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☢️NRC Reopens Comment Period for High Temperature Reactors Guide

On December 13, 2024, the U.S. Nuclear Regulatory Commission (NRC) solicited comments on draft Regulatory Guide (DG) DG-1436, "Acceptability of ASME Code, Section III, Division 5, `High Temperature Reactors.' " The public comment period closed on January 27, 2025. The NRC has decided to reopen the public comment period to allow more time for members of the public to develop and submit their comments.

🏭Law Enforcement Response in Power Reactor Physical Protection Programs

⚡NRC Draft Assessment for Palisades Nuclear Plant Operations Restart

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft environmental assessment (EA) and draft finding of no significant impact (FONSI) evaluating the environmental impacts from proposed Federal actions related to reauthorizing power operations at the Palisades Nuclear Plant (Palisades). Specifically, the NRC is considering an exemption request, a license transfer request, and license amendment requests (LARs) to support reauthorizing power operation under the NRC license. The U.S. Department of Energy (DOE), Loan Programs Office (LPO), is a cooperating agency on the draft EA. DOE LPO's proposed action is to provide Federal financial support (a loan guarantee) for refueling and resumption of power generation activities at Palisades.

⚛️NRC Proposes Amendment for MAGNASTOR® Storage System Compliance

The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel 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.