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INFORMATION REPORT SECY-01-0028 February 21, 2001
Contact: D. Terao, OEDO Office of Nuclear Reactor Regulation Closeout of MPA B111 - Individual Plant Examinations (IPE) An internal Division of Licensing Project Management memorandum was issued on February 12, 2001, to close out MultiPlant Action (MPA) B111. MPA-B111 involved the issuance of Generic Letter (GL) 88-20, "Individual Plant Examination for Severe Accident Vulnerabilities," dated November 23, 1988, and GL 88-20, Supplement 1, "Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities," dated August 29, 1989. The GL recommended that each operating plant and each near-term operating license plant perform an Individual Plant Examination (IPE) to search for severe accident vulnerabilities, or "outliers." As stated in the original GL: The general purpose of this examination was for each licensee to (1) develop an appreciation of severe accident behavior, (2) understand the most likely severe accident sequences that could occur at its plant, (3) gain a more quantitative understanding of the overall probabilities of core damage and fission product releases, and (4) if necessary, reduce the overall probabilities of core damage and fission product releases by modifying, where appropriate, hardware and procedures that would help prevent or mitigate severe accidents. The IPEs were reviewed by the Office of Nuclear Regulatory Research with assistance from various contractors, including Sandia National Laboratories, Brookhaven National Laboratory, Science and Engineering Associates, Inc., Scientech, Inc., Concord Associates, Inc., and SAIC. Normally a Level 1 (desktop) review was performed. In about six cases, the staff and its contractors conducted an onsite review of the detailed documents that supported the IPE methodology and conclusions (Level 2 review). In all cases, the results of the NRC review were sent to the respective licensees with a staff Safety Evaluation Report accompanied by the contractors' Technical Evaluation Reports in the areas of front-end (reactor), back-end (containment), and human reliability. V. C. Summer V.C. Summer has completed repair of the 'A' Loop hot leg nozzle-to-spool piece weld. The NRC Special Inspection Team conducted a public exit on February 15, 2001, at the site. The inspection identified two generic issues related to the capability of Code-accepted NDE and concerns regarding residual stress due to multiple repairs. No licensee performance issues were identified. Restart is scheduled for the end of February 2001. The staff and industry will brief the ACRS on March 2, 2001, on the phenomenon and the generic implications of the indication found in the V. C. Summer A loop hot leg weld. The staff will issue its safety evaluation of the licensee's analysis for continued operation with identified indications in the B and C loop hot leg welds prior to the plant restart. Siemens Power Corporation By letter dated February 2, 2001, Siemens Power Corporation advised the NRC that a joint venture between Framatome and Siemens was formally completed on January 31, 2001. The joint venture is now known as Framatome ANP (Advanced Nuclear Power). The merged organization brings together all the nuclear-related activities of Siemens (including several locations in Germany, the Richland, WA facility, and several organizations in Atlanta, GA) and Framatome, (including several locations in France and those in Lynchburg, VA). Trojan Nuclear Plant License Termination Plan NRR has issued Amendment 206 to Facility Operating License NPF-1, approving the Trojan Nuclear Plant License Termination Plan (LTP). The design of the final site survey assumes that there is no groundwater contamination resulting from Trojan operations or decommissioning. Existing groundwater data is insufficient to determine if the groundwater is contaminated. As part of the LTP approval, the licensee is required to determine if site groundwater contains residual radioactivity from plant operations, based on the groundwater monitoring program described in the LTP. This is the first power reactor LTP approved since the requirements were established in 10 CFR 50.82 in 1996. The Trojan LTP includes a site characterization, identification of remaining site dismantlement activities, site remediation plans, the final survey plan, the method of compliance with the radiological criteria for license termination, an update of site-specific decommissioning costs, and an evaluation of environmental effects of license termination. NRR and NMSS worked closely to complete the review. The licensee is nearing completion of the dismantlement work except for those structures, systems, and components required for maintaining the fuel in the spent fuel pool. Trojan plans to remove the fuel from the spent fuel pool in 2003, or later. Two areas remain as important activities at Trojan. These are spent fuel pool management and implementation of the final survey program. Due to a decrease in the amount of site activity, the licensee has recently reduced site staffing levels from approximately 300 to 100. The remaining staff will be used to maintain the spent fuel pool programs, pursue resolution of dry cask storage issues, and perform final surveys to eventually release the site from the Part 50 license. Due