2024-23434. Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors  

  • Document ADAMS accession No./Web link/ Federal Register Citation
    Proposed Rule Documents
    Federal Register Notification, “Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors,” October, 2024 ML24095A161.
    “Draft Environmental Assessment for the Proposed Rule—Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors,” October, 2024 ML24095A163.
    “Draft Regulatory Analysis for the Proposed Rule: Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors,” October, 2024 ML24095A166.
    Information Collection Documents
    Draft Supporting Statement for Information Collection Analysis—10 CFR Part 53 ML21162A109.
    Draft Supporting Statement for Information Collection Analysis—10 CFR Part 26 ML23030A400.
    Draft Supporting Statement for Information Collection Analysis—10 CFR Part 50 ML24220A036.
    Draft Supporting Statement for Information Collection Analysis—10 CFR Part 73 ML23030A576.
    Draft Supporting Statement for Information Collection Analysis—NRC Form 361S ML24220A034.
    Draft Supporting Statement for Information Collection Analysis—NRC Form 366 ML24220A035.
    Draft Supporting Statement for Information Collection Analysis—NRC Form 893 and 894 ML24220A033.
    Proposed Rule—Part 26 Burden Tables for Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors ML24240A008.
    Proposed Rule—Part 50 Burden Tables for Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors ML24220A061.
    Proposed Rule—Part 53 Burden Tables for Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors ML24220A060.
    Proposed Rule—Part 73 Burden Tables for Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors ML24240A009.
    Draft NRC Form 361S, “Part 53 Plant Event Notification Worksheet” ML23032A443.
    Draft NRC Form 366, “Licensee Event Report (LER)” ML23032A445.
    Draft NRC Form 366A, “Licensee Event Report (LER) Continuation Sheet” ML23032A447.
    Draft NRC Form 366B, “Licensee Event Report (LER) (Failure Continuation)” ML23032A454.
    Draft NRC Form 893, “10 CFR Part 26, Subpart M, Single FFD Policy Violation Form” ML23032A435.
    Draft NRC Form 894, “10 CFR Part 26, Subpart M, Annual Reporting Form for FFD Performance Information” ML23032A439.
    Draft Regulatory Guidance Documents
    DG-1413, “Technology-Inclusive Identification Of Licensing Events For Commercial Nuclear Plants,” October, 2024 ML22257A173.
    DG-5073, “Fitness-For-Duty Programs For Commercial Nuclear Plants And Manufacturing Facilities Licensed Under 10 CFR Part 53,” October, 2024 ML22200A037.
    DG-5074, “Access Authorization Program for Commercial Nuclear Plants,” October, 2024 ML22199A246.
    DG-5075, “Establishing Cybersecurity Programs For Commercial Nuclear Plants Licensed Under 10 CFR Part 53,” October, 2024 ML22199A257.
    DG-5076, “Guidance for Technology Inclusive Requirements for Physical Protection of Licensed Activities at Commercial Nuclear Plants,” October, 2024 ML22203A131.
    ( print page 87013)
    DG-5078, “Fatigue Management For Nuclear Power Plant Personnel At Commercial Nuclear Plants Licensed Under 10 CFR Part 53,” October, 2024 ML22264A109.
    Draft ISG Documents
    Draft ISG DRO-ISG-2023-01, “Operator Licensing Programs,” October, 2024 ML22266A066.
    Draft ISG DRO-ISG-2023-02, “Interim Staff Guidance Augmenting NUREG-1791, `Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR 50.54(m),' for Licensing Commercial Nuclear Plants under 10 CFR Part 53,” October, 2024 ML22266A068.
    Draft ISG DRO-ISG-2023-03, “Development of Scalable Human Factors Engineering Review Plans,” October, 2024 ML22266A072.
    Other References
    American National Standards Institute/ANS-3.4-2013, “Medical Certification And Monitoring Of Personnel Requiring Operator Licenses For Nuclear Power Plants” https://webstore.ansi.org/​Standards/​ANSI/​ansians2013.
    ASME/ANS RA-S-1.4-2021, “Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants” https://www.asme.org/​codes-standards/​find-codes-standards/​probabilistic-risk-assessment-standard-for-advanced-non-light-water-reactor-nuclear-power-plants/​2021/​pdf.
    ASCE/SEI 43-19, “Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities” https://doi.org/​10.1061/​9780784415405.
    Federal Register notification—Final policy statement, “Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities; Final Policy Statement,” dated August 16, 1995 60 FR 42622.
    Federal Register notification—Final rule, “Fitness-for-Duty Programs,” dated June 7, 1989 54 FR 24468.
