Source: http://www.state.nv.us/nucwaste/news/nrc/nrc990813.htm
Timestamp: 2017-10-17 08:07:15
Document Index: 677320132

Matched Legal Cases: ['art 50', 'art 50', 'art 50', 'art 50', 'art 71', 'art 41', 'art 72', 'art 70', 'art 31', 'art 50', 'art 50', 'art 76', 'art 50']

NRC Weekly Information Report
For the Week Ending August 13, 1999
Public Meeting with Nuclear Energy Institute for Safeguards Performance Assessment
On August 11, 1999, NRR held a public Meeting with NEI to maintain dialogue with stakeholders on the preparation of the exercise rule, guidance, inspection procedure, and related changes to the Safeguards Performance Assessment program.
Operational Safeguards Response Evaluation
NRR conducted an Operational Safeguards Response Evaluation (OSRE) at Susquehanna Nuclear Power Plant from August 2 through 5, 1999. An OSRE evaluates a licensee's ability to respond to an external threat by focusing on (1) the interaction between the licensee's operations and security organizations in establishing priorities for protecting equipment and (2) the defensive strategies used to deny armed intruders access to critical equipment. While on site, the team observed table-top contingency drills, weapons training, and the licensee's force on force exercises. The team also interviewed armed response officers. The OSRE also includes a safety and safeguards review to ensure that security does not adversely impact safe plant operations or plant personnel safety. A representative from the State of Pennsylvania observed. A written report describing the results of the inspection is expected to be issued by the end of September.
Farley Nuclear Plant, Unit 1
The Southern Nuclear Operating Company (SNC) recently submitted a Regulatory Guide (R.G.) 1.174 risk-informed license amendment request to permit Farley Unit 1 to continue cycle 16 operation until the next scheduled refueling outage in February or March 2000. The amendment was submitted because SNC determined that some steam generator tubes may degrade beyond the structural margins required in the plant licensing basis.
As part of its review, the staff performed independent calculations of risk and estimated the likely condition of the Farley steam generator tubes at the end of the current operating cycle. The calculations indicated that the increase in risk from not performing a mid-cycle inspection was low and within the criteria of R.G. 1.174 and that the condition of the steam generators expected at the end of cycle 16 was consistent with the scope of the licensee's inspections completed in the previous refueling outage. On July 30, 1999, the staff informed SNC that it had completed its review and that the amendment request meets the acceptance criteria of R.G. 1.174. The staff plans to issue the license amendment shortly. According to the licensee, approval of the amendment will enable them to cancel their mid-cycle outage saving them approximately $30M. This was the first Time that a licensee used the risk-informed process for an amendment request involving a steam generator tube degradation issue.
Trojan - Reactor Vessel Shipment
On Friday, August 9, 1999, the Trojan reactor vessel (RV) was shipped by barge from the Trojan site. The barge and escorts (including a coast guard vessel) arrived at the Port of Benton on August 8. The RV was then transported over land, using a special transport vehicle with 320 wheels, to the US Ecology disposal facility on the Hanford Reservation. Two NRC staff members were onboard the barge and made the transit to Benton and then to US Ecology. The RV had been filled with low density cellular concrete and had up to 6 inches of steel shielding welded on. It weighed approximately 1000 tons. The package is being prepared to be moved into a trench on August 11 or August 12 for burial.
Public Meeting on Risk-Informed Part 50 - (Correction to Weekly Information Report -- Week Ending August 6 -- Correction Underlined)
The staff held a public Meeting on July 28, 1999, on issues associated with efforts to risk-inform Part 50. Attendees included representatives of the Nuclear Energy Institute (NEI), some licensees, and members of the public. Discussion included how to risk-inform 10 CFR 50.59, the pilot program, selective implementation, the potential impact of a risk-informed Part 50 on license renewal, the status of NEI's efforts to develop a petition for rulemaking to risk-inform Part 50, the contents of NEI's proposed guidance document for determining which structures, systems, and components (SSCs) would be Subject to the requirements of special treatment rules.
