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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A2362024-01-30030 January 2024 Preliminary Results of the Environmental Review, Subsequent License Renewal ML23355A1432024-01-17017 January 2024 January 17, 2024 Public Meeting Handout - Fusion Systems Rulemaking ML23258A1802023-11-0909 November 2023 November 9, 2023 Public Meeting Presentation--Fusion Systems Proposed Rule ML23296A1992023-11-0808 November 2023 Cumulative Effects of Regulation Public Meeting (11/08/2023): Renewing Nuclear Power Plant Operating Licenses Environmental Review (Rin 3150-AK32; NRC-2018-0296) ML23258A1712023-11-0101 November 2023 November 1, 2023 Public Meeting Presentation--Fusion Systems Proposed Rule NUREG-1556, November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule2023-10-31031 October 2023 November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule ML23240A7182023-08-29029 August 2023 Slides - Public Meeting on Regulatory Basis for Rb-82 Generators, Emerging Medical Technologies, and Other Medical Use of Byproduct Material ML23191A1532023-07-12012 July 2023 Public Meeting Presentation -- Proposed Rule: Regulatory Framework for Fusion Energy Systems ML23123A3292023-06-0606 June 2023 SGI Training ML13108A326 ML23123A3322023-06-0606 June 2023 SGI Pamphlet ML23062A7352023-04-14014 April 2023 Tanana Chiefs Conference 2023 Annual Convention NRC Presentation ML23137A0442023-04-11011 April 2023 April 11, 2023, Presentation to NOAA Narw Northeast U.S. Implementation Team - North Atlantic Right Whale and NRC Endangered Species Act Consultations ML23086C0722023-03-27027 March 2023 Presentation Slide for Monticello Scoping Webinar, March 29, 2023 ML23081A0392023-03-22022 March 2023 Presentation Slide for Monticello Public Scoping Meeting, March 22, 2023 ML23019A0122023-01-19019 January 2023 Inspection Manual Chapter 2602 and Associated Inspection Procedures Awareness Training for NRC & Agreement State Inspectors ML23012A2302023-01-12012 January 2023 Inspection Manual Chapter 2602 and Associated Inspection Procedures Public Presentation - Decommissioning Fuel Cycle, Uranium Recovery & Materials Inspection Program ML23006A0232022-12-15015 December 2022 NEIs Presentation for the December 15, 2022 Spent Fuel Priorities Meeting with NEI ML22334A1022022-12-0505 December 2022 Advisory Committee on the Medical Uses of Isotopes (ACMUI) Fall 2022 Meeting Handout ML22334A2692022-11-30030 November 2022 Advisory Committee on the Medical Uses of Isotope (ACMUI) Fall 2022 Meeting Handout (Revised) ML22326A2222022-11-23023 November 2022 Future of the National Materials Program Working Group Public Meeting: Presentation ML22311A5532022-11-16016 November 2022 Kairos Hermes NRC Staff Presentation at Nov 16 Public Meeting on the Draft Environmental Impact Statement for the Construction Permit for the Kairos Hermes Test Reactor ML22308A0502022-11-0303 November 2022 Presentation 2 Chapman NRC Background Slides Nov 3 2022 Discrete Radioactive Particle (DRP) Workshop ML22308A0512022-11-0303 November 2022 Presentation 3b Parks DRP Exposure Scenarios November 3, 2022 DRP Workshop Presentation ML22301A1612022-10-28028 October 2022 Discussion Questions for DRP Workshop ML22286A0712022-10-25025 October 2022 Harmonization of Transportation Safety Requirements with International Atomic Energy Agency Standards (Rin 3150-AJ85; NRC-2016-0179); Public Meeting Presentation ML22272A0382022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - SECY-23-XXXX Enclosure 1B Section-by-Section, Backfit and Issue Finality, and Availability of Guidance Documents ML22272A0362022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - SECY-23-XXXX Enclosure 1A Preamble (E.G. Statements of Consideration) ML22272A0392022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - SECY-23-XXXX Enclosure 1C Part 2 Through Part 53 Framework a Rule Language ML22272A0402022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - SECY-23-XXXX Enclosure 1D Part 53 Framework B Through Part 171 Rule Language ML22272A0422022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DG-1413 Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants