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The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel 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. 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.
Published
Feb 27, 2025
Comments Close
Mar 31, 2025
Citation
90 FR 10799
Agencies
1
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NRC-2024-0200
3150-AL23
10 CFR 72