⚛️Constellation Energy Receives Exemption for Nuclear Storage Operations
The U.S. Nuclear Regulatory Commission (NRC) issued an exemption to Constellation Energy Generation, LLC, permitting Nine Mile Point Generating Station (NMP) to maintain nine loaded and to load six new 89 multi-purpose canisters (MPC) with continuous basket shims in the HI-STORM Flood/Wind MPC Storage System at its NMP 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. 1032, Amendment No. 3, Revision No. 0 are not met.
Learn More⚛️NRC Confirms Effective Date for Holtec Storage Cask Regulations
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of April 21, 2025, for the direct final rule that was published in the Federal Register on February 4, 2025. This direct final rule amended the NRC's spent fuel storage regulations by revising the Holtec International HI-STORM UMAX Canister Storage System listing within the "List of approved spent fuel storage casks" to include Revision 1 to Amendment Nos. 0 through 2 to Certificate of Compliance (CoC) No. 1040. Revision 1 to Amendment Nos. 0 through 2 updates the CoC appendix A technical specifications for radiation protection and the associated bases information to clearly articulate the basis for the dose rate limits for the closure lids, modify the dose rate limit values and the description of the location of the dose rate measurements, and make other editorial changes.
Learn More⚛️NRC Amendments to NAC-MPC System Impacting Spent Fuel Storage
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 include Amendment No. 9 and revise Amendment Nos. 6, 7, and 8 to Certificate of Compliance (CoC) No. 1025. The addition of 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 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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