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Browse 69 rules and proposed rules from the Federal Register.
69
Total Regulations
Showing 31–60 of 69
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The U.S. Nuclear Regulatory Commission (NRC) is correcting a final rule that was published in the Federal Register on June 24, 2025, regarding the amendment of licensing, inspection, special project, and annual fees charged to NRC's applicants and licensees. This action is necessary to correct a typo to the dollar amount in the schedule of materials annual fees and fees for Government agencies licensed by the NRC.
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), dated August 1, 2022, submitted by Ralph O. Meyer. The petition requested that the NRC amend its regulations regarding the licensing safety analysis for loss-of-coolant accidents. The petition was docketed on August 1, 2022, and was assigned Docket No. PRM-50-124. The NRC is denying the petition because the NRC is addressing emergency core cooling system performance with a risk- informed and performance-based regulatory approach rather than a deterministic approach as suggested by the petitioner.
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking, dated November 23, 2019, submitted by John G. Parillo. The petition requested that the NRC develop a rule that would allow nuclear power plant licensees to voluntarily adopt a revised accident dose acceptance criteria for the control room, exclusion area boundary, and the low population zone outer boundary. The petition further requested revisions to clarify footnotes discussing these dose acceptance criteria in the applicable regulations. The NRC docketed the petition on February 19, 2020, and assigned it Docket No. PRM-50-121. The NRC is denying the petition because the information presented does not support rulemaking and the proposed changes are not necessary to provide reasonable assurance of adequate protection of public health and safety.
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking, dated August 19, 2019, submitted by Thomas A. Bergman on behalf of NuScale Power, LLC. The petition was docketed by the NRC on September 11, 2019, and was assigned Docket No. PRM-50-120. The petitioner requested that the NRC revise its regulations to add an alternative formula for calculating the mean value of the transition temperature shift described in American Society for Testing and Materials Standard E900-15 to the NRC's regulations and guidance documents. The NRC is denying the petition because the petitioner did not demonstrate the immediacy of any safety issues in the concerns raised in the petition and did not provide any new information that would warrant revision of the NRC's regulations.
The U.S. Nuclear Regulatory Commission (NRC) will consider in its rulemaking process issues raised in a petition for rulemaking (PRM), PRM-50-123, submitted by Thomas McKenna. The petitioner requested that the NRC amend its regulations to ensure protective actions in the event of a general emergency will likely do more good than harm.
The U.S. Nuclear Regulatory Commission (NRC) is amending its Program Fraud Civil Remedies Act (PFCRA) regulations to ensure compliance with the Administrative False Claims Act of 2023 (AFCA). The AFCA requires agencies to review and update existing regulations to ensure compliance with the AFCA amendments. This final rule includes changes to the NRC's PFCRA regulations required to meet the AFCA amendments and includes edits to correct typographical errors.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to revise the duration of design certifications (DCs). Specifically, this proposed rule would replace the 15-year duration for DCs with a 40-year duration period, both for existing DCs currently in effect and generically for future DCs, including renewals. This proposed rule would not change the date of issuance or renewal for existing DCs (i.e., the start date by which an existing DC may be referenced would remain unchanged). The proposed rule would also incorporate a minor editorial correction.
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to revise the duration of design certifications (DCs). Specifically, this direct final rule replaces the 15-year duration for DCs with a 40-year duration period, both for existing DCs currently in effect and generically for future DCs, including renewals. This direct final rule does not change the date of issuance or renewal for existing DCs (i.e., the start date by which an existing DC may be referenced remains unchanged). This direct final rule also incorporates a minor editorial correction.
The U.S. Nuclear Regulatory Commission (NRC) is amending the licensing, inspection, special project, and annual fees charged to its applicants and licensees. These amendments are necessary to comply with the Nuclear Energy Innovation and Modernization Act, which requires the NRC to recover, to the maximum extent practicable, approximately 100 percent of its annual budget, less certain amounts excluded from this fee recovery requirement. In addition, the NRC is making amendments to implement a reduced hourly rate for advanced nuclear reactor applicants and pre-applicants for certain activities as required by the Accelerating Deployment of Versatile, Advanced Nuclear for Clean Energy Act of 2024.
