Nuclear Regulatory Commission – Federal Register Recent Federal Regulation Documents

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has received a license amendment application from Northern States Power Company (NSPM) for an amendment to Materials License No. SNM-2506 for the Prairie Island Independent Spent Fuel Storage Installation (PI ISFSI) located in Welch, Minnesota. The amendment request seeks to revise the technical specifications (TS) for the PI ISFSI. NSPM proposes to allow use of a Code alternative as an option to the requirements of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section III, Division 1, Subsection NB, Paragraph NB-5130, by revising the TS to add the Code alternative to TS section 4.4, table 4.4-1, TN-40HT ASME Code Exceptions.

The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on Appendix B and conforming changes to other parts of its draft Regulatory Guide (DG), DG-1404, Revision 1 ``Guidance for a Technology-Inclusive Content-of-Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors.'' On May 25, 2023, the NRC published Revision 0 to DG-1404 requesting public comment, and on June 28, 2023, the NRC extended the public comment period to August 10, 2023. Since then, and consistent with item 1 in Appendix A to DG-1404, Revision 0, the NRC completed its development of Appendix B and revised DG-1404 (i.e., Revision 1) to include this appendix and made conforming changes to other parts of the document. Appendix B provides additional guidance for the scope, level of detail, elements, and plant representation for a probabilistic risk assessment (PRA) supporting a Licensing Modernization Project (LMP)-based construction permit application.

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Solicitation of Non-Power Operator Licensing Examination Data.''

On July 11, 2023, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on three draft documents that provide revised guidance for subsequent license renewal (SLR) and the associated technical bases for the revised guidance documents. The draft regulatory guidance documents consist of draft NUREG-2191, ``Generic Aging Lessons Learned for Subsequent License Renewal Report,'' Volumes 1 and 2, Revision 1 (GALL-SLR Report); draft NUREG-2192, ``Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants,'' Revision 1 (SRP-SLR); and draft NUREG-2221, ``Technical Bases for Changes in the Subsequent License Renewal Guidance Documents, NUREG-2191, Revision 1, and NUREG-2192, Revision 1,'' Supplement 1. The public comment period was originally scheduled to close on September 11, 2023. The NRC has decided to extend the public comment period to allow more time for members of the public to prepare and submit their comments.

Pursuant to section 189.a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular monthly 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 (NSHC), notwithstanding the pendency before the Commission of a request for a hearing from any person.

The U.S. Nuclear Regulatory Commission (NRC or the Commission) will convene an evidentiary session to receive testimony and exhibits in the uncontested proceeding regarding the application from Kairos Power LLC (Kairos) for a construction permit (CP) to construct a non- power test reactor termed Hermes in Oak Ridge, Tennessee. This mandatory hearing will consider safety and environmental matters relating to the requested CP.

The U.S. Nuclear Regulatory Commission (NRC, the Commission) is considering issuance of an amendment to Renewed Facility Operating License No. NPF-43, issued to DTE Electric Company, for operation of Fermi, Unit 2 (Fermi 2). The proposed amendment requests an amendment to the Fermi 2 Technical Specifications (TS) 3.7.2, to allow for a one-time extension of the Condition A Completion Time to allow repair of Division 1 Mechanical Draft Cooling Tower A and C fan pedestals while online. The proposed amendment is being requested due to an exigent circumstance pursuant to NRC regulations.

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``NRC Form 4, Cumulative Occupational Dose History.''

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on this proposed information collection. The information collection is entitled, ``Codes and Standards.''

The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to make miscellaneous corrections. These changes include updating organizational information, revising an address, and correcting reference, spelling, and grammatical errors. The amendments also make updates to replace gendered terms with inclusive, gender- neutral language. This document is necessary to inform the public of these non-substantive amendments to the NRC's regulations.

The U.S. Nuclear Regulatory Commission (NRC) is issuing a final Environmental Impact Statement (EIS), NUREG-2263, ``Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor: Final Report.'' The NRC staff is issuing a final EIS as part of the review of the application submitted by Kairos Power, LLC (Kairos) for a construction permit (CP). The Hermes test reactor is proposed to be built in the City of Oak Ridge, Tennessee.

