ML24219A049
| ML24219A049 | |
| Person / Time | |
|---|---|
| Issue date: | 08/15/2024 |
| From: | Christopher Hanson NRC/Chairman |
| To: | Comer J, Rodgers C US HR, Comm on Energy & Commerce, US HR, Comm on Oversight and Accountability |
| Carrie McCann | |
| Shared Package | |
| ML24200A307 | List: |
| References | |
| CORR-24-0070, LTR-24-0167 | |
| Download: ML24219A049 (1) | |
Text
NRC Documents (Interpretive Rules Category) 1 of 44 Publication Date Type Title Abstract Citation 7/17/24 Draft Regulatory Guide Draft Regulatory Guide:
Acceptable ASME Section XI Inservice Inspection Code Cases The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-3058. This DG is a proposed new Regulatory Guide (RG) 3.78 and provides applicants and licensees with methods that the NRC staff considers acceptable for specific or general independent spent fuel storage installation (ISFSI) licensees and certificate of compliance (CoC) holders to comply with NRC regulations for inservice inspection of confinement boundary components and aging management activities associated with the renewals of ISFSIs, general licensees, and CoC holders for spent fuel storage systems.
89 FR 58080 7/17/24 Regulatory Guide; Final Rule American Society of Mechanical Engineers Code Cases and Update Frequency The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to incorporate by reference revisions of three regulatory guides to approve new, revised, and reaffirmed code cases published by the American Society of Mechanical Engineers. This action allows nuclear power plant licensees and applicants for construction permits, operating licenses, combined licenses, standard design certifications, standard design approvals, and manufacturing licenses to use the code cases listed in these regulatory guides as voluntary alternatives to engineering standards for the construction, inservice inspection, and inservice testing of nuclear power plant components. These engineering standards are set forth in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code and American Society of Mechanical Engineers Operation and Maintenance Code, which are currently incorporated by reference into the NRC's regulations. Further, this final rule announces the availability of a related regulatory guide, not incorporated by reference into the NRC's regulations, that lists code cases that the NRC has not approved for use. Finally, this rulemaking provides more flexibility to licensees by expanding the code of record interval from ten years to two consecutive inservice testing and inservice inspection intervals.
89 FR 58039 7/15/24 Draft Regulatory Guide Draft Regulatory Guides:
Design-Basis Floods for Nuclear Power Plants and Guidance for Assessment of Flooding Hazards Due to Water Control Structure Failures and Incidents The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment two related draft Regulatory Guides (DG) namely DG-1290, Revision 1, "Design-Basis Floods for Nuclear Power Plants," proposed Revision 3 of Regulatory Guide (RG) 1.59 of the same name and DG-1417, "Guidance for Assessment of Flooding Hazards due to Water Control Structure Failures and Incidents," proposed new RG 1.256. DG-1290 provides guidance for applicants for new nuclear power plants (NPPs) on acceptable methods for evaluating design-basis floods and DG-1417 provides guidance for applicants on flooding hazards due to failure or other incidents at man-made water control structures including, but not limited to, dams and levees.
89 FR 57372 7/8/24 Regulatory Issue Summary Required Assessment of U.S. Department of Energy Laboratories by Licensees, Applicants, and Suppliers To Verify the Effective Implementation of Their Quality Assurance Programs The U.S. Nuclear Regulatory Commission (NRC) is issuing Regulatory Issue Summary (RIS) 2024-02, "Required Assessment of U.S. Department of Energy Laboratories by Licensees, Applicants, and Suppliers to Verify the Effective Implementation of Their Quality Assurance Programs." RIS 2024-02 clarifies the agency's regulatory position regarding the required assessment of U.S. Department of Energy national laboratories by licensees, applicants, and vendors to verify the effective implementation of the laboratories' quality assurance programs.
NRC Documents (Interpretive Rules Category) 2 of 44 Publication Date Type Title Abstract Citation 6/11/24 Regulatory Guide Regulatory Guide:
Qualification of Class 1E Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG),
1.210, "Qualification of Class 1E Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Production and Utilization Facilities." This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for the qualification of safety related or Class 1E battery chargers, inverters, and uninterruptible power supply systems for production and utilization facilities.
89 FR 49083 5/16/24 Regulatory Guide Regulatory Guide:
Suspicious Activity Reports The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.87, "Suspicious Activity Reports." This RG provides an approach acceptable to the NRC staff for licensees to use for reporting suspicious activity under NRC regulations, "Physical Protection of Plants and Materials", to local law enforcement, the Federal Bureau of Investigation, the NRC, and the Federal Aviation Administration.
89 FR 42767 4/29/24 Regulatory Guide Regulatory Guide:
Dedication of Commercial-Grade Items for Use in Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.164, "Dedication of Commercial-Grade Items for Use in Nuclear Power Plants." This RG describes methods that the staff of the NRC considers acceptable in meeting regulatory requirements for the dedication of commercial grade items and services used in nuclear power plants.
89 FR 33183 4/25/24 Regulatory Guide Regulatory Guide:
Installation Design and Installation of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG) 1.128, "Installation Design and Installation of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities." This RG describes an approach that is acceptable to the NRC staff to meet regulatory requirements for the installation design and installation of vented lead-acid storage batteries in production and utilization facilities.
89 FR 31601 4/25/24 Regulatory Guide Regulatory Guide:
Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.30, "Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Production and Utilization Facilities." This RG describes an approach that is acceptable to the NRC staff to meet the regulatory requirements for installation, inspection, and testing for Class 1E power, instrumentation, and control equipment at production and utilization facilities.
NRC Documents (Interpretive Rules Category) 3 of 44 Publication Date Type Title Abstract Citation 4/24/24 Regulatory Guide Regulatory Guide:
Preemption Authority, Enhanced Weapons Authority, and Firearms Background Checks The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.86, "Preemption Authority, Enhanced Weapons Authority, and Firearms Background Checks." This RG clarifies reporting and recording of security events and conditions adverse to security under NRC regulations, "Physical Protection of Plants and Materials."
89 FR 31077 4/3/24 Regulatory Guide Regulatory Guide:
Guidance for a Technology-Inclusive Content of Application Methodology To Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.253, Revision 0, "Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors." This new RG provides guidance to assist interested parties and prospective applicants in the development of content for major portions of their safety analysis reports required in applications for permits, licenses, certifications, and approvals by the NRC to ensure that applications for non-light water reactor (non-LWR) facility designs using the Licensing Modernization Project (LMP) process meet the minimum requirements for construction permit, operating license, combined license, or design certification applications.
89 FR 22912 3/26/24 Regulatory Guide Regulatory Guide:
Evaluating Deviations and Reporting Defects and Noncompliance The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.234, "Evaluating Deviations and Reporting Defects and Noncompliance." This RG describes methods that the staff of the NRC considers acceptable for complying with the provisions of NRC regulations.
89 FR 20845 2/29/24 Regulatory Guide Regulatory Guide: General Site Suitability for Nuclear Power Stations The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG), 4.7, "General Site Suitability for Nuclear Power Stations." Revision 4 to RG 4.7 describes the major site characteristics related to public health and safety and environmental issues that the NRC staff considers in determining the suitability of sites for commercial nuclear power stations.
89 FR 14743 2/29/24 Draft Regulatory Guide Draft Regulatory Guide:
Preparing Probabilistic Fracture Mechanics Submittals The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-1422, "Preparing Probabilistic Fracture Mechanics Submittals." This DG is proposed Revision 1 to Regulatory Guide (RG) 1.245, "Preparing Probabilistic Fracture Mechanics Submittals."
DG-1422 describes an approach that is acceptable to the staff of the NRC for performing probabilistic fracture mechanics (PFM) analyses in support of regulatory applications.
89 FR 14782 2/7/24 Regulatory Guide Regulatory Guide:
Guidelines for Lightning Protection for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG),
1.204, "Guidelines for Lightning Protection for Production and Utilization Facilities." This regulatory guide (RG) revision endorses, with clarifications and exceptions, the methods described in four Institute of Electrical and Electronics Engineers (IEEE) Standards (Std.). This revision also addresses one National Fire Protection Association standard and one Underwriters Laboratory standard as useful secondary references for demonstrating compliance with the applicable NRC regulations for adequate lightning protection of safety-related systems, structures, and components.
NRC Documents (Interpretive Rules Category) 4 of 44 Publication Date Type Title Abstract Citation 2/6/24 Staff Guidance; ISG Interim Staff Guidance:
Material Compatibility for Non-Light Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2023-01 "Material Compatibility for non-Light Water Reactors." The purpose of this ISG is to assist the NRC staff in reviewing certain applications for construction and operation of non-light water reactor designs, including power and non-power reactors.
89 FR 8065 1/26/24 Regulatory Guide Regulatory Guide:
Qualification of Safety-Related Actuators in Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.73, "Qualification of Safety-Related Actuators in Production and Utilization Facilities." This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for the qualification of safety-related actuators for production and utilization facilities.
89 FR 5087 1/12/24 Policy Statement Revision of the NRC Enforcement Policy The U.S. Nuclear Regulatory Commission (NRC) is publishing a revision to its Enforcement Policy.
This revision addresses the requirements of the Federal Civil Penalties Inflation Adjustment Act Improvements Act of 2015, which requires Federal agencies to adjust their maximum civil monetary penalty amounts annually for inflation.
89 FR 2111 1/8/24 Draft Regulatory Guide Draft Regulatory Guide:
Installation Design and Installation of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-1421, "Installation Design and Installation of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities." This DG is proposed Revision 3 of Regulatory Guide 1.128, "Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants,"
and provides methods acceptable to the NRC to meet regulatory requirements for the installation design and installation of vented lead-acid storage batteries in production and utilization facilities. It endorses, with clarifications, the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 484-2019, "IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications."
89 FR 895 12/20/23 Draft Regulatory Guide Draft Regulatory Guide:
Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1419, "Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Production and Utilization Facilities." This DG is proposed Revision 1 to Regulatory Guide (RG) 1.30, "Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30)." DG-1419 describes an approach that is acceptable to the NRC staff to meet the regulatory requirements for installation, inspection, and testing for Class 1E power, instrumentation, and control equipment at production and utilization facilities.
88 FR 87967 12/11/23 Regulatory Guide Regulatory Guide:
Damping Values for Seismic Design of Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG),
1.61, "Damping Values for Seismic Design of Nuclear Power Plants." This RG provides guidance on damping values that the NRC staff finds acceptable for use in the seismic response analysis of seismic Category I nuclear power plant structures, systems, and components. The specified damping values are intended for elastic dynamic seismic analysis where energy dissipation is accounted for by viscous damping.
NRC Documents (Interpretive Rules Category) 5 of 44 Publication Date Type Title Abstract Citation 11/17/23 Draft Regulatory Guide Draft Regulatory Guide:
Dedication of Commercial-Grade Items for Use in Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-1415, "Dedication of Commercial-Grade Items for Use in Nuclear Power Plants."
This DG is the proposed Revision 1 of Regulatory Guide (RG) 1.164 of the same title. This DG describes methods that the NRC staff considers acceptable in meeting regulatory requirements for dedication of commercial-grade items and services used in nuclear power plants.
88 FR 80195 11/17/23 Draft Regulatory Guide Draft Regulatory Guide:
Evaluating Deviations and Reporting Defects and Noncompliance The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-1416, "Evaluating Deviations and Reporting Defects and Noncompliance." This DG is the proposed Revision 1 of Regulatory Guide (RG) 1.234 of the same title. It describes methods that the NRC staff considers acceptable for complying with the provisions of NRC regulations.
88 FR 80196 11/16/23 Regulatory Guide; Final Rule Emergency Preparedness for Small Modular Reactors and Other New Technologies The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to include new alternative emergency preparedness requirements for small modular reactors and other new technologies. This final rule acknowledges technological advancements and other differences from large light-water reactors that are inherent in small modular reactors and other new technologies. The NRC is concurrently issuing Regulatory Guide 1.242, "Performance-Based Emergency Preparedness for Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities."
88 FR 80050 11/8/23 Regulatory Guide Regulatory Guide: Fire Protection for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 5 to Regulatory Guide (RG) 1.189, "Fire Protection for Nuclear Power Plants." It is being issued to correct typographic errors that appeared in RG 1.189, Revision 4 of the same name. In addition, Revision 5 contains edits to conform with the current template for RGs and fixes to a few reference numbering errors. The changes in Revision 5 are intended to improve clarity and do not substantially alter the staff's regulatory guidance.
