|Weekly Information Report|
For the Week Ending June 11, 1999
[ archive ]
The Weekly Information Report is compiled by the NRC Office of the Executive Director for Operations and includes highlights of Headquarters and Regional Office activities. For technical questions, please contact M. Satorius, OEDO by E-mail: firstname.lastname@example.org. For administrative questions, please contact Patricia Anderson at (301) 415-1703, or by E-mail: email@example.com. If you would like to request a hard copy, you may contact the NRC Public Document Room at (202) 634-3273, or by E-mail: mailto:firstname.lastname@example.org
Office of Nuclear Reactor Regulation
[ Prev | Next ]
The staff held a Meeting with Duke Energy Corporation, Virginia Electric Power Company, Framatome Cogema Fuels, and Duke Cogema Stone & Webster (these entities are informally named the "MOX Consortium"). The purpose of the Meeting was to discuss matters related to the proposed future use of MOX nuclear fuel at the 3 nuclear plants: Catawba, McGuire, and North Anna.
The proposed use of MOX in civilian nuclear reactors would play a significant role in the U.S. policy for disposal of 33 tons of excess weapons-useable plutonium. The tentative Schedule calls for testing lead MOX fuel assemblies during the 2000-2005 Time frame and full-scale use in one of the reactors during the 2005-2010 Time frame. The testing and full-scale use of MOX in a power reactor would require staff approval in the form of amendments to the operating license. The MOX Consortium's presentation was an overview covering the history leading to the proposed use of MOX fuel in the above plants (6 reactors), organization of the MOX Consortium, MOX experience worldwide, the future MOX fabrication facility, MOX fabrication techniques, technical data on MOX performance, methodologies for safety analyses, anticipated plant modifications to accommodate use of MOX fuel, regulatory requirements, and licensing issues.
The staff stated that it had been aware of the possibility of the proposed use of MOX fuel and had recently written an internal memorandum to the Commission on this Subject. The staff commended the MOX Consortium for making an informative and thorough presentation and for proposing a reasonable Schedule. The staff recommended that the MOX Consortium evaluate the need for exemptions from the regulations, as some of the regulations may be read as only being applicable to uranium fuel. The staff's summary of the Meeting was issued on June 9, 1999.
On June 7, 1999, the NRC staff met with public stakeholders and representatives of the Nuclear Energy Institute to discuss the preliminary results of the staff's recent efforts on potential spent fuel pool accidents at permanently shut down reactors. The staff's preliminary results indicate that the probability and consequences of an accident that would drain the spent fuel pool and result in a zirconium spent fuel cladding fire are too great to dismiss. These results are too preliminary to be applied to the existing regulatory process. The staff plans to conduct an independent, technical, quality review effort over the next six months to refine the assumptions made and ensure the results are applicable. The NRC plans to release its draft report with preliminary results in July 1999.
On June 8, 1999, NRC managers met with NEI and industry representatives and agreed to have a follow-up public Meeting and a public workshop to discuss the NRC staff's preliminary results in these areas.
On June 2, 1999, John Wilcox and Ed Ford of the Quality Assurance Vendor Inspection, Maintenance and Allegations Branch conducted Maintenance Rule (MR) training for Region III personnel. The regional attendees consisted mainly of inspectors from the Division of Reactor Safety and the Division of Reactor Projects. The training provides a risk-informed, performance-based method to satisfy routine and non-routine maintenance inspection program requirements by using "maintenance rule field work flow charts" to evaluate plant performance issues. These charts are a new type of inspection tool devised by members of the branch's Reliability and Maintenance Section to provide a visual, efficient inspection tool to inspectors performing inspection activities required by the Rule (10 CFR 50.65). The intent of the charts and the training is to allow the agency to make more efficient use of increasingly limited resources and still discharge its regulatory responsibilities in this area.
The training consisted of an overview of the new assessment and oversight process and the important role that the maintenance rule plays in that process. Mr. Wilcox presented the main elements of the new reactor oversight process and discussed the various areas where the MR interfaced with that new regulatory paradigm. Reference was also made to the Significance Determination Process (SDP) and its Place in the assessment and oversight process. Mr. Ford then utilized the new MR field flow charts to describe the general principles of applying the MR to an operating facility. This presentation consisted of a review of basic MR requirements and an explanation of how those requirements are expressed in a performance-based manner in the new MR field flow charts. The flow charts are designed to be an aid utilized by inspectors during the conduct of the risk-informed and performance-based MR activities implemented by the new and current inspection procedures.
