|Weekly Information Report|
For the Week Ending October 8, 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. Tschiltz, 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: firstname.lastname@example.org.
Office of Nuclear Reactor Regulation
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A public Meeting was held on September 28, 1999, to present the current Draft Regulatory Guide 1053, which describes pressure vessel fluence estimate methodologies. The Meeting was organized and run by the Office of Nuclear Regulatory Research, Materials Engineering Branch (E. Hackett, C. Fairbanks, and W. Jones). The technical presentation was by J. Carew of Brookhaven National Laboratory. Lambros Lois of the Reactor Systems Branch in the Division of Systems Safety and Analysis presented the regulatory perspective. The Meeting was well attended with participants from the Nuclear Energy Institute, General Electric San Jose, Framatome, Westinghouse Energy Systems, Bechtel, ABB Atom, and several utilities.
This was the third public Meeting and presented the incorporation of public comments from the second public Meeting (1996) and was open to additional public comments. The most notable changes to the guide were the incorporation of the Monte Carlo method and the presentation of boiling-water reactor and pressurized-water reactor benchmark problems. Several comments from the participants were discussed; however, the comment period will be open for 60 days as of September 28, 1999. The guide is scheduled for publication by December 2000.
Related to the rulemaking, the staff completed technical reviews for the power uprate and Appendix K exemption request for Comanche Peak Unit 2 based on the use of the Caldon, Inc., LEFM feedwater flow measurement system. The staff is also reviewing a topical report for the ABB Crossflow feedwater flow meter and the associated exemption request for Duane Arnold. These reviews are expected to be completed in the spring of 2000.
GPU Nuclear has discovered that two control rod assemblies (CRA) did not fully insert into their fuel assemblies during post-shutdown refueling outage insertion Time testing. Several other control rods exhibited slower than previous rod drop times. The TMI TS require insertion Time of 1.66 seconds from full out to 75% inserted (25% withdrawn). During the rod drop test, two CRAs did not fully insert, sticking at approximately 28% and 6% withdrawn. The CRA were inserted fully using the control rod drive system. The CRA that inserted to 6% met its TS insertion Time. The CRA that stuck at 28% withdrawn was declared inoperable.
The TMI experience was the first Time that a domestic Framatome B&W core has experienced rod insertion problems unrelated to CRDMs. Detailed refueling testing proved that mechanical contact between the CRA and the fuel assembly resulted in the sticking, not hydraulic binding in the CRDM. The licensee and Framatome will meet with the staff on or near October 21 at NRC headquarters to present the results of their root cause analysis for this problem. NRR and Region I held a conference call with GPUN and Framatome on September 29 to discuss the current causal assessment. The exact cause of the bowed fuel assemblies remains under review, but appears to be also associated with late in life fuel assemblies. GPUN must ensure adequate CRA insertion times, in accordance with the TMI-1 Technical Specifications (TS). Based on the root cause determination, the October 21 Meeting could lead to the need for some mid-cycle CRA testing.
Discussions by the Region with the Crystal River Resident Office indicated that during similar testing conducted on October 1: one CRA appeared to stick at approximately 7% and then slowly fully inserted, this CRA did not meet the insertion Time requirement; one CRA failed to meet the insertion Time but fully inserted; and several other CRAs met the insertion Time requirement but indicated increased times from the last performance.
On October 1, 1999, the staff issued a scheduler exemption to 10 CFR 54.17(c) for Catawba Units 1 and 2, and McGuire Unit 2. The Subject regulation specifies that "an application for a renewed license may not be submitted to the Commission earlier than 20 years before the expiration of the operating license currently in effect." The scheduler exemption permits the licensee to apply for renewal of the operating licenses of the four Catawba and McGuire units as early as June 13, 2001, when the McGuire Unit 1 operating license will have reached 20 years of age. By this Date, the Catawba Units 1 and 2 licenses will be 17 and 15 years old, respectively, and McGuire Unit 2 will have 18 years of operation. In its application for exemption, the licensee stated that it does not seek an exemption from the 40-year limit imposed on the operating licenses for power reactor facilities licensed under Section 103 of the Atomic Energy Act. This means that the operating lives of the 3 units could be shortened by 1-3 years from the theoretical maximum of 60, depending on when the renewed licenses are issued.