Four topics were identified as needing further discussion for the next public Meeting: (1) how will licensees treat SSCs that are removed from the scope of the special treatment rules (i.e., what does it mean to receive 'commercial grade' treatment (industry); (2) what level of qualification will be required for SSCs that are currently non-safety related that become in scope of the special treatment rules as a result of their safety significance (staff); (3) a description of the pilot program (industry); and (4) extent to which licensees can make changes to the qualification of SSCs under 10 CFR 50.59 without obtaining prior NRC approval (industry). The next public Meeting has been scheduled for August 26, 1999.
Status of Trojan Dry Cask Storage Operations
Portland General Electric (PGE) is investigating problems associated with a coating used on the interior of spent fuel storage casks to be used at the Trojan Independent Spent Fuel Storage Installation. The cask vendor, BNFL Fuel Solutions, is assisting in the investigation. The investigation was initiated after the coating did not perform as expected when submerged in the spent fuel pool. Nuclear Regulatory Commission (NRC) inspectors were onsite August 10-11, 1999, to observe the licensee's investigation. PGE has not placed any cask in service. Previously, PGE, in a letter dated July 22, 1999, informed NRC it would not resume loading operations until the coating problems had been resolved.
Meeting Regarding Design of a Transport Package for Low-Enriched Uranium Oxide
On August 9, 1999, the Spent Fuel Project Office staff met with General Electric Company (GE) to discuss the design of a new transportation package for low-enriched uranium oxides. GE subjected prototype packages to the hypothetical accident test sequence in 10 CFR Part 71. Based on the preliminary results, GE incorporated several design changes. GE plans to test the modified design in November 1999 and submit an application for package approval to the Nuclear Regulatory Commission in December 1999.
Meeting with Bureau of Land Management and Bureau of Indian Affairs
On August 9, 1999, staff from the Spent Fuel Project Office met with representatives of the Department of Interior's Bureau of Land Management (BLM) and Bureau of Indian Affairs (BIA). The purpose of the Meeting was to discuss the development of a second request for additional information regarding the environmental impact statement (EIS) being prepared in conjunction with the application from Private Fuel Storage, Limited Liability Corporation, for a license for an away-from-reactor independent spent fuel storage installation (ISFSI). This ISFSI would be located on the reservation of the Skull Valley Band of Goshute Indians. BLM and BIA are cooperating federal agencies in the development of the EIS. The Meeting was to ensure that concerns of all three agencies were included in the request for additional information.
Nuclear Fuel Services KAST Amendment
On August 3, 1999, the Division of Fuel Cycle Safety and Safeguards issued a license amendment to authorize the new Naval fuel manufacturing process at Nuclear Fuel Services (NFS) in Erwin, Tennessee. The licensee introduced enriched uranium into the process on August 11, 1999. Urgent work continues by the Nuclear Regulatory Commission (NRC) to review the NFS proposed automatic fire suppression system and the remaining process areas associated with uranium recovery. The NRC staff is reviewing the amendment that will authorize operation of the remaining uranium recovery areas.
Washington Post Article on Paducah Gaseous Diffusion Plant Worker Exposure to Plutonium
On August 8, 1999, the Washington Post published an article on the use of re-cycled uranium at the Paducah Gaseous Diffusion Plant. The article noted that from the 1950's to the mid-1970's uranium oxides from the recycled fuel from weapons production plants were re-fluorinated and fed into Paducah to be enriched. The recycled fuel had impurities including plutonium and other transuranics. The article raised issues about workers being unknowingly exposed to these transuranics and subsequent health problems. It also identified environmental contamination problems. The activities described in the article occurred while the facility was operating under the Department of Energy (DOE) and its predecessors. On August 9, 1999, Division of Fuel Cycle Safety and Safeguards (FCSS) personnel met with DOE officials at DOE Headquarters to discuss DOE's response to the issues identified in the article. DOE staff and press releases indicated that there would be a full investigation of the issues. FCSS is planning to conduct a special inspection at the Paducah and Portsmouth sites in the context of NRC's current regulatory responsibilities to verify the technical bases used for controlling uranium, transuranic, and technetium exposure.