ML22272A0472022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DRO-ISG-2023-01 Operator Licensing Programs ML22272A0492022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DRO-ISG-2023-02 Guidance for Assessing Exemption Requests from the Nuclear Power Plant Licensed Operator Staffing Requirements Specified in 10 CFR Part 50.54 ML22272A0512022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53- DRO-ISG-2023-03 Development of Scalable Human Factors Engineering Review Plans ML22272A0452022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DG-1414 Alternative Evaluation for Risk Insights (Aeri) Methodology ML22238A2542022-08-31031 August 2022 Slides - Reporting Events and Event Trending, 2022 Annual OAS Meeting ML22124A3012022-04-25025 April 2022 Dialog Presentation for Mashpee Wampanoag Tribe Regarding Pilgrim Liquid Effluent Discharges, April 25, 2022 ML22137A3232022-04-0505 April 2022 NRC 2022 and ACMUI 2021 Medical Event Summary Presentations ML22112A1042022-04-0505 April 2022 NRC Staff Medical Event Slide, April 5, 2022, FY21 ML22089A1892022-04-0505 April 2022 Advisory Committee on the Medical Uses of Isotopes (ACMUI) Spring Meeting 2022 Handout ML22094A1022022-04-0505 April 2022 Advisory Committee on the Medical Uses of Isotopes (ACMUI) Spring Meeting 2022 Revised Handout ML22097A1412022-03-24024 March 2022 Part 53 Rulemaking - Advanced Reactor Applications Presentation on March 24, 2022 ML22097A1312022-03-23023 March 2022 Decommissioning Rulemaking Presentation on March 23, 2022 ML22041A3352022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 5.84, Rev 1, Fitness-For -Duty Programs at New Reactor Construction Sites ML22042A1162022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Draft NUREG 1021, Rev 13, Operator Licensing Examination Standards for Power Reactors ML22042A1042022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 1.149, Rev 5, Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant Experience Requirements ML22041A5322022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline Standard Review Plan 19.1 Determining the Technical Adequacy of Probablistic Risk Assessment for Risk-Informed License Amendment Requests After Initial Fuel Load ML22041A5272022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline Standard Review Plan 19.0 Probablistic Risk Assessment and Accident Evaluation for New Reactors ML22041A4562022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.6.4 Access Authorization - Operational Program ML22041A4462022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.6.1 Physical Security-Combined License and Operating Reactors ML22041A4442022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.3 Emergency Planning 2024-01-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:NUREG
MONTHYEARNUREG-1437, Dfc, Site-Specific Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 2, Second Renewal, Regarding Subsequent License Renewal for Oconee Nuclear Station Units 1, 2, and 32024-02-29029 February 2024 NUREG-1437 Dfc, Site-Specific Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 2, Second Renewal, Regarding Subsequent License Renewal for Oconee Nuclear Station Units 1, 2, and 3 ML23355A1432024-01-17017 January 2024 January 17, 2024 Public Meeting Handout - Fusion Systems Rulemaking NUREG-1556, November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule2023-10-31031 October 2023 November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule ML23303A2212023-10-31031 October 2023 NUREG/BR-0096, Revision. 2, Instructions and Guidance for Completing Physical Inventory Summary Reports - NRC Form 327 Final Report NUREG-2266, Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels2023-08-31031 August 2023 NUREG-2266 Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels ML23123A3322023-06-0606 June 2023 SGI Pamphlet NUREG-1555, Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal2023-02-28028 February 2023 NUREG-1555 Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report2023-01-31031 January 2023 NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico2023-01-31031 January 2023 NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico ML22299A2382022-10-31031 