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Browse 69 rules and proposed rules from the Federal Register.
69
Total Regulations
Showing 1–30 of 69
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The U.S. Nuclear Regulatory Commission (NRC) plans to hold a virtual-only public meeting to discuss the proposed revisions to the agency's rules of practice and procedure to streamline contested adjudications in NRC licensing proceedings.
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations that implement the Freedom of Information Act (FOIA) to provide clarity, promote agency accountability, improve efficiency in responding to FOIA requests, update roles and responsibilities, and align the regulations with current Federal best practices for implementing FOIA. This final rule addresses the Department of Justice (DOJ) recommendation that the NRC update its FOIA regulations and incorporate the DOJ's model language for FOIA regulations, where appropriate. The NRC is not soliciting public comment for these changes because the change is limited to an agency rule of procedure and practice.
The U.S. Nuclear Regulatory Commission (NRC, agency, or Commission) is proposing to revise the agency's rules of practice and procedure to streamline contested adjudications in NRC licensing proceedings in response to the Accelerating Deployment of Versatile, Advanced Nuclear for Clean Energy Act of 2024 (ADVANCE Act) and Executive Order 14300, Ordering the Reform of the Nuclear Regulatory Commission.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference the 2023 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. This action is in accordance with the NRC's policy to periodically update the regulations to incorporate by reference new editions of the ASME Codes and is intended to maintain the safety of nuclear power plants and to make NRC activities more effective and efficient. The NRC also is proposing to amend its regulations to incorporate by reference proposed revisions of three regulatory guides, which would approve new, revised, and reaffirmed code cases published by the ASME. This proposed action would allow nuclear power plant licensees and applicants to use the code cases listed in these draft regulatory guides as voluntary alternatives to engineering standards for the construction, inservice inspection, and inservice testing of nuclear power plant components. This proposed rule also incorporates minor editorial corrections. The NRC is requesting comments on this proposed rule, on the draft versions of three regulatory guides, and the draft version of an additional regulatory guide which will not be incorporated by reference.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to augment the existing byproduct material framework to be inclusive of fusion machines. The NRC is proposing requirements that are technology-inclusive to accommodate the wide variety of anticipated fusion machine designs across the National Materials Program. The NRC is also issuing for comment draft guidance for the implementation of this proposed rule, entitled NUREG-1556, Volume 22, "Consolidated Guidance About Materials Licenses: Program- Specific Guidance About Fusion Machine Licenses." The NRC will conduct at least one public meeting to promote full understanding of the proposed rule and to facilitate public comments. We seek comment on all aspects of this proposed rule.
The U.S. Nuclear Regulatory Commission (NRC) is discontinuing three rulemaking activities. The purpose of this action is to inform members of the public that these rulemaking activities are being discontinued and to provide a brief discussion of the NRC's decision to discontinue them. These rulemaking activities will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).
The U.S. Nuclear Regulatory Commission (NRC) is correcting a document published in the Federal Register on January 8, 2026, regarding the confirmation of effective date for the direct final rule published in the Federal Register on December 3, 2025, amending the NRC's regulations to insert a conditional sunset date into certain regulations in response to Executive Order 14270, "Zero-Based Regulatory Budgeting to Unleash American Energy." This action is necessary to correct the number of comments docketed on the companion proposed rule.
The U.S. Nuclear Regulatory Commission (NRC) published two direct final rules in the Federal Register, which amended its spent fuel storage regulations by revising the NUHOMS[supreg] EOS Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment Nos. 3 and 4 to Certificate of Compliance No. 1042 on May 2, 2023 (88 FR 39119), and July 29, 2025 (90 FR 35640), respectively. Amendment No. 3 became effective on July 17, 2023, and Amendment No. 4 became effective on October 14, 2025. The technical specifications for the NUHOMS[supreg] EOS Dry Spent Fuel Storage System, Amendment Nos. 3 and 4 contained a typographical error. The purpose of this action is to correct the errors. The final rule contained minor errors in grammar, punctuation, and referencing. This document corrects the final rule by revising the sections that contain these errors.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of February 23, 2026, for the direct final rule that was published in the Federal Register on December 8, 2025. This direct final rule amended the certificate of compliance (CoC) to correct licensing basis deficiencies and updated the address in the CoC to reflect the new address of the applicant's headquarters offices.