On September 30, 1999, the staff issued an amendment to Comanche Peak Steam Electric Station (CPSES), Unit 2, Technical Specifications (TSs) and Facility Operating License that increased the rated thermal power by 1 percent to 3445 MW(th). CPSES requested this change due to its use of an upgraded feedwater flow measuring system - the leading edge flow meter (LEFM) made by Caldon, Inc. This system allows for a more accurate flow measurement and a corresponding increase in the accuracy of reactor thermal power measurements. The power uprate was made possible by an approved exemption (May 6, 1999) from Appendix K requirements for emergency core cooling system (ECCS) evaluation models. The staff completed its review and approval of the amendment in approximately 9 months.
The Inspection Program Branch and Region II staff attended the Region II Licensing Managers' Meeting in Charlotte, NC, on September 29, 1999. At this Meeting, the NRC staff discussed the status of the revised reactor oversight process pilot program implementation and answered questions from participants.
On October 1, 1999, the Operator Licensing and Human Performance Section (IOHS) went public with a new web site on the NRC's external server; the URL for the site is http://www.nrc.gov/NRC/REACT OR/OL/OLhome.html . The site provides background information on the operator licensing program, links to numerous related documents including regulations, NUREGs, SECY papers, and generic communications, and an avenue for stakeholders to submit comments and questions. IOHS is currently reviewing a large number of questions that were submitted to the Regional Offices during a series of operator licensing workshops conducted over the summer, and it plans to post the answers on the web site during a future update. IOHS believes that the web site will improve communications with facility licensees who are now preparing the majority of the initial licensing examinations.
On October 4, 1999, a final rule was published in the Federal Register (64 FR 53582). The rule revises sections 50.59, 72.48 and related sections that specify the conditions under which reactor licensees and spent fuel storage facility licensees or cask certificate holders, may make changes to their facilities without prior NRC approval.
The effective Date of the final rule for Part 50 licensees is 90 days following approval of regulatory guidance. The NRC staff plans to forward to the Commission a final regulatory guide that endorses an industry guidance document by May 30, 2000. The Nuclear Energy Institute submitted on September 17, 1999, draft Revision 1 to NEI 96-07 for NRC review and comment. A Meeting was held with NEI on October 6, 1999, to discuss the proposed guidance.
On September 30, 1999, the staff issued a license amendment which replaces the Fermi technical specifications in their entirety with new technical specifications based on the improved Standard Technical Specifications (STS). This is the 50th unit that has been approved to convert to the improved STS. The licensee will implement these revised technical specifications within 90 days. Issuance of this amendment completes an item in the Commission Tasking Memorandum.
The Commission has published a final rule amending 10 CFR Part 20 Subpart H and Appendix A. The amendments reaffirm the Commission's intent to apply ALARA principles to the sum of external and internal doses and to reduce the use of respirators when their use may cause more risk. The use of process or engineering controls, decontamination of work areas, access control, and other procedures are stressed. The automatic use of respiratory protection devices, which tends to increase worker external dose and stress, would be reduced correspondingly.
The final rule also recognizes new respiratory protection devices that have been proven effective, adopts new Assigned Protection Factors (APFs) and other ANSI recommendations and revises requirements for respiratory protection procedures, such as fit testing, to reflect current industry good practice and to conform to new regulations publishing by OSHA. The changes are believed by the staff to be a worker safety enhancement that may save NRC licensees an estimated 1.5 million dollars per year. The new rule is less prescriptive with No reduction in worker health or safety.
The final rule becomes effective 120 days after its publication.
