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{{#Wiki_filter:NRC Licensing of Small Modular Reactors (SMRs) | {{#Wiki_filter:NRC Licensing of Small Modular Reactors (SMRs) | ||
Purpose | Purpose | ||
* The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing SMRs (small light-water reactor technology) | * The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing SMRs (small light-water reactor technology) | ||
Modular designs Nuclear safety review areas Environmental review areas SMR review challenges SMR lessons-learned | Modular designs Nuclear safety review areas Environmental review areas SMR review challenges SMR lessons-learned | ||
Differences in Licensing SMRs | 2 Differences in Licensing SMRs | ||
* In general, the same regulatory framework applies to SMRs as to large LWRs; however, gaps may exist | * In general, the same regulatory framework applies to SMRs as to large LWRs; however, gaps may exist | ||
* Gaps in regulatory and guidance documents are a continually evolving challenge | * Gaps in regulatory and guidance documents are a continually evolving challenge | ||
* Gaps change according to changes in technologies and approaches | * Gaps change according to changes in technologies and approaches | ||
* Addressing gaps in a completely technology-neutral, meaningful way is difficult | * Addressing gaps in a completely technology-neutral, meaningful way is difficult | ||
Differences in Licensing SMRs | 3 Differences in Licensing SMRs | ||
* Not all gaps warrant the same amount of NRC focus or resources Safety or security significance Likelihood of guidance in that area actually being needed Timing of the need | * Not all gaps warrant the same amount of NRC focus or resources Safety or security significance Likelihood of guidance in that area actually being needed Timing of the need | ||
* The NRC is always scanning the horizon for future gaps and prioritizing them | * The NRC is always scanning the horizon for future gaps and prioritizing them | ||
Part 50 vs. Part 52 Licensing | 4 Part 50 vs. Part 52 Licensing | ||
Nuclear Safety Review Areas | 2 -step licensing - Part 50Alternative licensing - Part 52 | ||
Preliminary Safety Analysis Report Early Site Permit Design Certification | |||
Construction Permit Site/design information | |||
Construction and further design Final Safety Analysis Report | |||
Final Safety Construction Combined License Analysis Report complete Operating License Construction | |||
Operation* Verification (ITAAC) | |||
* Includes Pre-operational testing Operation* | |||
5 Nuclear Safety Review Areas | |||
* Site Characteristics and Site Parameters | * Site Characteristics and Site Parameters | ||
* Systems, Structures, Components, and Equipment Design | * Systems, Structures, Components, and Equipment Design | ||
Line 52: | Line 61: | ||
* Quality Assurance Program | * Quality Assurance Program | ||
* Human Factors Engineering | * Human Factors Engineering | ||
* Severe Accidents | * Severe Accidents | ||
Environmental Review Areas | 6 Environmental Review Areas | ||
* Seismology | * Seismology | ||
* Geology | * Geology | ||
Line 65: | Line 74: | ||
* Radiological Dose Consequences | * Radiological Dose Consequences | ||
* Emergency Preparedness (with FEMA) | * Emergency Preparedness (with FEMA) | ||
* Security Plan Feasibility | * Security Plan Feasibility | ||
SMR Review Challenges | 7 SMR Review Challenges | ||
* New first-of-a-kind designs Modular construction Completeness of the design Applicability of existing regulations Verification and validation of computer codes Applicability of prior operating experience | * New first-of-a-kind designs Modular construction Completeness of the design Applicability of existing regulations Verification and validation of computer codes Applicability of prior operating experience | ||
* Smaller applicant organizations in some cases Important that they have experience with nuclear licensing requirements Important that they are adequately staffed to address regulator questions in a timely manner during reviews 8 | * Smaller applicant organizations in some cases Important that they have experience with nuclear licensing requirements Important that they are adequately staffed to address regulator questions in a timely manner during reviews | ||
8 Modular Designs - AP1000 Modules | |||
CA01 Steam Generator / Refueling Channel CA02 In-Containment Refueling W ater Storage Tank (IRW ST) Interior W all CA03 IRW ST Perimeter W all CA04 Reactor Vessel Cavity CA05 Access Tunnel / Passive Core Cooling and Volume Control System Equipment Room W all CA20 Aux Building | |||
SMR Lessons-Learned | 9 SMR Lessons-Learned | ||
* A rigorous safety basis and understanding is still essential for new designs | * A rigorous safety basis and understanding is still essential for new designs | ||
* If an organization is mostly familiar only with large light water reactors (LWRs), a mindset change may need to occur | * If an organization is mostly familiar only with large light water reactors (LWRs), a mindset change may need to occur | ||
Line 79: | Line 90: | ||
* Complete understanding of the design as a whole assists the applicant and the regulator | * Complete understanding of the design as a whole assists the applicant and the regulator | ||
* Successful completion of first-of-a-kind reviews will result in streamlined Nth-of-a-kind reviews | * Successful completion of first-of-a-kind reviews will result in streamlined Nth-of-a-kind reviews | ||
* Early and frequent communication with applicants is crucial, both prior to and during the | * Early and frequent communication with applicants is crucial, both prior to and during the regulator s review | ||
10 NRC Licensing of Advanced Reactors Purpose | |||
* The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing Advanced Reactors (small non-light water reactor technology) | |||
Advanced Reactor design landscape Ensuring readiness for licensing Advanced Reactor designs | |||
12 New Non-Light Water Licensing | |||
Companies in active pre-application engagement: | |||
X-Energy TerraPower & GE-Hitachi Oklo Aurora - first Ka i ro s Powe r advanced reactor Terrestrial Energy USA licensing application General Atomics Energy submitted March 2020. Microreactor - Westinghouse Electric Company 1.5 MWe | |||
Advanced Reactor | |||
13 Broad Landscape of Advanced Reactor DesignsAdvanced Reactor Landscape | |||
Liquid Metal Cooled Fast High-Temperature Gas -Cooled Molten Salt Reactors Micro Reactors Reactors (MSR) Reactors (LMFR) (HTGR) | |||
TerraPower/GEH Kairos | TerraPower/GEH Kairos | ||
* Westinghouse (eVinci)* | * Westinghouse (eVinci)* | ||
(Natrium)* | (Natrium)* X-energy | ||
* GEH PRISM (VTR) | * GEH PRISM (VTR) Framatome Kairos (HermeslRTR) BWX Technologies | ||
* Transportable Westinghouse | |||
* Oklo Lead-Cooled | Advanced Reactor Liquid Salt Cooled X-energy Concepts StarCore Sodium-Cooled MIT Radiant l RTR Terrestrial | ||
* Preapplication | * Transportable | ||
Westinghouse TRISO Fuel TerraPower Ultra Safe Columbia Basin Southern (TP MCFR) lRTR University of Illinois RTR | |||
Hydromine General Atomics (EM2)* ACU lRTR | |||
* Oklo | |||
Lead-Cooled General Atomics Elysium Stationary ThorCon LEGEND ARDP Awardees Muons Demo Reactors In Licensing Review Flibe | |||
Risk Reduction | |||
* Preapplication Alpha Tech ARC-20 RTR Research/Test Reactor Liquid Salt Fueled | |||
Ensuring Readiness for Licensing | 14 Ensuring Readiness for Licensing | ||
Ensuring Readiness for Licensing | 15 Ensuring Readiness for Licensing | ||
* Risk-Informed Performance-Based Licensing Approaches Draft Regulatory Guide (DG) 1353 | * Risk-Informed Performance-Based Licensing Approaches Draft Regulatory Guide (DG) 1353 | ||
* Technology Inclusive Policy Issues Functional Containment Security Emergency Preparedness | * Technology Inclusive Policy Issues Functional Containment Security Emergency Preparedness | ||
* Nuclear Energy Innovation and Modernization Act (NEIMA) | * Nuclear Energy Innovation and Modernization Act (NEIMA) | ||
Questions?}} | 16 Questions?}} |
Latest revision as of 18:16, 19 November 2024
ML21293A233 | |
Person / Time | |
---|---|
Issue date: | 10/20/2021 |
From: | NRC/NRR/DNRL/NRLB |
To: | |
Dudek M | |
References | |
Download: ML21293A233 (17) | |
Text
NRC Licensing of Small Modular Reactors (SMRs)
Purpose
- The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing SMRs (small light-water reactor technology)
Modular designs Nuclear safety review areas Environmental review areas SMR review challenges SMR lessons-learned
2 Differences in Licensing SMRs
- Gaps in regulatory and guidance documents are a continually evolving challenge
- Gaps change according to changes in technologies and approaches
- Addressing gaps in a completely technology-neutral, meaningful way is difficult
3 Differences in Licensing SMRs
- Not all gaps warrant the same amount of NRC focus or resources Safety or security significance Likelihood of guidance in that area actually being needed Timing of the need
