⚛️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⚛️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.
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🛡️Holtec HI-STORM UMAX Storage System Compliance Updates
The U.S. Nuclear Regulatory Commission (NRC) is amending its 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 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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