nuclear Power Plants" On March 28, 2007, Revision 1 of Regulatory Guide 1.189 was issued. This revision added guidance for new reactor fire protection programs. Grand Gulf Early Site Permit Signing Ceremony On April 5, 2007, the Director of NRO signed the Grand Gulf Early Site Permit. The previous week, the Commission approved the issuance of an Early Site Permit for the Grand Gulf site, the second time that the Commission has approved the issuance of an Early Site Permit request. The first Early Site Permit, for the Clinton site, was approved in March 2007. Office of Nuclear Material Safety and Safeguards (NMSS) Decision on Differing Professional Opinion on Red Oil Events at the Proposed Mixed-Oxide Fuel Fabrication Facility Issued On March 23, 2007, the NMSS Director issued his decision on a Differing Professional Opinion (DPO) on Red Oil Events at the Proposed Mixed-Oxide (MOX) Fuel Fabrication Facility (DPO-2005-002). The Director agreed with the DPO Panel Report, which was prepared in accordance with Management Directive 10.159. Specifically, the Director agreed that the construction authorization for the MOX Fuel Fabrication Facility does not have to be revisited. The applicant for the facility has committed to provide additional information regarding its proposed approach for controlling red-oil events, in support of the review of the Operating License application. As part of the Operating License application review process, it is the applicant's responsibility to demonstrate adequate protection of the public health and safety and the environment, with respect to preventing or mitigating red-oil runaway reactions. BWX Technologies, Inc. License Renewal On March 29, 2007, the staff issued a renewal of the BWX Technologies, Inc. license for 20 years. This renewal period is consistent with the guidance provided by the Commission in Staff Requirement's Memorandum (SRM) 06-0186, dated September 26, 2006, and is the first fuel facility license renewal issued for more than 10 years. Public Meeting with Packaging Technology to Discuss the TRUPACT-III Full-Scale Drop-Test Results On March 29, 2007, the staff met with representatives from Packaging Technology, Inc. (Pac Tec) to discuss the test results for the full-scale model of the redesigned TRUPACT-III transportation package. This package will be used to transport transuranic waste. Discussions focused on the drop test required by 10 CFR 71.73, "Hypothetical accident conditions." After each drop, a vacuum test was performed to check the integrity of the containment. After the last drop, the full-scale model did not pass the vacuum test. Subsequent examination of the test unit indicated that debris from the simulated contents had entered into the seal region. As a result, Pac Tec is proposing to add a debris seal to the design. Pac Tec stated that it is planning to submit the application in May 2007. Office of Federal and State Materials and Environmental Management Programs (FSME) Pennsylvania Request to Become an Agreement State On March 29, 2007, staff issued a letter to the Commonwealth of Pennsylvania, documenting the results of the staff review of Pennsylvania's response to the NRC staff's comment letter, which documented the results of Pennsylvania's formal request to become an Agreement State. Pennsylvania's response addressed the two significant issues identified by the NRC staff, which included staffing levels and staff training and qualifications. The NRC staff plans to confirm, through continued interactions, the information and assurances provided by Pennsylvania. Office of Nuclear Regulatory Research (RES) Public Meeting of the NRC Digital Instrumentation and Control (I&C) Steering Committee with Representatives of the Industry On March 26, 2007, RES staff and industry representatives met to facilitate communication in the areas of digital I&C and human factors and to identify and track resolution of technical and regulatory issues for new and operating nuclear power plants. The revised structure for the NRC's Digital I&C Project Plan was presented and discussed. Schedule and budget concerns were also discussed. NEI indicated concern that NRC's requests for information concerning digital systems may be excessive. Briefing by SIMCO Technologies Inc., Quebec, Canada, on Their Concrete and Cementitious Materials Degradation Computer Code STADIUM On March 28, 2007, RES staff and other participants, including from the Department of Energy, were briefed regarding STADIUM. The STADIUM code, based in part on work completed by National Institute of Standards and Technology under contract to the NRC, calculates the transport of multiple ionic species in cementitious materials. It provides engineers with a tool that could assist in designing and assessing new concrete structures and cementitious grouts and in planning repair strategies for existing structures. Developed by a consortium of organizations, including federal agencies and universities, the code is already in use domestically and internationally in the design of large concrete structures. RES is evaluating the use of STADIUM code in reviews and applications of specific interest to the NRC. Public Meeting between Nuclear Energy Institute (NEI), the Electric Power Research Institute (EPRI), and the NRC on Industry's Plans to