to the reduced activity at Trojan, Region IV is planning to reduce its inspection effort, except in those areas related to the final survey program and spent fuel pool operations. Operator Licensing Meeting On February 9, 2001, the Director of the Division of Inspection Program Management, the Chief of the Operator Licensing, Human Performance, and Plant Support Branch, the Chief of the Operator Licensing and Human Performance Section, the Operator Licensing Branch Chiefs from all four Regional Offices, and key members of the headquarters operator licensing staff met with representatives of the Nuclear Energy Institute's (NEI) Initial Licensed Operator Focus Group in a public meeting held at the NEI Offices in Washington, DC. Representatives from each regional facility operator training organization and the Institute of Nuclear Power Operations also participated in the meeting. The meeting was convened to continue the dialog among operator licensing program stakeholders and to promote the effective and efficient implementation of Revision 8 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The discussion topics included the upcoming supplement to NUREG-1021, the recently issued Regulatory Issue Summary (RIS 2001-01) regarding the eligibility guidelines for operator license applicants, the generic fundamentals examination and website, the status of the reactivity manipulation rule change, and possible long-term options for continuing to improve the operator licensing process. Reactor Oversight Process The Inspection Program Branch (IIPB) conducted a public meeting with industry's Reactor Oversight Process (ROP) working group on February 7, 2001, to discuss and review proposed changes to the first revision of NEI 99-02, "Regulatory Assessment Performance Indicator Guideline." A draft of revised NEI 99-02 is expected to be issued for review and comment by mid-February 2001. The due date for submitting comments is March 16, 2001. IIPB will review all comments at an NRC/NEI public meeting on March 29, 2001. IIPB also conducted another of a continuing series of public meetings on February 8, 2001, with industry's working group on the ROP. The key issues discussed included: fault exposure time impact on unavailability performance indicators (PIs), piloting a replacement PI for unplanned power changes in the May/June 2001 time frame, the interim Physical Protection significance determination process (SDP) which was made publically available for use on February 8, 2001, by the Commission, enforcement discretion for PI reporting errors that ended on January 31, 2001, ROP Web page changes, and reviews of frequently asked questions (FAQs). The next meeting is tentatively scheduled for March 1-2, 2001. On February 9, 2001, the IIPB staff transmitted a survey questionnaire to solicit feedback from NRC internal stakeholders who have been involved with the reactor oversight process (ROP) during the first year of initial implementation. The results of this survey will be used to assess the need for program changes and will be incorporated, as appropriate, into the ROP self-assessment activities. The IIPB staff conducted a Division of Reactor Projects and Division of Reactor Safety regional counterparts meeting on February 5-6, 2001, at Region IV. The topic areas discussed included: feedback on inspection report audit plan, focus group topics associated with inspection program flexibility/resources and assessment and enforcement issues, resource data compiled on ROP, and alignment of inspection cycle/assessment. The group agreed that aligning the ROP annual cycle with the calender year was the most suitable alignment, and IIPB will develop guidance for the transition period of April - December 2001. Fitness-for-Duty Rule Implementation Workshops The staff of the Reactor Safeguards Section (RSS) in the Operator Licensing, Human Performance, and Plant Support Branch plans to conduct workshops with regional staff and external stakeholders on implementation of the Fitness-for-Duty Rule (10 CFR Part 26). Regional staff involved in overseeing NRC licensees' implementation of the revised Part 26 will participate in two workshops for regional personnel only, which are scheduled for February 28-March 1, 2001, and May 30-31, 2001, at Headquarters. External stakeholders, as well as regional personnel, will also participate in a workshop that is scheduled for March 20-22, 2001, in Rockville, MD in the NRC's TWFN auditorium. Additional details on the workshops, as they become available, can be obtained from the fitness-for-duty website at http://www.nrc.gov/reactors/operating/ops-experience/fitness-for-duty.html. Health Physics Society Meeting and International ALARA Symposium Two members of the Emergency Preparedness and Health Physics Section attended the joint meeting of the Health Physics Society (34th Midyear Topical on ALARA considerations in the 21st Century ) and the NEA (International ALARA Symposium), in Anaheim, CA, February 3-7, 2001. The staff presented the ALARA experience to date with the revised Reactor Oversight Process (ROP). In addition, a poster session was presented giving an overview of the entire revised ROP with emphases on the Occupational Radiation Safety cornerstone. The ROP web page was also demonstrated, using an NRC laptop computer, as part of the poster session.