88 FR 76989 10/30/23 Draft Regulatory Guide Draft Regulatory Guide:
Preemption Authority, Enhanced Weapons Authority, and Firearms Background Checks The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-5081, "Preemption Authority, Enhanced Weapons Authority, and Firearms Background Checks." This DG-5081 is proposed Revision 1 of Regulatory Guide (RG) 5.86 of the same name. This DG provides an approach acceptable to the NRC staff for use by licensees under NRC regulations, "Physical Protection of Plants and Materials," regarding stand-alone preemption authority, combined preemption authority and enhanced weapons authority, and firearms background checks.
88 FR 74070 10/27/23 Draft Regulatory Guide Draft Regulatory Guide:
Physical Security Event Notifications, Reports, and Records The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-5080, "Physical Security Event Notifications, Reports, and Records." This DG-5080 is a limited-scope proposed Revision 3 of Regulatory Guide (RG) 5.62 of the same name. This DG provides an approach acceptable to the NRC staff for licensees to use for reporting and recording of security events and conditions adverse to security under NRC regulations, "Physical Protection of Plants and Materials."
NRC Documents (Interpretive Rules Category) 6 of 44 Publication Date Type Title Abstract Citation 10/27/23 Draft Regulatory Guide Draft Regulatory Guide:
Suspicious Activity Reports The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft Regulatory Guide (DG), DG-5082, "Suspicious Activity Reports." This DG-5082 is proposed Revision 1 of Regulatory Guide (RG) 5.87 of the same name. This DG provides an approach acceptable to the NRC staff for licensees to use for reporting suspicious activity under NRC regulations, "Physical Protection of Plants and Materials," to local law enforcement, the Federal Bureau of Investigation, the NRC, and the Federal Aviation Administration.
88 FR 73769 10/18/23 Draft Regulatory Guide Draft Regulatory Guide:
General Site Suitability Criteria for Nuclear Power Stations The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-4034, "General Site Suitability Criteria for Nuclear Power Stations." This DG is a proposed Revision 4 for Regulatory Guide (RG) 4.7 of the same name which describes the major site characteristics related to public health and safety and environmental issues that the NRC staff considers in determining the suitability of sites for commercial nuclear power stations.
88 FR 71777 10/16/23 Regulatory Guide Regulatory Guide:
Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG),
1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors." This RG describes a method that the NRC staff considers acceptable in complying with regulations for design basis accident dose consequence analysis using an alternative source term. This guidance for light-water reactor (LWR) designs includes the scope, nature, and documentation of associated analyses and evaluations; consideration of impacts on analyzed risk; and content of submittals.
88 FR 71277 10/6/23 Draft Regulatory Issue Summary Required Assessment of U.S. Department of Energy Laboratories by Licensees, Applicants, and Suppliers To Verify the Effective Implementation of Their Quality Assurance Programs The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) that clarifies the agency's regulatory position regarding the required assessment of U.S. Department of Energy (DOE) national laboratories by licensees, applicants, and vendors to verify the effective implementation of the laboratories' quality assurance (QA) programs.
This draft RIS requires no action or written response on the part of an addressee.
88 FR 69555 9/29/23 Regulatory Guide Regulatory Guide: Weather Related Administrative Controls at Independent Spent Fuel Storage Installations The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 3.77 (Revision 0), "Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations." This RG provides applicants and licensees with methods that the NRC staff considers acceptable for specific or general independent spent fuel storage installation licensees and certificate of compliance holders to comply with NRC regulations for protection against environmental conditions and natural phenomena.
NRC Documents (Interpretive Rules Category) 7 of 44 Publication Date Type Title Abstract Citation 9/29/23 Regulatory Issue Summary Consideration of Current Operating Issues and Licensing Actions in License Renewal The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Issue Summary (RIS) 2014-06, "Consideration of Current Operating Issues and Licensing Actions in License Renewal." Revision 1 to RIS 2014-06 provides information to the addressees on how the NRC considers current operating issues in the license renewal review under NRC regulations. This RIS is intended for all holders of operating licenses and combined licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel. NRC regulations identify the technical information that must be submitted in a license renewal application to enable the NRC staff to make a determination that the license may be renewed. Pursuant to the regulations, an applicant is required to demonstrate that the effects of aging on the functionality of structures and components subject to an aging management review will be adequately managed; the consideration of recent operating experience is an important aspect of that demonstration. In addition, as required by NRC regulations, license renewal applicants need to update their applications with new information related to any current licensing basis changes during the NRC application review that could impact aging management of structures and components.
88 FR 67066 9/11/23 Regulatory Guide Regulatory Guide: Quality Assurance Program Criteria (Design and Construction)
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 6 to Regulatory Guide (RG),
1.28, "Quality Assurance Program Criteria (Design and Construction)". RG 1.28, Revision 6, endorses, with certain clarifications and regulatory positions, Part I and Part II requirements included in NQA-1-2017, NQA-1-2019, and NQA-1-2022 for the implementation of a quality assurance (QA) program during the design and construction phases of nuclear power plants and fuel reprocessing plants.
88 FR 62292 9/8/23 Draft Regulatory Guide Draft Regulatory Guide:
Guidance for a Technology-Inclusive Content-of-Application Methodology To Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on Appendix B and conforming changes to other parts of its draft Regulatory Guide (DG), DG-1404, Revision 1 "Guidance for a Technology-Inclusive Content-of-Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors." On May 25, 2023, the NRC published Revision 0 to DG-1404 requesting public comment, and on June 28, 2023, the NRC extended the public comment period to August 10, 2023. Since then, and consistent with item 1 in Appendix A to DG-1404, Revision 0, the NRC completed its development of Appendix B and revised DG-1404 (i.e., Revision 1) to include this appendix and made conforming changes to other parts of the document. Appendix B provides additional guidance for the scope, level of detail, elements, and plant representation for a probabilistic risk assessment (PRA) supporting a Licensing Modernization Project (LMP)-based construction permit application.
NRC Documents (Interpretive Rules Category) 8 of 44 Publication Date Type Title Abstract Citation 8/21/23 Regulatory Guide Regulatory Guide: Use of ARCON Methodology for Calculation of Accident-Related Offsite Atmospheric Dispersion Factors The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.249 (Revision 0), "Use of ARCON Methodology for Calculation of Accident-Related Offsite Atmospheric Dispersion Factors." This new RG describes an approach for reactor applicants and licensees for determining atmospheric relative concentration ([chi]/Q) values in support of modeling onsite releases to offsite boundaries from a design-basis accident. Also, this RG implements the methodology in RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," for offsite dose locations at boundaries.
88 FR 56750 8/21/23 Regulatory Guide Regulatory Guide: Volcanic Hazards Assessment for Proposed Nuclear Power Reactor Sites The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 4.26 "Volcanic Hazards Assessment for Proposed Nuclear Power Reactor Sites," to restore text and a Section heading inadvertently omitted from Section C, "Staff Regulatory Guidance," of Revision 0.
The restored text appeared in the draft guide released for public comment. In addition, there is a minor update of the Paperwork Reduction Act text in the RG. The changes do not represent substantive changes in the NRC staff's regulatory positions.
88 FR 56752 7/28/23 Regulatory Guide Regulatory Guide:
Cybersecurity Event Notifications The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG),
5.83, "Cybersecurity Event Notifications." This revision describes methods that the staff of the NRC considers acceptable for licensees to meet requirements in NRC regulations to report and record cybersecurity events.
88 FR 48717 7/25/23 Regulatory Guide Regulatory Guide: Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG),
1.152, "Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants." This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for promoting high functional reliability, design quality, and a secure development and operational environment (SDOE) for the use of programmable digital devices (PDDs) in the safety-related systems of nuclear power generating stations.
88 FR 47754 7/25/23 Regulatory Guide Regulatory Guide: Use of Plant Parameter Envelope in Early Site Permit Applications for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 4.27, "Use of Plant Parameter Envelope in Early Site Permit Applications for Nuclear Power Plants." This RG provides guidance for nuclear power plant applicants that elect to use the plant parameter envelope concept to assume certain design parameters for an early site permit application when a specific reactor technology has not been selected for a proposed site.
88 FR 47755 7/12/23 Regulatory Guide Regulatory Guide:
Performance-Based Containment Leak-Test Program The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG),
1.163, "Performance-Based Containment Leak-Test Program." This RG provides guidance on an acceptable performance-based leak-test program and leakage rate test methods, procedures, and analyses that may be used to comply with "Option B--Performance-Based Requirements" in NRC regulations for primary reactor containment leakage testing for water-cooled power reactors.
NRC Documents (Interpretive Rules Category) 9 of 44 Publication Date Type Title Abstract Citation 6/21/23 Regulatory Guide Regulatory Guide: Sizing Large Lead-Acid Storage Batteries The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.212, "Sizing Large Lead-Acid Storage Batteries. This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for sizing large lead-acid storage batteries for production and utilization facilities 88 FR 39995 6/13/23 Draft Regulatory Guide Draft Regulatory Guide:
Damping Values for Seismic Design of Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1364, "Damping Values for Seismic Design of Nuclear Power Plants." This DG is proposed Revision 2 of Regulatory Guide (RG) 1.61. This DG describes an approach on damping values that is acceptable to the NRC staff for use in meeting regulatory requirements for the seismic response analysis of seismic Category I nuclear power plant structures, systems, and components.
88 FR 38408 6/5/23 Draft Regulatory Guide Draft Regulatory Guide:
Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-3057, "Weather-Related Administrative Controls at Independent Spent Fuel Storage Installations." This DG is a proposed new regulatory guide (RG) 3.77 and provides licensees with methods that the NRC staff considers acceptable for specific or general licensees of an independent spent fuel storage installation and certificate of compliance holders to comply with protection against environmental conditions and natural phenomena.
88 FR 36514 5/25/23 Draft Regulatory Guide Draft Regulatory Guide:
Guidance for a Technology-Inclusive Content of Application Methodology To Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Regulatory Guide (DG-1404), "Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors." This DG is a proposed new regulatory guide to provide guidance to assist interested parties and prospective applicants for the development of content for major portions of their safety analysis reports required in applications for licenses, certifications, and approvals by the NRC to ensure that non-light water reactor (non-LWR) facility designs using the Licensing Modernization Project (LMP) process meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33846 5/22/23 Draft Regulatory Guide Draft Regulatory Guide:
Qualification of Safety-Related Actuators in Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1386, "Qualification of Safety-Related Actuators in Production and Utilization Facilities." This DG is the proposed Revision 2 of Regulatory Guide (RG) 1.73 "Qualification Tests for Safety-Related Actuators in Nuclear Power Plants." This DG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for the environmental qualification of safety related actuators in production and utilization facilities. It endorses, with exceptions, additions, and clarifications, the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 382-2019, "IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations and Other Nuclear Facilities."
NRC Documents (Interpretive Rules Category) 10 of 44 Publication Date Type Title Abstract Citation 5/19/23 Policy Statement Abnormal Occurrence Reporting The U.S. Nuclear Regulatory Commission (NRC) is proposing limited revisions to its policy statement on reporting abnormal occurrences (AO) to Congress. The proposed revisions are to the medical event criteria for determining events that are significant from the standpoint of public health or safety.
88 FR 32144 5/3/23 Regulatory Guide Regulatory Guide:
Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.89, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants." RG 1.89, Revision 2 provides guidance that the staff of the NRC considers acceptable to meet regulatory requirements for environmental qualification (EQ) of certain electric equipment important to safety.
88 FR 27692 5/3/23 Draft Regulatory Guide Draft Regulatory Guide:
Quality Assurance Program Criteria (Design and Construction)
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1403, "Quality Assurance Program Criteria (Design and Construction)." This DG is proposed Revision 6 of Regulatory Guide (RG) 1.28 of the same name. The proposed revision endorses Nuclear Energy Institute (NEI)14-05A, "Guidelines for the Use of Accreditation in Lieu of Commercial Grade Surveys for Procurement of Laboratory Calibration and Test Services," Revision 1, issued November 2020, as an acceptable approach for licensees and suppliers subject to the quality assurance (QA) requirements of NRC regulations. Also in this proposed revision, the NRC staff endorses the Part I and Part II requirements included in NQA-1-2017, NQA-1-2019, and NQA 2022 for the implementation of a QA program during the design and construction phases of nuclear power plants and fuel reprocessing plants.
88 FR 27713 5/3/23 Draft Regulatory Guide Draft Regulatory Guide:
Guidelines for Lightning Protection for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1409, "Guidelines for Lightning Protection for Production and Utilization Facilities."
This DG is the proposed Revision 1 of Regulatory Guide (RG) 1.204, "Guidelines for Lightning Protection of Nuclear Power Plants." DG-1409 describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for adequate lightning protection of safety-related systems, structures, and components (SSCs). This DG endorses, with clarifications, the methods described in Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 665-1995, "IEEE Standard for Generating Station Grounding"; IEEE Std. 666-2007, "IEEE Design Guide for Electrical Power Service Systems for Generating Stations"; IEEE Std. 1050-2004, "IEEE Guide for Instrumentation and Control Equipment Grounding in Generating Stations"; and IEEE Std. C62.23-2017, "IEEE Application Guide for Surge Protection of Electric Generating Plants."