October 2022 NUREG-2237, Supplement 1, Environmental Impact Statements for Holtec Internationals License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico NUREG-2248, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina. Final Report2022-07-31031 July 2022 NUREG-2248, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina. Final Report ML22181B0942022-07-31031 July 2022 NUREG-2237, Environmental Impact Statement for the Holtec International'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico Final Report NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance2022-07-29029 July 2022 NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance ML22175A2022022-06-30030 June 2022 NUREG/BR-0058, Rev. 5, Appendix K Monetary Valuation of Nonfatal Cancer Risk for Use in Cost-Benefit Analysis Dfc ML22175A2032022-06-30030 June 2022 NUREG/BR-0058 Dfc, Rev. 5, Appendix L Replacement Energy Costs NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material2022-03-31031 March 2022 NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material ML22042A1162022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Draft NUREG 1021, Rev 13, Operator Licensing Examination Standards for Power Reactors ML21209A9552021-07-31031 July 2021 NUREG-2239, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas Final Report ML21096A2922021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix F Data Sources - Dfc ML21096A2932021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix G Regulatory Analysis Methods and Data for Nuclear Facilities Other than Power Reactors - Dfc ML21096A2942021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix H Severe Accident Risk Analysis - Dfc ML21096A2952021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix I National Environmental Policy Act Cost-Benefit Analysis - Dfc ML21005A1532020-12-31031 December 2020 NUREG/BR-0520, State Programs at the U.S. Nuclear Regulatory Commission NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment2020-12-31031 December 2020 NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment NUREG-1556 Volume 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report2020-11-30030 November 2020 NUREG-1556, Vol. 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel2020-11-30030 November 2020 NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel NUREG-1507, Rev. 1, Minimum Detectable Concentrations with Typical Survey Instruments for Various Contaminants and Field Conditions2020-08-31031 August 2020 NUREG-1507, Rev. 1, Minimum Detectable Concentrations with Typical Survey Instruments for Various Contaminants and Field Conditions NUREG-2216, Review Plan for Transportation Packages for Spent Fuel and Radioactive Material2020-08-31031 August 2020 NUREG-2216 Review Plan for Transportation Packages for Spent Fuel and Radioactive Material ML20178A4332020-06-30030 June 2020 NUREG-BR-0204,Revision 3, Instructions for Completing the U.S. Nuclear Regulatory Commission'S Uniform Low-Level Radioactive Waste Manifest - Final Report ML20122A2202020-05-31031 May 2020 NUREG-2239 Dfc, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas ML20321A0972020-04-30030 April 2020 Chapter 3 - Principal Design Criteria Evaluation ML20321A0892020-04-30030 April 2020 Appendix 4A - Computational Modeling Software Technical Review Guidance ML20321A0982020-04-30030 April 2020 Chapter 4 - Structural Evaluation ML20321A0992020-04-30030 April 2020 Chapter 5 - Thermal Evaluation ML20321A1002020-04-30030 April 2020 Chapter 6 - Shielding Evaluation ML20321A1012020-04-30030 April 2020 Chapter 7 - Criticality Evaluation ML20321A1022020-04-30030 April 2020 Chapter 8 - Materials Evaluation ML20321A1122020-04-30030 April 2020 Chapter 17 - Technical Specifications Evaluation ML20321A1112020-04-30030 April 2020 Chapter 16 - Accident Analysis Evaluation ML20321A1102020-04-30030 April 2020 Chapter 15 - Quality Assurance Evaluation ML20321A1092020-04-30030 April 2020 Chapter 14 - Decommissioning Evaluation (SL) ML20321A1082020-04-30030 April 2020 Chapter 13 - Waste Management Evaluation (SL) ML20321A1072020-04-30030 April 2020 Chapter 12 - Conduct of Operations Evaluation ML20321A1062020-04-30030 April 