Department of Energy Material Storage Areas Delaying Seismic Modifications at Paducah
Nuclear criticality safety (NCS) concerns in Department of Energy (DOE) material storage areas have the potential to impact U.S. Enrichment Corporation's (USEC's) ability to complete seismic modifications in Paducah's cascade buildings as currently planned by June 30, 2000. Storage areas under DOE oversight exist in these and other buildings at Paducah and Portsmouth. These storage areas contain legacy material belonging to DOE. At Paducah, USEC needs access to these areas to complete seismic modifications that would increase the seismic capability of the C-331 and C-335 cascade buildings to withstand a design basis earthquake. Recent DOE concerns about ensuring NCS while moving the stored material to allow USEC access could impact USEC's ability to meet a completion Date of June 30, 2000. During the week of August 16, 1999, Division of Fuel Cycle Safety and Safeguards (FCSS) staff will meet with DOE and USEC at Paducah to attempt to resolve these issues.
Workshop with the Department of Energy Regarding Disposition Path(s) for High-Level Waste Contaminated Components
On August 2-4, 1999, staff from the Division of Waste Management attended, as observers, a Department of Energy (DOE) workshop at DOE's office near West Valley, New York, on disposition path(s) for high-level waste (HLW) contaminated components resulting from vitrification. The overall goals of the workshop were to address the concerns of DOE's Office of Eastern Operations in its June 7, 1999, memorandum, "West Valley Demonstration Project White Paper Concerning Encapsulating Glass Contaminated Inconel Melter Hardware in a High-Level Waste Vitrified Canister," and to review the "evaluation" process for incidental waste classification provided in Section II.B(2) of the DOE Order M435.1-1, "Radioactive Waste Management Manual." The workshop focused on developing a DOE decision analysis for determining how to dispose of HLW contaminated equipment. By implementing the incidental waste criteria of DOE M 435.1-1, Section II.B(2), DOE would evaluate how HLW contaminated equipment may be evaluated for low-level waste disposal, transuranic (TRU) waste disposal at the Waste Isolation Pilot Plant (WIPP), TRU mixed waste disposal at WIPP, or for HLW disposal at Yucca Mountain. Another aspect of the Meeting included the generation of different types of HLW contaminated component categories for evaluation by DOE according to the aforementioned decision analysis procedure. Several DOE sites also expressed interest in developing a memorandum of understanding (MOU) between DOE Headquarters and the Nuclear Regulatory Commission (NRC) for the review of incidental waste classifications at the various sites, similar to the current MOU between the DOE Savannah River site and NRC for the review of the HLW tank closure methodology. The staff is not encouraging such efforts and will notify the Commission if any DOE site proposes development of an MOU on the incidental waste topic.
Visit to the Center for Nuclear Waste Regulatory Analyses by Congressman Gonzalez
On August 10, 1999, Congressman Charles Gonzalez from the state of Texas visited the Center for Nuclear Waste Regulatory Analyses (Center). This visit was initiated by conversations between Commissioner Merrifield and Congressman Gonzalez. The Congressman, accompanied by a staff member, participated in a working luncheon with Southwest Research Institute (SwRI) President J. Dan Bates and the nine Vice Presidents of SwRI. Mr. Bates provided an overview of SwRI operations. Staff from the Office of Congressional Affairs and the Division of Waste Management accompanied the Congressman and participated in briefings of the Center's capabilities, and its support to a range of important NRC programs.
August 3, 1999 Meeting Between NRC and EPA Staff Meet to Discuss Coordination of Uranium Recovery Program Changes - (Correction to Weekly Information Report -- Week Ending August 6 -- Correction Underlined)
Staff from the Uranium Recovery and Low Level Waste Branch met with EPA staff from the Office of Radiation and Indoor Air (ORIA) to discuss future coordination of proposed changes to the Uranium Recovery Program. These changes are detailed in three Commission papers (SECY 99-011, 99-012, and 99-013) and include the new Part 41 rulemaking, active regulation of ground water at in situ leach uranium recovery facilities, alternate feed at conventional mills, and the disposal of wastes other than 11e.(2) byproduct material in mill tailings impoundments. These topics were also discussed in the June 17, 1999, Uranium Recovery Commission Meeting. EPA indicated ORIA as well as other EPA offices and regions could be impacted by NRC's potential programmatic changes in all three Commission papers. ORIA would function as a centralized contact point for EPA and NRC coordination. Staff plans to Schedule a future Meeting with EPA to discuss coordinating future activities between the two agencies, after the Commission votes on the recommendations in the SECY papers.
