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Category:Brochure
MONTHYEARML23123A3322023-06-0606 June 2023 SGI Pamphlet ML21055A5002021-02-24024 February 2021 Cnsc/Nrc Cooperation in Pre-Licensing Review Activities for Advanced Reactors ML19057A2542019-03-11011 March 2019 03/11-14/2019 - RIC 2019 Poster - Making the Rules: the Nrc'S Transparent Process and Centralized Organization for Rulemaking ML19064B4092019-03-0707 March 2019 Enclosure 2 - SLO Program Brochure ML19064B4062019-03-0707 March 2019 Enclosure 1 - NUREG/BR-0520, Revision 1 ML18162A1222018-05-21021 May 2018 Holtec-How to Comment with Email address-Spanish ML18162A1212018-05-21021 May 2018 Holtec-How to Comment with Email Address 2023-06-06
[Table view]Some use of "" in your query was not closed by a matching "". 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Meeting Presentation--Fusion Systems Proposed Rule NUREG-1556, November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule2023-10-31031 October 2023 November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule ML23240A7182023-08-29029 August 2023 Slides - Public Meeting on Regulatory Basis for Rb-82 Generators,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:Slides and Viewgraphs
MONTHYEARML24029A2362024-01-30030 January 2024 Preliminary Results of the Environmental Review, Subsequent License Renewal ML23355A1442024-01-17017 January 2024 January 17, 2024 Public Meeting Presentations - 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) SECY-21-0109, 11/2/2023 ACRS Full Committee Meeting: Increased Enrichment of Conventional and Accident Tolerant Fuel Designs for Light-Water Reactors2023-11-0202 November 2023 11/2/2023 ACRS Full Committee Meeting: Increased Enrichment of Conventional and Accident Tolerant Fuel Designs for Light-Water Reactors ML23258A1712023-11-0101 November 2023 November 1, 2023 Public Meeting Presentation--Fusion Systems Proposed Rule ML23258A1472023-10-11011 October 2023 October 11, 2023 Public Meeting Presentation--Fusion Systems Proposed Rule ML23241A9492023-09-0606 September 2023 09-06-2023 Rulemaking: Proposed Rule: Public Meeting Slides - ASME 2021-2022 Code Editions 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 ML23200A3452023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Jack Parrott on Decommissioning ML23186A0212023-06-0808 June 2023 Spent Nuclear Fuel Shipments in the Us: Addressing the Myths ML23123A3292023-06-0606 June 2023 SGI Training ML13108A326 ML23123A3322023-06-0606 June 2023 SGI Pamphlet ML23130A0332023-05-11011 May 2023 NRC Presentation Browns Ferry Subsequent License Renewal Pre-application Meeting, Environmental Overview ML23062A7352023-04-14014 April 2023 Tanana Chiefs Conference 2023 Annual Convention NRC Presentation ML23102A0522023-04-12012 April 2023 Meeting Slide: Information Meeting with Federally-Recognize Tribes Regarding the Proposed Rule Renewing Nuclear Power Plant Operating Licenses Environmental Review 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 ML23069A0132023-03-10010 March 2023 Pubic Meeting Slides - Proposed Rule: Renewing Nuclear Power Plant Operating Licenses - Environmental Review (Rin 3150-AK32; NRC-2018-0296) 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 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 ML22238A2542022-08-31031 August 2022 Slides - Reporting Events and Event Trending, 2022 Annual OAS Meeting ML22203A0192022-08-30030 August 2022 Patient Release Brochure Medical-Chinese Language ML22203A0202022-08-30030 August 2022 Patient Release Brochure Medical-French Language ML22203A0212022-08-30030 August 2022 Patient Release Brochure Medical-Spanish Language ML22221A1402022-08-10010 August 2022 Enclosure 2 - SGI Awareness Training ML22221A1412022-08-10010 August 2022 Enclosure 3 - Protection of SGI Pamphlet 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 ML22088A2252022-03-30030 March 2022 Kairos Environmental Audit Closeout Meeting Presentation 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 ML22140A3102022-03-0808 March 2022 clarkt-hv-th24 ML22046A0782022-03-0808 March 2022 RIC 2022 Digital Exhibit - VLSSIR in NMSS ML21302A2472021-11-0404 November 2021 Nuclear Waste Technical Review Board - NRCs Development and Use of Performance Assessment Presentation Slides ML21285A0412021-10-13013 October 2021 Summary of September 29, 2021 Meeting with the U.S. Fish and Wildlife Service Regarding Crocodile Monitoring at Turkey Point ML21271A1392021-09-28028 September 2021 ISFSI Pre-Application Meeting Presentation by Pacific Gas & Electric for License Amendment Request to Revise the License and Technical Specifications ML21236A3192021-08-26026 August 2021 August 26, 2021 Public Meeting Presentation of the Draft Environmental Impact Statement for the Columbia Fuel Fabrication Facility License Renewal ML21201A0282021-07-23023 July 2021 Handout for Meeting with Holtec on HI-STORM 100 Amendment No. 16 (July 27, 2021) ML21208A2222021-07-14014 July 2021 2-6 Survey Issues with Excavations from Recent Decommissionings 2024-01-30
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
Protection of Safeguards Information Requirements for Tribes Participating in the Advance Notification of Irradiated Reactor Fuel Shipments
General Requirement Information and material that meets the criteria set forth in Title 10 of the Code of Federal Regulations (10 CFR) 73.21, Protection of Safeguards Information: Performance Requirements, must be protected from unauthorized disclosure. The U.S. Nuclear Regulatory Commission (NRC) has determined that the information contained in the advance notification for shipments of irradiated reactor fuel and certain nuclear wastes is designated as Safeguards Information (SGI) due to its security significance. Each person who produces, receives, or acquires SGI shall ensure that it is protected against unauthorized disclosure. To meet this requirement, organizations and persons shall establish, implement, and maintain a system to protect SGI consistent with the requirements set forth in 10 CFR 73.21.