Develop Guidance for Implementing 10 CFR20.1406, "Minimization of Contamination" On March 28, 2007, staff met with representatives of NEI, and EPRI to exchange information on the progress of guidance development regarding 10 CFR 20.1406, "Minimization of Contamination." EPRI described ground-water protection efforts for advanced power plant designs, and RES staff discussed the current status of technical basis development for a regulatory guide on implementation of 10 CFR 20.1406. Current plans are to have a draft regulatory guide ready for internal NRC review late in April 2007, followed by a public comment period beginning in July 2007. Public Meeting of Task Working Group (TWG) Designated by the Digital I&C Steering Committee to Address the Subject of Digital System Communications that Involve Equipment Assigned to Different Safety Divisions On March 29, 2007, an NRC Task Working Group (TWG) discussed issues related to licensing digital I&C systems in new and operating nuclear power plants and fuel facilities. Changes to the project plan were discussed to bring the plan into conformance with the latest format established by the NRC's Digital I&C Steering Committee. The role of the designated industry participants as advisors, rather than TWG members, was clarified. A list of priorities for consideration by the TWG was proposed by the industry advisors and finalized. Industry participants described interchannel communications considerations and provisions for a particular digital platform, and for video display units that might be used for multiple safety divisions and for nonsafety control influence over safety-related equipment. Restrictions on safety/nonsafety interactions were also discussed extensively. Office of Nuclear Security and Incident Response (NSIR) Preliminary Notifications
Office of Administration (ADM) Industry Codes and Standards (AH76-Part 50) On April 5, 2007, the NRC published a proposed rule in the Federal Register (72 FR 16731) that would amend requirements adopted from industry codes and standards (AH76-Part 50). The proposed rule would incorporate by reference the 2004 Edition of Section III, Division 1 and Section XI, Division 1 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. The proposed rule would also incorporate by reference the 2004 Edition of the ASME Code for Operation and Maintenance of Nuclear Power Plants. The incorporation of new editions of the ASME Code is intended to ensure the continued safe operation of nuclear reactors. The comment period for this action closes June 19, 2007. Office of Information Services (OIS) Freedom of Information Act (FOIA) and Privacy Act (PA) Requests Received During the Period of March 30 through April 5, 2007:
Office of Human Resources (HR)
Office of Public Affairs (OPA) OPA received significant media inquiries on the following: Indian Point Unit 3 shutdown/restart data; siren testing and failures; transformer fire. NRC's preparations for new reactor applications, licensing process and design certifications. Issuance of the Final Safety Evaluation Report on Oyster Creek; status of license renewal application. Corrosion issues discussed, triggered by Exponent's report on crack growth rates for Davis Besse with the New York Times; The Plain-Dealer, Toledo Blade, and Platts. Inquires into Commissioner McGaffigan's withdrawal of his resignation letter. Other Public Affairs Items: OPA Regional staff assisted in numerous end-of cycle meetings.
Office of the Secretary (SECY)
Commission Correspondence
Federal Register Notices Issued - 10 CFR Part 73, Docket No. PRM-73-13, Union of Concerned Scientists; Receipt of Petition for Rulemaking. Region II (RII) Brunswick Nuclear Plant Category One Regulatory Conference and Management Meetings On April 5, 2007, representatives from Carolina Power and Light Company attended a Regulatory and Management Meeting in the Region II office. The purposes of the meetings were to discuss the trip of the Brunswick emergency diesel generator (EDG #1), failure of the engine crankshaft bearing and to discuss site and EDG improvements. Region IV (RIV) Palo Verde Public Meeting On April 3, 2007, the Regional Administrator and Deputy Executive Director for Reactor and Preparedness Programs, as well as Headquarters and Region IV staff conducted a public meeting in Avondale, Arizona, to discuss Palo Verde Nuclear Generating Station's safety performance for 2006. Participants included Arizona Public Service Company officials, NRC staff, three members of the Arizona Corporation Commission, local community leaders, and numerous members of the public. Arizona Corporation Commission Meeting On April 4, 2007, the Regional Administrator met with the Arizona Corporation Commission, at their request, to discuss the safety performance of the Palo Verde Nuclear Generating Station. In addition, the Regional Administrator answered questions concerning high level waste storage, transportation of radioactive material, radioactive waste reprocessing, and future nuclear power plant development. Several members of the local press attended the meeting. The Arizona Corporation Commission has jurisdiction over the quality of service and rates charged by public service utilities, such as Arizona Public Service Company. |
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