Draft Report on HPSI Reliability
RES has issued a draft report, "High-Pressure Safety Injection System Reliability, 1987-1997," for comment. This study is part of an ongoing evaluation of the reliability of risk-significant systems. Using data obtained from licensee event reports (LERs), the study provides an estimate of the High-Pressure Safety Injection (HPSI) system unreliability for pressurized water reactors. This is the first major evaluation by the NRC of the HPSI reliability using operating experience by the NRC.
Based on 1987-1997 operating experience, there were No failures of the entire HPSI system in 224 unplanned system demands. The frequency of unplanned HPSI demands and the number of reported HPSI failure events have declined over the period 1987 to 1997. The arithmetic average of HPSI system unreliability calculated using the operating experience for 72 pressurized water reactors is approximately 5 x 10-4, about the same as the average of HPSI system unreliability calculated using data extracted from individual examinations (IPEs) performed by the licensees. The unreliability of the individual plants varies by a factor of approximately 50, from 6 x 10-5 to about 3 x 10-3. This variability reflects the diversity found in HPI system designs rather than a difference in performance among plants.
The dominant contributions to HPSI unavailability are common cause failures of pumps failing to start or run, common cause failures of motor-operated valves, and independent failures in the shared suction path from the refueling water storage tank (RWST) to the HPSI pumps (tank, pipe, and valves). For some plants with both high-head and intermediate-head HPSI trains, IPE unreliability estimates are significantly optimistic because of the potential for failures in the RWST suction segment. In IPEs for these plants, the failure probability of the RWST suction segment may not have been properly incorporated.
After incorporating comments received from internal and external reviewers, this report will be published as a NUREG/CR document.
Workshop on Nondestructive Characterization of Embrittlement in Reactor Pressure Vessel Steels
RES/DET organized and participated in a workshop on nondestructive characterization of embrittlement in reactor pressure vessel (RPV) steels that was held in Boulder, CO, during the week of July 19, 1999. The Meeting was hosted by the National Institute of Standards and Technology (NIST), where NRC-sponsored research was conducted on this topic from 1996 through the present. The purpose of the research effort was to evaluate the feasibility of using nondestructive examination (NDE) techniques to assess the level of embrittlement in RPV steels caused by neutron irradiation. The significance of this effort relates to the potential for a more direct and accurate assessment of the level of embrittlement than is possible using the current technical and regulatory framework.
As a result of the NRC-sponsored research at NIST, feasibility was demonstrated for several NDE techniques; however, consistency and practical implementation remain highly problematic. There has also been interest on the part of the industry and international community in development of such techniques.
The workshop was attended by industry, academia, and laboratory researchers and included participants from Japan, Germany, Spain and Belgium. The workshop marked the conclusion of the NRC-sponsored effort at NIST and was used as an instrument to transmit the results of the effort to the industry and international community.
1. PN0-IV-99-032A, Entergy Operations, Inc. (Waterford 3), PLANT STARTUP FOLLOWING COMPLETION OF REPAIRS TO REACTOR COOLANT PUMP SEAL
2. PNO-IV-99-034, State of Texas Licensee, MEDICAL MISADMINISTRATION INVOLVING IODINE-131
3. PNO-IV-99-035, Union Electric Co. (Callaway 1), PLANT SHUTDOWN FOR GREATER THAN 72 HOURS DUE TO HEATER DRAIN LINE BREAK
On August 12, 1999, the Division of Contracts and Property Management conducted "Overview of the Acquisition Process." This training module is a primer for other workshops in the acquisition training program. The work familiarizes participants with the entire NRC acquisition process including FAR applicability, commercial contracts and DOE laboratory interagency agreements.
On August 12, 1999, the Division of Contracts and Property Management staff participated in the interactive Critical Thinking course. This was the first in-house non-procurement content course sponsored specifically for DCPM personnel. Others are being planned as a part of the Federal wide initiative to expand the role of procurement personnel as business managers.