The presentations were generally well received as demonstrated by the receptiveness of the attendees to the presented information and the thoughtful questions from the inspectors. It was pointed out that potential issues of consistency were mitigated by the standing MR enforcement panel and the inherent consultation process contained in the regulatory review requirement of the new flow charts. This "regulatory review" process was shown to be a necessary activity that not only assured good intra-agency communication regarding potential MR issues, but also served as a first screen to entering the SDP process.
This training is part of a multi-pronged outreach program conducted by the program office to assure a good understanding of the maintenance rule requirements and how to most effectively assure those requirements are met in a performance-based, risk-informed regulatory regime. Other elements of this outreach program include site training with a strong element of practical site-specific issue identification and resolution, a train-the-trainer program, and periodic workshops. To Date three regional presentations have been conducted, three DRS trainers have been trained, and five separate resident groups have received on-site hands-on training.
The pilot program to verify the revised reactor oversight process described in Commission papers SECY-99-007 and SECY-99-007A for nine plants started on May 30, 1999.
Preparations are being made for the Revised Reactor Oversight Process Pilot Workshop to be conducted in Irving, Texas the week of June 21, 1999.
As part of its efforts to communicate with external stakeholders regarding the revised reactor oversight process, the NRC conducted an evening public Meeting in the vicinity of Quad Cities area on June 8, 1999. At this Meeting, the NRC staff explained to members of the public the new risk informed oversight program and the nature of the pilot effort and answered questions from the audience. Future meetings are scheduled at other pilot plants such as Prairie Island 1&2 at Red Wing, MN on June 14, 1999, at 6 p.m.; Ft. Calhoun at Blair, NE on June 17,1999, at 7 p.m.; Cooper at Auburn, NE on June 22, 1999, at 7 p.m; and Sequoyah at Chattanooga, TN on June 28, 1999, at 6 p.m.
Bill Dean and Auggie Spector met with Congressional staff from the House Commerce Committee on June 9, 1999, to provide them information on the status of the revised reactor oversight process improvements.
The staff continued its biweekly meetings with NEI and other stakeholders associated with the revised reactor oversight process, holding a Meeting on June 9, 1999.
The U.S. Nuclear Regulatory Commission is issuing this information notice to alert addressees to potential problems associated with post-fire safe-shutdown circuit analysis. These potential problems could result in a vulnerability to fire-induced circuit failures that could prevent the operation or lead to malfunction of equipment necessary to achieve and maintain post-fire safe shutdown.
The U.S. Nuclear Regulatory Commission (NRC) is issuing this generic letter to:
During the period from June 1 through June 4, 1999, meetings were held between the NRC staff and its contractor Brookhaven National Laboratory (BNL), and representatives of Gosatomnadzor of Russia (GAN) and the Nuclear Regulatory Administration of Ukraine (NRA). The purpose of these meetings was to refine the scope of material that should be covered during the conduct of four classroom/consultation activities described in the Memoranda of Meetings, signed by the EDO. NRC staff representatives from the Division of Regulatory Improvement Programs, the Division of Engineering, the Division of Systems Safety & Analysis and the Office of Research participated in the meetings.
These planning meetings were the first to be performed this year according to a new model discussed during the annual meetings with GAN and NRA in December and January. During those meetings, the participants agreed to a new two-step approach for conducting classroom/consultation activities involving a planning Meeting in advance of the activity. The planning Meeting is intended to provide Russian and Ukrainian counterparts more opportunity to shape each activity up front, while involving direct access to the NRC staff specialists, who may not fully participate in the conduct of the activity because of constraints on staff resources. According to the new model, certain classroom/consultation activities will be conducted in Russia and the Ukraine, rather than the U.S., with the goal of reaching a wider audience, and strengthening the lines of communication between the reactor facility staff and the regulatory staff. Cooperation within the new model structure is also intended to modularize the training for certain activities so that future activities will build upon work previously accomplished.