The U.S. Nuclear Regulatory Commission issued this information notice to alert addressees to a recall of the Star brand, dry-type, fire protection sprinkler heads manufactured by the Mealane Corporation of Philadelphia, Pennsylvania.
The intent of this document was to inform addressees of actions taken by the staff to improve the agency's generic communications program and its implementation, specifically: (1) more clearly define each generic communications product and the distinctions between the several types of generic communications; (2) require the staff to obtain early senior NRC management acknowledgment of emergent generic issues and require the staff to initiate early interaction with the nuclear power industry when evaluating an issue; (3) implement a tiered approach to generic information requests; (4) develop simplified value-impact assessments when the compliance exception to the backfit rule (10 CFR 50.109) is invoked, in order to present senior management with additional information for making better informed decisions; and (5) use the Headquarters Daily Report to disseminate potentially generic information to licensees and to the public.
Office of Nuclear Material Safety and Safeguards
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On September 29, 1999, staff from the Division of Waste Management conducted a short Meeting and site visit at the Molycorp Washington, Pennsylvania, metal alloy processing facility to familiarize the staff with the buildings, facilities, and structures which will be the focus of licensee decommissioning activities described in the site decommissioning plan. Attendance at the Meeting included Nuclear Regulatory Commission (NRC) Headquarters staff, an inspector from Region I, representatives from the state of Pennsylvania, attorneys representing Canton Township, attorneys representing Molycorp, and news reporters from a local television station in Pittsburgh (KDKA). The NRC staff discussed the licensee's designation of "affected" and "unaffected" areas (as identified by NUREG/CR 5849) for the buildings remaining on the site, performed a general area survey, and took smears of selected building floors and equipment that remain in the areas the licensee has labeled as unaffected. The NRC project manager and an attorney representing Canton Township were interviewed by an attending news reporter. A follow-on news broadcast reported that the Township representative was pleased to see NRC with a significant presence at the site and that NRC will monitor Molycorp closely during the decommissioning process.
On September 30, 1999, staff of the Division of Waste Management (DWM) met with staff of BWX Technologies (BWXT) at the Nuclear Regulatory Commission (NRC) Headquarters. In addition to DWM staff, staff from NRC Region I, the Pennsylvania Department of Environmental Protection, and members of the Parks Township Board of Town Supervisors participated in the Meeting (by phone). The purpose of this Meeting was to allow the BWXT staff to provide DWM, and others, with an overview of the status of the decommissioning of the Parks Township, Pennsylvania, facility, to discuss the Schedule for completing the decommissioning and to discuss issues that could impact on the decommissioning Schedule. BWXT has been decommissioning the Parks Township facility since 1991 and is currently completing the final radiological surveys of above ground structures. BWXT expects to begin submitting evaluations of soil at the site in January 2000 and to complete the decommissioning, including one year of post remediation groundwater monitoring, in early 2002. Since 1998, DWM and BWXT have met on a quarterly basis to identify and discuss issues that could impact on the decommissioning.
On September 30, 1999, the Division of Waste Management (DWM) sponsored three training workshops by Dr. Vincent Covello on interaction with the public and risk communication for high-level waste (HLW) regulators. Dr. Covello, who spoke on general risk communication issues the previous day, agreed to provide a second day of sessions tailored to the communications challenges facing the Nuclear Regulatory Commission's (NRC's) HLW regulatory program. The need for improved risk communication by NRC staff was identified repeatedly by participants at public meetings held earlier this year on the proposed 10 CFR Part 63 regulations.
Following a special 90-minute session for division managers, Dr. Covello spent two hours addressing, "How to Talk to the Public About NRC's Program of HLW Regulation." The afternoon was devoted to a three-hour workshop, "Improving Public Communication in the HLW Program," aimed expressly at HLW staff who will be conducting public meetings in the coming months on topics such as NRC's proposed regulations in Part 63, defense-in-depth and multiple barriers provisions of Part 63, and development of NRC staff's Yucca Mountain Review Plan.
