ML23083B369

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M230330: Slides/Supporting Presentation Material - Staff Slides - Briefing on Nuclear Regulatory Research Program
ML23083B369
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Issue date: 03/30/2023
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M230330
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BRIEFING ON NUCLEAR REGULATORY RESEARCH PROGRAM Commission Meeting March 30, 2023

Cathy Haney Deputy Executive Director for M ate r i a l s , Wa ste , Re s e a rc h , S tate ,

Tr i b a l , C o m p l i a n c e , A d m i n i s t r a t i o n ,

and Human Capital Programs

Ray Furstenau Research Program Overview; Collaboration; Future Focused Research Mike Franovich NUCLEAR Research Contributions to Mission Success REGULATORY Fred Sock RESEARCH Cooperation with National Reactor Innovation Center under the Nuclear Energy Innovation Capabilities Act PROGRAM Louise Lund Enhancing the Research Program Through Stakeholder Outreach Thomas Boyce Fuel Cycle Research Cooperation 3

Ray Furstenau Director Office of Nuclear Regulatory Research

Be Ready for New Technologies

  • World-class expertise 199 RES FTE
  • Building capabilities to support our safety and security mission 67% RES staff with advanced degrees
  • Striking a balance of in-house and external capabilities $42 M contract support 5

Partnering for Success

  • Strong engagement with internal and >100 International external partners agreements
  • International activities
  • FIDES II and joint projects >10,000 Computer code users
  • Robust international safety analysis code user groups Rod Bundle Heat Transfer Facility CAMP Ad va n ced Tes t Rea ct or CSARP RAMP Ph oto cou rtes y of Ida h o Na tion a l La bora tory 6

Fostering Readiness for New Technologies and Regulatory Innovation

  • Future Focused Research (FFR) supports the mission and RES capabilities 46 University R&D
  • Mission-related R&D grants effectively engage grants (FY20-22) universities 24 FFR projects
  • Both programs are important for enabling the (FY20-23) safe use of advanced nuclear technologies Digital Twins FFR (FY20) Remote Operations FFR (FY21) 7

Mike Franovich Director Division of Risk Assessment Office of Nuclear Reactor Regulation

Research Helps Us Make Better Decisions Upgrades FLEX NFPA 805 improvements Analysis 2020 Derecho 9

Applying Expert RES Knowledge to Challenging Licensing Issues

  • Risk-informed, consequence-based solution
  • Approval of first-of-a-kind EPZ sizing method EPZ Sizing RISK 10

Research is Foundational to Reliable Regulations SOARCA Level 3 PRA Project SMR Licensing Regulatory Source Term RG 1.183 (Rev 1)

Collaborative Research 2005 2010 2015 2020 MELCOR & MACCS Code Development and Applications Post - 9/11 Security Studies Post-Fukushima Studies License Renewal

-Spent Fuel Pools (NUREG-2161) ATF/HBU Non-LWR Readiness GEIS

-Containment Venting (NUREG-2206) 11

Frederick Sock Structural Engineer Division of Engineering Office of Nuclear Regulatory Research

Nuclear Energy Innovation Capabilities Act Spurs NRIC Collaboration Organizational Structure

  • Nuclear Energy Innovation Center (NRIC) established as an addendum under NEICA memorandum of understanding framework Goal
  • Improving NRCs technical readiness for advanced nuclear reactor applications NRC Participation
  • Two NRC staff on assignment with NRIC
  • Advanced Construction Technology Initiative
  • Exploring 3 technologies to build a smaller SMR version 13

Benefits of Collaboration Between NRIC and NRC Preserving Regulatory Independence

  • NRIC addenda consistent with NRCs role as an independent regulator Benefits to NRC
  • Access and review new construction technologies
  • Evaluating inspection and acceptance criteria
  • Update NRC inspection procedures and manuals in support of staff readiness for future licensing activities 14

Vertical Shaft Construction Technology Vertical Shaft Sinking Machine Conventional use of retaining walls (secant piles, etc.)

15

Use of Steel Bricks' in Construction Steel Brick' as fabricated at shop Steel Brick' prototypes at Purdue from Caunton Engineering, to be filled with concrete for stress testing 16

Advanced Condition and Performance Monitoring & Digital Twin Seismometers to monitor construction 17

Louise Lund Director Division of Engineering Office of Nuclear Regulatory Research

Engaging Domestically and Globally Technical Access Technical Networks Timely Data Leadership Government-to- Complex Government Technical Issues Long-term Engage Relationships Industry 19

Leveraging a Spectrum of Instruments International Agreements Conferences Interagency and Symposia Contracts Agreements and Grants Codes and Standards Project-specific Agreements Public Meetings Memoranda of Bilateral Understanding Agreements 20

Partnering for Success Four Stakeholder Decades Engagement of Global is Enhancing Our Leadership in Readiness Nondestructive Activities on Artificial Examination Built Intelligence on Engagement and Outreach 21

Tom Boyce Branch Chief Materials and Structural Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards

Informing Regulation of Storage and Transportation Applications Mission-Ready Tools Staff Expertise Risk-Informed Regulator NRC tools & expertise for independent analysis of spent fuel licensing reviews 23

Ensuring Safe Storage

Readiness for Reprocessing

  • Readiness for applications
  • Technical assessments of pyroprocessing techniques Most of the fission products Uranium, other actinides, Uranium and salt and other actinides Oxide fuel from Metal thermal reactors Metal Salts Metallic fuel from from fast reactors 25

Readiness for Advanced Reactor Fuel Cycles ENRICHMENT FUEL FABRICATION REACTOR SPENT FUEL STORAGE 1 3 5 7 2 4 6 UF6 TRANSPORTATION FRESH FUEL IRRADIATED FUEL TRANSPORTATION TRANSPORTATION SCALE/MELCOR Non-LWR Fuel Cycle Demonstration Project Technical assessments of non-LWRs Domestic & international collaborations &

Gamma / Thermal monitoring industry Shield progress 26

Cathy Haney Deputy Executive Director for M ate r i a l s , Wa ste , Re s e a rc h , S tate ,

Tr i b a l , C o m p l i a n c e , A d m i n i s t r a t i o n ,

and Human Capital Programs

Glossary of NRC Computer Codes Computer Codes FAST - Code for simulating nuclear fuel behavior SCALE - Code for reactor physics and radiation shielding analysis MELCOR - Code for simulating nuclear reactor severe accidents MACCS - Code for simulating the dispersion of radioactive materials SPAR - Code for reactor risk assessments Code User Groups CAMP - Code Applications and Maintenance Program CSARP - Cooperative Severe Accident Research Program RAMP - Radiation protection computer code Analysis and Maintenance Program 28

Acronyms EPRI - Electric Power Research Institute EPZ - Emergency Planning Zone FLEX - Diverse and Flexible Coping Strategies FIDES II - Second Framework for Irradiation Experiments FTE - Full-Time Equivalent GEIS - Generic Environmental Impact Statement INL - Idaho National Laboratory NEA - Nuclear Energy Agency NFPA - National Fire Protection Association RH - Relative humidity T - Temperature SMR - Small Modular Reactor SOARCA - State-of-the-Art Reactor Consequence Analyses UNLP - University Nuclear Leadership Program 29

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