The planning meetings were successful in that GAN and NRA framed their needs and expectations for the training activities and provided suggestions for the course content that would be incorporated directly into the revised course outlines. The refined syllabus will be used to develop the material that will be presented in classroom/consultation activities to be conducted in the U.S. and in Moscow and Kyiv, by September 30, 1999.
Office of Nuclear Material Safety and Safeguards
[ Prev | Next ]
On June 2, 1999, staff from the Spent Fuel Project Office met with Gesellschaft für Nuklear-Behälter mbH (GNB) to discuss the CASTOR X/32 spent fuel storage and transport cask design. GNB presented information on the cask design and associated engineering analyses. GNB intends to submit an application later this year seeking a certificate of compliance for the storage of spent fuel under a general license. GNB's Schedule for submitting the associated transport application remains to be determined.
On June 2, 1999, two rail cars carrying depleted uranium hexafluoride (DUF6) cylinders onsite derailed while being moved several hundred yards from the cascade tails withdrawal stations to a cool-down area. Three rail cars were being pulled by a diesel track mobile unit. The track mobile unit and the first car in the train did not derail. Each rail car was carrying three 14-ton liquid DUF6 cylinders. Based on preliminary information, a defective rail tie is believed to have caused the derailment of the two rail cars. All the DUF6 cylinders remained in their rail car cradles. Plant staff assessed the derailed rail cars to be horizontally tilted at a 6 degree angle. A center-of-gravity analysis that had been previously done by the plant staff indicates that at a 34 degree horizontal tilt, the cylinders could roll out of the rail car cradles. The plant activated its Emergency Operations Center until it determined that the cylinders were in a safe condition. The plant is conducting a root-cause analysis of the incident. Region III is planning an inspection to review the incident.
On June 2-3, 1999, staff from the Division of Fuel Cycle Safety and Safeguards (FCSS) attended the annual Users Meeting of the Nuclear Materials Management and Safeguards System (NMMSS). NMMSS is the national data base for reporting and tracking of nuclear materials. The Meeting was attended by approximately 115 persons representing the NRC licensees, Department of Energy (DOE) sites, NRC, DOE, and the NMMSS system operator. The Meeting addressed changes in the NMMSS and its usage. The Meeting was followed on June 4, 1999, by the NMMSS Steering Committee Meeting. NRC is represented on the Steering Committee by representatives from FCSS and the Office of International Programs. The Steering Committee addressed problems identified by the users and the status of enhancements and corrective actions.
On June 2, 1999, the draft proposed 10 CFR Part 70 rule and supporting documents, including an associated Standard Review Plan, were provided to the Commission (SECY-99-147). The rule is risk-informed and performance-based in that it specifies performance requirements, consisting of consequences and associated likelihoods, that must be met, but allows the applicant/licensee flexibility in determining how they will be met. The rule and associated Standard Review Plan were developed considering extensive stakeholder input. A Commission Meeting to discuss the rule was conducted June 14, 1999.
On June 1 and June 3, 1999, staff from the Division of Industrial and Medical Nuclear Safety participated as the Nuclear Regulatory Commission (NRC) resource representative to the Conference of Radiation Control Program Directors (CRCPD) SR-1Committee. The Committee is developing suggested state regulations (SSR) for "Licensing Requirements for Uranium and Thorium Milling and Related Radioactive Material" -- Agreement State Part U regulations. The Agreement State Part U SSR incorporate the NRC 10 CFR Part 40 (and Appendix A) regulations relative to uranium recovery facilities. The group reached agreement on a proposed SSR that is now in the process of being finalized. The Part U SSR under development will be consistent with existing NRC regulations, including the April 12, 1999, final rule on "Radiological Criteria for License Termination of Uranium Recovery Facilities." In conjunction with this product, the CRCPD staff will propose that a member of the Part U working group be part of the NRC rulemaking team for the development of revised NRC regulations for uranium recovery facilities -- see SECY-99-011. This will allow future revisions to the Part U SSR to be completed in parallel with NRC revisions to uranium recovery regulations.