    Federal Register notification—Final rule, “Fitness for Duty Programs,” dated March 31, 2008 73 FR 16966.
    Federal Register notification—Final rule, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” dated August 28, 2007 72 FR 49352.
    Federal Register notification—Final rule, “Station Blackout,” dated June 21, 1988 53 FR 23203.
    Federal Register notification—Final rule, “Technical Specifications,” dated July 19, 1995 60 FR 36953, 36955.
    Federal Register notification—Guidance, “Mandatory Guidelines for Federal Workplace Drug Testing Programs,” dated January 23, 2017 82 FR 7920.
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    Federal Register notification—Policy Statement, “Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants,” dated August 8, 1985 50 FR 32138.
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    Federal Register notification—Policy Statement, “Tribal Policy Statement,” dated January 9, 2017 82 FR 2402.
    Federal Register notification—Policy Statement, “Policy Statement on the Regulation of Advanced Reactors,” dated October 14, 2008 73 FR 60612.
    Federal Register notification—Policy Statement, “Final Safety Culture Policy Statement,” dated June 14, 2011 76 FR 34773.
    Federal Register notification—Proposed rule, “Emergency Preparedness for Small Modular Reactors and Other New Technologies,” dated May 12, 2020 85 FR 28436.
    Federal Register notification—Proposed rule, “Regulatory Improvements for Production and Utilization Facilities Transitioning to Decommissioning,” dated March 3, 2022 87 FR 12254.
    Federal Register notification—Public meeting, “Reporting Requirements for Nonemergency Events at Nuclear Power Plants,” dated November 29, 2021 86 FR 67669.
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    ICRP, Publication 30 “Limits for Intakes of Radionuclides by Workers,” dated 1979 https://www.icrp.org/​publication.asp?​id=​ICRP%20Publication%2030%20(Index).
    Letter to Chairman Hanson, NRC, “Final Letter on Draft 10 CFR Part 53 Rulemaking Language,” dated November 22, 2022 ML22319A104.
    Letter to Chairman Hanson, NRC, “Fourth Interim Letter on 10 CFR Part 53 Rulemaking Language,” dated August 2, 2022 ML22196A292.
    Letter to Chairman Hanson, NRC, “Preliminary Proposed Rule Language For 10 CFR Part 53, Regulation of Advanced Nuclear Reactors, Interim Report,” dated May 30, 2021 ML21140A354.
    Letter to Chairman Hanson, NRC, “Preliminary Rule Language For 10 CFR Part 53, Subpart F, `Requirements for Operations,' Interim Report,” dated February 17, 2022 ML22040A361.
    Letter to Chairman Rempe, ACRS, “Response to the Advisory Committee on Reactor Safeguards, `Fourth Interim Letter on 10 CFR Part 53 Rulemaking Language,'” dated September 30, 2022 ML22249A073.
    Letter to Chairman Rempe, ACRS, “Response to the Advisory Committee on Reactor Safeguards Letter on Preliminary Rule Language for 10 CFR Part 53, Subpart F, `Requirements for Operations,' Interim Report,” dated March 30, 2022 ML22063A012.
    Letter to Chairman Sunseri, ACRS, “Part 53, Licensing and Regulation of Advanced Nuclear Reactors,” dated November 24, 2020 ML20311A006.
    ( print page 87014)
    Letter to Chairman Svinicki, NRC, “10 CFR Part 53, Licensing and Regulation of Advanced Nuclear Reactors,” dated October 21, 2020 ML20295A647.
    Michigan v. EPA, 135 S. Ct. 2699 (2015)
    National Library of Medicine, National Institutes of Health, Workshop Summary, “The Evolution of Telehealth: Where Have We Been and Where Are We Going?,” dated November 2012 https://www.ncbi.nlm.nih.gov/​books/​NBK207141/​.
    NEI 18-04, Rev. 1, “Risk-Informed Performance-Based Technology-Inclusive Guidance for Non-Light Water Reactors,” dated August 2019 ML19241A472.
    NIA, “Clarifying `Major Portions' of a Reactor Design in Support of a Standard Design Approval,” dated April 2017 https://www.nuclearinnovationalliance.org/​clarifying-major-portions-reactor-design-support-standard-design-approval.
    NRC, “A Regulatory Review Roadmap for Non-Light Water Reactors,” dated December 2017 ML17312B567.
    NRC, “Manufacturing License ML-1 for Production of Up to Eight Floating Nuclear Plants,” dated September 30, 1982 ML20070J215.
    NRC, “Risk-Informed and Performance-Based Human-System Considerations for Advanced Reactors,” dated March 2021 ML21069A003.