Persons Subject to These Requirements Any person who produces, receives, or acquires SGIregardless of whether he or she is a member of an entity or organization that the NRC regulatesis subject to the requirements (and sanctions) of 10 CFR 73.21. An organization or person that possesses SGI must inform contractors and suppliers that handle SGI of the existence of regulatory requirements and the need for proper protection (see additional guidance prescribed by 10 CFR 73.22 and referenced within this guidance document below). Federal, State, Tribal, or local law enforcement agencies with access to SGI also are subject to the regulatory requirements of 10 CFR 73.21. However, the NRC presumes that these law enforcement agencies have adequate information protection systems. The requirements under which entities may transfer information to a third party (i.e., on a need-to-know basis), still apply to law enforcement agencies, as do sanctions for unlawful disclosure. Entities or organizations that have arrangements with law enforcement agencies should advise them of the existence of the information protection requirements under 10 CFR 73.22 Protection of Safeguards Information:
Specific Requirements.
2 United States Nuclear Regulatory Commission
Criminal and Civil Sanctions The Atomic Energy Act of 1954, as amended, (AEA, the Act), Section 147a, explicitly provides that any person, whether or not a licensee of the Commission, who violates any regulations adopted under this section shall be subject to the civil monetary penalties of section 234 of this Act. Furthermore, willful violation of any regulation or Order governing SGI is a felony subject to criminal penalties in the form of fines or imprisonment, or both. (See Sections 147b and 223 of the Act.)
Information to be Protected The types of information and documents that must be protected as SGI are described in 10 CFR 73.22(a) and include, but are not limited to, nonpublic, security-related requirements such as the following:
(1) Physical protection. This requirement includes non-public security related information not classified as Restricted Data or National Security Information about physical protection of source, byproduct, or special nuclear material.
(2) Physical protection in transit. This requirement includes information about the transportation of, or delivery to a carrier for transportation of, irradiated reactor fuel, including the following:
(i) Schedules and itineraries for specific shipments of source material, byproduct material, high-level nuclear waste, or irradiated reactor fuel. Schedules for shipments of source material, byproduct material, high-level nuclear waste, or irradiated reactor fuel are no longer controlled as SGI 10 days after the last shipment of a current series.
(ii) A rrangements with and specific capabilities of local police response forces (information that is not already publicly available) and locations of safe havens identified along the transportation route.
Protection of Safeguards Information 3
Conditions for Access Consistent with the requirements set forth in 10 CFR 73.22(b), to gain access to SGI for its employees, agents, or contractors, an entity or organization must have an appropriate need-to-know determination from the possessor of the SGI, a Federal Bureau of Investigation (FBI) fingerprint criminal-history records check, and be deemed trustworthiness and reliability based on a background check. The Tribal official, Tribal officials designated representative, and Tribal law enforcement personnel are relieved from the requirement for an FBI fingerprint criminal-history records check and other elements of the background check prior to being granted access to SGI information.
The NRC has determined that Tribal officials, Tribal officials designated representatives, and Tribal law enforcement personnel who are designated to receive advance notifications for shipments of irradiated reactor fuel and certain nuclear wastes that may be transported within or across Tribal reservations have established a need to know for access to SGI.
Protection While in Use Consistent with the requirements set forth in 10 CFR 73.22(c), while in use, SGI shall be under the control of an authorized individual who meets the requirements for access to SGI. The primary consideration is limiting SGI access to those who have authorized access and an established need-to-know for the information. For Tribes, this individual is the person that has met the SGI access requirements and is designated by the Tribal official to receive the advance notifications for shipments of irradiated reactor fuel and certain nuclear wastes that may be transported within or across Tribal reservations.