On June 3, 1999, Office of Nuclear Material Safety and Safeguards staff met with staff of the Environmental Protection Agency's (EPA's) Office of Radiation and Indoor Air (ORIA) to discuss the technical issues associated with developing an approach to facilitate the disposal of radioactive mixed waste with low levels of radioactive material in Resource Conservation and Recovery Act (RCRA) permitted facilities without requiring these facilities to obtain a specific license under 10 CFR Part 61. Under this approach, EPA would develop generally applicable environmental standards defining the conditions for the safe disposal of the low-activity mixed waste. The standards would include radionuclide concentrations for mixed waste that could be disposed of in the RCRA permitted facility without site-specific dose modeling or performance assessments. The NRC would then develop the implementing regulations for licensing the disposal of the radioactive portion of the mixed waste.
During this Meeting, ORIA staff stated that it intended to base the environmental standards, and develop the concentrations of radionuclides that could be disposed of in the RCRA facility under the approach, on three criteria. First, for mobile radionuclides, the concentrations of radionuclides at a well 50 meters from the emplaced waste could not exceed the EPA's Maximum Contaminant Levels under the Safe Drinking Water Act. Second, the on-site doses to workers at the RCRA facility could not exceed 15 millirem per year. Finally, in No case could the waste exceed the NRC's criteria for Class A waste in 10 CFR Part 61. ORIA staff also stated that it planned on sending the draft regulatory language to the Office of Management and Budget (OMB) during the week of June 7, 1999. ORIA staff will provide the draft language to NRC staff, along with the Background Information Document and Regulatory Impact Analysis when it is provided to OMB. ORIA staff also intends to forward the draft regulatory language to the Department of Energy, Occupational Safety and Health Administration, and Department of Health and Human Services for interagency review and comment prior to publishing the draft regulations for public comment in September or October 1999.
On June 1-2, 1999, staff from the Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses presented papers and posters on Yucca Mountain at a special session of the American Geophysical Union's annual Meeting. The staff discussed results of its probabilistic risk analyses of seismicity, faulting, and volcanism, and results of its field, lab, and computer simulations of groundwater flow. DOE's maintenance and operations and other subcontractors (e.g., U.S. Geological Survey, Los Alamos National Laboratory) presented results of recent analyses of the unsaturated and saturated zone flow and transport, and discussed its approach to total system performance analysis, including the basis for its defense-in-depth analysis. A trend in assessment of Yucca Mountain natural hazards and site characteristics by the diverse presenters appears to be toward risk-based assessments and away from subsystem performance measures. This is the direction taken in the 10 CFR Part 63 proposed rule.
Several press articles were published that highlighted the Szymanski hypothesis which states that future invasion of hot water into a repository is likely. The staff currently considers the potential for future hydrothermal activity as unlikely. Evidence was presented at the Meeting from fluid inclusions and calcite crystallography that suggests at least one hydrothermal episode of unknown age occurred. DOE is sponsoring a joint geochemical study by scientists with diverse viewpoints on the upwelling hot water hypothesis to systematically collect and analyze calcites from repository depths. The staff are observers at the joint-calcite-study-group meetings and are awaiting results of the age determinations of the fluid inclusions.
On June 2-3, 1999, staff members from the Division of Waste Management and Region IV participated in the annual public workshop jointly sponsored by the National Mining Association and the NRC. The workshop was held in Denver, Colorado, with over 90 attendees representing members of the uranium industry, the Nuclear Energy Institute, DOE, NRC, Agreement States, and Non-Agreement States where NRC licensed uranium recovery activities occur. This workshop was the sixth consecutive public forum for presentation and discussion of regulatory issues affecting the uranium recovery industry. Staff presentations focused on the three uranium recovery commission papers currently before the Commission and recently released to the public, the recently published Uranium Recovery Decommissioning Rule, NRC's proposed Fee Rule, and NRC's efforts in streamlining the licensing review and inspection programs. Industry representatives presented their views on the above mentioned subjects and also their companies' experiences with licensing activities and the NRC Hearing process.
On June 3-4, 1999, DOE and NRC (supported by the Center for Nuclear Waste Regulatory Analyses and the Computerized Risk Assessment and Data Analysis Laboratory) conducted a technical exchange to discuss DOE's Geologic Framework Model 3.1 (GFM 3.1) for Yucca Mountain. GFM 3.1 is a revised version of GFM 3.0 which the staff reviewed and accepted last year. The staff is reviewing this model as a step in achieving a common understanding of the results of DOE's Integrated Site Geologic Model.