2020 Chapter 11 - Operation Procedures and Systems Evaluation ML20321A1052020-04-30030 April 2020 Chapter 10B - Radiation Protection Evaluation for Dry Storage Systems (CoC) ML20321A1042020-04-30030 April 2020 Chapter 10A - Radiation Protection Evaluation for Dry Storage Facilities (SL) ML20321A0882020-04-30030 April 2020 Appendix a - Interim Staff Guidance (ISG) Incorporated Into NUREG-2215 ML20321A0902020-04-30030 April 2020 Appendix 4B - Pool and Pool Confinement Facilities ML20321A0922020-04-30030 April 2020 Appendix 8A - Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671-15 ML20321A0932020-04-30030 April 2020 Appendix 8B - Fuel Cladding Creep 2024-02-29
[Table view]Some use of "" in your query was not closed by a matching "". Category:Draft
MONTHYEARML23355A1432024-01-17017 January 2024 January 17, 2024 Public Meeting Handout - Fusion Systems Rulemaking NUREG-1556, November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule2023-10-31031 October 2023 November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule NUREG-2266, Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels2023-08-31031 August 2023 NUREG-2266 Dfc, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels NUREG-1555, Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal2023-02-28028 February 2023 NUREG-1555 Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal ML22098A3032023-01-31031 January 2023 Preliminary Safety Evaluation Report for the HI-STORM 100 Cask System, Certificate of Compliance No. 1014 Renewal, Docket No. 72-1014 ML22026A5242022-10-17017 October 2022 Preliminary Safety Evaluation Report for NAC International, Inc. Magnastor Storage System, Certificate of Compliance No. 1031, Amendment No. 10 ML22272A0452022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DG-1414 Alternative Evaluation for Risk Insights (Aeri) Methodology ML22272A0422022-09-29029 September 2022 10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DG-1413 Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants ML22041A2252022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 1.174, Rev 4, an Approach for Using Probablistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis ML22042A1162022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Draft NUREG 1021, Rev 13, Operator Licensing Examination Standards for Power Reactors ML22042A1042022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 1.149, Rev 5, Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant Experience Requirements ML22041A3352022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 5.84, Rev 1, Fitness-For -Duty Programs at New Reactor Construction Sites ML22041A3102022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 5.66, Rev 3, Access Authorization Program for Nuclear Power Plants ML22041A2832022-02-0909 February 2022 Document to Support the ACRS Subcommittee Meeting Redline RG 4.7, Rev 4, General Site Suitability Criteria for Nuclear Power Stations ML22041A2712022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 1.206, Rev 2, Applications for Nuclear Power Plants ML22041A2342022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 1.200, Rev 4, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML22041A2292022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline RG 1.187, Rev 4, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments ML21208A1202021-12-14014 December 2021 Draft Regulatory Guide DG-4032,(RG 4.2 Rev 4), Preparation of Environmental Reports for Nuclear Power Stations ML21168A3652021-09-0909 September 2021 Preliminary Safety Evaluation Report for Renewed CoC No. 1008, Amendment Nos. 0, 1, 2, and 3 ML21223A3402021-08-11011 August 2021 Information Sheet: Draft Environmental Impact Statement for the License Renewal of the Westinghouse Columbia Fuel Fabrication Facility ML20122A2202020-05-31031 May 2020 NUREG-2239 Dfc, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas ML20069G4202020-03-31031 March 2020 NUREG-2237 Dfc, Environmental Impact Statement for the Holtec International'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel and High Level Waste ML19212A7682019-07-31031 July 2019 NUREG-BR-0007 Dfc, Rev. 8 Instructions for the Preparation