In all three sessions, Dr. Covello expanded upon the communications principles he had introduced in his general seminars the day before, adding anecdotes and discussion on topics such as the importance of and techniques for "message mapping," how to correct misinformation, and how the HLW staff should convey its licensing role and responsibilities for Yucca Mountain.
On September 30, 1999, staff from the Division of Waste Management (DWM) observed two Department of Energy (DOE) public meetings on DOE's draft Environmental Impact Statement (DEIS) for a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nye County, Nevada. DOE held the public meetings in Pahrump, Nevada, located about 80 kilometers (50 miles) southeast of Yucca Mountain. There were approximately 30 speakers, including representatives from the Office of the Governor for the state of Nevada, Nye County, Nevada; and non-governmental organizations. Concerns were expressed over a range of issues, including DOE's population estimates, the proposed transportation route near Pahrump, and the adequacy of DOE's involvement of citizens of Nye County, Nevada, in the DEIS process. Additional DOE public meetings on the DEIS are scheduled for 14 additional locations (seven within Nevada). Staff plans to observe as many of the public meetings in Nevada as possible, without impacting staff's review of the DEIS.
On September 30, 1999, at 10:35 a.m., a nuclear criticality accident took Place at the JCO Company's Tokaimura uranium process plant located northeast of Tokyo, Japan. Plant personnel were not able to return the system to a safe subcritical condition until 9:20 a.m. on October 1, 1999. Three plant employees were exposed to extremely high levels of radiation and about 55 other people, including emergency responders and 10 members of the public, received significant exposures above established limits. An investigation of the accident by the Japanese government is on-going at this Time. The Nuclear Regulatory Commission staff is monitoring the post-accident activities in Japan closely to gain lessons-learned from the accident.
On October 1, 1999, the Division of Industrial and Medical Nuclear Safety (IMNS) sponsored a facilitated public Meeting at the Nuclear Regulatory Commission (NRC) Headquarters on the proposed rule for regulation of general licensees. The proposed rule was described and implementation issues were addressed by a panel of 12 vendor participants and two IMNS staff. Approximately 25 non-NRC people attended. Six additional vendor representatives participated in the audience, several of whom provided comments and questions. Representatives from the states of Illinois and Washington participated by phone. Issues discussed included the following Subject areas: Agreement State compatibility levels; disclosure before purchasing and transfer; identification of responsible individuals and locations of use; tax payer identification number collection and use for tracking; voluntary early implementation by Agreement State vendor licensees; source and label change compliance issues; encouraging authorized disposal via civil penalties; source serial numbers; and a national database.
Incident Response Operations
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1. PNO-II-99-041, West Virginia University, THEFT OF TRITIUM-ILLUMINATED EXIT SIGNS
2. PNO-II-99-042, Florida Power & Light Co. (Saint Lucie 1 2), REACTOR OPERATORS INITIATE ACTIONS TO RELINQUISH NRC LICENSES
Office of Administration
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The current Restack floor (13th) is on Schedule for employees to move onto the floor as scheduled, from October 25, 1999 to October 28, 1999. Installation of the enclosed and open workstations began the week of October 4, 1999. The 13th floor will be occupied by employees from the 6th floor, which will be the next floor to be Restacked.
On September 28, 1999, the Division of Contracts and Property Management awarded contract NRC-28-99-207 to Bell Atlantic Network Services, Inc., for exchange carrier services, including emergency and back up service, to the NRC Region I location, as well as support for voice, data, and video connectivity, and interface with FTS2000/2001. This fixed-price requirements contract has a ceiling of $174,860. The period of performance is October 1, 1999 through September 30, 2004. To streamline the procurement process, proposal preparation Time was reduced, only one SEP panel member was used, information was communicated electronically with the SEP and contractors, and simplified evaluation criteria were used.