88 FR 27714 4/24/23 Draft Regulatory Guide Draft Regulatory Guide:
Cybersecurity Event Notifications The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-5079, "Cybersecurity Event Notifications." This DG is proposed Revision 1 to Regulatory Guide (RG) 5.83 of the same name. This proposed revision describes methods that the staff of the NRC considers acceptable for licensees to meet requirements in NRC regulations to report and record cybersecurity events.
NRC Documents (Interpretive Rules Category) 11 of 44 Publication Date Type Title Abstract Citation 4/21/23 Draft Regulatory Guide Draft Regulatory Guide:
Release of Patients Administered Radioactive Material The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-8061, "Release of Patients Administered Radioactive Material." This DG is proposed Revision 2 to Regulatory Guide (RG) 8.39 of the same name. This proposed revision provides licensees with methods that are acceptable to the NRC for the release of patients after a medical procedure involving the administration of unsealed byproduct material, such as radiopharmaceuticals, or implants that contain radioactive material.
88 FR 24495 3/27/23 Regulatory Guide Regulatory Guide:
Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 of Regulatory Guide (RG) 1.129, "Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Production and Utilization Facilities." This revised guidance provides information to manage vented lead-acid battery degradation such that a battery in service would retain its readiness for supporting design-basis events. It endorses, with certain clarifying regulatory positions, Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 450-2020, which provides the recommended maintenance, test schedules, and testing procedures intended to optimize the life and performance of permanently installed vented lead-acid storage batteries used for standby power applications. It also provides guidance to determine when batteries should be replaced.
88 FR 18005 3/10/23 Draft Regulatory Guide Draft Regulatory Guide:
Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1374, "Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants." This DG is proposed Revision 4 of Regulatory Guide (RG) 1.152, "Criteria for Use of Computers in Safety Systems of Nuclear Power Plants." DG-1374 describes an approach that is acceptable to the NRC staff to meet regulatory requirements for promoting high functional reliability, design quality, and a secure development and operational environment (SDOE) for the use of programmable digital devices (PDDs) in the safety-related systems of nuclear power generating stations.
88 FR 14957 3/7/23 Draft Regulatory Issue Summary Consideration of Current Operating Issues and Licensing Actions in License Renewal The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) concerning how the NRC considers current operation of a facility in the NRC's license renewal review under NRC regulations. NRC regulations identify the technical information that must be submitted in a license renewal application (LRA) to enable the NRC staff to make a determination that the license may be renewed. In part, an applicant is required to demonstrate that the effects of aging on the functionality of structures and components subject to an aging management review will be adequately managed; the consideration of recent operating experience is an important aspect of that demonstration. In addition, as required by NRC regulations, license renewal applicants need to update their applications with new information related to any current licensing basis changes that could impact aging management of structures and components.
NRC Documents (Interpretive Rules Category) 12 of 44 Publication Date Type Title Abstract Citation 3/6/23 Draft Regulatory Guide Draft Regulatory Guide:
Sizing of Large Lead-Acid Storage Batteries The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1418, "Sizing of Large Lead-Acid Storage Batteries." This DG is proposed Revision 2 of Regulatory Guide (RG) 1.212 of the same name. DG-1418 describes an approach that is acceptable to the NRC staff to meet regulatory requirements for sizing of large lead-acid storage batteries for production and utilization facilities. It endorses, with clarifications, the Institute of Electrical and Electronic Engineers (IEEE) Standard 485-2020, "IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications."
88 FR 13735 3/6/23 Draft Regulatory Guide; Proposed Rule American Society of Mechanical Engineers Code Cases and Update Frequency The U.S. Nuclear Regulatory Commission (NRC) 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 American Society of Mechanical Engineers. This proposed action would allow nuclear power plant licensees and applicants for construction permits, operating licenses, combined licenses, standard design certifications, standard design approvals, and manufacturing licenses 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. The NRC is requesting comments on this proposed rule and on the draft versions of the three regulatory guides proposed to be incorporated by reference. The NRC also is making available a related draft regulatory guide that lists code cases that the NRC has not approved for use. This draft regulatory guide will not be incorporated by reference into the NRC's regulations. In addition, this rulemaking proposes to extend the time periods required for licensees to update their codes of record.
88 FR 13717 3/3/23 NUREG Renewing Nuclear Power Plant Operating Licenses-Environmental Review The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its environmental protection regulations by updating the Commission's 2013 findings on the environmental effect of renewing the operating license of a nuclear power plant. The NRC proposes to redefine the number and scope of the environmental issues that must be addressed during the review of each application for license renewal. As part of this update, the NRC has prepared draft Revision 2 to NUREG-1437, "Generic Environmental Impact Statement for License Renewal of Nuclear Plants" (LR GEIS), to account for new information and to address the impacts of initial license renewals, which the previous versions considered, as well as first subsequent license renewals. The draft revised LR GEIS provides the technical basis for this proposed rule. The NRC is providing an opportunity for interested parties to submit comments on this proposed rule, the draft revised LR GEIS, and associated draft guidance.
88 FR 13329 2/21/23 Draft Regulatory Guide Draft Regulatory Guide:
Perimeter Intrusion Alarm Systems The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft Regulatory Guide (DG), DG-5065, "Perimeter Intrusion Alarm Systems." This DG is proposed Revision 4 to Regulatory Guide (RG) 5.44 of the same name. This proposed revision describes an approach acceptable to the NRC staff for meeting requirements in NRC regulations related to the functions of perimeter intrusion detection sensors and detection methods.
NRC Documents (Interpretive Rules Category) 13 of 44 Publication Date Type Title Abstract Citation 2/13/23 Regulatory Guide Qualification of Connection Assemblies for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 of Regulatory Guide (RG) 1.156, "Qualification of Connection Assemblies for Production and Utilization Facilities." This revised guide was updated to endorse "Institute of Electrical and Electronics Engineers" Std. 572-2019 to provide the latest technical information on approaches to satisfy the qualification requirements for connection assemblies. This includes guidance that when used in conjunction with the guidance in RG 1.89, "Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants," provides an acceptable method of demonstrating compliance with the NRC regulations pertaining to the environmental qualification of connectors, terminations, and environmental seals in combination with cables or wires as assemblies for service in production and utilization facilities to ensure that the connection assemblies can perform their safety functions.
Further, the revised guide modifies the title of the RG to include other nuclear facilities, as discussed in the RG Section A, under Applicability.
88 FR 9105 2/13/23 Regulatory Guide Cyber Security Programs for Nuclear Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.71, "Cyber Security Programs for Nuclear Power Reactors." Revision 1 incorporates references to industry guidance on identifying and protecting critical digital assets for safety-related, important to safety, balance of plant, and emergency preparedness equipment. It also clarifies guidance on defense-in-depth for cyber security and includes updated text based on the latest National Institute of Standards and Technology (NIST) and International Atomic Energy Agency (IAEA) cyber security guidance. Specifically, this revision clarifies issues identified from cyber security inspections, insights gained through the Security Frequently Asked Questions (SFAQ) process, documented cyber security attacks, new technologies, and new regulations. This revision also considers the changes in the most recent revision to the NIST Special Publications (SP) 800-53, upon which Revision 0 of Regulatory Guide (RG) 5.71, "Cyber Security Programs for Nuclear Facilities" was based.
88 FR 9117 2/7/23 Regulatory Guide Acceptability of ASME Code,Section III, Division 5, High Temperature Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG),
1.87, "Acceptability of ASME Code,Section III, Division 5, `High Temperature Reactors.' " This RG describes an approach that is acceptable to the NRC staff to assure the mechanical/structural integrity of components that operate in elevated temperature environments and that are subject to time-dependent material properties and failure modes. It endorses, with exceptions and limitations, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code (ASME Code)Section III, "Rules for Construction of Nuclear Facility Components," Division 5, "High Temperature Reactors," and Code Cases N-861, N-862, N-872, and N-898. The NRC is also issuing NUREG-2245, "Technical Review of the 2017 Edition of ASME Section III, Division 5, `High Temperature Reactors,' " that documents the NRC staff's review of the 2017 Edition of ASME Section III, Division 5, certain portions of the 2019 Edition, and Code Cases N-861 and N-862. The technical basis for the NRC's endorsement of Code Cases N-872 and N-898 is contained in Technical Letter Report (TLR)-RES/DE/REB-2022-01, "Review of Code Cases Permitting Use of Nickel-Based Alloy 617 in Conjunction with ASME Section III, Division 5."
NRC Documents (Interpretive Rules Category) 14 of 44 Publication Date Type Title Abstract Citation 2/1/23 Draft Regulatory Guide Qualification of Class 1E Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1412, "Qualification of Class 1E Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Production and Utilization Facilities." This DG is the proposed Revision 1 of Regulatory Guide (RG) 1.210, "Qualification of Safety-Related Battery Chargers and Inverters for Nuclear Power Plants." DG-1412 describes an approach that is acceptable to the NRC staff to meet regulatory requirements for the qualification of safety related or Class 1E battery chargers, inverters, and uninterruptible power supply systems for production and utilization facilities. It endorses Institute of Electrical and Electronic Engineers (IEEE) Standard (Std.) 650-2017, "IEEE Standard for Qualification of Class 1E Static Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Nuclear Power Generating Stations."
88 FR 6672 1/30/23 Responding to comments on an interpretation of its requirements; Proposed Rule; Discontinuation Industrial Radiographic Operations and Training The U.S. Nuclear Regulatory Commission (NRC) is responding to public comments on an interpretation of its requirements for industrial radiographic operations and Agreement State Compatibility Category change for these requirements published in the Federal Register on June 1, 2021. As a result of these actions, the NRC is discontinuing a planned rulemaking activity and is denying an associated petition for rulemaking, PRM-34-6.
88 FR 5811 11/15/22 Regulatory Issue Summary Operational Leakage The U.S. Nuclear Regulatory Commission (NRC) is issuing Regulatory Issue Summary (RIS) 2022-02, "Operational Leakage." This RIS clarifies the NRC staff's position on the NRC requirements for evaluation, control, and treatment of operational leakage in systems required to be operable by plant technical specifications (TS). This RIS is intended for all holders of operating licenses and combined licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel. This RIS emphasizes that operational leakage must be addressed in the same manner as leakage detected during an American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code,Section XI, pressure test. That is, when operational leakage is found in a system that is within the scope of ASME BPV Code,Section XI, and is required to be operable by plant TS, the component must be evaluated by the licensee for operability. Structural integrity determinations must be conducted in accordance with the applicable provisions of the original construction code, the ASME BPVC,Section XI, or otherwise addressed through authorized methods.
NRC Documents (Interpretive Rules Category) 15 of 44 Publication Date Type Title Abstract Citation 11/3/22 Regulatory Guide Acceptability of ASME Code,Section XI, Division 2, "Requirements for Reliability and Integrity Management (RIM)
Programs for Nuclear Power Plants," for Non-Light Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.246, "Acceptability of ASME Code,Section XI, Division 2, `Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors." This RG describes an approach that is acceptable to the NRC staff for the development and implementation of a preservice inspection (PSI) and inservice inspection (ISI) program for non-light water reactors (non-LWRs). It endorses, with conditions, the 2019 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Division 2, for non-LWR applications. This RG also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis.
87 FR 66227 11/3/22 Regulatory Guide Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.250, "Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants." RG 1.250 provides guidance that the staff of the NRC considers acceptable to meet, in part, regulatory requirements for the dedication of commercial-grade digital instrumentation and control items (I&C) for use in nuclear power plant safety applications.
87 FR 66228 9/8/22 Regulatory Guide Insider Mitigation Program The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.77, "Insider Mitigation Program," to provide licensees and applicants with agency approved guidance for complying with NRC regulations. RG 5.77 applies to nuclear power reactors that contain protected or vital areas. Licensees should use defense-in-depth methodologies to minimize the potential for an insider to adversely affect, either directly or indirectly, the licensee's capability to prevent significant core damage or spent fuel sabotage.