and Distribution of Materials Status Reports, U.S. Department of Energy/U.S. Nuclear Regulatory Commission Forms 742 and 742C. ML19059A4032019-06-27027 June 2019 Draft Regulatory Basis GTCC Rulemaking ML19157A1112019-06-0606 June 2019 Preliminary Draft Proposed Regulatory Guide 8.39, Release of Patients Administered Radioactive Materials, Revision 1 (Phase 1) for ACMUI Review with Note ML19008A0952019-01-11011 January 2019 01/23/2019 - Predecisional - Advisory Committee on Reactor Safeguards Sub-Committee Public Meeting Regulatory Guide 2.7 for Non-Power Production or Utilization Facility License Renewal (Rin 3150-AI96, NRC-2011-0087) NUREG-1280, Final Draft Guidance, Rev. 2, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Strategic Special Nuclear Material.2018-08-22022 August 2018 NUREG-1280, Final Draft Guidance, Rev. 2, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Strategic Special Nuclear Material. NUREG-2158, Final Draft Guidance, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Low-Enriched Uranium Enrichment Facilities.2018-08-22022 August 2018 NUREG-2158, Final Draft Guidance, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Low-Enriched Uranium Enrichment Facilities. ML18233A3742018-08-12012 August 2018 NUREG-1065, Rev. 3, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Special Nuclear Material of Low Strategic Significance - Final Draft Redline ML18045A0872018-01-25025 January 2018 Draft Safety Evaluation for Revised Emergency Plan at Vermont Yankee to Reflect ISFSI-only Configuration ML17145A3402017-05-0101 May 2017 Draft Regulatory Guide DG-5062 for Fuel Cycle Cyber Security Documents for June 8, 2017, ACRS Full Committee Meeting ML16273A1592016-10-0606 October 2016 Draft Regulatory Guide DG-5062: Cyber Security Programs for Nuclear Fuel Cycle Facilities (Proposed New Reg Guide) ML16221A0842016-08-10010 August 2016 Draft Regulatory Guide DG-5062 - Cyber Security Programs for Nuclear Fuel Cycle Facilities ML14310A3392015-09-0303 September 2015 Draft Regulatory Guide DG-5049, Independent Assessment of Nuclear Material Control and Accounting Systems ML15198A0212015-08-27027 August 2015 Draft Regulatory Basis - Cyber Security at Fuel Cycle Facilities ML13219B2042014-02-0606 February 2014 Draft Regulatory Guide (DG) - 3044, Corrective Action Programs for Fuel Cycle Facilities ML12087A0352013-11-18018 November 2013 Draft Regulatory Guide DG-3042, (Proposed Revision 2 of Regulatory Guide 3.50, Dated September 1989), Standard Format and Content for a License Application for an Independent Spent Fuel Storage Installation or a Monitored Retrievable Storag ML0506102582005-03-25025 March 2005 Sher Bahadur Memo Request to Waive CRGR Review of Proposed Revision to Regulatory Guide 3.71 Nuclear Criticality Safety Standards for Fuels and Materials Facilities ML0506103222005-03-25025 March 2005 John T. Larkin Memo Request to Waive Acrs/Acnw Review of Proposed Revision to Regulatory Guide 3.71, Nuclear Criticality Safety Standards for Fuels and Materials Facilities ML0321801641990-11-13013 November 1990 Draft Regulatory Guide, Format and Content for the License Application for the High-level Waste Repository. ML0319200771990-07-13013 July 1990 Topical Guidelines for the Licensing Support System 2024-01-17
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Text
Fusion Systems Rulemaking NOTE: The Nuclear Regulatory Commission (NRC) is making a select portion of the preliminary draft guidance available to the public solely for the purpose of providing information to the public and to provide preparatory material for upcoming public meetings. This language does not represent a final NRC staff position, nor has it been reviewed by NRC management. Therefore, the preliminary draft guidance may undergo significant revision during the rulemaking process.
The NRC is not requesting public comments on this preliminary draft guidance, and no stakeholder requests for a comment period will be granted at this stage in the rulemaking process.
Following Commission direction to proceed with the proposed rule, the NRC will seek public comment on the proposed rule along with the draft guidance in the Federal Register.
