⚛️Fort St. Vrain License Amendment
The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by the Department of Energy (DOE) for an amendment to Special Nuclear Materials (SNM) License No. SNM-2504, for the Fort St. Vrain (FSV) independent spent fuel storage installation (ISFSI) located in Platteville, Colorado. The requested amendment revises certain license conditions and technical specifications (TS) by adjusting references to relevant organizational components of DOE, correcting prior clerical drafting errors, and changing the description of a DOE official who is responsible for the operation and nuclear safety of the FSV ISFSI and for ensuring its compliance with certain conditions and requirements of the license and applicable regulations.
Learn More⚛️Amendment to Certificate of Compliance 1042 for Spent Fuel Storage
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the TN Americas LLC, NUHOMS[supreg] EOS Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 4 to Certificate of Compliance No. 1042. Amendment No. 4 changes the certificate of compliance to incorporate a method to determine new loading patterns, introduce a steel plate composite option, introduce the use of MAVRIC software for a confirmatory run of the HSM-MX dose rates, make technical specification changes for consistency and terminology clarification, make various updated final safety analysis report editorial corrections for consistency and clarification, add measured exposures from past loading campaigns, allow use of a blended Portland cement, change the use of the MX-Loading Crane, and clarify the scenarios under which the maximum heat loads can be reduced.
Learn More⚛️NRC Dockets License Amendment for Fort St. Vrain Storage Facility
The U.S. Nuclear Regulatory Commission (NRC) has received and docketed a license amendment application from the Department of Energy (DOE or the licensee) for amendment of Materials License No. SNM-2504, for the Fort St. Vrain (FSV) independent spent fuel storage installation (ISFSI) located in Platteville, Colorado. The requested amendment would revise certain license conditions and technical specifications (TS) by adjusting references to relevant organizational components of DOE, correcting prior clerical drafting errors, and changing the description of a DOE official who is responsible for the operation and nuclear safety of the FSV ISFSI and for ensuring its compliance with certain conditions and requirements of the license and applicable regulations. The NRC will process the application in accordance with NRC regulations, as further explained in the supplementary information section of this notice.
Learn More⚛️NRC Confirms Effective Date for Spent Fuel Storage Regulation
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of June 3, 2025, for the direct final rule that was published in the Federal Register on March 20, 2025. This direct final rule amended the NAC International, Inc., MAGNASTOR[supreg] Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 15 to Certificate of Compliance No. 1031.
Learn More⚡NRC Updates on MAGNASTOR® Storage System Regulations
The U.S. Nuclear Regulatory Commission (NRC) is correcting a direct final rule that was published in the Federal Register on March 20, 2025, revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 15 to Certificate of Compliance No. 1031. This action is necessary to replace an incorrect phrase in the SUMMARY caption of the document.
Learn More⚛️NRC Updates Approval for NAC International's Spent Fuel Cask
The U.S. Nuclear Regulatory Commission (NRC) is correcting a proposed rule that was published in the Federal Register on March 20, 2025, revising the NAC International, Inc. MAGNASTOR[supreg] Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 15 to Certificate of Compliance No. 1031. This action is necessary to replace an incorrect phrase in the Summary caption of the document.
Learn More⚛️Amendment 15 to Approved Spent Fuel Storage Casks Regulations
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. 15 to Certificate of Compliance No. 1031. Amendment No. 15 revises the certificate of compliance to add a new variation of the Lightweight MAGNASTOR[supreg] Transfer Cask design, add a new concrete cask design, increase the maximum system head load capacity, add new loading patterns, add a thermal shunt for short loading patterns, remove the 5 percent burnup penalty, increase Passive MAGNASTOR[supreg] Transfer Cask heat load, add two new pressurized-water reactor fuel types to support future operations, modify the transportable storage canister lid to allow additional clearance near the top center of the basket, and correct and clarify principal design criteria, operating procedures, and the acceptance criteria and maintenance program. This amendment also makes corresponding revisions to previously approved drawings for the concrete cask, Technical Specifications Appendix A and Appendix B, specific chapters of the final safety analysis report, and several license drawings.
Learn More⚛️Proposed NRC Amendments for Spent Fuel Storage Regulations
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend 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. 15 to Certificate of Compliance No. 1031. Amendment No. 15 revises the certificate of compliance to add a new variation of the Lightweight MAGNASTOR[supreg] Transfer Cask design, add a new concrete cask design, increase the maximum system head load capacity, add new loading patterns, add a thermal shunt for short loading patterns, remove the 5 percent burnup penalty, increase Passive MAGNASTOR[supreg] Transfer Cask heat load, add two new pressurized-water reactor fuel types to support future operations, modify the transportable storage canister lid to allow additional clearance near the top center of the basket, and correct and clarify principal design criteria, operating procedures, and the acceptance criteria and maintenance program. This amendment also makes corresponding revisions to previously approved drawings for the concrete cask, Technical Specifications Appendix A and Appendix B, specific chapters of the final safety analysis report, and several license drawings.
Learn More⚛️NRC Grants Exemption for Constellation Energy at Nine Mile Point
The U.S. Nuclear Regulatory Commission (NRC) issued an exemption to Constellation Energy Generation, LLC, permitting Nine Mile Point Nuclear Station (NMP) Units 1 and 2 to use the Holtec HI-STORM Flood/Wind (FW) Multi-Purpose Canister (MPC) Storage System, including the use of the HI-TRAC VW transfer cask during loading and transport operations, at the NMP independent spent fuel storage installation, for six MPC-89, in a near-term loading campaign beginning in May 2025, where the terms, conditions, and specifications in Certificate of Compliance No. 1032, Amendment No. 3, Revision 0, are not met.
Learn More⚛️NRC Updates Spent Fuel Storage Regulations for HI-STORM 100 Cask System
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International HI- STORM 100 Cask System listing within the "List of approved spent fuel storage casks" to include Renewed Amendment No. 19 to Certificate of Compliance No. 1014. Renewed Amendment No. 19 revises the certificate of compliance to update the acceptance criteria and method of evaluation (MOE) for the HI-STORM 100 system tipover accident for equipment combinations involving multi-purpose canisters (MPCs) with Metamic-HT baskets. This involves applying a new stress-based criteria and completing new evaluations consistent with the new tipover acceptance criteria and MOE and involves some adjustments of the existing deflection criteria.
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