87 FR 54861 3/3/22 Regulatory Guide; Final Rule Approval of American Society of Mechanical Engineers' Code Cases The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to incorporate by reference revisions of three regulatory guides to approve new, revised, and reaffirmed code cases published by the American Society of Mechanical Engineers. The NRC is also incorporating by reference one NRC NUREG associated with a condition on one of the regulatory guides. This action allows nuclear power plant licensees and applicants for construction permits, operating licenses, combined licenses, standard design certifications, standard design approvals, and manufacturing licenses to use the code cases listed in these regulatory guides as voluntary alternatives to engineering standards for the construction, inservice inspection, and inservice testing of nuclear power plant components. These engineering standards are set forth in the American Society of Mechanical Engineers' Boiler and Pressure Vessel Codes and American Society of Mechanical Engineers' Operation and Maintenance Codes, which are currently incorporated by reference into the NRC's regulations. Further, this final rule announces the availability of a related regulatory guide, not incorporated by reference into the NRC's regulations, that lists code cases that the NRC has not approved for use.
NRC Documents (Interpretive Rules Category) 16 of 44 Publication Date Type Title Abstract Citation 1/14/22 Draft Regulatory Issue Summary Operational Leakage The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) Operational Leakage. The NRC staff seeks to clarify regulatory requirements for all licensees of boiling and pressurized water reactors that apply to operational leakage. This draft RIS is a clarification for the NRC requirements for evaluation, control, and treatment of operational leakage in systems required to be operable by plant technical specifications (TS).
87 FR 2361 11/23/21 Draft Regulatory Guide Guidance for Implementation of 10 CFR 50.59, "Changes, Tests and Experiments," at Non-Power Production or Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-2007, "Guidance for Implementation of 10 CFR 50.59, "Changes, Tests and Experiments, at Non-power Production or Utilization Facilities. This DG describes an approach that is acceptable to the NRC staff to meet the regulatory requirements "Changes, tests and experiments, at a nonpower production and utilization facility (NPUF), as defined in the DG.
86 FR 66464 11/12/21 Policy Statement Controlled Unclassified Information Program The U.S. Nuclear Regulatory Commission (NRC) is issuing this Statement of Policy to set forth its expectation regarding the treatment of controlled unclassified information (CUI). This final policy statement describes how the NRC will comply with regulations issued by the National Archives and Records Administration (NARA) that direct agencies to minimize the risk of unauthorized disclosure of controlled unclassified information while allowing timely access by authorized holders. This policy statement aligns with similar actions taken by other Federal agencies to communicate changes in agency CUI policy to align with NARA requirements. During the transition to the CUI program, all elements of the NRC's existing Sensitive Unclassified Non-Safeguards Information (SUNSI) program will remain in place.
86 FR 62713 6/3/21 Policy Statement Evidence-Building and Evaluation Policy Statement The U.S. Nuclear Regulatory Commission (NRC) is issuing an Evidence-Building and Evaluation Policy Statement that describes the general standards that guide the NRC's "evidence-building" activities, consistent with the Foundations for Evidence-Based Policymaking Act of 2018. The policy statement is intended to provide agency personnel and stakeholders with a clear understanding of the expectations related to the NRC's standards for evidence-building activities, which includes analyses, research, assessments, and evaluations performed by the agency for programmatic, operational, regulatory, and policy decision making. These standards include rigor, relevance and utility, transparency, collaboration, independence and objectivity, and ethics.
86 FR 29683 6/1/21 Rule Industrial Radiographic Operations and Training The U.S. Nuclear Regulatory Commission (NRC) is issuing a notification of interpretation on industrial radiographic operations at temporary radiography jobsites and an Agreement State Compatibility Category change. The interpretation and Compatibility Category change are effective immediately with a 30-day post-promulgation comment period. The NRC is taking this action to respond to a petition for rulemaking from the Organization of Agreement States (OAS).
NRC Documents (Interpretive Rules Category) 17 of 44 Publication Date Type Title Abstract Citation 2/9/21 Regulatory Guide Criteria for Development of Evacuation Time Estimate Studies (NUREG/CR-7002, Revision 1)
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to NUREG/CR-7002, "Criteria for Development of Evacuation Time Estimate Studies." This revised NUREG provides guidance to meet NRC requirements for development of evacuation time estimates (ETEs) to support emergency planning. This revision reflects the importance of various ETE model parameters based on the results of an applied research study on ETEs. The format and criteria provided in this document will support consistent application of the ETE methodology and will facilitate consistent NRC review of ETE studies.
86 FR 8685 2/2/21 Draft Regulatory Guide; Proposed Rule Approval of American Society of Mechanical Engineers' Code Cases The U.S. Nuclear Regulatory Commission (NRC) 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 American Society of Mechanical Engineers. The NRC is also incorporating by reference one NRC NUREG associated with a proposed condition on one of the regulatory guides. This proposed action would allow nuclear power plant licensees, and applicants for construction permits, operating licenses, combined licenses, standard design certifications, standard design approvals and manufacturing licenses, 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. The NRC is requesting comments on this proposed rule and on the draft versions of the three regulatory guides proposed to be incorporated by reference. The NRC is also making available a related draft regulatory guide that lists Code Cases that the NRC has not approved for use. This draft regulatory guide will not be incorporated by reference into the NRC's regulations.
86 FR 7820 7/19/24 Draft Report Level 3 Probabilistic Risk Assessment Project Documentation (Volume 7)
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft report on the Level 3 Probabilistic Risk Assessment (PRA) project; specifically, "Volume 7: Dry Cask Storage PRA."
89 FR 58805 5/24/24 Notice Effect of Statutory Prohibition on Uranium Imports From the Russian Federation The U.S. Nuclear Regulatory Commission (NRC) is issuing a notice explaining how recently enacted legislation that prohibits imports of certain uranium products (natural uranium and low-enriched uranium) from the Russian Federation affects imports under NRC licenses. After the statutory prohibition becomes effective, importers will no longer be able to use the NRC general license to import these materials from the Russian Federation unless they first obtain a waiver from the U.S.
Department of Energy (DOE). The NRC will return any specific license applications for such imports without action.
NRC Documents (Interpretive Rules Category) 18 of 44 Publication Date Type Title Abstract Citation 5/1/24 NUREG Final Revision to Branch Technical Position 7-19, Guidance for Evaluation of Defense in Depth and Diversity To Address Common-Cause Failure Due to Latent Design Defects in Digital Instrumentation and Control Systems The U.S. Nuclear Regulatory Commission (NRC) is issuing a final revision to the following section of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plans: LWR Edition": Branch Technical Position (BTP) 7-19, "Guidance for Evaluation of Defense in Depth and Diversity to Address Common-Cause Failure Due to Latent Design Defects in Digital Instrumentation and Control Systems."
89 FR 35251 4/17/24 NUREG Draft NUREG: Event Report Guidelines The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-1022, Revision 3, Supplement 2, "Event Report Guidelines." Draft NUREG-1022, Revision 3, Supplement 2, provides updated guidance for nuclear power reactor licensees and can be used for evaluating and reporting degraded or unanalyzed conditions as described in those regulations.
89 FR 27463 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project Chapter 10, Control of Occupational Dose The U.S. Nuclear Regulatory Commission (NRC) issuing Interim Staff Guidance (ISG) DANU-ISG-2022-04, Chapter 10, "Control of Occupational Dose." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23054 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project Chapter 9, Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-03, Chapter 9, "Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23058 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project Chapter 12, Post-Manufacturing and Construction Inspection, Testing, and Analysis Program The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-06, Chapter 12, "Post-manufacturing and construction Inspection, Testing, and Analysis Program." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
NRC Documents (Interpretive Rules Category) 19 of 44 Publication Date Type Title Abstract Citation 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project Chapter 11, Organization and Human-System Considerations The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-05, Chapter 11, "Organization and Human-System Considerations." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23062 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project, "Risk-Informed, Performance-Based Fire Protection Program (for Operations)"
The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-09, "Risk-Informed, Performance-Based Fire Protection Program (for Operations)." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23065 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project, Risk-Informed Inservice Inspection/Inservice Testing Programs for Non-LWRs The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-07, "Risk-Informed Inservice Inspection/Inservice Testing Programs for Non-LWRs." The purpose of this ISG is to provide guidance to prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23067 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Review of Risk-Informed, Technology-Inclusive Advanced Reactor Applications-Roadmap The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-01, "Review of Risk-Informed, Technology-Inclusive Advanced Reactor Applications--
Roadmap." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23071 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project Chapter 2, Site Information The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-02, Chapter 2, "Site Information." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
NRC Documents (Interpretive Rules Category) 20 of 44 Publication Date Type Title Abstract Citation 4/3/24 Staff Guidance; ISG Interim Staff Guidance:
Advanced Reactor Content of Application Project, "Risk-Informed Technical Specifications" The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) DANU-ISG-2022-08, "Risk-Informed Technical Specifications." The purpose of this ISG is to provide guidance for prospective applicants in preparing applications for non-light water reactor (non-LWR) designs that use the Licensing Modernization Project (LMP) process and to assist the NRC staff in determining whether such applications meet the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
89 FR 23073 10/24/23 NUREG Proposed Revision to Standard Review Plan Branch Technical Position 7-19, Guidance for Evaluation of Defense In Depth and Diversity To Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," Branch Technical Position (BTP) 7-19, Revision 9, "Guidance for Evaluation of Defense In Depth and Diversity To Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems." The NRC seeks comments on the proposed draft BTP 7-19 revision of the Standard Review Plan (SRP) that provides the NRC staff with guidance for evaluating an applicant's assessment of the adequacy of defense in depth and diversity (D3) for a proposed digital instrumentation and control (DI&C) system.
88 FR 73051 10/19/23 Staff Guidance; ISG Draft Interim Staff Guidance: Radiological Survey and Dose Modeling of the Subsurface To Support License Termination The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft Interim Staff Guidance (ISG), DUWP-ISG-02, "Radiological Survey and Dose Modeling of the Subsurface to Support License Termination." The purpose of this draft ISG is to provide guidance on surveys of open surfaces in the subsurface, including open excavations, materials planned for reuse, and substructures. This draft ISG also provides guidance on the use of commonly used decommissioning dose modeling codes for submerged and partially submerged substructures to develop clean-up levels, and on methods to evaluate risk from existing groundwater contamination. This draft ISG supplements guidance found in NUREG-1757, Volume 2, Revision 2, which pertains to licensees subject to the license termination rule found in NRC regulations. If finalized, this ISG is intended for use by applicants, licensees, and NRC staff. The guidance is also available to Agreement States and the public.
NRC Documents (Interpretive Rules Category) 21 of 44 Publication Date Type Title Abstract Citation 9/1/23 NUREG Draft NUREG:
Environmental Evaluation of Accident Tolerant Fuels With Increased Enrichment and Higher Burnup Levels The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-2266, "Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels." This study evaluates the reasonably foreseeable impacts of near-term accident tolerant fuel (ATF) technologies with increased enrichment and higher burnup levels to 8 wt% uranium-235 (U-235) and up to 80 GWd/MTU, respectively, on the uranium fuel cycle, transportation of fuel and waste, and decommissioning for light-water reactors (LWRs) (i.e., a bounding analysis).
88 FR 60507 8/21/23 Draft Report Level 3 Probabilistic Risk Assessment Project Documentation (Volume 4)
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft report on the Level 3 Probabilistic Risk Assessment (PRA) project; specifically, "Volume 4: Overview of Reactor, At Power, Level 1, 2, and 3 PRAs for Internal Fires, Seismic Events, and High Winds."
88 FR 56885 8/2/23 NUREG Proposed Revision to Standard Review Plan Section 15.0, "Introduction-Transient and Accident Analyses" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on draft NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," Section 15.0, Revision 4, "Introduction--Transient and Accident Analyses." The NRC seeks comments on the proposed draft section revision of the Standard Review Plan (SRP), concerning the evaluation of the safety of a nuclear power plant that requires analyses of the plant's responses to postulated equipment failures or malfunctions. Such analyses help to determine the limiting conditions for operation, limiting safety system settings, and design specifications for components and systems to protect public health and safety.
88 FR 50918 7/11/23 NUREG Draft NUREG: Revision to Subsequent License Renewal Guidance Documents, and Supplement to Associated Technical Bases Document The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment three draft NUREGs that provide revised guidance for subsequent license renewal (SLR) and the associated technical bases for the revised guidance documents. The draft NUREGs consist of draft NUREG-2191, "Generic Aging Lessons Learned for Subsequent License Renewal Report," Volumes 1 and 2, Revision 1 (GALL-SLR Report); draft NUREG-2192, "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants," Revision 1 (SRP-SLR); and draft NUREG-2221, "Technical Bases for Changes in the Subsequent License Renewal Guidance Documents, NUREG-2191, Revision 1, and NUREG-2192, Revision 1," Supplement 1.