Preliminary Draft NUREG-1556, Volume 22 Consolidated Guidance About Materials Licenses Program-Specific Guidance About Fusion System Licenses Table Of Contents ABSTRACT FOREWORD LIST OF FIGURES LIST OF TABLES ACKNOWLEDGMENTS ABBREVIATIONS 1 PURPOSE OF REPORT 2 AGREEMENT STATES 2.1 Jurisdiction Determination 2.2 Reciprocal Recognition of Specific Licenses 3 MANAGEMENT RESPONSIBILITY 3.1 Commitments and Responsibilities 3.2 Safety Culture 4 APPLICABLE REGULATIONS 5 HOW TO FILE 5.1 Application Preparation 5.2 Where to File 5.3 Paper Applications 5.4 Electronic Applications 6 IDENTIFYING AND PROTECTING SENSITIVE INFORMATION 7 APPLICATION AND LICENSE FEES 8 CONTENTS OF AN APPLICATION 8.1 Item 1: License Action Type 8.2 Item 2: Name and Mailing Address of Applicant 8.2.1 Notification of Bankruptcy Proceedings 8.3 Item 3: Address(es) Where Licensed Material Will Be Used or Possessed 8.4 Item 4: Person to Be Contacted about This Application
Preliminary Draft NUREG-1556, Volume 22 (November 1, 2023) 8.5 Item 5: Radioactive Material 8.5.1 Unsealed and Sealed Byproduct Material 8.5.2 Financial Assurance and Recordkeeping for Decommissioning 8.5.3 Environmental Review 8.6 Item 6: Purpose(s) for Which Licensed Material Will Be Used 8.7 Item 7: Individual(s) Responsible for Radiation Safety Program and Their Training and Experience 8.7.1 Radiation Safety Officer 8.7.2 Individuals Authorized to Handle Licensed Material 8.8 Item 8: Training for Individuals Working in or Frequenting Restricted Areas 8.9 Item 9: Facilities and Equipment 8.9.1 General Description of Facility and Site 8.9.2 Access Control 8.9.3 Shielding 8.9.4 Fire Protection 8.9.5 Radiation Monitors 8.9.6 Tritium Handling System 8.9.7 Breeding Blankets 8.9.8 Heat Removal 8.9.9 Power Failures 8.10 Item 10: Radiation Protection Program 8.10.1 Audit Program 8.10.2 Radiation Monitoring Instruments 8.10.3 Material Control and Accountability 8.10.3.1 Activation Products 8.10.3.2 Tritium Production 8.10.4 Occupational Dose 8.10.4.1 Tritium Bioassay Program 8.10.5 Public Dose 8.10.6 Operating Procedures 8.10.7 Emergency Procedures 8.10.8 Surveys and Leak Tests 8.10.9 Maintenance 8.10.10 Transportation 8.10.11 Minimization of Contamination 8.10.12 Evaluation to Determine Need for Offsite Emergency Plan 8.10.12.1 Accident Scenarios 8.10.12.2 Offsite doses from accident scenarios 8.10.13 Effluent Monitoring 8.10.14 Environmental Surveillance 8.10.15 Security Program 8.11 Item 11: Waste Management 8.12 Item 12: License Fees 8.13 Item 13: Certification 9 LICENSE AMENDMENTS AND RENEWALS 9.1 Timely Notification of Transfer of Control 10 APPLICATIONS FOR EXEMPTIONS 11 TERMINATION OF ACTIVITIES Page 2 of 6 ADAMS Accession No. ML23258A172
Preliminary Draft NUREG-1556, Volume 22 (November 1, 2023)
APPENDICES APPENDIX A U. S. NUCLEAR REGULATORY COMMISSION FORM 313 APPENDIX B SUGGESTED FORMAT FOR PROVIDING INFORMATION REQUESTED IN ITEMS 5 THROUGH 11 OF NRC FORM 313 FOR A POSSESSION LICENSE APPENDIX C TYPICAL DUTIES AND RESPONSIBILITIES OF THE RADIATION SAFETY OFFICER APPENDIX D FACILITIES AND EQUIPMENT CONSIDERATIONS APPENDIX E SAMPLE AUDIT PROGRAM APPENDIX F RADIATION-MONITORING, INSTRUMENT SPECIFICATIONS, AND MODEL SURVEY INSTRUMENT AND AIR-SAMPLER CALIBRATION PROGRAM APPENDIX G METHODOLOGIES FOR DETERMINING DOSES FROM ACCIDENTAL RELEASES APPENDIX H GENERAL TOPICS FOR SAFE USE OF RADIONUCLIDES AND MODEL EMERGENCY PROCEDURES APPENDIX I TYPICAL NOTIFICATION AND REPORTING REQUIREMENTS APPENDIX J RADIATION SAFETY SURVEY TOPICS APPENDIX K MODEL LEAK TEST PROGRAM AND PROCEDURES APPENDIX L APPLICABLE U.S. DEPARTMENT OF TRANSPORTATION REGULATIONS APPENDIX M MODEL WASTE MANAGEMENT PROCEDURES APPENDIX N RADIATION SAFETY TRAINING APPENDIX O CHECKLIST FOR REQUESTS TO WITHHOLD PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE (UNDER 10 CFR 2.390)