During the technical exchange, several questions from the staff and its contractors were addressed by DOE dealing with the details of the model construction techniques and the rationales for developing the new GFM 3.1. Another issue discussed was the qualification of all the data used to construct the GFM 3.1 model. The DOE intends to have all data qualified and issue a report on the model's completeness in the first Quarter of FY 2000. The staff and DOE concluded that the objectives of the technical exchange were met. Further, based on an NRC internal evaluation of GFM 3.1 and understanding of the main differences between GFM 3.0 and GFM 3.1, the staff considers GFM 3.1 to be adequate for representing the stratigraphy, faults, fault blocks, geologic cross sections, and topography of Yucca Mountain.
Incident Response Operations
[ Prev | Next ]
On May 25-27, 1999, members of Region I and IRO participated as players in the Indian Point Post-Plume Phase exercise conducted in Albany, NY. IRO coordinated Federal participation by the NRC, FEMA, DOE, USDA, and EPA. This effort is part of an NRC focus on supporting post-plume phase exercises with enhanced Federal participation. In preparation for this exercise, State Outreach Training was conducted for the State of New York in January of this year.
On June 8, 1999, a member of Region IV and IRO conducted a State Outreach Training session in Glen Rose, TX, in preparation for the Post-Plume Phase exercise to be conducted with Comanche Peak and the State of Texas on July 21, 1999. The Outreach session included presentations by IRO on Federal response and compensation issues, by DOE on the resources of the Federal Radiological Monitoring and Assessment Center, by EPA on the Protective Action Guides, by USDA on the FDA Protective Action Guides, and by the State of Texas. The Outreach training was followed by a planning session with IRO assisting in the development of the Tabletop exercise that will focus on the post-plume phase.
1. PNO-I-99-027, North Country Hospital, MEDICAL MISADMINISTRATION DURING DIAGNOSTIC USE OF IODINE-131
2. PNO-II-99-022, Western Soil, Inc., STOLEN NUCLEAR GAUGE
3. PNO-II-99-023, Florida Power & Light Co., (Saint Lucie 2), ST. LUCIE UNIT 2 SHUTDOWN IN EXCESS OF 72 HOURS
4. PNO-III-99-030, United Hospital, RECEIPT OF PACKAGE WITH RADIATION LEVELS EXCEEDING DOT LIMITS
5. PNO-III-99-030, Consumer Power Co., (Palisades 1), MINOR HYDROGEN BURNS DURING CASK WELDING ACTIVITIES
Office of Administration
[ Prev | Next ]
A direct final rule that amends the regulations governing participation in proceedings conducted under the NRC's rules of practice was published in the Federal Register June 1, 1999 (64 FR 29212). The action clarifies that federally-recognized Indian tribal governments are entitled to participate in these proceedings on the same basis as other governmental units. The direct final rule becomes effective August 2, 1999.
The companion proposed rule to this direct final rule was published in the Federal Register on June 1, 1999 (64 FR 29246). The comment period closes July 1, 1999.
A final rule making several minor amendments to the Commission's informal Hearing procedures for adjudications in materials and operator licensing proceedings was published in the Federal Register on June 1, 1999 (64 FR 29213). The final rule corrects a cross-referencing error in the provisions concerning the method of filing documents and changes the method of service of proceedings on the NRC staff. The final rule became effective June 1, 1999.
On Thursday, June 10, 1999 (64 FR 31447) the final rule entitled, "Revision of Fee Schedules; 100% Fee Recovery, FY 1999," was published. The rule revises Parts 170 and 171 to ensure NRC compliance with the Omnibus Budget and Reconciliation Act of 1990, which mandates that the NRC recover approximately 100 percent of its budget authority in Fiscal Year 1999, less amounts appropriated from the Nuclear Waste Fund and the General Fund. The amount to be recovered for FY 1999 is approximately $449.6 million. The final rule becomes effective August 9, 1999.
The 14th floor of the Restack project is completed and employee moves were completed on Tuesday, June 8, 1999. The next Restack floor is the 15th and work began on June 9, 1999. Completion is expected mid-August.
On Thursday, June 10, 1999, a representative from the Division of Facilities and Security attended a PEPCO briefing on PEPCO's Y2K status. While some systems have been tested and certified ready, all system tests are to be completed by the end of June. PEPCO feels confident that they will be able to provide power without interruptions at the New Year.
