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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Meeting Presentation--Fusion Systems Proposed Rule NUREG-1556, November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule2023-10-31031 October 2023 November 1, 2023 Public Meeting Handout Preliminary Draft Guidance (NUREG-1556, Volume 22) Fusion Systems Proposed Rule ML23240A7182023-08-29029 August 2023 Slides - Public Meeting on Regulatory Basis for Rb-82 Generators,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: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
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ACRS Future Plants Subcommittee 10 CFR Part 53 Licensing and Regulation of Advanced Nuclear Reactors July 20, 2020 1
Background
- Advance Notice of Proposed Rulemaking, Approaches to Risk-Informed and Performance-Based Requirements for Nuclear Power Reactors, dated May 4, 2006 (71 FR 26267)
- NRCs Vision and Strategy report (12/16) for non-light-water reactors and related implementation action plans identified a potential rulemaking to establish a regulatory framework
- Nuclear Energy Innovation and Modernization Act (NEIMA; Public Law 115-439) signed into law in January 2019 requires the NRC to complete a rulemaking to establish a technology-inclusive, regulatory framework for optional use for commercial advanced nuclear reactors no later than December 2027 2
Background - NEIMA (1) ADVANCED NUCLEAR REACTORThe term advanced nuclear reactor means a nuclear fission or fusion reactor, including a prototype plant with significant improvements compared to commercial nuclear reactors under construction as of the date of enactment of this Act, (9) REGULATORY FRAMEWORKThe term regulatory framework means the framework for reviewing requests for certifications, permits, approvals, and licenses for nuclear reactors.
(14) TECHNOLOGY-INCLUSIVE REGULATORY FRAMEWORKThe term technology-inclusive regulatory framework means a regulatory framework developed using methods of evaluation that are flexible and practicable for application to a variety of reactor technologies, including, where appropriate, the use of risk-informed and performance-based techniques and other tools and methods.
3
SECY-20-0032, Rulemaking Plan
- SECY-20-0032, Rulemaking Plan on Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors, dated April 13, 2020
- Proposing a new 10 CFR part that could address performance requirements, design features, and programmatic controls for a wide variety of advanced nuclear reactors throughout the life of a facility.
- Focus the rulemaking on risk-informed functional requirements, building on existing NRC requirements, Commission policy statements, and recent activities (e.g.,
SECY-19-0117)
4
Technology Inclusive Regulatory Framework Project Life Cycle Requirements Functional System Construction Operation Retirement Definition Design Design
- Fundamental Safety Functions
- Prevention, Mitigation, Testing Surveillance Performance Criteria Maintenance (e.g., F-C Targets)
- Normal Operations Configuration (e.g., effluents) Control
- Other Design Changes Plant/Site (Design, Construction, Configuration Control)
Clarify Controls Analyses (Prevention, Mitigation, Compare to Criteria) and Distinctions Between Plant Documents (Systems, Procedures, etc.)
LB Documents (Applications, SAR, TS, etc.)
5
Example - Possible Layout
- Technology-Inclusive Safety Objectives o Regulatory limits, safety goals
- Construction and Manufacturing Requirements
- Requirements for Operation
- Decommissioning Requirements
- Applications for Licenses, Certifications and Approvals
- Maintaining and Revising Licensing Basis Information
- Reporting and Administrative Requirements 6
NRC Staff White Paper
- The NRC staff developed a white paper (ADAMS ML20195A270) to support discussions with ACRS and other stakeholders
- Soliciting information that:
- 1) Defines the scope of stakeholder interest in a rulemaking to develop a technology inclusive framework for advanced nuclear reactors,
- 2) Identifies major issues and challenges related to technology-inclusive approaches to licensing and regulating a wide variety of advanced nuclear reactor designs,
- 3) Supports prioritizing and developing plans to resolve identified issues within the rulemaking for the wide variety of advanced nuclear reactor designs, and
- 4) Supports the development of the proposed rule and related guidance.
- Staff receptive to feedback on any aspect of developing a technology-inclusive regulatory framework to support the regulatory objective, whether or not in response to a question listed in this white paper or future solicitations.
7
Part 53 Rulemaking Objectives
- 1) Provide reasonable assurance of adequate protection of the public health and safety and common defense and security at reactor sites at which advanced nuclear reactor designs are deployed, to at least the same degree of protection as required for current-generation light water reactors;
- 2) Protect health and minimize danger to life or property to at least the same degree of protection as required for current-generation light water reactors;
- 3) Provide greater operational flexibilities where supported by enhanced margins of safety that may be provided in advanced nuclear reactor designs;
- 4) Ensure that the requirements for licensing and regulating advanced nuclear reactors are clear and appropriate; and
- 5) Identify, define, and resolve additional areas of concern related to the licensing and regulation of advanced nuclear reactors.
8
Questions for Public Feedback
- 1. Regulatory Objectives: Are the regulatory objectives, as articulated above, understandable and achievable? If not, why not? Should there be additional objectives? If so, please describe the additional objectives and explain the reasons for including them.
- 2. Scope and Types of Advanced Nuclear Reactors: Should the scope of the rulemaking be limited to advanced nuclear reactors as defined in NEIMA or should the scope include all future applications for licenses, certifications, or approvals for commercial nuclear reactors regardless of design?