APPENDIX P SAFETY CULTURE STATEMENT OF POLICY APPENDIX Q COMMENCEMENT OF CONSTRUCTION AT EXISTING AND PROPOSED BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIAL FACILITIES APPENDIX R TRAINING FOR RADIATION SAFETY OFFICERS AND FUSION OPERATORS APPENDIX S CONSTRUCTION MONITORING AND ACCEPTANCE TESTING APPENDIX T GUIDANCE FOR DEMONSTRATING THAT UNMONITORED INDIVIDUALS ARE NOT LIKELY TO EXCEED 10 PERCENT OF THE ALLOWABLE OCCUPATIONAL DOSE LIMITS APPENDIX U GUIDANCE FOR DEMONSTRATING THAT INDIVIDUAL MEMBERS OF THE PUBLIC WILL NOT RECEIVE DOSES EXCEEDING THE ALLOWABLE LIMITS Page 3 of 6 ADAMS Accession No. ML23258A172
Preliminary Draft NUREG-1556, Volume 22 (November 1, 2023) 8.8 ITEM 8: TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRICTED AREAS Regulations: 10 CFR 19.12, 10 CFR 30.33 Criteria: Individuals whose assigned duties involve exposure to radiation or radioactive material (from both licensed and unlicensed sources) and in the course of their employment are likely to receive in a year an occupational dose of radiation greater than 1 millisievert (mSv) [100 millirem (mrem)], must receive instruction commensurate with their duties and responsibilities, as required by 10 CFR 19.12, Instructions to Workers.
Discussion: Before beginning work with or in the vicinity of licensed material, all individuals who are likely to receive an occupational dose in excess of 1 millisievert (mSv) [100 millirem (mrem)] in a year must receive radiation safety training commensurate with their assigned duties and specific to the licensees radiation safety program. Each individual should also receive periodic refresher training at no more than 12-month intervals.
Licensees should not assume that safety instruction has been adequately covered by prior employment or academic training. Site-specific training should be provided for all individuals.
Particular attention should be given to persons performing work with radioactive materials that may require special procedures, such as hot cell work, waste processing, and animal handling.
Ancillary personnel (e.g., clerical, housekeeping, security) whose duties may require them to work in the vicinity of radioactive material (whether escorted or not) need to be informed about radiation hazards and the appropriate precautions. The licensee should assess each individuals involvement with licensed material and cover each applicable subject appropriately.
Training may be in the form of lecture, demonstrations, recorded media, or self-study, and should emphasize practical subjects important to the safe use and possession of licensed material. The guidance in Appendix N of this NUREG may be used to develop a training program. The program should consider both the topics pertinent for each group of workers and the method and frequency of training. The licensee should determine whether the training succeeded in conveying the desired information and adjust the training program as necessary.
This assessment may be performed by a written/oral test with pass/fail criteria or observation of the individual in the performance of assigned duties. Remedial training for missed test questions or other areas of apparent weakness should be conducted or additional formal training planned to cover deficient areas.
The person conducting the training should be a qualified individual (e.g., a person who meets the qualifications for RSO [radiation safety officer] or AU [authorized user] on the license and is familiar with the licensees program).
Response from Applicant: Submit a description of the radiation safety training program, including topics covered, groups of workers, assessment of training, qualifications of instructors, and the method and frequency of training.