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the TN Americas LLC, NUHOMS[supreg] Extended Optimized Storage (EOS) Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 5 to Certificate of Compliance (CoC) No. 1042. Amendment No. 5 revises the CoC to add a new heat load zone configuration (HLZC) for the EOS-37PTH canister, increasing the maximum heat load to 54 kW per dry shielded canister (DSC) for storage in the EOS-Horizontal Storage Module (HSM) and transfer using EOS-Transfer Casks (TC)125/135; clarifies acceptance criteria for minor surface imperfections on high strength low-alloy (HSLA) basket plates in the Updated Final Safety Analysis Report (UFSAR); and makes editorial updates to the UFSAR and Technical Specification (TS) revisions to align with Amendment No. 4, improve readability, and correct code references.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the TN Americas LLC, NUHOMS[supreg] Extended Optimized Storage (EOS) Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 5 to Certificate of Compliance (CoC) No. 1042. Amendment No. 5 would revise the CoC to add a new heat load zone configuration for the EOS-37PTH canister, increasing the maximum heat load to 54 kW per dry shielded canister for storage in the EOS- Horizontal Storage Module and transfer using EOS-Transfer Casks TC125/ 135; clarify acceptance criteria for minor surface imperfections on high strength low-alloy basket plates in the Updated Final Safety Analysis Report (UFSAR); and make editorial updates to the UFSAR and Technical Specification revisions to align with Amendment No. 4, improve readability, and correct code references.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of January 26, 2026, for the direct final rule that was published in the Federal Register on September 26, 2025. This direct final rule amended the regulations to incorporate by reference a regulatory guide that approved unconditioned code cases published by the American Society of Mechanical Engineers. This action allows nuclear power plant applicants and licensees to use the code cases as voluntary alternatives to engineering standards for nuclear power plant components.
The U.S. Nuclear Regulatory Commission (NRC) plans to hold a public meeting to discuss the recently published proposed rule that proposes amending its regulations to incorporate by reference the Institute of Electrical and Electronics Engineers Standard (Std) 603- 2018, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations," and the accompanying Draft Regulatory Guide (DG) DG-1251, Revision 1, "Guidance for the Power, Instrumentation, and Control Portions of Safety Systems for Nuclear Power Plants."
The U.S. Nuclear Regulatory Commission (NRC) is issuing an interpretation of its regulations to include non-power production or utilization facilities (NPUFs) licensed under section 103 of the Atomic Energy Act of 1954, as amended (AEA), within the scope of the NRC's backfitting regulations and to exclude non-commercial NPUFs licensed under section 104 of the AEA from the scope of the NRC's backfitting regulations. The interpretation is effective immediately with a 30-day post-promulgation comment period.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of January 8, 2026, for the direct final rule that was published in the Federal Register on December 3, 2025, except for one provision that is being withdrawn. This direct final rule amended the NRC's regulations to insert a conditional sunset date into certain regulations in response to Executive Order 14270, "Zero-Based Regulatory Budgeting to Unleash American Energy." The NRC is withdrawing an amendment that would have established a conditional sunset date to the NRC's provisions for aircraft impact assessment.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603-2018, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." The IEEE Std 603-2018 is the most recent version of IEEE Std 603 that addresses the power, instrumentation, and control safety systems for nuclear power reactors. This amendment also incorporates editorial changes that do not change the technical information. The NRC plans to hold a public meeting to promote full understanding of the proposed rule and facilitate public comments.
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel regulations by revising the NAC International, Inc., NAC- UMS[supreg] Universal Storage System (NAC-UMS[supreg]) design listing within the "List of approved spent fuel storage casks" to include Renewed Amendment No. 10, and to revise Renewed Amendment Nos. 5 through 9 to Certificate of Compliance No. 1015. The addition of Renewed Amendment No. 10 and Revision 1 to Renewed Amendment Nos. 5 through 9 for the certificate of compliance (CoC) corrects licensing basis deficiencies and updates the address in the CoC to reflect the new address of the applicant's headquarters offices.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel regulations by revising the NAC International, Inc., NAC-UMS[supreg] Universal Storage System (NAC-UMS[supreg]) design listing within the "List of approved spent fuel storage casks" to include Renewed Amendment No. 10, and to revise Renewed Amendment Nos. 5 through 9 to Certificate of Compliance (CoC) No. 1015. The addition of Renewed Amendment No. 10 and Revision 1 to Renewed Amendment Nos. 5 through 9 of the certificate of compliance would correct licensing basis deficiencies and update the address in the CoC to reflect the new address of the applicant's headquarters offices.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to insert a conditional sunset date into certain regulations in response to Executive Order (E.O.) 14270, "Zero-Based Regulatory Budgeting to Unleash American Energy."
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to insert a conditional sunset date into certain regulations in response to Executive Order (E.O.) 14270, "Zero-Based Regulatory Budgeting to Unleash American Energy."