    NRC Form 890, “Single Positive Test Form” ML22013B187.
    NRC Form 891, “Annual Reporting for Drug and Alcohol Tests” ML22013B240.
    NRC From 892, “Annual Fatigue Reporting Form” ML22013B250.
    NUREG-0654/FEMA-REP-1, Revision 2, “Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,” dated December 2019 ML19347D139.
    NUREG-0880, “Safety Goals for Nuclear Power Plant Operation,” dated May 1983 ML071770230.
    NUREG-1530, Revision 1, “Reassessment of NRC's Dollar Per Person-Rem Conversion Factor Policy, Final Report,” dated February 2022 ML22053A025.
    NUREG/BR-0058, Revision 5, “Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission,” dated April 2017 ML17100A480.
    NUREG/CR-5884, “Revised Analyses of Decommissioning for the Reference Pressurized Water Reactor Power Station,” dated November 1995 ML14008A187.
    NUREG/CR-6187, Volume 1, “Revised Analyses of Decommissioning for the Reference Boiling Water Reactor Power Station,” dated July 1996 ML14008A186.
    OMB Circular No. A-119, “Federal Participation in the Development and Use of Voluntary Consensus Standards and in Conformity Assessment Activities,” dated February 19, 1998 https://obamawhitehouse.archives.gov/​omb/​circulars_​a119_​a119fr.
    PNNL, Technical Letter Report, “The Use of Electronic Communications to Perform Determinations of Fitness,” dated August 2017 ML18081A607.
    Pre-decisional DG, “Technology-Inclusive, Risk-Informed, and Performance-Based Methodology for Seismic Design of Commercial Nuclear Plants,” dated October 3, 2022 ML22276A149.
    Research Information Letter 2021-04, “Feasibility Study on a Potential Consequence-Based Seismic Design Approach for Nuclear Facilities,” dated April 2021 ML21113A066.
    RG 1.110, Revision 1, “Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors,” dated October 2013 ML13241A052.
    RG 1.134, Revision 4, “Medical Assessment Of Licensed Operators Or Applicants For Operator Licenses At Nuclear Power Plants,” dated September 2014 ML14189A385.
    RG 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Revision 3, dated January 2018 ML17317A256.
    RG 1.208, “A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion,” dated March 2007 ML070310619.
    RG 1.232, “Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors,” Revision 0, dated April 2018 ML17325A611.
    RG 1.233, Revision 0, “Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors,” dated June 2020 ML20091L698.
    RG 1.247, “Acceptability of Probabilistic Risk Assessment Results for Non-Light-Water Reactor Risk-Informed Activities,” issued March 2022 for trial use ML21235A008.
    RG 5.73, “Fatigue Management for Nuclear Power Plant Personnel,” dated March 20, 2009 ML083450028.
    RG 5.77, “Insider Mitigation Program,” Revision 1, dated September 08, 2022 ML16342B024.
    RG 5.81, “Target Set Identification and Development for Nuclear Power Reactors,” Revision 1, dated December 2019 (non-public) ML13151A355.
    SECY-18-0096, “Functional Containment Performance Criteria For Non-Light-Water-Reactors,” dated September 28, 2018 ML18115A157.
    SECY-19-0117, “Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors,” dated December 2019 ML18311A264 (package).
    SECY-20-0032, “Rulemaking Plan on `Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN-3150-AK31; NRC-2019-0062,'” dated April 13, 2020 ML19340A056.
    SECY-20-0070, “(Redacted) Technical Evaluation of the Security Bounding Time Concept for Operating Nuclear Power Plants,” dated November 8, 2021 ML20126G265 (package).
    SECY-22-0072, “Proposed Rule: Alternative Physical Security Requirements for Advanced Reactors (RIN 3150-AK19),” dated August 2, 2022 ML21334A003 (package).
    SECY-83-293, “Amendments to 10 CFR 50 Related to Anticipated Transients Without Scram (ATWS) Events,” dated July 19, 1983 ML21278A823 (non-public); ML21278A994 (non-public).
    SECY-93-092, “Issues Pertaining to the Advanced Reactor (PRISM, MHTGR, and PIUS) and CANDU 3 Designs and their Relationship to Current Regulatory Requirements,” dated April 8, 1993 ML040210725.
    ( print page 87015)
    SRM-SECY-10-0121, “Modifying the Risk-Informed Regulatory Guidance for New Reactors,” dated March 2, 2011 ML110610166.
    SRM-SECY-17-0100, “Security Baseline Inspection Program Assessment Results and Recommendations for Program Efficiencies,” dated October 8, 2018 ML18283A072.
