⚛️Proposed Rule on Revised NAC Multi-Purpose Canister Compliance
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel regulations by revising the NAC Multi-Purpose Canister (NAC-MPC) System listing within the "List of approved spent fuel storage casks" to include Amendment No. 9 and revise Amendment Nos. 6, 7, and 8 to Certificate of Compliance (CoC) No. 1025. Amendment No. 9 and the revisions to Amendment Nos. 6, 7, and 8 amend the description of the vertical concrete cask (VCC) in the CoC and technical specifications to make a distinction between the VCC body and the VCC lid, in terms of applicability of the American Concrete Institute (ACI) Specifications ACI 349 and ACI 318.
Learn More🏢NRC Sunshine Act Meetings Schedule Overview
The Nuclear Regulatory Commission has announced its schedule for public meetings in early 2025, including briefings on various topics relevant to the nuclear industry. The meetings are open to the public and will be held in Rockville, Maryland, with options for virtual attendance available.
Learn More⚛️NRC Terminates SNM-2512 License for Idaho Spent Fuel Facility
The U.S. Nuclear Regulatory Commission (NRC) is terminating Special Nuclear Material (SNM) License No. SNM-2512 for the Idaho Spent Fuel Facility (ISFF). By letter dated November 26, 2024, the U.S. Department of Energy (DOE) requested that the NRC terminate the ISFF license. The ISFF has not been constructed, no physical or principal activities authorized by the license have been conducted, and no nuclear materials have been possessed under the license. Consequently, the ISFF site is approved for unrestricted use.
Learn More⚛️NRC Issues Regulatory Guide 3.78 for Inservice Inspection Compliance
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 3.78 (Revision 0), "Acceptable ASME Section XI Inservice Inspection Code Cases." This new RG provides applicants and licensees with methods that the NRC staff considers acceptable for specific or general independent spent fuel storage installation (ISFSI) licensees and certificate of compliance (CoC) holders to comply with NRC regulations for inservice inspection of confinement boundary components and aging management activities associated with the renewals of ISFSIs, general licensees, and CoC holders for spent fuel storage systems.
Learn More☢️NRC Reopens Comment Period for High Temperature Reactors Guide
On December 13, 2024, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on draft Regulatory Guide (DG) DG-1436, "Acceptability of ASME Code, Section III, Division 5, `High Temperature Reactors.' " The public comment period closed on January 27, 2025. The NRC has decided to reopen the public comment period to allow more time for members of the public to develop and submit their comments.
Learn More⚠️NRC Notice on License Amendments for Palo Verde Facility Operations
The U.S. Nuclear Regulatory Commission (NRC or the Commission) received and is considering approval of a request to amend three licenses. The request is for Palo Verde Nuclear Generating Station, Units 1, 2, and 3. For each license amendment, the NRC proposes to determine that it involves no significant hazards consideration (NSHC). Because the amendment request contains sensitive unclassified non- safeguards information (SUNSI), the NRC is issuing an order imposing procedures to obtain access to SUNSI for contention preparation by persons who file a hearing request or petition for leave to intervene.
Learn More⚛️NRC Issues Updates on Spent Fuel Storage Regulations and Compliance
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 14 and revisions to Amendment Nos. 0 through 13 to Certificate of Compliance No. 1031. Amendment No. 14 and revisions to Amendment Nos. 0 through 13 revise the certificate of compliance to add a revised method of evaluation for the non-mechanistic tipover accident, clarify in the technical specifications that damaged missing grid spacers only apply to pressurized-water reactor fuel assembles, clarify inlet and outlet vent blockage and surveillance requirements in limiting condition for operation 3.1.2 in Appendix A to the certificate of compliance and associated technical specification bases, and remove the reference to Type II Portland cement in the description of the certificate of compliance. The NRC is also correcting typographical errors in Revision 1 to Amendment Nos. 11 to 13 and Amendment No. 14 to Certificate of Compliance No. 1031.
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