Chief Information Officer
[ Prev | Next ]
Referral by Department of Commerce. (FOIA/PA 99-250)
Advanced Medical Services/Picker International, site at 1020 London Rd., Cleveland, OH. (FOIA/PA 99-251)
Depleted uranium, staff reports regarding bullets or projectiles used by U.S. Navy in Viegues, Puerto Rico. (FOIA/PA 99-252)
IMPAC listing. (FOIA/PA 99-253)
NUREG-1092, reference on page II-33, 4/20/83 memo from L. Rouse to J. Norberg. (FOIA/PA 99-254)
Nuclear Power Plant Life Extension, OGC analysis of legal issues, 1/13/89 memo. (FOIA/PA 99-255)
Office of Human Resources
[ Prev | Next ]
|BERG, Lawrence||NUCLEAR PROCESS ENGINEER||NMSS|
|HAWKINS, Cheryl||SUMMER TECHNICAL INTERN||ACRS/
|HENRY, Alvin||SUMMER TECHNICAL INTERN||NMSS|
|TORRES-COLON, Robert||HEALTH PHYSICIST||NMSS|
|WOLFF, Evan||SUMMER TECHNICAL INTERN||NMSS|
|ZEMBRUSKI, Elizabeth||SUMMER LEGAL INTERN||ASLBP|
Office of Public Affairs
[ Prev | Next ]
There was press interest at headquarters in the new fee rule.
Region I has fielded numerous questions about NRC approval of the latest repair for core shroud cracks at Nine Mile Point.
Region II is working with a Charlotte Observer reporter on a story about emergency planning at Duke Power's plants.
Region IV has provided information to a Sacramento Bee reporter for a story on low-level waste in California.
|99-117||Nuclear Regulatory Commission Honors Employees|
|99-118||NRC Amends Licensing, Inspection and Annual Fees|
|99-119||NRC Invites Public to Submit Nominations for the Advisory Committee on Reactor Safeguards (clarification and deadline change)|
|99-120||NRC Approves Transfer of License for Colorado Spent Fuel Storage Facility to DOE|
|98-121||NRC Considers Amending License for Pennsylvania Facility; Offers Opportunity for Hearing|
|III-99-37||NRC Staff to Meet With Commonwealth Edison Officials to Discuss Performance at Dresden Nuclear Power Plant|
|IV-99-24||NRC to Hold Public Meeting to Describe New NRC Inspection Program for Fort Calhoun|
Office of International Programs
[ Prev | Next ]
Mrs. Michele Rivasi, French Parliamentarian and member of the Parliamentary Office for the Evaluation of Scientific and Technical Options, led a three-member delegation that visited NRC on June 7. Mrs. Rivasi is preparing a report for the Parliamentary Office on the impact of radioactive waste on public health and the environment and is visiting U.S. government agencies to obtain information on this Subject. The delegation was briefed by members of the Division of Waste Management staff and separately met with Commissioner Dicus who answered questions relating to radiation protection practice in the U.S.
The Agreement for Cooperation Concerning Peaceful Uses of Nuclear Energy between the U.S. and Ukraine came into force on May 28, 1999.
Office of the Secretary
[ Prev | Next ]
|1. SECY-99-147||6/2/99||Proposed Rulemaking - Domestic Licensing of Special Nuclear Material|
||Staff Review of U.S. Department of Energy Viability Assessment for a High-Level Radioactive Waste Repository at Yucca Mountain, Nevada|
|Commission Voting Record on 99-074||5/10/99||(same)|
|3. SRM on SECY-98-300||6/8/99||Options for Risk-Informed Revisions to 10 CFR Part 50 - "Domestic Licensing of Production and Utilization Facilities"|
|Commission Voting Record on 98-300||6/8/99||(same)|
|4. SECY-99-135||5/18/99||Interim Enforcement Policy Regarding Enforcement Discretion for Nuclear Power Plants During the Year 2000 Transition|
|5. SECY-99-148||6/3/99||Credit for Existing Programs for License Renewal|
|6. SECY-99-123||4/28/99||Oklahoma Agreement State Negotiations: State Proposal to Limit Scope of Agreement|
|SRM on 99-123||6/10/99||(same)|
|Commission Voting Record on 99-123||6/10/99||(same)|
|Negative Consent Documents|
|1. SECY-99-140||5/20/99||Recommendation for Reactor Fire Protection Inspections (WITS Item 199700021)|
|2. SECY-99-134||5/18/99||Agency Contingency Plans for the Year 2000 Computer Problem in the Nuclear Industry|
|1. SECY-99-143||5/26/99||Revisions to Generic Communication Programs|
|2. SECY-99-142||5/26/99||Paducah Seismic Upgrades Certificate Amendment Request|
|1. M990504B||6/9/99||Staff Requirements - Meeting on Planning, Budgeting and Performance Management Process (PBPM) and Institutionalizing Change, Tuesday, May 4, 1999|
1. Letter to Congress, dated June 5, 1999, provides the final revisions to the NRC fee regulations in 10 CFR 170 and 171.