The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking (PRM) from Thomas Basso on behalf of the Nuclear Energy Institute, dated January 22, 2025, requesting that the NRC revise its regulations to remove specific conditions, clarify a specific requirement, and incorporate requested code cases to the next revisions of regulatory guides 1.84 and 1.147, which will be incorporated by reference into the agency's rulemaking on industry standards. The petition was docketed by the NRC on March 6, 2025, and has been assigned Docket No. PRM-50-127. The NRC is examining the issues raised in PRM-50-127 to determine whether they should be considered in rulemaking. The NRC is requesting public comment on this petition at this time.
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing a rulemaking activity, "Long-Term and Unattended Water Makeup of Spent Fuel Pools," and denying a petition for rulemaking. The petitioner requested that the NRC amend its regulations to require that nuclear power plant licensees ensure long-term cooling and unattended water makeup of spent fuel pools (SFPs). The purpose of this action is to inform members of the public that this rulemaking activity is being discontinued and to provide a brief discussion of the NRC's decision to discontinue the rulemaking and deny the aspects of the petition not previously addressed by the NRC.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of June 3, 2025, for the direct final rule that was published in the Federal Register on March 20, 2025. This direct final rule amended 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.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of May 27, 2025, for the direct final rule that was published in the Federal Register on March 13, 2025. This direct final rule amended 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 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.
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing its Policy Statement on the Treatment of Environmental Justice Matters in NRC Regulatory and Licensing Actions (Environmental Justice Policy Statement) and its Environmental Justice Strategy. The NRC is withdrawing these documents to reflect a recent executive order on Environmental Justice.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of May 13, 2025, for the direct final rule that was published in the Federal Register on February 27, 2025. This direct final rule amended the NAC International, Inc. Multi-Purpose Canister System listing within the "List of approved spent fuel storage casks" to include Amendment No. 9 and revisions to Amendment Nos. 6, 7, and 8 to Certificate of Compliance No. 1025.
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 3.65, "Standard Format and Content of Decommissioning Plans for Materials Licensees." This RG is being withdrawn because it is not needed to endorse NUREG-1757, "Consolidated Decommissioning Guidance: Decommissioning Process for Materials Licensees," Volume 1, "Decommissioning Process for Materials Licensees." NUREG-1757 provides the most current guidance on decommissioning nuclear facilities to support license termination for applicants, licensees, and NRC staff reviewers.
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comments a proposed Interim Enforcement Policy (IEP) titled, "Enforcement Discretion for General Licensee Adoption of CoC Holder- Generated Changes." This proposed IEP would allow enforcement discretion for certain general licensee violations related to their adoption of a change generated by the Certificate of Compliance holder.
The U.S. Nuclear Regulatory Commission (NRC) is correcting a proposed rule that was published in the Federal Register on March 20, 2025, 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. This action is necessary to replace an incorrect phrase in the Summary caption of the document.
The U.S. Nuclear Regulatory Commission (NRC) is correcting a direct final rule that was published in the Federal Register on March 20, 2025, 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. This action is necessary to replace an incorrect phrase in the SUMMARY caption of the document.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend 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.
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.
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.
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.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend 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.
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-1423, "Emergency Response Planning and Preparedness for Nuclear Power Reactors." This DG is proposed Revision 7 of Regulatory Guide (RG) 1.101, "Emergency Response Planning and Preparedness for Nuclear Power Reactors." This proposed revision would endorse Revision 1 of the Nuclear Energy Institute (NEI) white paper, "Enabling a Remote Response by Members of an Emergency Response Organization," dated September 2024, and Revision 7 of NEI 99-01, "Development of Emergency Action Levels for Non-Passive Reactors," dated September 2024.
Applicability of Requirements During the Movement of Radioactive Material Within a Temporary Jobsite
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.
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.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend the licensing, inspection, special project, and annual fees charged to its applicants and licensees. The proposed amendments are necessary to comply with the Nuclear Energy Innovation and Modernization Act, which requires the NRC to recover, to the maximum extent practicable, approximately 100 percent of its annual budget less certain amounts excluded from this fee recovery requirement. In addition, the NRC is proposing amendments to implement a reduced hourly rate for advanced nuclear reactor applicants and pre-applicants for certain activities as required by the Accelerating Deployment of Versatile, Advanced Nuclear for Clean Energy Act of 2024.