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INFORMATION REPORT SECY-07-0067 April 6 , 2007
Contact: L. Rakovan, OEDO Office of Nuclear Reactor Regulation (NRR) Containment Coatings Testing at McGuire From March 20-22, 2007, the staff witnessed adhesion testing of containment coatings that was being conducted at McGuire Unit 1. The testing was conducted by Duke Power personnel and consultants under the auspices of Electric Power Research Institute/Nuclear Utility Coating Council (NUCC). Containment coating testing is being conducted at several plants in 2006/2007 to demonstrate that aged protective coatings maintain adequate adhesion. McGuire is the third unit to perform the testing. The results from the McGuire testing and that at other plants will be used to evaluate licensee supplemental responses to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," and in resolution of Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on PWR Sump Performance." Quad Cities and Dresden - Management Meeting Regarding Extended Power Uprate Issues On March 22, 2007, a Category 1 public meeting was held between representatives of NRR and NRC Region III staff, and the Exelon Generating Company (Exelon). The purpose of this meeting was to discuss Exelon’s actions to address issues arising from extended power uprate (EPU) operation at the Quad Cities Nuclear Power Station (Quad Cities) Units 1 and 2. Exelon personnel reviewed EPU issues and their corrective actions, including steam dryer replacements, upgrades to electromatic relief valves, and installation of acoustic side branches to reduce steam line vibrations. Steam dryer replacements are complete at both Quad Cities units and at Dresden Nuclear Power Station (Dresden) Unit 3. Dresden Unit 2 dryer will be replaced during its fall 2007 refueling outage. The NRC staff indicated that it has not identified any issues that prevent Exelon continuing full EPU operation at Quad Cities and Dresden. Exelon plans to submit a letter in April 2007 documenting its ongoing EPU issues corrective actions commitments. Waterford 3 - Public Meeting on Steam Generator Batwing Degradation Issue On March 22, 2007, NRC staff met with Entergy at NRC’s office in Rockville, Maryland to discuss the technical understanding of the steam generator batwing degradation condition, to review analyses supporting safe plant operation, to review the mitigation actions taken, and to discuss Entergy’s plans for a mid-cycle outage to inspect the steam generator batwings and their support structures. Based on its understanding of the potential impact of the batwing degradation condition on tube integrity, Entergy has concluded that inspections on the secondary side of the steam generators should be sufficient to assure plant safety. Entergy will be prepared to conduct primary site inspections, if needed. The mid-cycle outage will occur in the fall of 2007. Office of Nuclear Material Safety and Safeguards (NMSS) Honeywell Licensee Performance Review On March 21, 2007, NMSS staff, along with Region II Senior Management, conducted a public meeting to formally present the findings of the 2006 Licensee Performance Review for the Honeywell uranium conversion facility. The meeting was held at the Community Center in downtown Metropolis, Illinois. The meeting was attended by plant personnel from Honeywell and members of the public. Conclusion of American Centrifuge Plant Mandatory Hearings On March 21, 2007, the Atomic Safety and Licensing Board (Board) completed its mandatory hearing for the USEC Inc. (USEC) American Centrifuge Plant. The Board considered a range of safety and environmental issues associated with the construction, operation, and decommissioning of the proposed facility, during the 3-day hearing. It is expected to render its findings on whether to grant or deny a license to USEC by April 13, 2007. Staff Observe Audit of U.S. Department of Energy (DOE) Technical Data Management System On March 22, 2007, staff completed an observation of a DOE, Office of Civilian Radioactive Waste Management, Office of Quality Assurance audit of the Technical Data Management System. The audit was conducted in Las Vegas, Nevada. Its objectives were to evaluate the effectiveness of the processes for controlling technical data, the timeliness of data submittal to the Project's Technical Data Management System, and the traceability of submitted data to the processes and products that reference the data. The NRC observers assessed the effectiveness of DOE's audit team and the audit process, in achieving the audit objectives. Final Interim Staff Guidance on Level of Design Detail and Estimating Reliability On March 22, 2007, a notice was published in the Federal Register (72 FR 13534) that responded to public comments on draft Interim Staff Guidance, "Preclosure