Nuclear Regulatory Commission November 21, 2007 – Federal Register Recent Federal Regulation Documents

Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events; Reopening of Comment Period for Information Collection
Document Number: E7-22761
Type: Proposed Rule
Date: 2007-11-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is reopening the comment period specific to the information collection aspects of a proposed rule published on October 3, 2007 (72 FR 56275), that would amend NRC's regulations to provide updated fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) pressure vessels. The comment period for comments specific to the information collection aspects of the proposed rule, closed on November 2, 2007.
Regulations for the Safe Transport of Radioactive Material; Notice of Document Availability and Request for Comments
Document Number: E7-22759
Type: Proposed Rule
Date: 2007-11-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft revision of the International Atomic Energy Agency's (IAEA) ``Regulations for the Safe Transport of Radioactive Material'' (TS-R-1), which is scheduled for publication in 2009. The NRC and the U.S. Department of Transportation (DOT) jointly will be submitting comments on the draft document to the IAEA. We are requesting input from the public to assist in developing the U.S. comments.
Notice of Availability on Model Safety Evaluation; Model No Significant Hazards Determination, and Model Application for Licensees That Wish to Adopt TSTF-478, Revision 2, “BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control”
Document Number: E7-22740
Type: Notice
Date: 2007-11-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) and a model application related to the modification of containment combustible gas control requirements in technical specifications (TS) for Boiling Water Reactors (BWR). The NRC staff has also prepared a model no-significant-hazards-consideration (NSHC) determination related to this matter. The purpose of these models is to permit the NRC to efficiently process license amendment applications that propose to adopt TSTF-478, Revision 2, ``BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control.'' TSTF-478, Revision 2, deletes Standard Technical Specification (STS) 3.6.3.3, ``Containment Atmosphere Dilution (CAD) System'' and modifies STS 3.6.3.1, ``Drywell Cooling System Fans,'' in NUREG-1433, ``Standard Technical Specifications General Electric Plants, BWR/4, Rev. 3,'' to establish TS for containment combustible gas control requirements as permitted by revised 10 CFR 50.44. 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 plants.
Notice of Opportunity To Comment on Model Safety Evaluation on Technical Specification Improvement for B&W Reactor Plants To Risk-Inform Requirements Regarding Selected Required Action End-States Using the Consolidated Line Item Improvement Process
Document Number: E7-22738
Type: Notice
Date: 2007-11-21
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) and model license amendment request (LAR) relating to changes to the end-state requirements for required actions in B&W reactor plants' technical specifications (TS). Current technical specification action requirements frequently require that the unit be brought to cold shutdown when the technical specification limiting condition for operation for a system has not been met. Depending on the system, and the affected safety function, the requirement to go to cold shutdown may not represent the most risk effective course of action. In accordance with a qualitative risk analysis that provides a basis for changes to the action requirement to shutdown, where appropriate the shutdown end-state is changed from cold shutdown to hot shutdown. The affected TS are: