Nuclear Regulatory Commission 2006 – Federal Register Recent Federal Regulation Documents
Results 101 - 150 of 722
Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1, 2 and 3; Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment To Increase the Maximum Reactor Power Level
The U.S. Nuclear Regulatory Commission (NRC) has prepared a draft Environmental Assessment (EA) as its evaluation of a request by the Tennessee Valley Authority (TVA) for license amendments to increase the maximum thermal power at Browns Ferry Nuclear Plant (BFN) from 3458 megawatts-thermal (MWt) to 3952 MWt for Units 2 and 3 and from 3293 MWt to 3952 MWt for Unit 1. These represent power increases of approximately 15 percent for BFN Units 2 and 3 and a total of 20 percent for BFN Unit 1. As stated in the NRC staff's position paper dated February 8, 1996, on the Boiling-Water Reactor Extended Power Uprate (EPU) Program, the NRC staff would prepare an environmental impact statement if it believes a power uprate would have a significant impact on the human environment. The NRC staff did not identify any significant impact from the information provided in the licensee's EPU applications for BFN Units 1, 2, and 3, or from the NRC staff's independent review; therefore, the NRC staff is documenting its environmental review in an EA. Also, in accordance with the position paper, the draft EA and Finding of No Significant Impact are being published in the Federal Register with a 30-day public comment period.
Notice of Public Meeting
The NRC and DOE announce their intent to conduct a public meeting to discuss interactions during the review of non-high-level waste determinations under the National Defense Authorization Act (NDAA) for Fiscal Year 2005. The meeting date, time and location are listed below: Date: Thursday, November 16, 2006. Time: 9 a.m. to 11 a.m. Location: L'Enfant Plaza Hotel, Meeting RoomsMonet 1 and 2, 480 L'Enfant Plaza, Washington, DC 20024, phone: 202-484-1000. Agenda: 9-9:15: Introductions and Opening Remarks. 9:15-10:45: Discussion of NDAA consultation. 10:45-11: Opportunity for Public Comment.
Massachusetts Attorney General; Receipt of Petition for Rulemaking
The Nuclear Regulatory Commission (NRC) is publishing for public comment a notice of receipt of a petition for rulemaking, dated August 25, 2006, which was filed with the Commission by Diane Curran on behalf of Massachusetts Attorney General. The petition was docketed by the NRC on September 19, 2006, and has been assigned Docket No. PRM-51- 10. The petitioner requests that the NRC revoke certain regulations in their entirety, and revoke other regulations to the extent that these regulations, in the petitioner's view, state, imply, or assume that the environmental impacts of storing spent nuclear fuel in high-density pools are not significant; issue a generic determination to clarify that the environmental impacts of high-density pool storage of spent fuel, will be considered significant; and require that any NRC licensing decision concerning high-density pool storage of spent nuclear fuel be accompanied by an environmental impact statement that addresses the environmental impacts of this storage and alternatives for avoiding or mitigating any environmental impacts. The petitioner is seeking the generic treatment of spent fuel pool hazards because he believes that a pool accident at any operating nuclear power plant in the New England and Mid-Atlantic states could significantly affect the health, environmental, and economic well-being of Massachusetts.
E. Russell Ritenour, Ph.D.; Receipt of Petition for Rulemaking
The Nuclear Regulatory Commission (NRC) has received and requests public comment on a petition for rulemaking dated September 10, 2006, filed by E. Russell Ritenour, Ph.D. (petitioner) on behalf of the American Association of Physicists in Medicine (AAPM). The petition has been docketed by the NRC and has been assigned Docket No. PRM-35- 20. The petitioner is requesting that the NRC amend the regulations that govern medical use of byproduct material to revise what it calls the ``grandfather'' provision to recognize individual diplomates of certifying boards that were previously named in these regulations before October 25, 2005.
Protection of Safeguards Information
The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations for the protection of Safeguards Information (SGI) to protect SGI from inadvertent release and unauthorized disclosure which might compromise the security of nuclear facilities and materials. The amendments would affect certain licensees, information, and materials not currently subject to SGI regulations, but which are within the scope of Commission authority under the Atomic Energy Act of 1954, as amended (AEA). The NRC originally published a proposed rule on SGI on February 11, 2005 (70 FR 7196). The NRC is again publishing the proposed rule on SGI protection requirements in order to allow the public to comment on changes to the proposed rule text in response to public comment and to reflect amendments to the AEA in the Energy Policy Act of 2005 (EPAct) and Commission Orders issued to licensees authorized to possess and transfer items containing certain quantities of radioactive material.
Notice of Availability of Model Safety Evaluation on Technical Specification Improvement To Modify Requirements Regarding LCO 3.10.1, Inservice Leak and Hydrostatic Testing Operation Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to the modification of shutdown testing requirements in technical specifications (TS) for Boiling Water Reactors (BWR). The NRC staff has also prepared a model no-significant-hazards-consideration (NSHC) determination relating to this matter. The purpose of these models is to permit the NRC to efficiently process amendments that propose to modify LCO 3.10.1. The proposed changes would revise LCO 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than [200] [deg]F as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4. Licensees of nuclear power reactors to which the models apply could then request amendments, confirming the applicability of the SE and NSHC determination to their reactors.