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Preliminary Draft NUREG-1556, Volume 22 (November 1, 2023) 8.10.7 EMERGENCY PROCEDURES Regulations: 10 CFR 20.1101, 10 CFR 20.1801, 10 CFR 20.1802, 10 CFR 20 Subpart J, 10 CFR 20.2201, 10 CFR 20.2202, 10 CFR 20.2203, 10 CFR 30.32(k)(2), 10 CFR 30.50 Criteria: The licensee must have and follow emergency or abnormal event procedures appropriate for items listed in 10 CFR [Code of Federal Regulations]. Emergency procedures should include notifying the NRC during and after emergencies and abnormal events.
Discussion: Emergency or abnormal event procedures must be developed, maintained, and implemented to ensure that radiation doses received by occupational workers and members of the public during emergencies or abnormal events are ALARA [as low as reasonably achievable].
Copies of emergency procedures should be provided to all fusion energy system operators. In addition, the licensee must post current copies of emergency procedures applicable to licensed activities at each site. If posting of procedures is not practicable, the licensee may post a notice that describes the documents and states where they may be examined.
Accidents and emergencies can happen during any operation with radionuclides, including their transportation, use, production processes, transfer, and disposal. Such incidents can result in contamination or release of material to the environment, and unintended radiation exposure to workers and members of the public. In addition, such incidents as loss or theft of licensed material, sabotage, fires, and floods can jeopardize the safety of personnel and members of the public. It may therefore be necessary to develop written procedures to minimize, as much as possible, the impact of these incidents on personnel, members of the public, and the environment. Applicants who plan to possess quantities of material in excess of the applicable amounts listed in 10 CFR 30.72, Schedule C, may also be required to submit an "Emergency Response Plan for Responding to a Release" see Section 8.10.12 for more information.
Applicants should establish written procedures to handle events ranging from a minor spill to a major accident that may require intervention by outside emergency response personnel. Written procedures should be included for specific accident scenarios such as spills or releases outside a containment enclosure, malfunction of air supply or exhaust systems, personnel overexposures, unauthorized entry, and natural phenomena. These procedures should include provisions for immediate response, afterhours notification, handling of each type of emergency, equipment, and the appropriate roles of users and the radiation safety staff. Except for minor spills or releases of radioactivity that can be controlled and cleaned up by the user, the licensee staff should have a clear understanding of their limitations in an emergency, along with step-by-step instructions and clear guidelines for whom to contact.
The procedures should clearly identify telephone numbers of the RSO or other individuals who can provide assistance, including the manufacturer (or distributor) and State and local agencies.
The procedures should include actions to be taken immediately after discovering the emergency or abnormal event. Emergency procedures should also include notifying the NRC when any event specified in Appendix I of this NUREG occurs. Licensees that possess an aggregated Category 1 or Category 2 quantity of radioactive material must be able to monitor and immediately detect, assess, and respond to any actual or attempted unauthorized entries into security zones and coordinate, to the extent practicable, with local law enforcement authorities for responding to threats to the licensees facility.
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Preliminary Draft NUREG-1556, Volume 22 (November 1, 2023)
Licensees should have a sufficient number of appropriate and calibrated survey instruments readily available. All equipment should be periodically inspected for proper operation and replenished as necessary.
The level of detail should be sufficient to demonstrate that regulatory requirements have been addressed. Appendix H of this NUREG includes model emergency procedures. Applicants may adopt these procedures or develop their own, incorporating the safety features included in these model procedures.
Response from Applicant: The applicant should state that emergency procedures will be developed and documented before production of licensed material. In addition, the applicant should state that emergency procedures will be implemented and maintained.
The applicant should submit a statement that "Procedures will be revised only if:
(1) the changes are reviewed and approved by the licensee management and the RSO in writing, (2) the licensee staff is provided training in the revised procedures prior to implementation, (3) the changes are in compliance with NRC regulations and the license, and (4) the changes do not degrade the effectiveness of the program."
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