88 FR 44160 6/21/23 Staff Guidance; ISG Draft Interim Staff Guidance: Use of the Decommissioning Trust Fund During Operations for Major Radioactive Component Disposal The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft Interim Staff Guidance (ISG) "Use of the Decommissioning Trust Fund During Operations for Major Radioactive Component Disposal. The purpose of this proposed ISG is to provide the NRC staff's regulatory position to licensees of nuclear power reactors regarding the use of funds from the decommissioning trust fund dedicated to the radiological decommissioning of a reactor facility for the disposal of major radioactive components (MRCs) while the facility is in an operational status. This proposed ISG may be used in connection with requests for exemption from NRC regulations related to the withdrawal of funds from reactor decommissioning trust funds (DTFs).
22 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 05/31/23 NUREG NUREG: Artificial Intelligence Strategic Plan:
Fiscal Years 2023-2027 The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-2261, "Artificial Intelligence Strategic Plan: Fiscal Years 2023-2027," dated May 31, 2023. The NRC's Artificial Intelligence (AI)
Strategic Plan, establishes the vision and goals for the NRC to continue to improve its skills and capabilities to review and evaluate the application of AI to NRC-regulated activities, maintain awareness of technological innovations, and ensure the safe and secure use of AI in NRC-regulated activities. The AI Strategic Plan includes five goals: (1) ensure NRC readiness for regulatory decision-making, (2) establish an organizational framework to review AI applications, (3) strengthen and expand AI partnerships, (4) cultivate an AI proficient workforce, and (5) pursue use cases to build an AI foundation across the NRC.
88 FR 34899 05/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 12, "Post-Construction Inspection, Testing, and Analysis Program" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 06, Chapter 12, "Post-Construction Inspection, Testing, and Analysis Program." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33920 05/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project, "Risk-informed Performance-Based Fire Protection Program (for Operations)"
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 09, "Risk-informed Performance-based Fire Protection Program (for Operations)." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33922 05/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Review of Risk-Informed, Technology Inclusive Advanced Reactor Applications-Roadmap The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 01, "Review of Risk-Informed, Technology Inclusive Advanced Reactor Applications--Roadmap." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications 88 FR 33924
23 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 5/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project, "Risk-informed Technical Specifications" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 08, "Risk-informed Technical Specifications." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33926 5/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 11, "Organization and Human-System Considerations" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 05, Chapter 11, "Organization and Human-System Considerations." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33928 5/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 9, "Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 03, Chapter 9, "Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33930 5/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 10, "Control of Occupational Dose" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 04, Chapter 10, "Control of Occupational Dose." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, manufacturing licenses, standard design approval, or design certifications.
24 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 5/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project, "Risk-informed Inservice Inspection/Inservice Testing" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 07, "Risk-informed Inservice Inspection/Inservice Testing." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined license, manufacturing licenses, standard design approval, or design certifications.
88 FR 33938 5/25/23 Staff Guidance; ISG Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 2, "Site Information" The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022- 02, Chapter 2, "Site Information." The purpose of this proposed ISG is to provide guidance to assist the NRC staff in determining whether an application for a non-light water reactor (non-LWR) design that uses the Licensing Modernization Project (LMP) process meets the minimum requirements for construction permits, operating licenses, combined licenses, manufacturing licenses, standard design approval, or design certifications.
88 FR 33940 3/7/23 Staff Guidance; ISG Material Compatibility for Non-Light Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment on its draft Interim Staff Guidance (ISG) "Material Compatibility for non-Light Water Reactors, DANU-ISG-2023-01." The purpose of this draft ISG is to assist the NRC staff in reviewing certain applications for construction and operation of non-light water reactor designs, including power and non-power reactors.
88 FR 14186 3/6/23 Bulletin NRC Bulletin 2012-01:
Design Vulnerability in Electric Power System The U.S. Nuclear Regulatory Commission (NRC) is issuing this notice to inform all holders of operating licenses and combined licenses for nuclear power reactors of the closure of "NRC Bulletin 2012-01: Design Vulnerability in Electric Power System" (Bulletin). NRC has completed evaluations and inspections of the responses and other actions taken by the licensees of the nuclear power plants in response to NRC Bulletin 2012-01. The staff has approved the actions to be taken by the licensee for Vogtle Units 3 and 4 following commencement of operations and will inspect these actions under the Reactor Oversight Process. The NRC staff concludes that any potential adverse impact on nuclear plant safety due to an open phase condition (OPC) in the plant offsite power system has been adequately addressed by the licensees.
88 FR 13855 2/17/23 NUREG Report on Waste Burial Charges:
Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-1307, Revision 19, "Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities." This report, which is revised periodically, explains the formula acceptable to the NRC for determining the minimum decommissioning fund requirements for nuclear power reactor licensees, as required by NRC regulations. Specifically, this report provides the adjustment factor and updates the values for the labor, energy, and waste burial escalation factors of the minimum formula 88 FR 10388
25 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 2/7/23 NUREG Information Collection:
NRC Form 327, Special Nuclear Material (SNM) and Source Material (SM)
Physical Inventory Summary Report, and NUREG/BR-0096, Instructions and Guidance for Completing Physical Inventory Summary Reports The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, "NRC Form 327, Special Nuclear Material (SNM) and Source Material (SM) Physical Inventory Summary Report, and NUREG/ BR-0096, Instructions and Guidance for Completing Physical Inventory Summary Reports."
88 FR 8001 12/8/22 NUREG Standard Review Plan for Applications for 10 CFR Part 70 Licenses for Possession and Use of Special Nuclear Materials of Critical Mass but Not Subject to the Requirements in 10 CFR part 70, Subpart H The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2212, "Standard Review Plan for Applications for 10 CFR part 70 Licenses for Possession and Use of Special Nuclear Materials of Critical Mass but not Subject to the Requirements in 10 CFR part 70, subpart H." This NUREG contains information intended to provide staff guidance to assist applicants and licensees in preparing license applications for possession and use of special nuclear materials (SNM) exceeding specific threshold quantities. It describes methods or approaches acceptable to the NRC staff for implementing NRC requirements in the Code of Federal Regulations.
87 FR 75295 11/29/22 NUREG Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft report entitled, NUREG-1307, Revision 19, "Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities." This report, which is revised periodically, explains the formula acceptable to the NRC for determining the minimum decommissioning fund requirements for nuclear power reactor licensees, as required by NRC regulations. Specifically, this report provides the adjustment factor and updates the values for the labor, energy, and waste burial escalation factors of the minimum formula.
87 FR 73345 11/17/22 Draft Regulatory Guide Performance-Based Containment Leak Test Program The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1391, "Performance-Based Containment Leak Test Program". This DG is proposed Revision 1 to regulatory guide (RG) 1.163 of the same name. The proposed revision provides guidance on an acceptable performance-based leak-test program, leakage-rate test methods, procedures, and analyses that may be used to comply with NRC regulations.
26 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 11/14/22 Staff Guidance; ISG Safety Review of Light-Water Power Reactor Construction Permit Applications The U.S. Nuclear Regulatory Commission (NRC) is issuing Interim Staff Guidance (ISG) "Safety Review of Light-Water Power Reactor Construction Permit Applications" to clarify existing guidance and to assist the NRC staff in determining whether an application to construct a light-water power reactor (LWR) facility meets the minimum requirements to issue a construction permit (CP). The NRC anticipates the submission of power reactor CP applications in the next few years based on preapplication engagement initiated by several prospective applicants. This guidance is applicable to all applicants for a CP for a light-water power reactor but not to non-LWR applicants or those following the Advanced Reactor Content of Application Project (ARCAP) guidance to the extent the guidance is issued as final and is relevant to the application from a technical and regulatory perspective.
87 FR 68202 10/17/22 Regulatory Guide Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities The U.S. Nuclear Regulatory Commission (NRC) is addressing comments received after issuing for public comment on the trial use of the new regulatory guide (RG) 1.247, "Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities." The NRC will not make any changes to the RG as a result of these comments.
87 FR 62894 10/14/22 Regulatory Guide Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.248, "Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities." This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for managing, monitoring, and mitigating the aging effects on electrical equipment. It endorses Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 1205 2014, "IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities."
87 FR 62462 8/29/22 Draft Regulatory Guide Maintenance, Testing, and Replacement of Vented Lead Acid Storage Batteries for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1401, "Maintenance, Testing, and Replacement of Vented Lead Acid Storage Batteries for Production and Utilization Facilities". This DG is the proposed Revision 4 to Regulatory Guide (RG) 1.129. RG 1.129 describes methods that are acceptable to the NRC staff pertaining to the maintenance, testing, and replacement of vented lead acid storage batteries in production and utilization facilities.
87 FR 52814 8/29/22 Regulatory Guide Monitoring Criteria and Methods To Calculate Occupational Radiation Doses The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 8.34, "Monitoring Criteria and Methods to Calculate Occupational Radiation Doses." This revised guidance is an approach that is acceptable to the staff of the NRC for monitoring and determining the dose to occupationally exposed individuals. It provides updated criteria and methods to calculate occupational radiation doses to demonstrate compliance with the NRC regulations and it reflects current generally accepted methods and procedures available for radiation protection.
27 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 8/8/22 Regulatory Guide Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 5 of Regulatory Guide (RG) 1.82, "Water Sources for Long-Term Cooling Following a Loss-of-Coolant Accident." This revised guidance updates the guidance for sumps and suppression pools that provide water sources for emergency core cooling, containment heat removal, or containment atmosphere cleanup systems. It also provides guidelines for evaluating the adequacy and the availability of the sump or suppression pool for long-term recirculation cooling following a loss-of-coolant accident, and the use of containment accident pressure in determining the net positive suction head for the emergency core cooling and containment heat removal pumps.
87 FR 48202 7/29/22 NUREG High Energy Arcing Fault Hazard Frequency and Consequence Modeling The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft NUREG-2262, "High Energy Arcing Fault Frequency and Consequence Modeling."
87 FR 45806 7/22/22 NUREG Consolidated Decommissioning
- Guidance, Characterization, Survey, and Determination of Radiological Criteria The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-1757, Volume 2, Revision 2, "Consolidated Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria." NUREG-1757 has been revised to address lessons learned and experience gained from review of license termination plans, decommissioning plans, and final status surveys for licensees undergoing license termination since the last revision to the document in September 2006.
This NUREG is intended for use by applicants, licensees, and the NRC staff.
87 FR 43906 7/8/22 NUREG Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-2159, Revision 1, "Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance." This NUREG provides information to facilitate compliance with NRC regulations applicable to the fundamental nuclear material control plans required of certain types of licensees.
28 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 7/6/22 NUREG Regulatory Analysis Guidelines The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment two draft appendices to NUREG/BR-0058, Revision 5, "Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission." Guidance in these draft appendices provides information that the staff will use when performing cost-benefit analyses in support of regulatory decisions.Section II of this document describes each draft appendix.
87 FR 40280 7/5/22 NUREG NRC's Fiscal Years 2023-2027 Artificial Intelligence Strategic Plan The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on the NRC's Fiscal Years (FY) 2023-2027 Artificial Intelligence (AI) Strategic Plan. Specifically, the NRC would like input on the overall strategy as well as the agency's strategic goals presented in draft NUREG-2261 "Artificial Intelligence Strategic Plan: Fiscal Year 2023-2027," actions to realize those strategic goals, potential challenges in achieving the outlined goals, and how to address key challenges and external factors.
The information gathered will be used to inform the development of the NRC's FY 2023-2027 AI Strategic Plan. The NRC is also announcing a virtual public meeting to receive comments on this document. The meeting will allow interested members of the public to submit their comments.
87 FR 39874 6/13/22 Draft Regulatory Issue Summary Personnel Access Authorization Requirements for Non-Immigrant Foreign Nationals Working at Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) that reminds licensees of the NRC requirement that prior to granting or reinstating unescorted access (UA) or certifying unescorted access authorization (UAA) to non-immigrant foreign nationals for the purpose of performing work, licensees shall validate that the foreign national's claimed non-immigration status is correct. This is important to ensure that individuals to whom a licensee intends to grant UA to nuclear power plant protected or vital areas or any individual for whom a licensee or applicant intends to certify UAA, are trustworthy and reliable such that they do not constitute an unreasonable risk to public health and safety or the common defense and security, including the potential to commit radiological sabotage.
87 FR 35798 5/19/22 Regulatory Guide Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG) 3.54, "Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation." This RG includes methods acceptable to the NRC staff for calculating spent nuclear fuel heat generation rates for use for an Independent Spent Fuel Storage Installation. Revision 3 incorporates corrections to Appendix A, Table A-1 that were erroneously recorded in the previous revision (Revision 2 to this RG). In general, this revision presents an up-to-date methodology for determining heat generation rates and it also allows loading of higher burnup fuel by using more accurate methods for decay heat calculations.
