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Rule 4 Feb 2025 regulatory compliance, spent fuel storage, safety standards, administrative practice and procedure, reporting and recordkeeping requirements, nuclear energy, intergovernmental relations, penalties, radiation protection, whistleblowing, hazardous waste, security measures, indians, nuclear industry, holtec international

🛡️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.

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Compliance, Regulatory Requirements 3 Jan 2025 compliance, regulations, spent fuel, administrative practice and procedure, reporting and recordkeeping requirements, nuclear energy, intergovernmental relations, penalties, radiation protection, whistleblowing, hazardous waste, security measures, indians, nrc, magnastor

⚛️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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