Safety Analysis - Level of Information and Reliability Estimation." The interim guidance clarifies review guidance in NUREG-1804, "Yucca Mountain Review Plan." Both the notice and final guidance HLWRS-ISG-02 are in the NRC's Agencywide Documents Access and Management System; the accession number is ML070260204. NRC and the DOE Quarterly Management Meeting On March 27, 2007, NRC and DOE staffs held a "Quarterly Management Meeting" on the DOE high-level waste program. Discussions included program updates and quality assurance issues, such as the DOE root-cause analysis regarding U.S. Geological Survey e-mails. The meeting was open to the public and was attended by interested parties, stakeholders, and members of the press. Public Meeting with Holtec International to Discuss the HI-STORM 100U Design Concept Certificate of Compliance Amendment Application and Structural Issues Office of Nuclear Regulatory Research (RES) Completion of Regulatory Guides for Use in New Reactor Licensing On March 28, 2007, the staff completed the publication of the high-priority regulatory guides (RGs) which needed to be completed in March 2007 to support new reactor licensing activities. In July 2006, the staff had identified 31 RGs to be revised or developed by March 2007 to support new reactor licensing activities. Two were later identified as exceptions and not to be completed by March 2007. One is the proposed revision to RG 1.93, "Availability of Electric Power Sources," which was subsequently evaluated and determined to not be needed and withdrawn. The second is completion of RG 1.206, "Combined License Applications for Nuclear Power Plants (LWR Edition)," which is being delayed until after incorporation of Commission comments related to the final Part 52 rule. In the interim, certain sections of RG 1.206 will be released for preliminary use prior to final publication of the RG. This completes the staff efforts with the high-priority regulatory guides. The staff will now begin work on the next phases of regulatory guides revision and development in accordance with the plan to review and update, as necessary, all regulatory guides. Office of Nuclear Security and Incident Response (NSIR) Preliminary Notifications
Office of Administration (ADM) Project on Government Oversight and Union of Concerned Scientists (PRM-50-83) On March 29, 2007, the NRC published a document in the Federal Register (72 FR 14713) that requests comment on a petition for rulemaking submitted by the Project on Government Oversight and Union of Concerned Scientists (PRM-50-83). The petitioners request an amendment that would require periodic demonstrations by applicable local, State, and Federal authorities to ensure that nuclear power plants can be adequately protected against radiological sabotage greater than the design basis threat. The comment period for this action closes June 12, 2007. Office of Information Services (OIS)
Freedom of Information Act (FOIA) and Privacy Act (PA) Requests Received During the Period of March 23 through March 29, 2007:
Office of Human Resources (HR)
Office of Public Affairs (OPA) The OPA received significant media inquiries on the following: Japanese Boiling Water Reactor Criticality Incident. Massachusetts Attorney General's (AG's) lawsuit against NRC on denial of AG's request for a hearing on Pilgrim's application; AG's petition for rulemaking that encompasses spent fuel concerns in licensing renewals. NRC's preparations for new reactor applications, licensing process and design certifications. Contamination issues regarding missing source from a two-source gauge stolen in Philadelphia. Other Public Affairs Items: Coverage of Chairman Klein, accompanied by Commissioners Merrifield and Lyons, testifying before the House Energy and Water Appropriations subcommittee on the NRC budget. Assisted, the Office of Nuclear Material Safety and Safeguards staff with an interview with Inside NRC about progress on development of a framework for oversight of fuel cycle facilities similar to an Reactor Oversight Process that was recommended by the Office of the Inspector General in their recent audit. MSNBC.com continues to come up with questions about the issue of the Marshal's Service providing law enforcement deputization for the Office of Investigations.
Office of the Secretary (SECY)
Commission Correspondence
Federal Register Notices Issued
Region II (RII) Browns Ferry Nuclear Plant Visit On March 30, the Regional Administrator and Regional management visited the Browns Ferry Nuclear Plant for a site tour and met with licensee management with both licensee management and members of the NRC Operational Readiness Assessment Team (ORAT), who are planning the Unit 1 ORAT inspection. Office of Congressional Affairs (OCA)
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