Nuclear Regulatory Commission June 5, 2018 – Federal Register Recent Federal Regulation Documents

Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Nuscale; Notice of Meeting
Document Number: 2018-12024
Type: Notice
Date: 2018-06-05
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on APR1400
Document Number: 2018-12022
Type: Notice
Date: 2018-06-05
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Effect of LWR Water Environments on the Fatigue Life of Reactor Materials
Document Number: 2018-11996
Type: Notice
Date: 2018-06-05
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG/ CR-6909, Revision 1, ``Effect of LWR Water Environments on the Fatigue Life of Reactor Materials.'' This report summarizes the results of NRC research efforts and work performed at Argonne National Laboratory on the fatigue of piping and pressure vessel steels in light-water reactor (LWR) environments. Revision 1 of this report provides updates and improvements to the environmental fatigue correction factor approach based on an extensive update to available laboratory fatigue data from testing and results available since this report was first published in 2007. This final document also incorporates changes to address public comments provided on the draft of Revision 1 of NUREG/CR-6909.
Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components
Document Number: 2018-11995
Type: Notice
Date: 2018-06-05
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.207, ``Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components.'' This RG describes methods and procedures that the staff of the NRC considers acceptable for use in determining the acceptable fatigue lives of components evaluated by a cumulative usage factor calculation in accordance with the fatigue design provisions in Section III, ``Rules for Construction of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to account for the effects of light-water reactor water environments.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
Document Number: 2018-11843
Type: Notice
Date: 2018-06-05
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued, from May 8, 2018, to May 21, 2018. The last biweekly notice was published on May 22, 2018.
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
Document Number: 2018-10982
Type: Notice
Date: 2018-06-05
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of three amendment requests. The amendment requests are for River Bend Station, Unit 1; Grand Gulf Nuclear Station, Unit 1; and Browns Ferry Nuclear Plant, Units 1, 2, and 3. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration. Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI) an order imposes procedures to obtain access to SUNSI for contention preparation.
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