Protection While in Storage Consistent with the requirements set forth in 10 CFR 73.22(c), while unattended, SGI shall be stored in an approved security storage container, meaning (1) a steel filing cabinet (located within a controlled access facility) equipped with a steel locking bar and a three-position, changeable combination GSA approved padlock, or (2) a security filing cabinet 4 United States Nuclear Regulatory Commission
marked General Services Administration Approved Security Container on the exterior of the top drawer or door. Entities shall limit knowledge of lock combinations or access to keys protecting SGI to a minimum number of personnel who have a need-to-know for operating purposes and are otherwise authorized access to SGI in accordance with regulatory requirements. Entities shall strictly control access to lock combinations or keys to prevent their disclosure or release to an unauthorized individual.
Reproduction of Matter Containing SGI Consistent with the requirements set forth in 10 CFR 73.22(e), possessors of SGI may reproduce it to the minimum extent necessary without permission of the originator. Digital copiers that scan and retain images of documents represent a potential security concern. Entities and organizations must evaluate copiers used to reproduce SGI to ensure that unauthorized personnel cannot obtain SGI through memory retention or network connectivity. Organizations should clearly identify copiers used to reproduce SGI as being approved for the reproduction of SGI and place them in a location that discourages surreptitious use and ensures control over the machines immediate proximity.
Transportation of Documents and Other Matter Consistent with the requirements set forth in 10 CFR 73.22(f), when transporting documents containing SGI outside an authorized place of use or storage, possessors of the information shall enclose it in two sealed envelopes or wrappers. The inner envelope or wrapper shall contain the name and address of the intended recipient and be marked on both sides, top and bottom, with the words Safeguards Information.
The outer envelope or wrapper must be opaque, contain the address of the intended recipient and the address of the sender, and must not bear any markings or indication that the envelope or wrapper contains SGI.
Any commercial delivery company that offers computerized tracking features may transport SGI (U.S. First Class, Registered, Express, or Certified Mail). Any individual authorized access under regulatory requirements may also transport SGI. Within a facility, individuals may transport SGI in a single opaque envelope or wrapperor without single Protection of Safeguards Information 5
or double wrappingprovided that employees take adequate measures to protect the material against unauthorized disclosure. Individuals who transport SGI should keep the documents in their personal possession at all times or ensure that the information is appropriately secured to prevent unauthorized disclosure.
Processing of SGI on Electronic Systems Consistent with the requirements set forth in 10 CFR 73.22(g), entities and organizations may transmit SGI over an open network, provided that the e-mail system encrypts messages on a standalone computer or computer system using a method that the NRC has approved. In such instances, the organization will select a commercially available encryption system that the National Institute of Standards and Technology (NIST) has validated as conforming to Federal Information Processing Standard (FIPS) 140-2, Security Requirements for Cryptographic Modules, or later. Request for the approval of a selected encryption system must be forwarded to the NRC prior to use for encrypting and transmitting SGI.
The NRC only approves encryption methods for SGI that meet FIPS 140-2 or later. NIST maintains a listing of all validated encryption systems at http://csrc.nist.gov/cryptval/140-1/1401val.htm.
Telecommunications Consistent with the requirements set forth in 10 CFR 73.22(f),
organizations may not transmit SGI over unprotected telecommunications circuits except under emergency or extraordinary conditions. Only an NRC-approved secure electronic device, such as a secure facsimile or secure telephone device, shall transmit SGI outside an authorized place of use or storage, provided that the transmitter and receivers implement procedures that will ensure that SGI is protected before and after the transmission or e-mail. For the purpose of this requirement, emergency or extraordinary conditions are defined as any circumstances that require immediate communications to report, summon assistance for, or respond to a security event (or an event that has potential security significance).
6 United States Nuclear Regulatory Commission
Destruction Consistent with the requirements set forth in 10 CFR 73.22(i), possessors of documents containing SGI shall destroy them when they are no longer needed. Burning and shredding are acceptable methods of destruction that prevent members of the public at large from reconstructing documents by means available to them. A document is considered completely destroyed when it is in pieces measuring one-quarter inch or smaller and mixed with several pages or documents. The pieces, when measured, must not be wider than one-quarter inch vertically or horizontally.
Additional information on the protection of SGI is available in Regulatory Guide 5.79, PROTECTION OF SAFEGUARDS INFORMATION, which is available on the NRC website at http://pbadupws.nrc.gov/docs/ML1032/ML103270219.pdf Protection of Safeguards Information 7
U.S. Nuclear Regulatory Commission NUREG/BR-0362 October 2012