List of Approved Spent Fuel Storage Casks; Revision, NUHOMS 24-P and NUHOMS 52-B (Part 72)
A proposed rule that would amend the list of spent fuel storage cask designs approved by regulation was published in the Federal Register on July 29, 1999 (64 FR 41050). The proposed rule would add an amended version of Certificate of Compliance Number 1004 to reflect a change in ownership of the certificate. The comment period on this action closes October 12, 1999
Domestic Licensing of Special Nuclear Material; Possession of a Critical Mass of Special Nuclear Material (Part 70)
A proposed rule that would amend the regulations governing the domestic licensing of special nuclear material for licensees authorized to possess a critical mass of special nuclear material that are engaged in specified activities was published in the Federal Register on July 30, 1999 (64 FR 41338). The proposed rule would identify appropriate consequence criteria and the level of protection necessary to prevent or mitigate accidents that exceed these criteria; require affected licensees to perform an integrated safety analysis to identify potential accidents at the facility and the items relied on for safety necessary to prevent these accidents or mitigate their consequences; require measures to ensure that items relied on for safety are available and reliable; require the inclusion of safety bases, integrated a summary of the integrated safety assessment, with the license application; and allow licensees to make certain changes to their safety program without prior NRC approval. The comment period for this action closes October 13, 1999.
Policy and Procedure for NRC Enforcement Actions: Interim Enforcement Policy Regarding Enforcement Discretion for Nuclear Power Plants During the Year 2000 Transition
A document amending the NRC Enforcement Policy (NUREG-1600, rev. 1) was published in the Federal Register on July 30, 1999 (64 FR 41474). The amendment adds an interim policy that the NRC will follow to exercise enforcement discretion for noncompliance with license conditions, including technical specifications, because of year 2000 (Y2K) related situations. The action becomes effective August 30, 1999.
Requirements for Those Who Possess Certain Industrial Devices Containing Byproduct Material To Provide Certain Information (Part 31)
A final rule that adds an explicit requirement that general licensees who possess certain measuring, gauging, or controlling devices that contain byproduct material provide the NRC with certain information concerning these devices was published in the Federal Register on August 4, 1999 (64 FR 42269). The NRC intends to request information about devices that present a comparatively higher risk of exposure to the public or property damage. The final rule is intended to help ensure that devices containing byproduct material are properly maintained, transferred, and are not inadvertently discarded. The final rule becomes effective October 4, 1999.
Changes to Quality Assurance Requirements; Responses to Comments (Part 50)
A document responding to comments received on the direct final rule that permits power reactor licensees to make certain changes to their quality assurance programs without obtaining NRC approval before making the changes was published in the Federal Register August 6, 1999 (64 FR 42823). The NRC did not receive any significant adverse comments in response to an identical proposed rule that was published concurrently with the direct final rule in the Federal Register (64 FR 9030 and 9035; February 23 1999). This document responds to the comments received and questions raised in the comments and provides NRC's reasons for determining that the comments are not significant adverse comments. The direct final rule became effective April 26, 1999.
Interim Enforcement Policy for Use During the NRC Power Reactor Oversight Process Pilot Plant Study
A document amending the NRC Enforcement Policy (NUREG-1600, rev. 1) was published in the Federal Register on August 9, 1999 (64 FR 43229). The amendment revises the policy for the treatment of violations of 10 CFR Part 50 and associated license conditions during the pilot plant study of the new NRC power reactor oversight process. The action becomes effective on the implementation Date of the pilot plant study.