    SRM-SECY-20-0032, “Rulemaking Plan on `Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN-3150-AK31; NRC-2019-0062),'” dated October 2, 2020 ML20276A293.
    SRM-SECY-20-0045, “Population Related Siting Considerations for Advanced Reactors,” dated July 30, 2022 ML22194A885.
    SRM-SECY-98-144, “Staff Requirements—SECY-98-144—White Paper on Risk-Informed and Performance-Based Regulations,” dated February 24, 1999 ML003753593.
    SECY-23-0021, “Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN 3150-AK31),” March 1, 2023 ML21162A095.
    SECY-23-0021, Enclosure 1, “Draft Federal Register Notification” ML21162A102.
    SECY-23-0021, Enclosure 2, “Draft Environmental Assessment for the Proposed Rule—Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors” ML21162A104.
    SECY-23-0021, Enclosure 3, “Draft Regulatory Analysis for the Proposed Rule: Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors” ML21165A112.
    SECY-23-0021, Enclosure 4, “Alternative Approaches Considered for Selected Topics During the Development of 10 CFR Part 53 ML22244A001.
    SECY-23-0021, Enclosure 5, “Estimated Resources for The Risk-Informed, Technology-Inclusive Regulatory Framework For Advanced Reactors Rulemaking” ML22304A099 (non-public).
    Staff Requirements—SECY-23-0021, “Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN 3150-AK31),” March 4, 2024 ML24064A047 (package).

Document Information

Published:
10/31/2024
Department:
Nuclear Regulatory Commission
Entry Type:
Proposed Rule
Action:
Proposed rule.
Document Number:
2024-23434
Dates:
Submit comments by December 30, 2024. Comments received after this date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received before this date.
Pages:
86918-87128 (211 pages)
Docket Numbers:
NRC-2019-0062
RINs:
3150-AK31: Risk-Informed, Technology Inclusive Regulatory Framework for Advanced Reactors [NRC-2019-0062]
RIN Links:
https://www.federalregister.gov/regulations/3150-AK31/risk-informed-technology-inclusive-regulatory-framework-for-advanced-reactors-nrc-2019-0062-
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Accounting, Administrative practice and procedure, Alcohol abuse, Antitrust, Classified information, Confidential business information, Drug abuse, Drug testing, Education, Emergency medical services, Environmental impact statements, Environmental protection, Exports, Fees, Fire prevention, Flags, Freedom of information, Government contracts, Government employees, Hazardous materials transportation, Hazardous waste, Imports, Indians, Insurance, Intergovernmental relations, Investigations, ...
PDF File:
2024-23434.pdf
Supporting Documents:
» Alternative Evaluation for Risk Insights (AERI) Framework - Preliminary Draft Regulatory Guide DG-1414
» Part 53 Rulemaking - Framework B Development Process and Provisions White Paper with Requirements Crosswalk and Applications Table
» 1/06/22 - NRC Staff Presentation Slides for Public Meeting RE: 10 CFR Part 53, "Licensing and Regulation of Advanced Nuclear Reactors" - Part 26, "Fitness for Duty Programs," Preliminary Proposed Rule Language
» Discussion Table for Preliminary Rule Language for the Part 53 Rulemaking: Subpart G - "Decommissioning Requirements"
» Discussion Table for Preliminary Rule Language for the Part 53 Rulemaking: Part 26 - "Fitness For Duty Programs"
» 12/16-17/2021 - Advisory Committee on Reactor Safeguards (ACRS) Future Plant Designs Subcommittee, 10 CFR Part 53 "Licensing and Regulation of Advanced Nuclear Reactors” – Use of Graded PRA, Subpart F – Requirements for Operations” (Staffing), and Update on TICAP/ARCAP Guidance
» 10/26/2021 - NRC Presentation for Public Meeting RE: Subpart F, "Staffing, Training, Personnel Qualifications, and Human Factors Requirements"
» Discussion Table for Preliminary Rule Language for the Part 53 Rulemaking: Subpart H - "Licenses, Certifications, and Approvals" - Sections Related to Manufacturing Licenses, Construction Permits, Operating Licenses, and Combined Licenses
» Discussion Table for Preliminary Rule Language for the Part 53 Rulemaking: Part 5X - "Technology-Inclusive Alternative Requirements For Commercial Nuclear Plants
» Discussion Table for Preliminary Rule Language for the Part 53 Rulemaking: Subpart H - "Licenses, Certifications, and Approvals"
CFR: (24)
10 CFR 1
10 CFR 2
10 CFR 10
10 CFR 11
10 CFR 19
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