9
Questions for Public Feedback
- 3. Technical Requirements versus Licensing Process: Should the framework focus only on those regulations related to technical standards (i.e., design, operational and programmatic requirements) and rely on the existing licensing processes in Parts 50 (e.g., construction permit and operating license) and 52 (e.g., early site permit, combined license, etc.) or should the framework develop a new alternative licensing process that looks different than the existing processes? If the latter, what should this new licensing process look like? Should this new process be self-contained, such that it would provide its own licensing, procedural, administrative, and reporting requirements?
10
Questions for Public Feedback
- 4. Performance Criteria: NEIMA calls for a technology-inclusive framework for advanced nuclear reactors, which encompasses a wide range of reactor technologies and power levels. To what extent should the NRC try to define a single set of performance criteria for all technologies and sizes (e.g., estimated offsite doses from postulated events),
versus developing specific regulatory approaches for different categories of advanced nuclear reactors such as microreactors and fusion reactors?
11
Questions for Public Feedback
- 5. Risk Metrics: In a risk-informed performance-based regulatory regime, should risk metrics be included in the regulations? Possible examples of risk metrics include the quantitative health objectives described in the NRCs Safety Goals for the Operation of Nuclear Power Plants Policy Statement (51 FR 28004, Aug. 4, 1986, as corrected and republished, 51 FR 30028, Aug. 21, 1986) and the frequency-consequence targets described in SECY 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.
12
Questions for Public Feedback
- 6. Facility Life Cycle: How could the new Part 53 licensing and regulatory framework align with the design, construction, operation, and decommissioning phases of an advanced nuclear reactor facilitys life cycle?
- 7. Definitions: Should terms in the new Part 53 have identical definitions to terms in Parts 50 and 52? For example, SECY-19-0117 proposes to accept definitions for terms such as safety related and design basis event for non-light water reactors applications that differ from the definitions provided in 10 CFR Part 50. If possible, please provide alternative terminology for non LWR technologies.
13
Questions for Public Feedback
- 8. Performance-Based Regulation: How should the requirements developed for this alternative regulatory framework incorporate performance-based concepts such as those described in NUREG/BR-0303, Guidance for Performance-Based Regulation?
14
Questions for Public Feedback
- 9. Identifying Levels of Protection: Regulatory requirements in Parts 50 and 52 have been imposed as either needed to:
- 1) ensure a facility provides adequate protection to the health and safety of the public and is in accord with the common defense and security; or 2) provide a substantial increase in the overall protection of the public health and safety or the common defense in security when the costs of implementation are justified in view of the increased protection. Should specific requirements developed in this Part 53 rulemaking be identified as either needed to provide reasonable assurance of adequate protection or justified as cost-effective safety improvements?
15
Questions for Public Feedback
- 10. Integrated Approach to Rulemaking: In developing the requirements for this alternative regulatory framework, how can an integrated approach be developed to address areas such as safety, security, emergency preparedness, and other means to prevent or mitigate the potential release of radionuclides from an advanced nuclear reactor?
16
Questions for Public Feedback
- 11. Consistency with Historical Standards: SECY-19-0117 describes a methodology that is meant to support the licensing process through identifying key safety functions, events that might challenge those functions, performance criteria for equipment and related programmatic controls, and defense in depth. The methodology uses risk-informed and performance-based criteria that are derived from existing regulations related to potential offsite doses and from the NRCs Safety Goal Policy Statement (51 FR 30028; dated August 21, 1986). Should this rulemaking use these existing criteria or should this opportunity be used to adopt or develop alternative criteria? If so, please describe possible alternatives and explain the reasons for using them within the regulatory framework being developed for advanced nuclear reactors.
17
Questions for Public Feedback
- 12. Quality Assurance: Should quality assurance, as it is currently defined in Appendix B to Part 50, be a requirement in the new risk-informed, performance-based regulatory framework?
Alternatively, should NRC regulations defer to internationally recognized, independent certification schemes for assessing quality processes at commercial nuclear facilities and at suppliers of equipment and services?
18
Questions for Public Feedback
- 13. Stakeholder Documents, Standards, Guidance: The NRC encourages active stakeholder participation through development of proposed supporting documents, standards, and guidance. In such a process, the proposed documents, standards, and guidance would be submitted to and reviewed by NRC staff, and the NRC staff could endorse them, if appropriate. Is there any interest by stakeholders to develop proposed supporting documents, standards, or guidance?
19
Questions for Public Feedback
- 14. Other Issues: Are there significant issues, possible approaches, or other topics related to the initial crafting of a regulatory framework for advanced nuclear reactors that are not addressed in the above questions? If so, please identify the subject areas and, if possible, provide a suggestion on how the new framework could resolve the issue or incorporate a proposed approach.
20
Part 53 Rulemaking 21
Backup Slide - Integrated Approach Siting near densely Functional populated areas Containment EP for SMRs (SECY-18-0096) and ONTs Licensing Modernization (SECY-18-0103)
Project Insurance and Liability Environmental Reviews Consequence Based Security (SECY-18-0076) 22