Freedom of Information and Privacy Act Requests received during the 5-Day Period of August 6, 1999 through August 12, 1999:
Referral from DOE. (FOIA/PA 99-316)
OI report 1-98-005. (FOIA/PA 99-317)
Platina Refining Laboratories/Handy and Harmon at 4301 South Clinton Ave., South Plainfield, NJ. (FOIA/PA 99-318)
CHESKI, Douglas PROPERTY INVENTORY TECHNICIAN ADM
DROZD, Andre SR REACTOR ENGINEER NRR
EUCHNER, Jennifer LEGAL INTERN OGC
KIRK, Mark SR MATERIALS ENGINEER RES
BREWER, Sarita REACTOR SYSTEMS ENGINEER NRR
CRANE, Randall REACTOR ENGINEER RIII
ECKERT, Lonny RADIATION SPECIALIST RI
GRAVEY, Eric SUMMER LEGAL INTERN OGC
GRUBEL, Richard ENGINEERING AIDE (COOP) NMSS
JOSEPH, Alix SUMMER LEGAL INTERN OGC
JOZWIAK, Christopher SUMMER TECHNICAL INTERN OGC
LACKNER, Flora GENERAL SCIENTIST INTERN NMSS
SAENGRAYIB, Charles SUMMER CLERICAL RIII
STEINER, Paul REACTOR ENGINEER RII
ZEMBRUSKI, Elizabeth SUMMER LEGAL INTERN NMSS
There was a large volume of calls in HQ and the Regions regarding press coverage of the Paducah uranium enrichment facilities and alleged plutonium contamination.
There was high interest in the Public Citizen report regarding design documentation deficiencies at nuclear power plants.
Mal Knapp was interviewed by ABC News regarding the NRC's activities regarding the clearance of solid radioactive materials.
99-168 NRC Establishes Policy for Regulatory Actions for Nuclear Power Plants that are not "Y2K Ready"
99-169 Note to Editors: ACRS Meeting
99-170 NRC Grants GPU Nuclear's Request to Reduce Insurance Coverage for Shut-Down Three Mile Island Unit 2
99-171 Bill Borchardt Named Director of the NRC's Office of Enforcement
99-172 NRC Begins Review of DOE's Draft Environmental Statement on Yucca Mountain Waste Repository
99-173 NRC Advisory Committee on Nuclear Waste to Meet in Rockville, Maryland
99-174 Pilot Program Evaluation Panel to Meet in Rockville, Maryland
99-175 NRC Denies Three Petitions From NIRS on Year 2000 Concerns
99-176 NRC Proposes Eliminating Non-Combustibility Requirement for Fire Barrier Penetration Seals at Nuclear Plants
99-177 Note to Editors: Meeting Time Change
99-178 NRC Changes Regulations for Renewing or Amending USEC Certificates
I-99-67 NRC Appoints New Senior Resident Inspector at Salem Nuclear Plant
Y2K Early Warning System (YEWS) Videoconference with IAEA
On August 12, OIP and IRO staff held a videoconference with contacts in the IAEA Division of Radiation and Waste Safety to describe NRC's interest in and support for YEWS and to discuss ways in which the system might be more broadly known and used by the international nuclear community. NRC staff suggested that IAEA could provide a link from its external web site to YEWS to give ready access to its Member States. IAEA asked questions about the security of the system, the reliability of the reported information, legal liability, and matters related to Member State obligations under other reporting regimes. IAEA and the NRC staff agreed to draft information about YEWS for dissemination to IAEA Member States, and the NRC staff also agreed to consider broadening the scope of YEWS, beyond nuclear reactors, to include medical facilities.
1. SECY 99-170 07/01/99 Summary of Decommissioning Fund Status Report
SRM on 99-170 08/10/99 (Same)
Comm. Voting Record on 99-170 08/10/99 (Same)
2. COMSECY-99-020 6/25/99 NRC Response to Request for Support of Federal Tax Relief for Whistleblowers
SRM on 99-020 7/30/99 (same)
Chairman Dicus comments on 99-020 7/9/99 (same)
Comm. Diaz comments on 99-020 7/12/99 (same)
Comm. McGaffigan comments on 99-020 7/12/99 (same)
Comm. Merrifield comments on 99-020 7/13/99 (same)
3. SRM on Secy 99-159 8/12/99 Potential Policy Issues Raised by Non-Owner Operators
Commission Voting Record on Secy 99-159 8/12/99 (Same)
SECY 99-159 6/21/99 (Same)
SECY 99-194 7/29/99 Litigation Report-1999-4
1. M990730 08/09/99 Briefing on Performance Assessment Progress in LLW. HLW, and SDMP, 07/30/99
1. Letter to Shannon Doyle, dated August 6, 1999, concerns support for legislation similar to H.R. 2792, the "Employment Discrimination Award Tax Relief Act" (incoming letter dated April 23, 1999, also released).