29 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 5/13/22 Draft Research Information Letter Modeling High Energy Arcing Fault Hazards and Zones of Influence The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment two draft Research Information Letter reports, "Predicting High Energy Arcing Fault Zones of Influence for Aluminum Using a Modified Arc Flash Model, Evaluation of a modified model bias, uncertainty, parameter sensitivity and zone of influence estimation, Draft for public comment," and "Determining the Zone of Influence for High Energy Arcing Faults using Fire Dynamics Simulator, Draft for public comment."
87 FR 29395 4/31/2022 NUREG U.S. Nuclear Regulatory Commission Strategic Plan, Fiscal Years 2022-2026 he strategic plan, covering Fiscal Years 2022-2026, provides the blueprint for the agency to plan, implement and monitor the work needed to achieve its three strategic goals: (1) ensure the safe and secure use of radioactive materials, (2) continue to foster a healthy organization, and (3) inspire stakeholder confidence in the NRC. The strategic plan also provides an overview of the NRCs responsibilities and lays out how the agency uses data and evidence to inform decisionmaking to accomplish objectives and strategies to achieve the agencys strategic goals.
ML22067A170 4/22/22 Draft Report Level 3 Probabilistic Risk Assessment Project Documentation (Volume 3x)
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft report on the Level 3 Probabilistic Risk Assessment (PRA) project; specifically, "Volume 3x: Overview of Reactor, At-Power, Level 1, 2, and 3 PRAs for Internal Events and Internal Floods."
87 FR 24205 4/21/22 Draft Regulatory Guide Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1389, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors." This DG is proposed Revision 1 to Regulatory Guide (RG) 1.183 which describes a method that the NRC staff considers acceptable in complying with regulations for design basis accident dose consequence analysis using an Alternative Source Term. This guidance for light-water reactor (LWR) designs includes the scope, and documentation of associated analyses and evaluations; consideration of impacts on analyzed risk; and content of submittals.
87 FR 23891 4/11/22 Draft Regulatory Guide Qualification of Class 1E Connection Assemblies for Production and Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1400, "Qualification of Class 1E Connection Assemblies for Production and Utilization Facilities." This DG is the proposed Revision 2 to Regulatory Guide (RG) 1.156. Methods described in RG 1.156 are acceptable to the NRC staff pertaining to the environmental qualification of connectors, terminations, and environmental seals in combination with cables or wires as assemblies for service in nuclear power plants to ensure that the connection assemblies can perform their safety functions.
87 FR 21221 3/24/22 Regulatory Guide Acceptability of Probabilistic Risk Assessment Results for Advanced Non-Light Water Reactor Risk-Informed Activities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment and for trial use, a new regulatory guide (RG) 1.247, "Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities." This new guidance describes one acceptable approach for determining whether the acceptability of the probabilistic risk assessment (PRA) used to support a PRA application is sufficient to provide confidence in the results for non-light water reactors (NLWRs) and risk-informed activities. As a trial RG, this issuance does not provide final staff positions and the guidance within may be revised based on experience obtained by the NRC with its use after its publication.
30 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 3/18/22 Draft Regulatory Guide Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1402, "Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants." This DG is a proposed new regulatory guide for the dedication of commercial-grade digital instrumentation and control (I&C) items for use in nuclear power plant safety applications.
87 FR 15456 3/15/22 NUREG Fuel Qualification for Advanced Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-2246, "Fuel Qualification for Advanced Reactors." The purpose of this NUREG report is to provide a fuel qualification assessment framework for use by applicants for proposed advanced reactors using fuel designs and operating environments that differ from traditional light water reactor fuel. Specifically, the framework provides objective criteria, derived from regulatory requirements, that when satisfied, would support regulatory findings for licensing.
87 FR 14583 3/3/22 Draft Regulatory Guide Cyber Security Programs for Nuclear Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-5061, Revision 1, "Cyber Security Programs for Nuclear Power Reactors." DG 5061, Revision 1, incorporates reference to industry whitepapers on identifying safety, important to safety, balance of plant, and emergency preparedness Critical Digital Assets. It also clarifies guidance on defense-in-depth for cyber security and includes updated text based on the latest National Institute of Standards and Technology (NIST) and International Atomic Energy Agency cyber security guidance.
Specifically, this proposed revision clarifies issues identified from cyber security inspections, insights gained through the Security Frequently Asked Questions (SFAQ) process, documented cyber security attacks, new technologies, and new regulations. This proposed revision also considers the changes in the most recent revision to the NIST Special Publications (SP) 800-53, upon which Revision 0 of Regulatory Guide (RG) 5.71, "Cyber Security Programs for Nuclear Facilities" was based.
87 FR 12208 3/3/22 Regulatory Guide Guidance for the Application of Radiological Sabotage Design-Basis Threat in the Design, Development, and Implementation of a Physical Security Program That Meets 10 CFR 73.55 Requirements The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 5.69, "Guidance for the Application of Radiological Sabotage Design-Basis Threat in the Design, Development, and Implementation of a Physical Security Program that Meets 10 CFR 73.55 Requirements," as a final RG. RG 5.69 provides a method that the NRC staff finds acceptable for an applicant or licensee to use in applying the design-basis threats (DBTs) in the development of a physical security program that meets the requirements of NRC regulations. Through interactions with stakeholders during physical security inspections, including security baseline inspections, force-on-force exercises, and enforcement activities, the NRC identified areas where a need for additional clarity and/or sufficient technical information is warranted. Revision 1 to RG 5.69 addresses these areas. In addition, revisions to this guidance include changes to the DBT adversary characteristics necessary to align with changes to NRC security requirements made since the publication of Revision 0 to RG 5.69 in 2007.
31 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 3/1/22 Draft Regulatory Guide Acceptability of ASME Code Section III, Division 5, High Temperature Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment supplemental information for draft regulatory guide (DG), DG-1380 (proposed Revision 2 to Regulatory Guide [RG]
1.87), "Acceptability of ASME Code Section III, Division 5, `High Temperature Reactors."' This DG endorses, with conditions, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code)Section III, "Rules for Construction of Nuclear Facility Components," Division 5, "High Temperature Reactors," and Code Cases N-861 and N-862. On August 20, 2021, the NRC published DG-1380 requesting public comment. Since then, the NRC staff has reviewed Code Cases N-872 and N-898 for potential endorsement. This supplemental notice informs the public that the NRC staff is considering endorsement of these two additional Code Cases in the final RG 1.87 (Revision 2) and requests comments on the proposed endorsement and revisions.
87 FR 11490 2/25/22 NUREG Reassessment of NRC's Dollar per Person-Rem Conversion Factor Policy The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-1530, Revision 1, "Reassessment of NRC's Dollar Per Person-Rem Conversion Factor Policy." This revision to NUREG-1530 updates the dollar per person-rem conversion factor and establishes a method for keeping this factor up-to-date. The NRC uses the dollar per person-rem conversion factor in cost-benefit analyses to determine the monetary valuation of the consequences associated with radiological exposure and establishes this factor by multiplying a value of a statistical life (VSL) coefficient by a cancer mortality risk coefficient.
87 FR 10829 2/25/22 Regulatory Guide Guidance for Implementation of 10 CFR 50.59, "Changes, Tests and Experiments," at Non-Power Production or Utilization Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 2.8 (Revision 0), Guidance for Implementation of 10 CFR 50.59, "Changes, Tests and Experiments," at Non-Power Production or Utilization Facilities. This RG describes an approach that is acceptable to the NRC staff to meet the regulatory requirements, "Changes, tests and experiments," at a non-power production and utilization facility, as defined in RG 2.8.
87 FR 10831 2/23/22 Draft Regulatory Guide Design-Basis Floods for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1290, "Design Basis Floods for Nuclear Power Plants." This DG is proposed Revision 3 of Regulatory Guide (RG) 1.59. DG-1290 proposes methods that the NRC staff considers acceptable for use in the determination of design-basis floods for nuclear power plants (NPPs).
87 FR 10260 2/8/22 Draft Regulatory Guide Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1385, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident." This DG is proposed Revision 5 to Regulatory Guide (RG) 1.82, which describes an approach that may be used to determine quality standards acceptable to the NRC staff, to meet the regulatory requirements for sumps and suppression pools that provide water sources for emergency core cooling, containment heat removal, or containment atmosphere cleanup systems. It also provides guidelines for evaluating the adequacy and the availability of the sump or suppression pool for long-term recirculation cooling following a loss-of-coolant-accident, and the use of containment accident pressure in determining the net positive suction head for the emergency core cooling and containment heat removal pumps. This proposed revision guidance applies to both the pressurized-water reactor (PWR) and boiling-water reactor (BWR) types of light-water reactors.
32 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 2/3/22 Draft Regulatory Guide Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1393, "Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations." This proposed DG describes methods that are acceptable to the NRC staff to use for assessing, monitoring, and mitigating aging effects on electrical equipment used in nuclear power generating stations.
87 FR 6204 1/26/22 NUREG Preparing Probabilistic Fracture Mechanics Submittals The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.245 (Revision 0), "Preparing Probabilistic Fracture Mechanics Submittals" and accompanying NUREG/CR 7278, "Technical Basis for the use of Probabilistic Fracture Mechanics in Regulatory Applications."
This RG describes a framework to develop the contents of a licensing submittal that the staff of the NRC considers acceptable when performing probabilistic fracture mechanics (PFM) analyses in support of regulatory applications. The NUREG provides the technical basis for RG 1.245.
87 FR 4058 12/22/21 Regulatory Guide Quality Group Classifications and Standards for Water-,
Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 6 to Regulatory Guide (RG),
1.26 "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." Revision 6 to RG 1.26 incorporates additional information that provides guidance for alternative quality classification systems for components in light-water reactor (LWR) nuclear power plants and updates the staff position regarding classification of Quality Group C components to reflect the latest guidance on systems that contain radioactive material since Revision 5 (02/2017), of RG 1.26 was issued. The appendices to this revised RG provide guidance for alternative quality classification systems for components in LWR nuclear power plants.
86 FR 72641 12/22/21 Regulatory Guide Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG),
1.78, "Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated Hazardous Chemical Release." The revision of RG 1.78 describes an approach that is acceptable to the NRC staff to meet regulatory requirements for evaluating the habitability of a nuclear power plant control room during a postulated hazardous chemical release. Releases of hazardous chemicals, onsite and off-site, can result in the nearby control room becoming uninhabitable.
33 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 12/21/21 Regulatory Guide Control of Heavy Loads at Nuclear Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Regulatory Guide (RG) 1.244 (Revision 0), "Control of Heavy Loads at Nuclear Facilities." RG 1.244 is a new regulatory guide to endorse selected national consensus standards related to heavy load handling that replace NRC technical reports. The national consensus standards provide greater flexibility in the selection of lifting equipment and have incorporated recent operating experience to provide a more accurate risk-informed perspective of heavy load handling activities.
86 FR 72287 12/17/21 Draft Regulatory Guide Monitoring Criteria and Methods To Calculate Occupational Radiation Doses The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-8060, "Monitoring Criteria and Methods to Calculate Occupational Radiation Doses." This DG is proposed Revision 1 to Regulatory Guide (RG) 8.34 of the same name. This proposed revised guidance describes an approach that is acceptable to the staff of the NRC to meet the NRC regulations for monitoring and determining the dose to occupationally exposed individuals.
86 FR 71676 12/15/21 Regulatory Guide Geologic and Geotechnical Site Characterization Investigations for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG) 1.132, "Geologic and Geotechnical Site Characterization Investigations for Nuclear Power Plants." It provides guidance on field investigations for determining the geologic, geotechnical, geophysical, and hydrogeologic characteristics of a prospective site for engineering analysis and design of nuclear power plants.
86 FR 71291 12/14/21 Staff Guidance; ISG Safety Review of Light-Water Power-Reactor Construction Permit Applications The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft interim staff guidance (ISG), "Safety Review of Light-Water Power-Reactor Construction Permit Applications." The NRC staff is preparing for the review of construction permit applications. The purpose of this ISG is to clarify existing guidance and to assist the NRC staff in determining whether an application to construct a light-water power-reactor facility meets the minimum requirements to issue a construction permit.
86 FR 71101 11/26/21 Regulatory Guide Evaluations of Explosions Postulated To Occur at Nearby Facilities and on Transportation Routes Near Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG)1.91, "Evaluations of Explosions Postulated to Occur at Nearby Facilities and on Transportation Routes Near Nuclear Power Plants. The revision of RG 1.91 describes methods that the NRC finds acceptable for applicants and licensees of nuclear power reactors to use in evaluating postulated accidental explosions at nearby facilities and transportation routes.