Incorporation by Reference of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Cases
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference the latest revisions of two previously incorporated regulatory guides (RGs) that approve Code Cases published by the American Society of Mechanical Engineers (ASME). Specifically, these are Revision 34 of RG 1.84, ``Design and Fabrication Code Case Acceptability, ASME Section III'' (temporarily designated as Draft Regulatory Guide DG-1133), and Revision 15 of RG 1.147, ``Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1'' (temporarily designated as Draft Regulatory Guide DG- 1134). This proposed action would allow licensees to use the Code Cases listed in the regulatory guides as alternatives to requirements in the ASME Boiler and Pressure Vessel (BPV) Code regarding the construction and inservice inspection of nuclear power plant components. Toward that end, the NRC has issued for public comment drafts of the two revised guides in the agency's Regulatory Guide Series. This series has been developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC's regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in its review of applications for permits and licenses.
Incorporation by Reference of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Cases
The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference the latest revisions of two previously incorporated regulatory guides (RGs) that approve Code cases published by the American Society of Mechanical Engineers (ASME). These RGs are 1.84, ``Design and Fabrication Code Case Acceptability, ASME Section III,'' Revision 34 and RG 1.147, ``Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1,'' Revision 15. This proposed action would allow licensees to use the Code Cases listed in the regulatory guides as alternatives to requirements in the ASME BPV Code regarding the construction and inservice inspection of nuclear power plant components.
Power Reactor Security Requirements
The Nuclear Regulatory Commission (NRC) is proposing to amend the current security regulations and add new security requirements pertaining to nuclear power reactors. Additionally, this rulemaking includes new security requirements for Category I strategic special nuclear material (SSNM) facilities for access to enhanced weapons and firearms background checks. The proposed rulemaking would: Make generically applicable security requirements imposed by Commission orders issued after the terrorist attacks of September 11, 2001, based upon experience and insights gained by the Commission during implementation; fulfill certain provisions of the Energy Policy Act of 2005; add several new requirements that resulted from insights from implementation of the security orders, review of site security plans, and implementation of the enhanced baseline inspection program and force-on-force exercises; update the regulatory framework in preparation for receiving license applications for new reactors; and impose requirements to assess and manage site activities that can adversely affect safety and security. The proposed safety and security requirements would address, in part, a petition for rulemaking (PRM 50- 80) that requests the establishment of regulations governing proposed changes to facilities which could adversely affect the protection against radiological sabotage.
Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire, Draft Report for Comment
On October 12, 2006 (71 FR 60200), the Nuclear Regulatory Commission (NRC) issued for public comment NUREG 1852, ``Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire, Draft Report for Comment.'' A request has been made to extend the public comment period such that the public will have a full 60 days to review this report. Currently, the Federal Register specifies that the public comment period ends on November 6, 2006, less than 30 days after the issuance of the Federal Register Notice.
Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Fire Protection; Notice of Meeting
Notice of Opportunity To Comment on Model Safety Evaluation on Technical Specification Improvement To Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) and model application relating to the modification of technical specification (TS) requirements regarding the habitability of the control room envelope (CRE). The NRC staff has also prepared a model no-significant-hazards-consideration (NSHC) determination relating to this matter. The purpose of these models is to permit the NRC to efficiently process amendments that propose to revise the CRE emergency ventilation system TS action and surveillance requirements for the CRE boundary, and to add a new TS administrative controls program, ``Control Room Envelope Habitability Program.'' Licensees of nuclear power reactors to which the models apply could then request amendments, confirming the applicability of the SE and NSHC determination to their reactors. The NRC staff is requesting comment on the model SE and model NSHC determination prior to announcing their availability for referencing in license amendment applications.
Licenses, Certifications, and Approvals for Nuclear Power Plants; Supplemental Proposed Rule
The Nuclear Regulatory Commission (NRC) is proposing to supplement its proposed rule entitled ``Licenses, Certifications, and Approvals for Nuclear Power Plants,'' which was published on March 13, 2006 (71 FR 12782). The NRC is proposing to supplement that proposed rule by amending the regulations applicable to limited work authorizations (LWA), which allow limited construction activities on nuclear power plants to commence before a construction permit or combined license is issued. This supplemental proposed rule would modify the scope of activities that are considered construction requiring a LWA and would also make changes to the review and approval process for LWA requests. The NRC is proposing these changes to enhance the efficiency of its licensing and approval process for new nuclear reactors.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 3
The Nuclear Regulatory Commission (NRC) is amending its regulations revising the Holtec International HI-STORM 100 cask system listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 3 to Certificate of Compliance Number 1014. Amendment No. 3 will revise Technical Specification (TS) 3.1.3, to eliminate cooling of the Multi-Purpose Canister (MPC) cavity prior to reflood with water, as part of cask unloading operations; TS 3.3.1, to allow linear interpolation between minimal soluble boron concentrations, for certain fuel enrichments in the MPC-32/32F; Appendix B, Section 1, to make modifications to the definitions of fuel debris, damaged fuel assembly, and non-fuel hardware; and Appendix B, Section 2, to permit the storage of pressurized water reactor fuel assemblies with annular fuel pellets in the top and bottom 12 inches of the active fuel length. Other changes will be made to incorporate minor editorial corrections.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 3
The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations revising the Holtec International HI-STORM 100 cask system listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 3 to Certificate of Compliance Number 1014. Amendment No. 3 would revise Technical Specification (TS) 3.1.3, to eliminate cooling of the Multi-Purpose Canister (MPC) cavity prior to reflood with water, as part of cask unloading operations; TS 3.3.1, to allow linear interpolation between minimal soluble boron concentrations, for certain fuel enrichments in the MPC-32/32F; Appendix B, Section 1, to make modifications to the definitions of fuel debris, damaged fuel assembly, and non-fuel hardware; and Appendix B, Section 2, to permit the storage of pressurized water reactor fuel assemblies with annular fuel pellets in the top and bottom 12 inches of the active fuel length. Other changes would be made to incorporate minor editorial corrections.
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