Nuclear Regulatory Commission 2025 – Federal Register Recent Federal Regulation Documents
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Constellation Energy Generation, LLC; LaSalle County Station Units 1 and 2; Independent Spent Fuel Storage Installation; Exemption
The U.S. Nuclear Regulatory Commission (NRC) issued an exemption to Constellation Energy Generation, LLC, permitting LaSalle County Station (LSCS) to maintain four loaded and to load four new 68M multi-purpose canister with continuous basket shims in HI-STORM 100 Cask System at its LSCS Units 1 and 2 independent spent fuel storage installation in a storage condition where the terms, conditions, and specifications in the Certificate of Compliance No. 1014, Amendment No. 8, Revision No. 1, are not met.
Constellation Energy Generation, LLC; Peach Bottom Atomic Power Station, Units 2 and 3; Notice of Intent To Prepare a Supplement to the Supplemental Environmental Impact Statement
The U.S. Nuclear Regulatory Commission (NRC, the Commission) staff will prepare a supplement to NUREG-1437, "Generic Environmental Impact Statement for License Renewal of Nuclear Plants," Supplement 10, Second Renewal, "Regarding Subsequent License Renewal for Peach Bottom Atomic Power Station Units 2 and 3," dated January 2020 (the final supplemental environmental impact statement (SEIS)) in order to complete its evaluation of the environmental impacts of the subsequent license renewal (SLR) of Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (Peach Bottom), Units 2 and 3, respectively. The supplement will address new information since the issuance of the final SEIS. A draft of the supplement will be issued for public comment.
Northern States Power Company, a Minnesota Corporation; Monticello Nuclear Generating Plant, Unit 1; Subsequent License Renewal and Record of Decision
The U.S. Nuclear Regulatory Commission (NRC) has issued Subsequent Renewed Facility Operating License No. DPR-22 to Northern States Power Company, a Minnesota corporation (NSPM, or the licensee), for Monticello Nuclear Generating Plant, Unit 1 (Monticello). In addition, the NRC has prepared a record of decision (ROD) that supports the NRC's decision to issue Subsequent Renewed Facility Operating License No. DPR-22.
List of Approved Spent Fuel Storage Casks: NAC International, Inc. MAGNASTOR® Storage System, Certificate of Compliance No. 1031, Amendment No. 14 and Revisions to Amendment Nos. 0 Through 13
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel 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.
List of Approved Spent Fuel Storage Casks: NAC International, Inc. MAGNASTOR® Storage System, Certificate of Compliance No. 1031, Amendment No. 14 and Revisions to Amendment Nos. 0 Through 13
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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