Office of Nuclear Material Safety and Safeguards Stakeholder Meeting on Case Studies in Gas Chromatographs, Static Eliminators, and Fixed Gauges On February 9, 2001, the Risk Task Group staff held a public meeting to discuss its case studies on gas chromatographs, static eliminators, and fixed gauges. These case studies are part of the staff's overall effort to develop an approach for using risk information in the nuclear materials and waste regulatory process. The purpose of this meeting was to: (1) communicate to stakeholders the status of these case studies; (2) receive feedback and comments from stakeholders before continuing with the case studies; and (3) solicit from stakeholders comments or insights regarding the use of risk information in the Nuclear Regulatory Commission's (NRC's) regulation of gas chromatographs, fixed gauges, and static eliminators. Approximately 30 stakeholders, from industry, citizens' groups, and the NRC, attended the meeting and provided comments. Some stakeholders commented that the staff needs to collect and evaluate more data before drawing any conclusions. Stakeholders also commented that other technical aspects should be addressed in the risk assessment, including the likelihood of occurrence, the half-life of the isotope in question, and economic risks. Another stakeholder stated that the staff should get agreement states and other stakeholders involved, and draw upon their experience. Also, one stakeholder expressed concern that the conclusions made in these case studies would be extrapolated to more consequential activities in the materials and waste arenas. The staff emphasized that no decisions or final conclusions have been made on the case studies and that the purpose of the meeting was for the staff to solicit feedback before continuing with the case studies. Meeting with Virginia Power to Discuss Ongoing Development of Review Guidance for 10 CFR Part 72 License Renewal On February 8, 2001, Spent Fuel Project Office staff met with Virginia Power to discuss the ongoing development of review guidance for 10 CFR Part 72 license renewal. The staff addressed the specific comments provided by the utility on the staff's initial guidance issued in June 2000. The staff also discussed its philosophy and preliminary guidance in the materials area, which will be the primary area of focus for the review of renewal applications. The staff intends to issue draft guidance for comment in the near future, consistent with Virginia Power's schedule for commencing work on the Part 72 renewal application for Surry's site-specific license, which is expected in Spring 2002. Meeting with BNFL Fuel Solutions and Consumers Energy Regarding Amendment Request to Support Big Rock Point Decommissioning On February 7, 2001, Spent Fuel Project Office staff met with BNFL Fuel Solutions and Consumers Energy to discuss a planned April 2001 amendment request for the FuelSolutionsTM spent fuel dry storage cask. Big Rock Point, a future user of the FuelSolutionsTM canister, seeks approval by July 2002 to support decommissioning and dismantlement of the spent fuel pool. Moab Mill (Atlas) Public Meeting On February 7, 2001, the Nuclear Regulatory Commission (NRC) held
a public meeting in Moab, Utah, as part of its commitment to public participation
in actions related to the remediation of the nearby, former Atlas Corporation,
uranium mill tailings site. At NRC's invitation, the current licensee
for the site, the Moab Mill Reclamation Trust, represented by its trustee,
PricewaterhouseCoopers (PWC), and the Department of Energy (DOE
Meeting on Trustee Actions Prior to Transfer of the Moab Mill (Atlas) Site to the Department of Energy On February 8, 2001, at the invitation of the Executive Director of the Utah Department of Environmental Quality (DEQ), staff from the Nuclear Regulatory Commission, the Department of Energy (DOE), PricewaterhouseCoopers (PWC), the DEQ, and Grand County elected officials met at DEQ offices in Salt Lake City, Utah. The purpose of the meeting was to discuss actions that PWC could take at the mill site to facilitate transfer of the site to DOE in the best possible condition and the costs of those actions. This was a follow-up to a meeting held in Moab, Utah, on January 21, 2001. The participants agreed to continue working on the list of actions and priorities previously identified. DOE agreed to take the lead in working with the other participants to reach consensus and prepare a report identifying specific actions, priorities, and estimated costs by February 22, 2001. Moab Mill (Atlas) Stakeholders Meeting On February 8, 2001, staff from the Nuclear Regulatory Commission (NRC) participated in a meeting of the Atlas Stakeholders group, held at the Utah Department of Environmental Quality offices in Salt Lake City, Utah. NRC made a brief presentation on activities to be conducted prior to transfer of the site to the Department of Energy (DOE) and NRC's role after transfer. Presentations were also made by PricewaterhouseCoopers and DOE. A member of the groundwater subcommittee discussed its activities and role in the future. Near the end of the meeting, a representative of the U.S. Fish and Wildlife Service (FWS) announced that FWS had just sent a letter to NRC withdrawing the biological opinion of July 29, 1998, related to reclamation of the site and also withdrawing the incidental take provisions. Several stakeholders expressed concern that the FWS action would delay or even prevent further activities designed to better prepare the site for transfer to DOE, and that they would have to further evaluate the FWS letter that was distributed. Stakeholder Meeting on Fuel Cycle Standard Review Plan On February 8, 2001, Division of Fuel Cycle Safety and Safeguards staff met with stakeholders in a public meeting at the Nuclear Regulatory Commission (NRC) Headquarters to discuss Chapter 3 (Integrated Safety Analysis) of the Standard Review Plan. The Nuclear Energy Institute's comment letter of November 16, 2000, was discussed and staff presented a description and explanation of Chapter 3 and its Appendix A. This meeting resulted in an improved understanding by stakeholders of NRC objectives for the use of Chapter 3 in determining and communicating the risk inherent in the design and operation of fuel cycle facilities. Several action items for the staff were established involving possible revisions to Chapter 3 material. Joint Procedure Between the Department of Energy and the Nuclear Regulatory Commission Response to Emergencies in the Leased Areas at the Gaseous Diffusion Plants On February 8, 2001, the Division of Fuel Cycle Safety and Safeguards staff was informed that the Department of Energy (DOE) has signed the Joint Procedure Between the DOE and the Nuclear Regulatory Commission (NRC) "Response to Emergencies in the Leased Areas at the Gaseous Diffusion Plants." This Joint Procedure delineates the framework and the responsibilities of both agencies when responding to Gaseous Diffusion Plant emergencies. It focuses on the coordination of the type of event information to be communicated, timely and effective information exchange, information release to a third party, transfer of lead federal agency responsibility, the recovery plan, and termination of the emergency. The staff will incorporate this Joint Procedure into the responders' implementing procedures. This Joint Procedure is required by the "Memorandum of Understanding Between the Nuclear Regulatory Commission and the Department of Energy on Cooperation Regarding the Gaseous Diffusion Plants," signed on October 28, 1997. The 1997 Memorandum of Understanding called for DOE and NRC to develop appropriate joint procedures which will ensure compatibility in response to emergencies in leased areas under NRC regulatory oversight. Meeting with Representatives from the U.S. Enrichment Corporation On February 13, 2001, staff from the Division of Fuel Cycle Safety and Safeguards met with representatives from the U.S. Enrichment Corporation (USEC) to discuss technical issues associated with the review of the Paducah higher assay upgrade project certificate amendment request. The objectives of the meeting were to discuss recent technical issues which have arisen during the Nuclear Regulatory Commission's review of the nuclear safety analyses performed for the Normetex pumps used at the facility. The staff is continuing to review information submitted by USEC to justify the use of the pumps at the higher enrichment level. Several paths to resolution were discussed and both parties agreed to continue to work to resolve this issue prior to the scheduled amendment issue date of March 16, 2001. University of Nevada Announces Results of Its Fluid Inclusion Investigation of Yucca Mountain On February 8, 2001, the University of Nevada Las Vegas (UNLV) issued a press release announcing the findings of a two-year investigation it conducted of the fluid history beneath Yucca Mountain. The investigation analyzed data from the so-called two-phase fluid inclusions found in the calcite deposits beneath the Mountain, and sought to determine the presence and timing of