86 FR 67506 9/30/21 Draft Regulatory Guide Acceptability of ASME Code Section XI, Division 2, Requirements for Reliability and Integrity Management (RIM)
Programs for Nuclear Power Plants, for Non-Light Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1383, "Acceptability of ASME Code Section XI, Division 2, `Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors." This proposed DG describes an approach that is acceptable to the NRC staff for the development and implementation of a preservice inspection (PSI) and inservice inspection (ISI) program for non-light water reactors (non-LWRs). It endorses, with conditions, the 2019 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),
Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Division 2, for non-LWR applications. This RG also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis.
34 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 9/23/21 NUREG Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2159, "Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance." This draft NUREG provides information to facilitate compliance with NRC regulations applicable to fundamental nuclear material control plans.
86 FR 52926 9/23/21 NUREG Preparing Probabilistic Fracture Mechanics Submittals The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1382, "Preparing Probabilistic Fracture Mechanics Submittals" and accompanying draft NUREG/CR-7278, "Technical Basis for the use of Probabilistic Fracture Mechanics in Regulatory Applications." This DG is proposed new Regulatory Guide (RG) 1.245. This draft guide describes a framework to develop the contents of a licensing submittal that the staff of the NRC considers acceptable when performing probabilistic fracture mechanics (PFM) analyses in support of regulatory applications. The draft NUREG provides the technical basis for DG-1382.
86 FR 52927 9/23/21 NUREG NRC's Full Draft Strategic Plan for Fiscal Years 2022 Through 2026 The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on its Fiscal Years (FYs) 2022-2026 Full Draft Strategic Plan. The Full Draft Strategic Plan provides the agency's proposed strategic goals and objectives and proposed strategies for achieving them. The NRC encourages and welcomes stakeholder feedback that can help inform the continued development of the NRC's FYs 2022-2026 Strategic Plan and evidence building and evaluation activities.
86 FR 52931 9/23/21 Regulatory Guide Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste The U.S. Nuclear Regulatory Commission (NRC) is issuing revision 3 of Regulatory Guide (RG) 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste." The revision of RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for; (1) measuring, evaluating, and reporting plant related radioactivity in effluents and solid radioactive waste shipments from NRC licensed facilities, and (2) assessing and reporting the public dose to demonstrate compliance with NRC regulations.
35 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 9/17/21 NUREG Operator Licensing Examination Standards for Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-1021, Revision 12, "Operator Licensing Examination Standards for Power Reactors."
86 FR 51925 9/13/21 NUREG Considerations for Estimating Site-Specific Probable Maximum Precipitation at Nuclear Power Plants in the United States of America The U.S. Nuclear Regulatory Commission (NRC) is issuing a knowledge management NUREG, NUREG/KM-0015, "Considerations for Estimating Site-Specific Probable Maximum Precipitation at Nuclear Power Plants in the United States of America." The NRC staff and Oak Ridge National Laboratory have prepared a reference document summarizing recent lessons-learned in connection with a review of the site-specific probable maximum precipitation (SSPMP) estimates used by some nuclear power plant owners and operators in connection with a recent re-evaluation of external flooding at their respective project sites.
86 FR 50913 9/7/21 Regulatory Guide Safety-Related Steel Structures and Steel-Plate Composite Walls for Other Than Reactor Vessels and Containments The U.S. Nuclear Regulatory Commission (NRC) is issuing Regulatory Guide (RG) 1.243, "Safety-Related Steel Structures and Steel-Plate Composite Walls for Other Than Reactor Vessels and Containments." RG 1.243 is a new guide that proposes guidance to meet regulatory requirements for safety-related steel structures and steel plate composite walls for other than reactor vessels and containments by endorsing with exceptions, the 2018 edition of ANSI/ANS N690-2018, "Specification for Safety-Related Steel Structures for Nuclear Facilities."
86 FR 50190 8/20/21 NUREG Acceptability of ASME Code Section III, Division 5, High Temperature Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1380 (proposed Revision 2 to Regulatory Guide [RG] 1.87), "Acceptability of ASME Code Section III, Division 5, `High Temperature Reactors"' and accompanying draft NUREG-2245, "Technical Review of the 2017 Edition of ASME Section III, Division 5, `High Temperature Reactors,"'
that documents the NRC staff's review of the 2017 Edition of ASME Section III, Division 5, certain portions of the 2019 Edition, and associated Code Cases N-861 and N-862. This DG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements for mechanical/
structural integrity of components that operate in elevated temperature environments and that are subject to time-dependent material properties and failure modes. It endorses, with conditions, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code)
Section III, "Rules for Construction of Nuclear Facility Components," Division 5, "High Temperature Reactors." The draft NUREG provides the technical basis for DG-1380.
86 FR 46888 8/18/21 Draft Regulatory Guide Site Characterization Investigations for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1392, "Site Characterization Investigations for Nuclear Power Plants." It is proposed Revision 3 of Regulatory Guide (RG) 1.132. DG-1392 proposes guidance on field investigations for determining the geologic, geotechnical, geophysical, and hydrogeologic characteristics of a prospective site for engineering analysis and design of nuclear power plants.
36 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 8/17/21 Draft Regulatory Guide Use of ARCON Methodology for Calculation of Accident-Related Offsite Atmospheric Dispersion Factors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-4030, "Use of ARCON Methodology for Calculation of Accident-Related Offsite Atmospheric Dispersion Factors." This proposed new regulatory guide (RG) describes an approach for reactor applicants and licensees for determining atmospheric relative concentration ([chi]/Q) values in support of modeling onsite releases to offsite boundaries from a design-basis accident.
Also, this proposed guidance implements the methodology in RG 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," for offsite dose locations at boundaries.
86 FR 46024 8/2/21 Regulatory Guide Seismic Design Classification for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 6 to Regulatory Guide (RG) 1.29, "Seismic Design Classification for Nuclear Power Plants." This RG describes a method that the staff of the NRC considers acceptable for use in identifying and classifying those features of light-water-reactor nuclear power plants that must be designed to withstand the effects of the safe-shutdown earthquake. Revision 6 corrects a minor error in the numbering of the elements in Section C, "Staff Regulatory Guidance."
86 FR 41525 8/2/21 Draft Regulatory Guide Evaluations of Explosions Postulated To Occur at Nearby Facilities and on Transportation Routes Near Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG)-1388, "Evaluations of Explosions Postulated to Occur at Nearby Facilities and on Transportation Routes Near Nuclear Power Plants." This DG is proposed Revision 3 to Regulatory Guide (RG) 1.91.
RG 1.91 describes methods that the NRC finds acceptable for applicants and licensees of nuclear power reactors to use in evaluating postulated accidental explosions at nearby facilities and transportation routes.
86 FR 41525 7/28/21 Draft Regulatory Guide Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1387, "Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated Hazardous Chemical Release." This DG is a proposed Revision 2 to Regulatory Guide (RG) 1.78, which describes an approach that is acceptable to the NRC staff to meet regulatory requirements for evaluating the habitability of a nuclear power plant control room during a postulated hazardous chemical release. Releases of hazardous chemicals, onsite or off-site, can result in the nearby control room becoming uninhabitable.
86 FR 40661 7/21/21 Regulatory Guide Implementation of Aging Management Requirements for Spent Fuel Storage Renewals The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 3.76 (Revision 0), "Implementation of Aging Management Requirements for Spent Fuel Storage Renewals." This new guidance describes an approach that is acceptable to the staff of the NRC to meet the regulatory requirements for spent fuel storage renewals. It addresses requirements for the renewal of specific licenses for independent spent fuel storage installations (ISFSIs) and certificates of compliance (CoCs) for spent fuel storage cask designs pursuant to NRC requirements.
37 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 7/7/21 NUREG Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-2242, "Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030. This report updates previous estimates of replacement energy costs for potential shutdowns of U.S. nuclear electricity-generating units due to a temporary power reactor outage to implement safety modifications or the loss of generation associated with a possible severe reactor accident. The final NUREG largely, is unchanged from the draft issued for public comment but has been revised to reflect the recent change to retirement dates for Byron Units 1 and 2, and Dresden Units 2 and 3.
86 FR 35837 6/30/21 Regulatory Guide Plant-Specific, Risk-Informed Decisionmaking:
Inservice Testing The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.175, "Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing." This RG has been revised to incorporate additional information since Revision 0 was issued, particularly information to be consistent with the terminology and defense-in-depth philosophy provided in RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," as well as to endorse a standard by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Operations and Maintenance.
86 FR 34787 6/30/21 NUREG Fuel Qualification for Advanced Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2246, "Fuel Qualification for Advanced Reactors." The purpose of this NUREG report is to provide a fuel qualification assessment framework for use by applicants. Specifically, the framework provides objective criteria, derived from regulatory requirements, that when satisfied, would support regulatory findings for licensing.
86 FR 34794 6/28/21 Regulatory Guide Volcanic Hazards Assessment for Proposed Nuclear Power Reactor Sites The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 4.26, "Volcanic Hazards Assessment for Proposed Nuclear Power Reactor Sites." This RG provides guidance for facilitating the NRC staff's review of volcanic hazards assessments performed by applicants to support the siting of new nuclear power reactors. The RG also provides applicants with the methods and approaches the NRC staff considers acceptable for the assessment of volcanic hazards in license applications for sites with Quaternary volcanoes within the site region or with Quaternary volcanic deposits within the site vicinity.
86 FR 34057 6/25/21 NUREG Revisions to Uniform Low-Level Radioactive Waste Manifest Forms The U.S. Nuclear Regulatory Commission (NRC) announces the availability of revisions to the NRC Form 540 (Uniform Low-Level Radioactive Waste Manifest (Shipping Paper)), NRC Form 541 (Uniform Low-Level Radioactive Waste Manifest (Container and Waste Description)), and NRC Form 542 (Uniform Low-Level Radioactive Waste Manifest (Manifest Index and Regional Compact Tabulation)). The forms are available for implementation, consistent with the forms included in NUREG/BR-0204, Revision 3, "Instructions for Completing NRC's Uniform Low-Level Radioactive Waste Manifest."
38 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 6/24/21 Draft Regulatory Guide Use of Plant Parameter Envelope in Early Site Permit Applications The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-4029, "Use of Plant Parameter Envelope in Early Site Permit Applications." DG-4029 is a new regulatory guide that proposes guidance for nuclear power plant applicants that elect to use the plant parameter envelope (PPE) concept to assume certain design parameters for an early site permit (ESP) application when a specific reactor technology has not been selected for a proposed site. It incorporates the PPE portions of NRC Review Standard (RS)-002, "Processing Applications for Early Site Permits." The issuance of this DG allows the NRC staff to withdraw the outdated guidance in RS-002 while retaining the PPE information in it for future use by prospective ESP applicants.
86 FR 33384 6/16/21 NUREG Multi-Agency Radiation Survey and Site Investigation Manual, Revision 2 The Department of Defense (DoD), Department of Energy (DOE), Environmental Protection Agency (EPA) and the Nuclear Regulatory Commission (NRC) are announcing for public comment the availability of a draft revision document, entitled the "Multi-Agency Radiation Survey and Site Investigation Manual" (MARSSIM). MARSSIM provides information on planning, conducting, evaluating, and documenting environmental radiological surveys of surface soil and building surfaces for demonstrating compliance with regulations. MARSSIM, when finalized as Revision 2, will be a multi-agency consensus document. The agencies are seeking public comment in order to receive feedback from the widest range of interested parties and to ensure that all information relevant to developing the document is received. The agencies will review public comments received on the draft MARSSIM Revision 2 as well as comments from a concurrent, independent, scientific peer review.
The Agencies will review comments received during the public comment period and make revisions to the document as appropriate.
86 FR 32034 6/11/21 Regulatory Guide Guidance for Implementation of Changes, Tests, and Experiments The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG),
1.187. This Revision (i.e., Revision 3) addresses a clarification to the RG in response to post-promulgation comments on RG 1.187, Revision 2. This RG provides licensees with a method that the NRC considers acceptable for use in complying with the Commission's regulations on the process by which licensees, under certain conditions, may make changes to their facilities and procedures as described in the final safety analysis report (FSAR) (as updated) (also referred to as the updated final safety analysis report), and conduct tests or experiments not described in the FSAR (as updated),
without obtaining a license amendment pursuant to NRC requirements.
86 FR 31346 6/1/21 Regulatory Guide Emergency Response Planning and Preparedness for Nuclear Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 6 to Regulatory Guide (RG), RG 1.101, "Emergency Response Planning and Preparedness for Nuclear Power Reactors." This revision of RG 1.101 endorses Revision 0 of the Nuclear Energy Institute (NEI) white paper, "Implementing a 24-Month Frequency for Emergency Preparedness Program Reviews," issued in November 2019, and Appendix A, "Recommended Drill and Exercise Objectives," to NEI 06-04, "Conducting a Hostile Action-Based Emergency Response Drill," Revision 3, issued September 2016. In addition, this revision includes guidance found in previous revisions of RG 1.101, updated NRC guidance documents, and other documents previously endorsed by the NRC to consolidate the list of these guidance documents into a single revision of the RG.
