Nuclear Regulatory Commission October 2012 – Federal Register Recent Federal Regulation Documents
Results 51 - 61 of 61
Burnup Credit in the Criticality Safety Analyses of Pressurized Water Reactor Spent Fuel in Transportation and Storage Casks
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing a Spent Fuel Storage and Transportation Interim Staff Guidance (SFST-ISG)-8, Revision 3, entitled, ``Burnup Credit in the Criticality Safety Analyses of PWR [Pressurized Water Reactor] Spent Fuel in Transportation and Storage Casks.'' This SFST-ISG provides guidance for use by NRC staff when reviewing applications requesting burnup credit in the criticality safety analyses of pressurized water reactor spent nuclear fuel (SNF) in transportation packages and storage casks. SFST-ISG-8, Revision 3, includes two major changes in the staff recommendations: (1) optional credit for fission product and minor actinide neutron absorbing isotopes in the SNF composition, and (2) misload analyses and additional administrative procedures in lieu of a burnup measurement at the time of loading.
Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing a revision to Regulatory Guide (RG) 1.52, ``Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants.'' This guide applies to the design, inspection, and testing of air filtration and iodine adsorption units of engineered-safety-feature (ESF) atmosphere cleanup systems in light-water-cooled nuclear power plants.
Control of Ferrite Content in Stainless Steel Weld Metal
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing for public comment draft regulatory guide (DG), DG-1279, ``Control of Ferrite Content in Stainless Steel Weld Metal.'' This guide describes a method that the NRC staff considers acceptable for controlling ferrite content in stainless steel weld metal. Revision 4 updates the guide to remove references to outdated standards and to remove an appendix that has been incorporated into relevant specifications.
Regulatory Guide 5.67, Material Control and Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic Significance
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 5.67, ``Material Control and Accounting for Uranium Enrichment Facilities Authorized to Produce Special Nuclear Material of Low Strategic Significance.'' The guide is being withdrawn because it is no longer needed and more extensive guidance can be found in NUREG/CR-5734, ``Recommendations to the NRC on Acceptable Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium Facilities'' which was issued in November 1991.
Non-Power Reactor License Renewal
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is publishing the final regulatory basis for rulemaking to streamline non-power reactor license renewal. This final regulatory basis incorporates input from the public, licensees, certificate holders, and other stakeholders provided during the public comment period that ended July 31, 2012. This regulatory basis provides the technical basis to support proceeding with rulemaking to streamline and enhance the Research and Test Reactor (RTR) License Renewal Process. This contemplated rulemaking also recommends conforming changes to address technical issues in existing non-power reactor regulations. The NRC has developed a final technical basis for this proposed rulemaking that describes the agency's overall objectives, conceptual approaches, potential solutions, integration with agency strategic goals, and related technical and regulatory clarity issues.
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