fluids with elevated temperatures that may be indicative of geothermal activity. This was a highly visible investigation because it addressed an important question concerning the suitability of Yucca Mountain for construction of a repository for disposal of spent fuel and high-level nuclear waste. At issue is whether or not this potential repository site is going to be subject to geothermal activity during its planned 10,000-year life, with the state of Nevada consultants saying that it is, and the U.S. Geological Survey experts saying that it is not. The UNLV press release indicated that fluids with elevated temperatures ranging from 45 to 60 degrees C were present throughout the site in the geological past, but that the data provide no evidence for the presence of the two-phase fluids at Yucca Mountain in the past two million years. Some samples constrain the presence of these fluids to more than 4 to 5 million years. The press release further indicated that the results of the investigation do not allow a determination if the fluids that precipitated the secondary minerals beneath Yucca Mountain originated as surface water or upwelling fluids, but they noted that their observations are not consistent with a hydrothermal origin for secondary minerals at the site. Repository Design and Thermal-Mechanical Effects Key Technical Issue Technical Exchange On February 6-8, 2001, staff of the Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses met with the Department of Energy (DOE) and its Management and Operating Contractor staff during a Technical Exchange (TE) held in Las Vegas. The topic of the TE was the Repository Design and Thermal-Mechanical Effects (RDTME) Key Technical Issue (KTI). The TE addressed each of the four subissues under the RDTME KTI which are as follows: (1) Design Control Process; (2) Seismic Design of the Repository; (3) Thermal-Mechanical Effects; and (4) Repository Seals. Following the TE, the staff and the DOE agreed to categorize the subissues in the following manner: The DOE presentations and discussions at the TE confirmed that the DOE has sufficient information to address subissues 1 and 4. The TE also confirmed that the DOE plan to prepare Topical Report #3 on seismic design inputs, should mean the DOE will have enough information to address subissue 2; however, the staff has not reached any conclusions about the outcome of its review of that information. Finally, the TE discussions, together with the 21 specific agreements between DOE and the Nuclear Regulatory Commission staff, should mean the DOE will have sufficient information to address all components of subissue 3, subject again to the understanding the staff has not reached any regulatory conclusions about its review of the information. According to the agreements, most of the results of the studies and analyses agreed to be undertaken by DOE will be available to the staff in fiscal years 2002 and 2003.
Office of Nuclear Regulatory Research Comparison of the Indian and the New Madrid Earthquakes Prior to the recent earthquake a number of prominent seismologists had drawn comparisons between the Kutch region of India and the New Madrid seismic zone in the central United States. The recent earthquake has aroused interest in these comparisons and has generated a significant number of high quality digital seismograms from both regional and worldwide seismographic stations. Some of the apparent similarities are:
Significant post-earthquake investigations that will increase the knowledge base for the comparison of these two apparently analogous areas are planned by the U.S. Geological Survey, the Indian Geological Survey, numerous research institutes and universities around the world, and commercial geoscience companies. There is currently no reason for a significant change to the present assessment of the seismic hazard in the New Madrid zone. The old adage that lightning does not strike twice in the same place is not true for the town of Bhuj. Bhuj was devastated in the January 26, 2001, event (there are reports that 10,000 residents out of a population of 35,000 have perished), and Bhuj suffered a reported 2,000 fatalities/casualties from the 1819 earthquake. While the NRC is not actively engaged in discussions on nuclear issues with India, it has communicated this recent earthquake, with the Indian geoscience community through the U.S. Geological Survey and university-based research organizations. These leads will be actively pursued to bring to bear the lessons to be learned to US seismic hazard issues as rapidly as possible.
Incident Response Operations Preliminary Notifications
Office of Administration List of Approved Spent Fuel Storage Casks: NAC-UMS Revision (Part 72) A document confirming the effective date of February 20, 2001, for a direct final rule that revised the NAC-UMS cask system listing within the list of approved spent fuel storage casks was published in the Federal Register on February 16, 2001(66 FR 10569). The amendment allows holders of power reactor operating licenses as general licensees to store PWR design basis fuel assemblies in accordance with revised technical specifications and Maine Yankee site-specific spent fuel in the NAC-UMS. List of Approved Spent Fuel Storage Casks: TN-32 Revision (Part 72) A document confirming the effective date of February 20, 2001, for a direct final rule that revised the TN-32 cask system listing within the list of approved spent fuel storage casks was published in the Federal Register on February 16, 2001(66 FR 10569). The amendment will allow holders of power reactor operating licenses to store spent fuel in the cask under revised conditions. Acquisition Training On February 15, 2000, the Division of Contracts and Property Management presented Acquisition for Certification and Training Program module, "Organizational Conflicts of Interest." The training presentation includes a discussion of what constitutes a conflict of interest (COI) and how the Agency regulations treat COI. Lectures also include the process for identifying and resolving COI situations for both contract awards to the private sector and DOE Laboratory agreements. Contract Award On February 15, 2001, a cost plus fixed fee contract for work entitled, "Regulatory Strengthening Through Provision of Basic Office Equipment" was awarded to Mega-Tech., Inc., of Falls Church Virginia under the 8(a) program. The award was made pursuant to NRC's Memorandum of Understanding with the U.S. Small Business Administration dated September 24, 1999 which streamlined the process for delegating authority to make 8(a) awards. The Contractor is responsible for providing all the necessary personnel, facilities, materials , equipment, etc., to enhance the Armenia Nuclear Regulatory Authority and Kasakhstan Atomic Energy Commission capabilities to perform safety and regulatory oversight of Soviet-designed reactors through the provision of basic office-related equipment. The contract award amount is $337,823.18, and period the performance is February 15, 2001, through February 14, 2002, with 3 six-month option periods. Procurement streamlining methods implemented were: reduced proposal preparation time, electronic transmittal of the statement of work, SBA/NRC MOU. Small Agency Council DCPM participated in the February 13, 2001, quarterly meeting of the Small Agency Council (SAC.) The General Services Administration representatives presented information about the new Federal Business Opportunity (FedBizOpps) website that replaces the Commerce Business Daily. GSA representatives also gave an on-line tour of the new website. DCPM staff shared their experience using this user-friendly website to post presolicitation information.
Chief Information Officer Freedom of Information and Privacy Act Requests received during the Period of February 9, 2001 through February 15, 2001:
Office of Human Resources
Office of Enforcement A revision to the Enforcement Policy addressing Base Civil Penalties for Loss, Abandonment, or Improper Transfer or Disposal of Sources was issued on December 18, 2000. This revision was published with a companion final rule involving 10 CFR Parts 30, 31, and 32, governing certain industrial devices containing byproduct material that are licensed pursuant to the general license provisions of 10 CFR 31.5. The inclusion of separate base civil penalty amounts considers both the cost of proper disposal and the relative risk to the public from sources that are lost, abandoned, or improperly transferred of disposed of. The new base civil penalty structure is roughly equivalent to three times the cost of proper disposal. The revision becomes effective on February 16, 2001. The electronic version of the Enforcement Policy on OE's web site has been updated to include this change. The Enforcement Manual will be updated shortly to reflect this change.
Office of Public Affairs Media Interest Myron Fliegel, NMSS, was interviewed by a reporter from the Salt Lake Tribune regarding the U.S. Fish & Wildlife Service's withdrawal of the final biological opinion and the incidental take statement for the reclamation of the Atlas Uranium Mill Tailings site. One reporter attended a meeting at D.C. Cook to discuss plant performance issues, and a reporter from a CBS news affiliate called for an update. There were some press inquiries in Region II on the Atomic Safety and Licensing Board order regarding the Shearon Harris spent fuel pool issue.