39 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 5/28/21 Regulatory Guide Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG), RG 1.205, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants. This RG describes an approach that is acceptable to the NRC staff to meet the regulatory requirements in the NRC's regulations and the National Fire Protection Association (NFPA) Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, which is incorporated by reference in the NRC's regulations.
86 FR 28915 5/28/21 Regulatory Guide Fire Protection for Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG),
1.189, "Fire Protection for Nuclear Power Plants. This RG describes an approach that is acceptable to the NRC staff to meet the regulatory requirements in the NRC's regulations governing a civilian nuclear power generating plant's fire protection program.
86 FR 28916 5/21/21 Staff Guidance; ISG Supplemental Guidance for Radiological Consequence Analyses Using Alternative Source Terms The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Interim Staff Guidance (ISG) Supplemental Guidance for Radiological Consequence Analyses Using Alternative Source Terms. This draft ISG proposes changes to the NRC's license amendment request (LAR) review guidance document. This ISG is not intended as standalone guidance but instead supplements NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition" Section 15.0.1, "Radiological Consequence Analyses Using Alternative Source Terms." NUREG-0800, Section 15.0.1 was published in July 2000 and is not scheduled to be updated for several years. This ISG provides additional guidance for the NRC staff reviewing LARs that request to increase the main steam isolation valve (MSIV) leakage allowed by technical specifications (TS) for boiling water reactors (BWRs).
86 FR 27657 5/7/21 Draft Regulatory Guide Quality Group Classifications and Standards for Water-,
Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1371, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." This proposed Revision 6 of Regulatory Guide (RG) 1.26, incorporates additional information that provides guidance for alternative quality classification systems for components in light-water reactor (LWR) nuclear power plants and updates the staff position regarding classification of Quality Group C components to reflect the latest guidance on systems that contain radioactive material since Revision 5 (02/2017), of RG 1.26 was issued. The appendices to this RG provide guidance for alternative quality classification systems for components in LWR nuclear power plants.
40 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 5/4/21 Draft Regulatory Guide Control of Heavy Loads at Nuclear Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1381, "Control of Heavy Loads at Nuclear Facilities." This DG is a proposed new regulatory guide to endorse selected national consensus standards related to heavy load handling that replace NRC technical reports. The national consensus standards provide greater flexibility in the selection of lifting equipment and have incorporated recent operating experience to provide a more accurate risk-informed perspective of heavy load handling activities.
86 FR 23750 4/23/21 Regulatory Guide Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.178, "Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping." Revision 2, incorporates information to be consistent with the terminology and defense-in-depth philosophy provided in RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," as well as to reference the American Society of Mechanical Engineers Code Case N-716-1, "Alternative Classification and Examination Requirements,Section XI, Division 1."
86 FR 21772 4/16/21 NUREG Regulatory Analysis Guidelines The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment four draft appendices to NUREG/BR-0058, Revision 5, "Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission." The guidance provided in the draft appendices refines the information the staff uses when performing a cost-benefit analysis and addresses emergent policy issues and guidance enhancements. The draft appendices also incorporate pertinent information from NUREG/BR-0184, "Regulatory Analysis Technical Handbook." A description of each draft appendix is provided in the Discussion section of this document.
86 FR 20208 4/6/21 Draft Regulatory Guide Plant-Specific, Risk-Informed Decisionmaking:
Inservice Testing The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment Revision 1 to draft regulatory guide (DG), DG-1286, "Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing."
This DG is proposed Revision 1 of RG 1.175, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing." It has been revised to incorporate additional information since Revision 0 was issued, particularly information to be consistent with the terminology and defense-in-depth philosophy provided in RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," as well as to endorse a standard by the American Society of Mechanical Engineers Code for Operations and Maintenance of Nuclear Power Plant (OM Code).
86 FR 17860 3/19/21 Regulatory Guide Training and Qualification of Security Personnel at Nuclear Power Reactor Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 of Regulatory Guide (RG) 5.75, "Training and Qualification of Security Personnel at Nuclear Power Reactor Facilities." This RG updates training and qualification guidance that incorporates lessons learned and reflects changes that have been made in associated rules and guidance documents since the original publication of the guide. This guide describes approaches and methodologies that the NRC staff considers acceptable for the training and qualification of all personnel who are assigned duties and responsibilities required for the implementation of the Commission-approved security plans, licensee response strategies, and implementing procedures at nuclear power reactor facilities.
41 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 3/19/21 Policy Statement Enhancing Participation in NRC Public Meetings The U.S. Nuclear Regulatory Commission (NRC) has revised its policy statement, "Enhancing Participation in NRC Public Meetings," to further clarify and enhance participation in public meetings conducted by the NRC. The revised policy statement redefines the three categories of public meetings and identifies the level of public participation offered at each category of meeting. The revised policy statement also clarifies notification expectations for meetings that include physical presence in the meeting room and meetings that rely solely on remote access technology such as teleconferencing. The revisions will improve the consistency of the NRC's public meetings and help participants better prepare for NRC meetings.
86 FR 14964 3/17/21 Draft Regulatory Guide Emergency Response Planning and Preparedness for Nuclear Power Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1357, "Emergency Response Planning and Preparedness for Nuclear Power Reactors." This DG is proposed Revision 6 of Regulatory Guide (RG) 1.101, "Emergency Response Planning and Preparedness for Nuclear Power Reactors." This proposed revision endorses Revision 0 of the Nuclear Energy Institute (NEI) white paper, "Implementing a 24-Month Frequency for Emergency Preparedness Program Reviews," issued November 2019. In addition, this proposed revision includes guidance found in previous revisions of RG 1.101, updated NRC guidance documents, and other documents previously endorsed by the NRC to consolidate the list of these guidance documents into a single revision of the RG.
86 FR 14651 3/10/21 Regulatory Guide Fresh and Spent Fuel Pool Criticality Analyses The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.240, "Fresh and Spent Fuel Pool Criticality Analyses." This regulatory guide (RG) describes an approach that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable to demonstrate that NRC regulatory requirements are met for subcriticality of fuel assemblies stored in fresh fuel vaults and spent fuel pools at light-water reactor (LWR) power plants. It endorses, with clarifications and exceptions, the Nuclear Energy Institute (NEI) guidance document NEI 12 16, "Guidance for Performing Criticality Analyses of Fuel Storage at Light Water Reactor Power Plants,"
Revision 4.
86 FR 13762 3/5/21 Staff Guidance; Design Review Guide Design Review Guide for Instrumentation and Controls for Non-Light-Water Reactor Reviews The U.S. Nuclear Regulatory Commission (NRC) is issuing a Design Review Guide (DRG) entitled "Instrumentation and Controls for Non-Light-Water Reactor (non-LWR) Reviews." This DRG provides guidance for the NRC staff to use in reviewing the Instrumentation and Controls (I&C) portions of applications for advanced non-LWRs within the bounds of existing regulations. The guidance supports NRC's Non-LWR Vision and Strategy, Implementation Action Plan Strategy 3, which involves developing: (1) Guidance for flexible regulatory review processes for non-LWRs within the bounds of existing regulations; and (2) a new non-LWR regulatory framework that is risk-informed and performance-based, and that features NRC staff's review efforts commensurate with the demonstrated safety performance of non-LWR technologies 86 FR 12989
42 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 2/25/21 Regulatory Guide Guidance for Changes During Construction for New Nuclear Power Plants Licenses The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.237, entitled "Guidance for Changes During Construction for Nuclear Power Plants Being Constructed Under a Combined License Referencing a Certified Design Under 10 CFR part 52." This regulatory guide (RG) describes a process that the NRC staff considers acceptable for implementation of changes to the design of structures, systems, and components of a facility being constructed under a combined operating license that references a certified design.
86 FR 11563 2/25/21 Staff Guidance; ISG Changes to Subsequent License Renewal Guidance Documents The U.S. Nuclear Regulatory Commission (NRC) is issuing three Interim Staff Guidance (ISG) documents that update aging management criteria for mechanical, structural, and electrical structures and components in the NRC's subsequent license renewal (SLR) guidance documents.
Specifically, the ISGs revise guidance contained in NUREG-2191, "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report," and NUREG-2192, "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants." These ISGs are intended to facilitate preparation of SLR applications by clarifying existing guidance for aging management and adding new guidance, which also will facilitate the NRC staff's review of SLR applications.
86 FR 11564 2/22/21 Regulatory Guide Setpoints for Safety-Related Instrumentation The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG) 1.105, "Setpoints for Safety-Related Instrumentation." This RG describes an approach that is acceptable to the staff of the NRC to meet regulatory requirements ensuring that setpoints for safety-related instrumentation are established and maintained within the technical specification limits. RG 1.105 has been revised to incorporate additional information regarding American National Standards Institute (ANSI)/International Society of Automation (ISA) Standard 67.04.01-2018, "Setpoints for Nuclear Safety Related Instrumentation."
86 FR 10601 2/22/21 Regulatory Guide Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to Regulatory Guide (RG) 1.136, "Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments." It updates the guidance for materials, design, construction, fabrication, examination, and testing of concrete containments in nuclear power plants through endorsement, with exceptions, of the 2019 edition of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel (B&PV) Code,Section III, Division 2 (American Concrete Institute (ACI) Standard 359-19),
"Code for Concrete Containments."
86 FR 10602 2/10/21 Draft Regulatory Guide Safety-Related Steel Structures and Steel-Plate Composite Walls for Other Than Reactor Vessels and Containments The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG-1304, "Safety-Related Steel Structures and Steel-Plate Composite Walls for other than Reactor Vessels and Containments." DG-1304 is a new guide that proposes guidance to meet regulatory requirements for safety-related steel structures and steel-plate composite walls for other than reactor vessels. DG-1304 endorses, with exceptions and clarifications, the 2018 edition of American National Standards Institute/American Nuclear Society (ANSI/AISC) N690, "Specification for Safety-Related Steel Structures for Nuclear Facilities."
43 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 2/3/21 NUREG Report on Waste Burial Charges; Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-1307, Revision 18, "Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities." This report, which is revised periodically, explains the formula acceptable to the NRC for determining the minimum decommissioning fund requirements for nuclear power reactor licensees, as required by NRC regulations. Specifically, this report provides the adjustment factor and updates the values for the labor, energy, and waste burial escalation factors of the minimum formula.
86 FR 8049 1/29/21 NUREG Final Revision to Branch Technical Position 7-19 Guidance for Evaluation of Defense in Depth and Diversity To Address Common-Cause Failure Due to Latent Design Defects in Digital Safety Systems The U.S. Nuclear Regulatory Commission (NRC) is issuing a final revision to Branch Technical Position (BTP) 7-19, "Guidance for Evaluation of Defense in Depth and Diversity to Address Common Cause Failure due to Latent Design Defects in Digital Safety Systems" of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition."
86 FR 7577 1/29/21 NUREG; Staff Guidance; ISG Notice of Consolidation Effort To Streamline the Review Process Pertaining to Staff Guidance for Spent Fuel Storage and Radioactive Material Transportation Packages The U.S. Nuclear Regulatory Commission (NRC) has completed a consolidation effort to streamline the review process pertaining to staff guidance for spent fuel storage and radioactive material transportation packages. NUREG-1536, and NUREG-1567 have been consolidated into NUREG-2215 (NRC-2017-0211), and similarly, NUREG-1609 and NUREG-1617 have been consolidated into in NUREG-2216 (NRC-2019- 0132), as well as all associated supplements and Spent Fuel Storage and Transportation Interim Staff Guidance (ISG). A notice of this consolidation has been posted on each of the affected web pages and redirects to NUREG-2215 and NUREG-2216 have been provided. Note that the retired standard review plans (SRPs) and ISG still remain available for reference as legacy documents, with links provided on each web page.
86 FR 7578 1/22/21 NUREG Knowledge and Abilities Catalog for Nuclear Power Plant Operators:
Westinghouse AP1000 Pressurized Water Reactors The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG-2103, "Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized Water Reactors."
44 of 44 NRC Documents (Interpretive Rules Category)
Publication Date Type Title Abstract Citation 1/21/21 Regulatory Guide An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 1.177, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications."
Revision 2 of RG 1.177 includes guidance to develop risk-informed applications for technical specification (TS) changes that considers engineering issues and applies risk insights. It provides guidance acceptable to the staff for using risk information to evaluate changes to nuclear power plant TS completion times (CTs), surveillance frequencies (SFs) and to assess the impact of such proposed changes on the risk associated with plant operation. In addition, it supplements RG 1.174, Revision 3, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis".