ML23004A056
ML23004A056 | |
Person / Time | |
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Issue date: | 06/28/2022 |
From: | Ian Jung NRC/NRR/DANU/UTB1 |
To: | |
References | |
Download: ML23004A056 (1) | |
Text
Development of Regulations and Guidance for Advanced Reactors Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors June 28 - July 2, 2022 Ian Jung, USNRC
U.S. Nuclear Regulatory Commission The NRC's mission is to license and regulate the Nation's civilian use of radioactive materials to provide reasonable assurance of adequate protection of public health and safety and to promote the common defense and security and to protect the environment.
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NRC is preparing for a Variety of Advanced Nuclear Technologies Research Molten Salt Small and Test Reactors Modular Reactors Reactors A number of current and EVOLVING potential applications High-LANDSCAPE Temperature Liquid Metal Micro-Gas-Cooled Cooled Fast Reactors Reactors Reactors
- Many different reactor technologies
- Range of sizes from < 10 MWt to 600 MWt
- Multiple reactors on a single site
- Hazards vary with power level and radionuclide inventory 3
4 Vision & Strategy Nuclear Energy Innovation and Modernization Act (NEIMA; Public Law 115-439), dated 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 5
Modernizing the Regulatory Framework 10 CFR Part 53 Functional Emergency Containment Preparedness Physical Environmental Security Review Technology-Inclusive, Risk-Informed, and Performance-Based Regulatory Framework Licensing Fuel Modernization Qualification Project (LMP) Content of Siting Application 10 CFR = Title 10 of the Code of Federal Regulations 6 NRC Website on advanced reactors
10 CFR Part 53 is being developed
- Optional rule; 10 CFR Parts 50 and 52 remain for use
- Promote regulatory stability, predictability, and clarity
- Reduce requests for exemptions from the current requirements in 10 CFR Parts 50 and 52
- Establish new requirements to address advanced reactor technologies
- Recognize technological advancements in reactor design
- Credit the response of advanced nuclear reactors to postulated event sequences, including slower response times and relatively small and slow release of fission products NRC Website on 10 CFR Part 53 rulemaking 10 CFR Part 53, Risk-Informed, Technology Inclusive Regulatory Framework for Advanced Reactors 7
Part 53 Risk-Informed Parts 50/52 Approach
- Frequency & Consequence-Oriented
- Prescriptive Requirements Requirements
- Optimized for Specific Technology Technology-Inclusive Explicit Consideration of Defense-In-vs
- Augmented for Operating Experience Depth
- Conservative Assumptions &
- Expanded Use of Graded Performance Analyses Requirements 10 CFR Part 53 would evolve existing requirements into a modern, risk-informed, performance-based approach
Part 53 rulemaking addresses plant lifecycle with appropriate flexibilities and safety focus 9
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10 CFR Part 53 Subpart B - Technology-Inclusive Safety Requirements
- Safety Objectives (B) Safety Criteria What function(s)
- Safety Criteria (e.g., a barrier, cooling) are needed to satisfy safety criteria
- Safety Functions (B) Safety Functions
- Licensing Basis Events What design features (e.g., a structure, system)
- Defense-in-Depth are provided to fulfill the safety function(s)
(DID) (C) Design Features (and Human Actions)
- Normal Operations What design criteria (e.g., leak rate, cooling and Protection of capacity) are needed for design feature Plant Workers (C) Functional Design Criteria (Personnel; Concept of Operations) 10
- Consideration of stakeholder requests for an option for a more traditional, deterministic licensing framework for advanced reactors 10 CFR Part 53
- Provides technology-inclusive alternatives to LWR-centric Traditional requirements in 10 CFR Parts 50 and 52 Approach
- Aligns with international standards (i.e., Internal Atomic Energy Agency)
- Guidance for systematic searches for hazards, initiating events, and event sequences 11
Rulemaking Schedule 12
Other rulemaking activities
- Physical Security
- Establish alternative, consequence-oriented physical security requirements for advanced reactors
- The rule and guidance under development
- Provide alternative, consequence-oriented emergency preparedness requirements for SMRs and other new technologies
- The proposed rule is with the Commission
- DG-1350 provides a technology-inclusive, RIPB approach to radiological dose assessment
- Generic Environmental Impact Statement
- Streamline the environmental review process
- Technology-neutral plant parameter envelope and site parameter envelope approach
- The draft proposed rule was provided to the Commission (SECY-21-0098) 13
Technology-inclusive, risk-informed, and performance-based methodology to inform licensing basis and content of application for licenses, certifications, and approvals of non-Regulatory LWRs Guide (RG)
Endorses Nuclear Energy Institute 1.233 (NEI) 18-04 with clarifications 14
Risk-informed performance-based guidance for non-LWR licensing basis development NEI 18-04 Known as the Licensing Modernization Project (LMP)
Technology-inclusive methodology for:
- Selecting licensing basis events
- Classifying structures, systems, and components (SSCs), and associated risk-informed special treatments
- Determining the defense-in-depth (DID) adequacy 15
NEI 18-04 Methodology 16
NEI 18-04: The Frequency-Consequence Target 17
NEI 18-04: SSC Safety Categories 18
Content of Application Guidance
- To develop technology-inclusive, risk-informed and performance-based application guidance
- In support of 10 CFR Parts 50, Part 52, and Part 53 applications
- TICAP (Industry-led): Guidance to develop the content for LMP-based portions of the safety analysis report
- ARCAP (NRC-led): Guidance that describes the contents for an entire application
- Guidance will be revised in accordance with the 10 CFR Part 53 rulemaking underway NRC Website on ARCAP/TICAP ARCAP: Advanced Reactor Content of Application Project TICAP: Technology Inclusive Content of Application Project (TICAP) 19
ARCAP/TICAP - Nexus Outline Safety Analysis Report (SAR) - Additional Portions of Based on TICAP Guidance Application
- 1. General Plant Information, Site
- Technical Specifications Description, and Overview of the
- Technical Requirements Manual Safety Case
- Quality Assurance Plan (design)
- 2. Methodologies and Analyses
- 3. Licensing Basis Event Analysis (design)
- 4. Integrated Evaluations
- Quality Assurance Plan
- 5. Safety Functions, Design Criteria, and (construction and operations)
SSC Safety Classification Audit/inspection of Applicant
- 6. Safety-Related SSC Criteria and Records
- Physical Security Plan Capabilities
- Calculations
- 7. Non-Safety-Related with Special
- Analyses program Treatment SSC Criteria and
- System Descriptions
- SNM material control and Capabilities
- Design Drawings accounting plan
- Design Specifications
- Cyber Security Plan
- 8. Plant Programs
- Procurement Specifications
- Fire Protection Program Additional SAR Content - Outside the
- Probabilistic Risk Assessment (operational)
Scope of TICAP
- Radiation Protection Program
- 9. Control of Routine Plant Radioactive
- Offsite Dose Calculation Manual Effluents, Plant Contamination, and
- Inservice inspection/Inservice Solid Waste testing Program
- Environmental Report
- 10. Control of Occupational Doses
- Site Redress Plan
- 11. Organization and Human-System
- Exemptions, Departures, and Considerations Variances
- 12. Post-construction Inspection, Testing
- Facility Safety Program (under and Analysis Programs consideration for 10 CFR Part 53 applications)
- SAR structure based on clean sheet approach
- Additional contents of application outside of SAR are still under discussion. The above list is draft and for illustration purposes only.
- NEI 21-07, Technology Inclusive Guidance for Non-Light Water Reactors Safety Analysis Report Developing a Content for Applicants Utilizing NEI 18-04 Regulatory Methodology Guide for TICAP
- Chapters 1 - 8 of the safety guidance analysis report based on RG 1.233/NEI 18-04
- To issue a Regulatory Guide to endorse it with clarifications 21
- Acceptability of probabilistic risk assessment (PRA) for non-LWR risk-informed activities RG 1.247
- Endorses, with staff exceptions, a consensus PRA standard (ASME/ANS RA-S-1.4-2021)
- Guidance on how the General Design Criteria (GDCs) in Appendix A of 10 CFR Part 50 may be adapted for non-LWR designs.
- Guidance for developing Principal Design Criteria (PDCs) for non-LWR designs as required by applicable regulations.
RG 1.232 - Appendix A: the technology-inclusive Advanced Reactor Design Criteria (ARDCs)
- Appendix B: Design criteria for sodium-cooled fast reactors (SFR-DCs)
- Appendix C: Design criteria for modular high temperature gas reactors (MHTGR-DCs) 23
- Methodology for establishing functional containment performance criteria for non-LWRs
- Technology-inclusive, risk-informed, and performance-based Functional - Versus prescriptive Containment criteria
- Commission approved the staff proposal in SECY-18-0096 24
- A reactor functional containment, consisting of multiple barriers internal and/or RG 1.232 external to the reactor and its cooling system, shall be provided MHTGR-DC 16 to control the release of radioactivity to the environment Containment and to ensure that the functional containment design conditions design important to safety are not exceeded for as long as postulated accident conditions require.