1. International Uranium (USA) Corporation, Docket No. 40-8681-MLA-7; Designation of Presiding Officer (Peter B. Bloch).
2. Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Planning and Procedures; Notice of Meeting on July 13, 1999.
3. Advisory Committee on Reactor Safeguards; Meeting of the Subcommittee on Plant License Renewal; Revised.
[ Prev | Next ]
On Wednesday June 9, 1999, the NRC held a public Meeting to discuss the results of the Limerick Generating Station Plant Performance Review. The principal PECO Nuclear representatives included: the President, PECO Nuclear; Sr. Vice President, Nuclear Operations; Vice President, Limerick Generating Station; and Plant Manager, Limerick Generating Station. The principal NRC representatives included: the Regional Administrator, Deputy Director, Division of Reactor Projects, and the Branch Chief for Limerick Generating Station. PECO responded positively to the NRC presentation and discussed their actions taken or planned to continue to improve performance at Limerick. There were only two media representatives and No other members of the public in attendance.
On June 8, 1999, Region I Division of Nuclear Materials Safety staff met with licensee representatives in order to discuss license renewal and site remediation issues at the Safety Light Corporation facility in Bloomsburg, Pennsylvania. The discussion centered on issues important to renewal of the license, including the status of remediation of the underground silos, plans for other decommissioning activities, status of the funds from a previous insurance settlement, and the status of on-going insurance settlement negotiations.
A Pre-decisional Enforcement Conference was conducted with the former Radiation Safety Officer of Special Testing Laboratories, Inc. on June 10, 1999, to discuss an apparent violation of 10 CFR 30.10, "Deliberate Misconduct." The principle areas of concern were apparent deliberate violations by the individual of NRC requirements which include: (1) directing of untrained individuals to use gauges; (2) failing to provide individuals with the necessary dosimetry while they were using the gauges; (3) providing false information to the NRC; and (4) using gauges contrary to an Order Suspending License issued to Testwell Craig Labs of Connecticut (predecessor company to Special Testing Laboratories, Inc.).
[ Prev | Next ]
On June 11, 1999, representatives from the Tennessee Valley Authority were in the Regional Office to attend a closed management Meeting to discuss the Employee Concerns Program with respect to recent initiatives, trends and concern resolution methodologies.
[ Prev | Next ]
Members of the Region III and Office of Nuclear Reactor Regulation staff met June 8, 1999, with officials of Commonwealth Edison Company to discuss the most recent plant performance review for the Quad Cities Nuclear Power Station. The Meeting, which was open to public observation, was at the plant site.
Members of the Region III staff met June 10, 1999, in the regional office with representatives of U. S. Enrichment Corporation for a predecisional enforcement conference on an apparent violation of NRC requirements in the company's response to a December 9, 1998, fire at the Portsmouth Gaseous Diffusion Plant.
Office of Congressional Affairs
[ Prev | Next ]
|Congressional Hearing Schedule, No. 23|
|TBA||TBA||S. 1090, Superfund Reauthorization||Senators
Environment and Public Works
|TBA||TBA||Security at DOE Laboratories||Reps.
Energy & Power
||S. 608, Nuclear Waste Policy Act||Senators
Energy and Natural Resources
|10:00||TBA||H.R. 1828, Electricity Competition||Reps.
Energy & Power
|10:00||TBA||Price-Anderson, Nuclear Worker Safety at DOE Facilities||Reps.
Oversight & Investigations
|10:00||Former Security Chief of DOE||Security Lapses at DOE Facilities||Reps.