- The NRC is always scanning the horizon for future gaps and prioritizing them
4 Part 50 vs. Part 52 Licensing
2 -step licensing - Part 50Alternative licensing - Part 52
Preliminary Safety Analysis Report Early Site Permit Design Certification
Construction Permit Site/design information
Construction and further design Final Safety Analysis Report
Final Safety Construction Combined License Analysis Report complete Operating License Construction
Operation* Verification (ITAAC)
- Includes Pre-operational testing Operation*
5 Nuclear Safety Review Areas
- Site Characteristics and Site Parameters
- Systems, Structures, Components, and Equipment Design
- Reactor Internals
- Reactor Coolant and Connected Systems
- Engineered Safety Features
- Digital Instrumentation and Controls/Electrical Power
- Auxiliary Systems
- Steam and Power Conversion Systems
- Radioactive Waste Management and Radiation Protection
- Conduct of Operations
- Initial Test Program and ITAAC
- Transient and Accident Analysis
- Technical Specifications
- Quality Assurance Program
- Human Factors Engineering
- Severe Accidents
6 Environmental Review Areas
- Seismology
- Geology
- Hydrology
- Meteorology
- Geography
- Demography (population distribution)
- Site Hazards Evaluation
- Radiological Effluent Releases
- Radiological Dose Consequences
- Emergency Preparedness (with FEMA)
- Security Plan Feasibility
7 SMR Review Challenges
- New first-of-a-kind designs Modular construction Completeness of the design Applicability of existing regulations Verification and validation of computer codes Applicability of prior operating experience
- Smaller applicant organizations in some cases Important that they have experience with nuclear licensing requirements Important that they are adequately staffed to address regulator questions in a timely manner during reviews
8 Modular Designs - AP1000 Modules
CA01 Steam Generator / Refueling Channel CA02 In-Containment Refueling W ater Storage Tank (IRW ST) Interior W all CA03 IRW ST Perimeter W all CA04 Reactor Vessel Cavity CA05 Access Tunnel / Passive Core Cooling and Volume Control System Equipment Room W all CA20 Aux Building
9 SMR Lessons-Learned
- A rigorous safety basis and understanding is still essential for new designs
- If an organization is mostly familiar only with large light water reactors (LWRs), a mindset change may need to occur
- Sustained focus on the most safety-significant aspects of the design is important
- Complete understanding of the design as a whole assists the applicant and the regulator
- Successful completion of first-of-a-kind reviews will result in streamlined Nth-of-a-kind reviews
- Early and frequent communication with applicants is crucial, both prior to and during the regulator s review
10 NRC Licensing of Advanced Reactors Purpose
- The purpose of this section is to provide an understanding of the differences that the NRC is encountering with licensing Advanced Reactors (small non-light water reactor technology)
Advanced Reactor design landscape Ensuring readiness for licensing Advanced Reactor designs
12 New Non-Light Water Licensing
Companies in active pre-application engagement:
X-Energy TerraPower & GE-Hitachi Oklo Aurora - first Ka i ro s Powe r advanced reactor Terrestrial Energy USA licensing application General Atomics Energy submitted March 2020. Microreactor - Westinghouse Electric Company 1.5 MWe
13 Broad Landscape of Advanced Reactor DesignsAdvanced Reactor Landscape
Liquid Metal Cooled Fast High-Temperature Gas -Cooled Molten Salt Reactors Micro Reactors Reactors (MSR) Reactors (LMFR) (HTGR)
TerraPower/GEH Kairos
- Westinghouse (eVinci)*
(Natrium)* X-energy
Advanced Reactor Liquid Salt Cooled X-energy Concepts StarCore Sodium-Cooled MIT Radiant l RTR Terrestrial
- Transportable
Westinghouse TRISO Fuel TerraPower Ultra Safe Columbia Basin Southern (TP MCFR) lRTR University of Illinois RTR
Hydromine General Atomics (EM2)* ACU lRTR
- Oklo
Lead-Cooled General Atomics Elysium Stationary ThorCon LEGEND ARDP Awardees Muons Demo Reactors In Licensing Review Flibe
Risk Reduction
- Preapplication Alpha Tech ARC-20 RTR Research/Test Reactor Liquid Salt Fueled
14 Ensuring Readiness for Licensing
15 Ensuring Readiness for Licensing
- Risk-Informed Performance-Based Licensing Approaches Draft Regulatory Guide (DG) 1353
- Technology Inclusive Policy Issues Functional Containment Security Emergency Preparedness
16 Questions?