On September 30, 1999, the Division of Contracts and Property Management awarded contract NRC-04-99-050 to SAIC, entitled, "Support for Collection and Analysis of Occupational Radiation Exposure Data" in the amount of $772,802. The period of performance is September 30, 1999, to September 29, 2001, with three one-year options. The contractor will provide support to NRC for collection and analysis of occupational radiation exposure data for evaluating licensee performance and for conducting health effects research. The data will be further utilized by the NRC to identify high dose facilities and to identify dose trends. The following streamlining measures were used: limit competition to known sources, simplified evaluation criteria, and award without discussions.
On September 24, 1999, the Administrator of the Small Business Administration executed a Memorandum of Understanding with the NRC which will expedite the award of 8(a) actions. 8(a) is the section of the Small Business Act which provides a program for small and socially disadvantaged business to be awarded government contracts on a non-competitive basis. With this MOU, NRC contracting officers can directly execute 8(a) procurement actions with the firms without a co-signature from SBA. In addition, the contracting officers need only wait for 5 days for a response to an offering letter to SBA. These provisions can save up to twenty days of procurement acquisition lead Time for 8(a) contract awards.
On October 7, 1999, the Division of Contracts and Property Management conducted its Acquisition for Project Managers module, "Organizational Conflict of Interest" (COI). The training presentation included a discussion of what constitutes a conflict of interest and how the Agency regulations treat COI. Lectures also included the process for identifying and resolving COI situations for both contract awards to the private sector and DOE laboratory agreements. Class participants worked in groups to analyze situations to determine if COI existed and, if so, how to resolve the COI.
A proposed rule that would allow holders of nuclear power plant operating licenses to reduce the assumed power level used in evaluations of emergency core cooling system performance was published in the Federal Register on October 1, 1999 (64 FR 53270). The proposed rule would allow interested licensees to pursue small, but cost-beneficial, power uprates without compromising the safety margin of the facility. The comment period on this action closes December 15, 1999.
A final rule that amends the regulations concerning the authority for licensees of production or utilization facilities to make changes to the facility or procedures, or to conduct tests or experiments, without prior NRC approval was published in the Federal Register on October 4, 1999 (64 FR 53582). The final rule clarifies the specific types of changes, tests, and experiments that require evaluation and revises the criteria that determine when NRC approval is needed. Portions of the action become effective on February 1, 2000, April 5, 2000, and 90 days after the issuance of appropriate regulatory guidance.
A final rule that amends the regulations governing the use of respiratory protection and other controls to restrict internal exposure to radioactive material was published in the Federal Register on October 7, 1999 (64 FR 54543). The final rule makes the regulations more consistent with the philosophy of controlling the sum of internal and external radiation exposure, reflects current guidance on radiation protection, and makes the requirements less prescriptive without reducing worker protection. The final rule becomes effective February 4, 2000.
Chief Information Officer
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Contract, Spotless Janitorial Services, RS-ADM-00-005. (FOIA/PA 2000-0001)
Gutierriz-Palmenberg, Inc., letters cited under item 24 of license #27-29103-01. (FOIA/PA 2000-0002)
Chief Financial Officer
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One of the provisions of the FY 1999 Final Fee Rule (effective August 9, 1999) was to bill fees for all of Project Managers productive Time. It took longer than anticipated to understand the responsibilities of current project managers so that the automated billing system could be modified. The necessary changes to the billing system have now been made, but the fourth quarter FY 1999 billing cycle will not include approximately six weeks of full cost billing of Program Managers. Part 170 full cost billing for Project Managers was implemented effective September 26, 1999, and the costs will be included in the Part 170 invoices issued for the first quarter of FY 2000.
Office of Human Resources
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|BIXLER, Cynthia||SECRETARY||R I|
|DYKE, Jimmy||RESIDENT INSPECTOR
|WILSON, George||REACTOR ENGINEER||RIII|
|MEADOWS, Thomas||REACTOR ENGINEER (EXAMINER)||RIV|
Office of Public Affairs
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The staff fielded calls on the reactor leak in South Korea, and continued to receive inquiries on the accident in Japan.