The U.S. Nuclear Regulatory Commission (NRC) is correcting the preamble of a proposed rule that was published in the Federal Register on August 8, 2023, to amend its regulations to incorporate by reference the 2021 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code and the 2022 Edition of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants, Division 1: OM Code: Section IST, for nuclear power plants. This action is necessary to correct an editorial error to include reference to missing standards.

The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 4.26 ``Volcanic Hazards Assessment for Proposed Nuclear Power Reactor Sites,'' to restore text and a Section heading inadvertently omitted from Section C, ``Staff Regulatory Guidance,'' of Revision 0. The restored text appeared in the draft guide released for public comment. In addition, there is a minor update of the Paperwork Reduction Act text in the RG. The changes do not represent substantive changes in the NRC staff's regulatory positions.

The Nuclear Regulatory Commission (NRC, the Commission) has received a limited work authorization (LWA) application from Carbon Free Power Project, (CFPP) LLC to conduct certain early construction activities at the Idaho National Laboratory (INL) for which either a construction permit or a combined license would otherwise be required.

The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order suspending the general license authority under NRC regulations to export special nuclear material, source material, and deuterium for nuclear end use to the People's Republic of China. Exporters are no longer authorized to use the general license to export special nuclear material, source material, or deuterium for nuclear end use to the People's Republic of China and now must apply for a specific license in accordance with NRC regulations.

Notice is hereby given that effective August 9, 2023, the U.S. Nuclear Regulatory Commission (NRC) has assumed regulatory authority to evaluate and approve sealed source and device (SS&D) applications in the State of New York and approved the Governor of the State of New York's request to relinquish this authority.

The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register (FR) on July 11, 2023, requesting public comment on three draft NUREGs that provide revised guidance for subsequent license renewal and the associated technical bases for the revised guidance documents. This action is necessary to correct tables within the Draft NUREG-2192, ``Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants, Draft Report for Comment,'' Revision 1.

Pursuant to section 189.a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular monthly 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 (NSHC), notwithstanding the pendency before the Commission of a request for a hearing from any person.

The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to a request dated June 30, 2022, as supplemented by letters dated September 13, 2022, and January 20, and May 5, 2023, from Southern Nuclear Operating Company to allow the use of AXIOM fuel rod cladding material in lead test assemblies 7ST1, 7ST2, 7ST3, and 7ST4, for up to two cycles of operation at Vogtle Electric Generating Plant, Unit 2.

The U.S. Nuclear Regulatory Commission (NRC) has issued an exemption in response to a request dated June 30, 2022, as supplemented by letters dated September 13, 2022, and January 20, and May 5, 2023, from Southern Nuclear Operating Company to allow the use of AXIOM fuel rod cladding material in lead test assemblies 7ST1, 7ST2, 7ST3, and 7ST4, for up to two cycles of operation at Vogtle Electric Generating Plant, Unit 2.

The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``IAEA Design Information Questionnaire Forms.''

The U.S. Nuclear Regulatory Commission (NRC) is providing public notice of receipt and availability of an application for construction permits for a two-unit reactor facility from Kairos Power, LLC. The application for the construction permits was received on July 14, 2023.

The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC Multi-Purpose Canister (NAC-MPC) System listing within the ``List of approved spent fuel storage casks'' to renew, for 40 years, the initial certificate and Amendment Nos. 1 through 8 of Certificate of Compliance No. 1025. The renewal of the initial certificate and Amendment Nos. 1 through 8 revises the certificate of compliance's conditions and technical specifications to address aging management activities related to the structures, systems, and components important to safety of the dry storage system to ensure that these will maintain their intended functions during the period of extended storage operations.

The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Section 15.0, Revision 4, ``IntroductionTransient and Accident Analyses.'' The NRC seeks comments on the proposed draft section revision of the Standard Review Plan (SRP), concerning the evaluation of the safety of a nuclear power plant that requires analyses of the plant's responses to postulated equipment failures or malfunctions. Such analyses help to determine the limiting conditions for operation, limiting safety system settings, and design specifications for components and systems to protect public health and safety.