Office of International Programs Visit of New Japan Electric Power Information Center Manager On Wednesday, Mr. Satoshi Ito, the new General Manager of the Washington Office of the Japan Electric Power Information Center (JEPIC) met with two members of the OIP staff. JEPIC represents the interests of the newly created Japanese Ministry of Energy, Trade and Industry (METI) and the Japanese electric utilities. Mr. Ito described the responsibilities of METI and their interactions with the Japan Nuclear Safety Commission. Protocol on Research Reactor Safety IAEA plans to raise again with its Member States the need for adding a formal protocol on research reactors to the Convention on Nuclear Safety. To date, the U.S. has been favorably disposed towards international action to address safety-deficient research reactors, but has not supported the idea of adding a protocol to the CNS. Such a change would require Congressional review and consent.
Office of the Secretary
Commission Correspondence
Federal Register Notices Issued
Region I Meeting with Whittaker Corporation Representatives of Region I and the Office of Nuclear Material Safety and Safeguards (NMSS) held a meeting with Whittaker Corporation on February 15, 2001 in Headquarters. The meeting discussed NRC's review of the licensee's risk assessment dated September 2000 for Whittaker's Greenville, PA, SDMP site. The meeting was attended by Whittaker's Vice President, members of Scientech, Inc., Whittaker's decommissioning consultant, members of the Commonwealth of PA's Bureau of Radiation Protection, and Regional and NMSS staff. At the conclusion of the meeting, Scientech and Whittaker stated that they had all the information needed to finalize their plans for disposition of the site and that they would notify the NRC in the near future of their plans.
Region II Employee Concerns Program Forum On February 12, the Regional Administrator addressed the Employee Concerns Program Forum, in Atlanta, on the topic of "NRC and Nuclear Industry Future Challenges." The Forum was also attended by the Agency Allegations Advisor and the Region II allegations staff. Semi-Annual Region II Licensing Counterparts Meeting On February 14, the Regional Administrator and other regional managers attended the Semi-Annual Region II Licensing Counterparts meeting in Atlanta. Topics of discussion included the status of the Revised Reactor Oversight Program, 10 CFR 50.59 Inspections and Maintenance Rule Inspections. Duke Energy Corporation - McGuire Self-Assessment On February 13, representatives from Duke Energy Corporation were in the Regional Office to discuss the licensee's assessment of performance at the McGuire nuclear plant. The meeting was held in the Region II office and was open to the public. Region II Federal Women's Program On February 15, the Region II Federal Women's Program hosted, in celebration of Black History Month, the Inman Middle School Dancers who performed a traditional dance. In addition, there was African American cuisine for sampling. All Regional staff members were invited to attend these activities. South Carolina Electric and Gas Company - V. C. Summer Public Exit Meeting On February 15, the Special Inspection Team held a public exit meeting at the V. C. Summer nuclear plant. The Special Inspection Team summarized the conclusions from the NRC review of the licensee's corrective actions for a crack and repair of the pipe and weld area in hotleg "A" of the reactor coolant system.
Region III Region III Staff Holds Quad Cities Regulatory Conference Region III staff members on February 13 met with Exelon Generation Company representatives to discuss recent inspection findings on radiation protection at the Quad Cities plant. The plant is located in Cordova, Illinois. During the meeting, participants discussed a potential white finding associated with planning problems concerning occupational radiation doses. The doses were incurred during a recent refueling outage when workers were replacing safety relief valves. One reporter attended the meeting which was held in the regional office. Staff Discusses D.C. Cook Plant Performance Staff members from the regional office and the Office of Nuclear Reactor Regulation met with American Electric Power officials on Thursday, February 15 to discuss the performance of units 1 and 2, and containment interior wall issues at the D.C. Cook plant in Bridgman, Michigan. Plant officials told staff members that they had received positive results concerning the ongoing containment structure analysis on both units. The analysis involves strength-versus-load calculations to assure design compliance. Plant officials said they expect to complete the Unit 1 analysis in May and Unit 2 calculation inputs will be verified during the next refueling outage. One reporter attended the public meetings.
Office of Congressional Affairs CONGRESSIONAL HEARING SCHEDULE, No. 3
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),
also participated in the public meeting. Presentations were made by the
three organizations, focusing on recently completed and planned future
activities at the site, followed by a question and answer session. Recent
legislation will result in transfer of the site to DOE with the responsibility
to perform remediation. Approximately 50 people in addition to NRC, PWC,
and DOE representatives attended the public meeting.