National Geographic is preparing to publish a story on nuclear waste.
|99-211||NRC Considers Changes to Regulations for Reactor Safety Analysis Requirements|
|99-212||27th Annual Water Reactor Safety Information Meeting to be Held October 25-27 in Bethesda, MD|
|99-213||Note to Editors: Advisory Committee on the Medical Uses of Isotopes Meeting|
|99-214||NRC Will Study Japanese Accident for Possible Safety Enhancements|
|99-215||Note to Editors: ACRS Meeting November 3|
|I-99-86||NRC to Hold October Workshop, Meeting in Connecticut on Reactor Decommissioning|
Office of International Programs
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Janice Dunn Lee, Director, Office of International Programs is part of the U.S. delegation participating in the October 12-13, 1999 Nuclear Energy Agency (NEA) Steering Committee Meeting in Paris, France. The Steering Committee will be addressing issues such as Poland's application for membership, and a proposed Memorandum of Understanding between the NEA and the International Atomic Energy Agency. The Committee will also convene in special session to hold a policy debate on "Nuclear Safety in Central and Eastern European Countries and the Newly Independent States (of the Former Soviet Union): What are the Implications for Future NEA Strategies?"
On Wednesday, October 13, local representatives from the Japan Electric Power Information Center (JEPIC), at the request of the Japan Ministry of International Trade and Industry (MITI), will tour the Operations Center for an overview presentation. They have also asked to discuss NRC's "Whistleblower" program.
Office of the Secretary
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|1. COMSECY-99-029||8/19/99||Continued State Presence at Permanently Shut Down Nuclear Power Facilities Undergoing Decommissioning|
|SRM on 99-029||9/9/99||(same)|
|Chmn. Dicus comments on 99-029||8/30/99||(same)|
|Comm. Diaz comments on 99-029||9/1/99||(same)|
|Comm. McGaffigan comments on 99-029||9/1/99||(same)|
|Comm. Merrifield comments on 99-029||8/30/99||(same)|
|2. SECY-99-219||8/30/99||Proposed Revision to the Enforcement Policy to Address the Process for Assessing the Significance of Violations|
|SRM on 99-219||10/7/99||(same)|
|Comm. Voting Record on 99-219||10/7/99||(same)|
|Negative Consent Documents|
|1. SECY-99-225||9/8/99||Rulemaking Plan for Changes to 10 CFR Part 55 to Reduce Unnecessary Regulatory Burden Associated with the Use of Simulation Facilities in Operator Li censing|
|SRM on 99-225||10/5/99||(same)|
|Comm. McGaffigan comments on 99-225||9/28/99||(same)|
1. Letter dated 8/27/99 to Chairman Greta Joy Dicus from Jack L. Brock, Jr., GAO, re Information Security: NRC's Computer Intrusion Detection Capabilities.
2. Letter to Ralph E. Beedle, Nuclear Energy Institute, dated September 28, 1999, concerns the development of a program for assessment of the effectiveness of reactor security performance (incoming letter dated August 31, 1999, also released).
3. Letter from Annette Vietti-Cook, SECY, to Fawn Shillinglaw, dated September 21, 1999, concerns final NRC action on Petition for Rulemaking PRM-72-3.
4. Letter to Congress, dated September 20, 1999, concerns the "Federalism" Bills -- S. 1214 and H.R. 2245 .
5. Letter to Congress, dated September 20, 1999, concerns the proposed NRC funding reductions in H.R. 2605.
6. Letter to Congress, dated September 20, 1999, provides the August report on the status of NRC licensing and regulatory duties.
1. 10 CFR Part 2; Rules of Practice for Domestic Licensing Proceedings and Issuance of Orders; Public Meeting on October 26-27, 1999.
2. 10 CFR Part 72; Expand Applicability of Part 72 to Holders of, and Applicants for, Certificates of Compliance; Final Rule.
3. (NUREG-1600, Rev. 1) NRC Enforcement Policy; Enforcement Acton Against Nonlicensees Under 10 CFR Part 72.