2. Letters to Congress, the Departments of Labor and Treasury, and the Office of Management and Budget transmitting a copy of the August 6, 1999, NRC response to Shannon Doyle and the related April 23, 1999, incoming letter.
3. Letter from Representatives John D. Dingell and Ron Klink, dated August 6, 1999, requesting an NRC staff briefing on the Tennessee Department of Environmental Conservation's approval of the release of 6,000 tons of contaminated nickel from a production facility.
4. Letter to Congress, dated July 30, 1999, provides the NRC quarterly report on the nondisclosure of Safeguards Information.
1. 10 CFR Part 76; Certification Renewal and Amendment Processes; Final Rule.
2. Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Planning and Procedures; Notice of Meeting.
3. 10 CFR Part 50; Elimination of the Requirement for Noncombustible Fire Barrier Penetration Seal Materials and Other Minor Changes; Proposed Rule.
Meeting to Discuss Haddam Neck Decommissioning Status
On August 11, 1999, Ronald Bellamy, Chief, Decommissioning and Laboratory Branch and other NRC staff met with senior representatives from the Connecticut Yankee Atomic Power Company and the management team of its decommissioning contractor, Bechtel Power Corporation to discuss the transfer of decommissioning responsibilities to Bechtel. The mobilization of workers, an overview from a recent stand-down from decommissioning activities because of worker safety issues, and plans for the removal, transport and disposal of the Haddam Neck steam generators were also discussed. The Meeting was held at the Connecticut Information Center in Haddam Neck to permit public observation. A second phase of the Meeting included a question and answer period with the public. Both the NRC and the licensee participated in these discussions with an audience of approximately 30 people. The Connecticut State Liaison Officer and two representatives from the U.S. Environmental Protection Agency, Region I Office also attended the Meeting. There was media coverage of the Meeting.
American Nuclear Society Utility Working Group Conference
The Director, Division of Reactor Safety participated in the American Nuclear Society Utility Working Group Meeting in Amelia Island, Florida, August 8-12, 1999.
Licensing/Inspection Outreach Workshop in Puerto Rico
Two NRC Region II inspectors/license reviewers recently conducted a workshop for the Radiological Health Division of the Puerto Rico Health Department in San Juan on licensing and inspection of radioactive materials. The Division had requested Region II to lead the seminar, as a part of their preparation to start licensing the use of certain naturally occurring and accelerator produced radioactive materials in Puerto Rico. Examples of applications include portable moisture/density gauges containing radium and medical uses of thallium and palladium. The inspectors presented consolidated guidance that the NRC uses to license and inspect analogous applications which contain byproduct material.
Southeast Plant Manager's Meeting
The Regional Administrator accompanied the NRC's Executive Director for Operations and participated in the Southeast Plant Manager's Meeting held in Williamsburg, Virginia on August 13.
The Region II Training Manager's Conference
The Region hosted the annual Region II Training Managers Conference on August 12-13. In addition to Region II management and staff, and approximately 60 licensee training program representatives, the Director, Division of Inspection Programs, NRR also participated in the Meeting.
Closed Meeting with Bill Miller, Inc.
A Predecisional Enforcement Conference was held in the Region IV office on August 11, 1999, between the Director, Division of Nuclear Materials Safety, other NRC staff members, and the President and Vice President of Bill Miller, Inc. The purpose of the conference was to discuss the apparent violations in NRC Inspection Report No. 030-15283/98-01. This Meeting was closed to members of the general public.
Congressional Hearing Schedule, No. 31
SD-406 10:00 Markup S. 1090, Superfund Reauthorization Senators Chafee/Baucus
Portner 09/23/99
TBA TBA Commission NRC Authorization Senators Inhofe/Graham
Clean Air, Wetlands, Private Property &
Note: Congress will return from August recess on September 8.
This page was last updated on August 20, 1999, by NRCWEB (nrcweb@nrc.gov).