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Other Guidance Developments Instrumentation and Controls
- Technology-inclusive, risk-informed, and performance-based
- Top-down, streamlined approach
- Design Review Guide for non-LWR Instrumentation and Controls Reviews published Fuel qualification
- To establish a performance-based fuel qualification assessment framework that would satisfy regulatory requirements
- NUREG-2246 published
- Developing guidance for liquid-fueled molten salt reactors Reliability and Integrity Management (RIM)
- American Society of Mechanical Engineers (ASME) SECTION XI, DIVISION 2
- A program to ensure that passive component reliability and integrity are properly managed
- Based on achieving an acceptable level of reliability
- Implement strategies to ensure that Reliability Targets for SSCs are defined, achieved, and maintained
- To publish RG 1.246 (DG-1383 in public)
Code of construction for high temperature reactors
- ASME SECTION III, DIVISION 5
- To publish RG 1.87, Revision 2 and NUREG-2245 26
Acronyms and Abbreviations ACU Abilene Christian University DID Defense-in-depth Agencywide Documents Access and Management EAB Exclusion area boundary ADAMS System ESP Early site permit AEA Atomic Energy Act F-C Frequency-consequence AOO Anticipated operational occurrence GDC General Design Criterion ARCAP Advanced reactor content of application project GEH GE Hitachi Nuclear Energy ARDC Advanced Reactor Design Criterion GEIS Generic Environmental Impact Statement ASME American Society of Mechanical Engineers GIV Generation IV BDBE Beyond design basis event HTGR High-temperature gas-cooled reactor CFR Code of Federal Regulations IAEA International Atomic Energy Agency COL Combined license ISI/IST Inservice inspection/inservice testing CP Construction permit LBE Licensing basis event DBA Design basis accident LMFR Liquid metal fast reactor DBE Design basis event LMP Licensing Modernization Project DC Design certification LWR Light-water reactor DG Draft Regulatory Guide 27
Acronyms and Abbreviations MCFR Molten chloride fast reactor RG Regulatory Guide MHTGR- Modular high-temperature gas-cooled reactor RIM Reliability and Integrity Management DC design criteria RIPB Risk-informed performance-based MIT Massachusetts Institute of Technology RTR Research and test reactor ML Manufacturing license SAR Safety analysis report MSR Molten salt reactor SDA Standard design approval MWt Megawatt thermal SFR-DC Sodium-cooled fast reactor design criteria NEI Nuclear Energy Institute SRM Staff Requirements Memorandum NEIMA Nuclear Energy Innovation and Modernization Act SSC Structure, system, and component NRC U.S. Nuclear Regulatory Commission Technology-inclusive content of application TICAP OL Operating license project P&ID Piping and instrumentation diagram PDC Principal design criterion PRA Probabilistic risk assessment QHO Quantitative health objective 28
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References 10 CFR Part 50, Domestic licensing of production and utilization facilities
- 2. 10 CFR Part 52, Domestic licensing of production and utilization facilities
- 3. ASME/ANS RA-S-1.4-2021, Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants
- 4. ASME Boiler & Pressure Vessel Code,Section III, Division 5 - High Temperature Reactors
- 5. ASME Boiler & Pressure Vessel Code,Section XI - Rules for Inservice Inspection of Nuclear Power Plant Components, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants
- 6. NEI 18-04, Revision 1, Risk-Informed Performance-Based Guidance for Non-Light Water Reactor Licensing Basis Development, August 19, 2019. (ADAMS Accession No. ML19241A472).
- 7. NEI 21-07, Revision 0, Technology Inclusive Guidance for Non-Light Water Reactors Safety Analysis Report Content for Applicants Utilizing NEI 18-04 Methodology, August 2, 2021. (ADAMS Accession No. ML21250A378).
- 8. NRC, SECY-18-0096, Functional Containment Performance Criteria for Non-Light-Water Reactors, Washington, DC, September 28, 2018. (ADAMS Accession No. ML18114A546).
- 9. NRC, SRM-SECY-18-0096, SECY-18-0096 - Functional Containment Performance Criteria for Non-Light-Water-Reactors, December 4, 2018. (ADAMS Accession No. ML18338A502).
- 10. Nuclear Energy Innovation and Modernization Act (NEIMA; Public Law 115-439), January 2019.
- 11. RG 1.232, Revision 0, Guidance for Developing Principal Design Criteria for Non-Light Water Reactors, April 2018. (ADAMS Accession No. 17325A611).
- 12. RG 1.233, Revision 0, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors, June 2020. (ADAMS Accession No. ML20091L698).
- 13. RG 1.247, Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities, March 2022. (ADAMS Accession No. ML21235A008).
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