4. ACRS Subcommittee Meeting on Planning and Procedures; Notice of Meeting on November 3, 1999.
5. Advisory Committee on Reactor Safeguards; Meeting Notice for November 4-6, 1999.
6. ACRS Meeting of the Subcommittee on Human Factors; Notice of Meeting Change to November 19, 1999.
7. Carolina Power & Light Company (Shearon Harris Nuclear Power Plant); Docket No. 50-400-LA; Notice (Opportunity to Make Oral or Written Limited Appearance Statements).
8. Consumers Power (Big Rock Point); Docket No. 50-155-ML; Notice of Reconstitution (G. Paul Bollwerk, III, Chairman).
9. Washington Public Power Supply System; Docket No. 40-460-OL; Notice of Reconstitution (G. Paul Bollwerk, III, Chairman).
10. Molycorp, Inc.; Docket Nos. 40-8794-MLA and 40-8778-MLA; Notice of Reconstitution (Charles Bechhoefer, Presiding Officer).
11. International Uranium (USA) Corporation; docket No. 40-8681-MLA-5; Notice of Reconstitution (G. Paul Bollwerk, III, Presiding Officer).
12. Cabot Performance Materials; Docket No. 40-9027-MLA; Notice of Reconstitution (Alan S. Rosenthal, Presiding Officer).
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Betsy Ullrich, Sr. Health Physicist, is at the IAEA in Vienna from September 28-October 8 as part of an international team writing a guidance document on the assessment of risk from activities involving radioactive material. Ms. Ullrich's involvement is an extension of her support to NMSS in the comprehensive risk evaluation of materials licensing and inspection.
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On October 7, the Director of the Division of Reactor Projects accompanied Commissioner Merrifield to the Virginia Electric Power Company's North Anna Nuclear Plant. The Commissioner toured the facility and the licensee discussed the license renewal process, use of risk information, and physical security requirements.
On October 6, representatives from Duke Energy Corporation attended a management Meeting in the regional office. The discussions included a review of recent station performance, operator performance and equipment reliability issues. The licensee also presented the status of several additional items of regulatory interest including EOPs, and control room ventilation.
On October 7, the Deputy Regional Administrator and two Industry Chief Nuclear Officers participated, via video conference from the Region II Office, in the Agency Meeting to discuss the pilot oversight process.
Roof Survey and Consultants Co., was issued an Order suspending their license with the exception of a requirement to transfer all material within 30 days as well as other associated tasks. The basis for the action was the licensee's failure to pay their annual fee for 1996. A previous order as well as repeated attempts to contact the licensee were not successful.
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On October 5, 1999, the Regional Administrator and members of the regional staff met in the regional office with representatives of Northern States Power Company to discuss improvement initiatives in the areas of operations and equipment reliability at the Monticello Nuclear Power Station.
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On October 7, 1999, a public Meeting was held at the Dwight D. Eisenhower Learning Center, located at the Wolf Creek Generating Station, to discuss the status of the licensee's radiation protection program. The licensee presented a review of the previous radiological protection program performance and the status of program improvements resulting from concerns identified during the recent incident investigation of a potential overexposure event. The Meeting was attended by representatives of the Wolf Creek Nuclear Station, the NRC Region IV office, and members of the public.
Office of Congressional Affairs
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|Congressional Hearing Schedule, No. 37|
|10:00||TBA||National Nuclear Security Administration||Senators
Energy and Natural Resources
|9:00||GAO, GSA, IRS, NTEU, AFGE||Quality Management by Federal Agencies||Senators
Oversight of Gov't Mgmnt, Restructur- ing, & the District of Columbia
|10:00||Frank Miraglia, DOE, GAO, NERC, UCS||Y2K & Nuclear Power: Will Reactors React Responsibly?||Reps.
Gov't Mgmnt, Info & Technology
|9:30||Carl Paperiello, DOE, others TBA||Paducah GDP||Senators
Energy and Water Development
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