The U.S. Nuclear Regulatory Commission (NRC) is rescinding a discrete number of regulations regarding agency rules of practice and procedure for general hearing management, formal adjudications, and administrative tort claims because they are either inconsistent with statutory requirements or duplicative of statutory requirements and other binding regulations. The NRC is not soliciting public comment on these changes because the changes are limited to agency rules of procedure and practice that do not affect the substantive rights and responsibilities of outside parties.
This notice is announcing that on September 25, 2025, David A. Wright, Chairman of the U.S. Nuclear Regulatory Commission (NRC or Commission), and Governor Edward Miner Lamont, Jr. of the State of Connecticut, signed an Agreement as authorized by Section 274b. of the Atomic Energy Act of 1954, as amended (the Act). Under the Agreement, the Commission discontinues its regulatory authority, and the State of Connecticut assumes regulatory authority over 11e.(1), 11e.(3), and 11e.(4) byproduct materials, source materials, and special nuclear materials in quantities not sufficient to form a critical mass.
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference a regulatory guide that approves unconditioned code cases published by the American Society of Mechanical Engineers (ASME). This action would allow nuclear power plant applicants and licensees to use the code cases as voluntary alternatives to engineering standards for nuclear power plant components. These standards are set forth in the ASME Boiler and Pressure Vessel Code and ASME Operation and Maintenance of Nuclear Power Plants, which are currently incorporated by reference into the NRC's regulations. The NRC is requesting comments on this proposed rule.
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to incorporate by reference a regulatory guide that approves unconditioned code cases published by the American Society of Mechanical Engineers (ASME). This action allows nuclear power plant applicants and licensees to use the code cases as voluntary alternatives to engineering standards for nuclear power plant components. These standards are set forth in the ASME Boiler and Pressure Vessel Code and ASME Operation and Maintenance of Nuclear Power Plants, which are currently incorporated by reference into the NRC's regulations.
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 7 to Regulatory Guide (RG) RG-1.101, "Emergency Response Planning and Preparedness for Nuclear Power Reactors." This revision updates the list of NRC-developed and NRC-endorsed guidance documents acceptable to meet the regulatory requirements for emergency response planning and preparedness. This revision also provides generic guidance for maintaining regulatory compliance for alert and notification systems (ANS) when making significant design changes, as well as provides guidance on a method to justify a 24-month frequency for emergency plan reviews.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of October 14, 2025, for the direct final rule that was published in the Federal Register on July 29, 2025. The direct final rule amended the TN Americas LLC, NUHOMS[supreg] EOS Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 4 to Certificate of Compliance No. 1042.
The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of September 15, 2025, for the direct final rule published in the Federal Register on July 2, 2025. This direct final rule amended the NRC's regulations to revise the duration of design certifications (DCs). This action replaced the 15-year duration for DCs with a 40-year duration period, both for existing DCs currently in effect and generically for future DCs. This direct final rule did not change the date of issuance for existing DCs (i.e., the start date by which an existing DC may be referenced remains unchanged). This direct final rule also incorporated a minor editorial correction.
The U.S. Nuclear Regulatory Commission (NRC) is issuing an Interim Enforcement Policy (IEP) titled, "Enforcement Discretion for General Licensee Adoption of CoC Holder-Generated Changes." This IEP allows 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 proposing to amend its spent fuel storage regulations by revising the TN Americas LLC, NUHOMS[supreg] EOS Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 4 to Certificate of Compliance No. 1042. Amendment No. 4 would change the certificate of compliance to incorporate a method to determine new loading patterns, introduce a steel plate composite option, introduce the use of MAVRIC software for a confirmatory run of the HSM-MX dose rates, make technical specification changes for consistency and terminology clarification, make various updated final safety analysis report editorial corrections for consistency and clarification, add measured exposures from past loading campaigns, allow use of a blended Portland cement, change the use of the MX- Loading Crane, and clarify the scenarios under which the maximum heat loads can be reduced.
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the TN Americas LLC, NUHOMS[supreg] EOS Dry Spent Fuel Storage System listing within the "List of approved spent fuel storage casks" to include Amendment No. 4 to Certificate of Compliance No. 1042. Amendment No. 4 changes the certificate of compliance to incorporate a method to determine new loading patterns, introduce a steel plate composite option, introduce the use of MAVRIC software for a confirmatory run of the HSM-MX dose rates, make technical specification changes for consistency and terminology clarification, make various updated final safety analysis report editorial corrections for consistency and clarification, add measured exposures from past loading campaigns, allow use of a blended Portland cement, change the use of the MX-Loading Crane, and clarify the scenarios under which the maximum heat loads can be reduced.