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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 2
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 3
* 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 4
* The NRC is always scanning the horizon for future gaps and prioritizing them


Part 50 vs. Part 52 Licensing 2-step licensing - Part 50                  Alternative 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 Construction Operating License Verification (ITAAC)
4 Part 50 vs. Part 52 Licensing
Operation*
                          *Includes Pre-operational testing  Operation*
5


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 6
* 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 7
* 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


Modular Designs - AP1000 Modules CA01 Steam Generator / Refueling Channel CA02 In-Containment Refueling Water Storage Tank (IRWST) Interior Wall CA03 IRWST Perimeter Wall CA04 Reactor Vessel Cavity CA05 Access Tunnel / Passive Core Cooling and Volume Control System Equipment Room Wall CA20 Aux Building 9
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 regulators review 10
* 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


NRC Licensing of Advanced Reactors
12 New Non-Light Water Licensing


Purpose
Companies in active pre-application engagement:
* 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)
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 design landscape Ensuring readiness for licensing Advanced Reactor designs 12
 
13 Broad Landscape of Advanced Reactor DesignsAdvanced Reactor Landscape


New Non-Light Water Licensing Companies in active pre-application engagement:
Liquid Metal Cooled Fast High-Temperature Gas -Cooled Molten Salt Reactors Micro Reactors Reactors (MSR) Reactors (LMFR) (HTGR)
X-Energy TerraPower & GE-Hitachi Oklo Aurora - first  Kairos Power advanced reactor Terrestrial Energy USA licensing application submitted March    General Atomics Energy 2020. Microreactor -  Westinghouse Electric Company 1.5 MWe 13


Advanced                        Reactor Broad Landscape of Advanced Reactor Designs 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)*                   X-energy
(Natrium)* X-energy
* GEH PRISM (VTR)                                       Kairos (HermeslRTR)       BWX Technologies Framatome Advanced Reactor                                       Liquid Salt Cooled             X-energy Concepts                     StarCore Radiant l RTR Sodium-Cooled                     MIT Terrestrial
* GEH PRISM (VTR) Framatome Kairos (HermeslRTR) BWX Technologies
* Transportable Westinghouse                                             TerraPower TRISO Fuel                                             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 ARDP Awardees                                               Muons LEGEND Demo Reactors         In Licensing Review                   Flibe Risk Reduction
Advanced Reactor Liquid Salt Cooled X-energy Concepts StarCore Sodium-Cooled MIT Radiant l RTR Terrestrial
* Preapplication                     Alpha Tech RTR Research/Test Reactor           Liquid Salt Fueled ARC-20 14
* 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 15
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) 16
* Nuclear Energy Innovation and Modernization Act (NEIMA)


Questions?}}
16 Questions?}}

Latest revision as of 18:16, 19 November 2024

Us Update - 27th Wgrnr Meeting Updated
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

  • 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 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
  • 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
  • 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
  • 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

(Natrium)* X-energy

  • GEH PRISM (VTR) Framatome Kairos (HermeslRTR) BWX Technologies

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

16 Questions?