ML24086A575

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Presentation Slides - Periodic Advanced Reactor Stakeholder Meeting 03272024
ML24086A575
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Issue date: 03/27/2024
From: Katie Wagner
NRC/NRR/DANU/UARP
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281 020 73
Download: ML24086A575 (1)
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Advanced Reactor Stakeholder Public Meeting

March 27, 2024

Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 281 020 73#

Time Agenda Speaker

10:00 am - 10:05 am Opening Remarks NRC

10:05 am - 10:15 am NRC/Idaho National Laboratory (INL) Consensus Codes and Standard Collaboration NRC Coordination Plan 10:15 am - 11:00 am Department of Energy s Advanced Reactor Regulatory Development Program Department of Energy/INL 11:00 pm - 11:30 am Federal Consultations During the Environmental Review Process: Lessons NRC Learned and Best Practices 11:30 am - 12:00 pm United States and Canada Cooperation on SMR Design Reviews - Successes in NRC Collaboration 12:00 pm - 1:00 pm Lunch Break All

1:00 pm - 1:45 pm Nuclear Energy Institute (NEI) Input on Regulatory Priorities for New and NEI Advanced Reactors 1:45 pm Closing Remarks NRC

2 Advanced Reactor Program Recent Highlights (Slide 1 of 4)

License applications currently under review:

Kairos Hermes 2 construction permit (CP) application - draft safety evaluation completed March 6, 2024.

Abilene Christian University (ACU) CP application - Environmental Assessment and Finding of No Significant Impact issued on March 14, 2024 (89 FR 18678).

A readiness assessment of TerraPowers preliminary CP application for the Kemmerer Power Station Unit 1 (Kemmerer Unit 1) was completed February 22, 2024. The corresponding readiness assessment report was issued March 19, 2024 (ML24060A227). The Kemmerer Unit 1 facility, utilizing the Natrium sodium fast reactor technology, would be constructed near Kemmerer, Wyoming, under the U.S. Department of Energys Advanced Reactor Demonstration Program (ARDP) demonstration pathway.

3 Advanced Reactor Program Recent Highlights (Slide 2 of 4)

NRC staff continue to conduct pre-application meetings with prospective applicants such as X Energy, LLC (X-energy), Westinghouse Electric Company, and Terrestrial Energy USA, Inc. and issue pre-application documents such as topical report safety evaluations, for example:

Pre-application Readiness Assessment Report for X-energys Xe-100 Preliminary Safety Analysis Report issued February 7, 2024 (ML24011A071)

Public Outreach Meeting for the forthcoming construction permit application for deployment of X-energys Xe-100 design at the Dow Chemical site in Calhoun County, TX held on February 15 in Port Lavaca, TX

Final safety evaluation issued on March 7, 2024, to University of Illinois at Urbana-Champaign for its topical report on accident analysis identification and safety classification methodology (ML24039A164)

4 Advanced Reactor Recent Highlights (Slide 3 of 4)

SECY 0020: Advanced Reactor Program Status - released March 12, 2024

SECY 0008: Micro-Reactor Licensing and Deployment Considerations: Fuel Loading and Operational Testing at a Factory - released February 8, 2024

ARCAP/TICAP: Final versions of the ten NRC guidance documents were made publicly available on March 25, 2024 ARCAP ISG documents are available via ADAMS Package No. ML24073A229 TICAP RG (RG 1.253, Rev. 0) is available under ADAMS No. ML23269A222

Regulatory Guide (RG 4.7, Rev. 4), General Site Suitability Criteria for Nuclear Power Stations Publication on February 22, 2024 (ML23348A082)

A Federal Register notice was issued February 29, 2024 (89 FR 14743)

Staff response to public comments published on Feb. 22 (ML23324A007)

5 Advanced Reactor Recent Highlights (Slide 4 of 4)

On March 12, 2024, the Canadian Nuclear Safety Commission (CNSC), the United Kingdom Office of Nuclear Regulation (ONR), and the USNRC, signed a Memorandum of Cooperation to increase collaboration on technical reviews of advanced reactor and small modular reactor technologies.

A Federal Register notice was issued February 16, 2024 (89 FR 12383),

regarding the final issuance of DANU-interim staff guidance (ISG) 2023-01, Material Compatibility for non -Light Water Reactors ( ML23188A178).

More information regarding the NRCs Advanced Reactor Program is available at the Integrated Review Schedule Dashboard and on web pages for individual projects, which can be accessed via the main Advanced Reactors web page.

6 New & Advanced Reactors: Codes & Standards Workshop Announcement

  • Public Workshop on Codes and Standards for New and Advanced Reactors
  • Will be held on April 4, 2024, from 9 AM to 5 PM ET
  • Hybrid meeting and use Microsoft Teams
  • Objective is to share of technical expertise and knowledge to identify opportunities to enhance aspects of the NRC s codes and standards program that could increase the efficiency of NRC s licensing and oversight of new and advanced reactors
  • Joint project between the NRC and Idaho National Laboratories
  • Background information can be found in the Coordination Plan
  • Registration is required on NRC s public website at: https://www.nrc. gov/public-involve/conference-symposia/new-adv-codes-standards.html.
  • Registration for virtual and in-person (for US citizens) participation will be open through April 4th.

7 New & Advanced Reactors: Codes & Standards Workshop

Agenda: Desired Outcomes:

Thursday, April 4, 2024

  • Near-term actions for development or Time To p i cendorsement of specific codes and Opening Theme: Purpose for meeting standards; 9:00 - 9:30 am Welcome and Introductions 9:30 - 10:15 am Opening Remarks: NRC Chair and INL Director
  • New or novel approaches to the 10:15 - 10:25 am Break development of regulatory guidance, Morning Theme: What codes & standards are needed to foster efficiencies (and their timeline)? aligned with the agency s Principles of 10:25 - 10:40 am Summary of DOE-NE Codes and Standards Activities Good Regulation; 10:40 - 10:55 am DOE Laboratory Studies on Adv Rx Needs 10:55 - 11:20 am Advanced Reactor Codes and Standards Collaborative (including Roadmap)
  • An NRC action plan with milestones and 11:20 - 11:45 am Discussion dates for implementation of proposed 11:45 am - 1:15 pm Lunch Break changes to improve the effectiveness and Afternoon Theme: How can NRC's codes and standards program be enhanced? efficiency of the NRC s codes and 1:15 - 1:30 pm NRC support to standards orgs and preparations for future reactors. standards program.

1:30 - 1:45 pm CNSC support to standards orgs and preparations for future reactors.

1:45 - 2:00 pm DOE NRIC's role preparing for future reactors 2:00 - 2:45 pm Codes and Standards Organizations activities to prepare for future reactors 2:45 - 3:00 pm Break 3:00 - 4:00 pm Reactor Vendor Perspectives 4:00 - 4:45 pm Discussion on the NRC Action Plan 4:45 - 5:00 pm Path Forward and Closing Remarks 8 Over view of DOE Re gulator y Development

Advanced Non-Water Technologies Jason Christensen, INL March 27, 2024 Overview of Regulatory Development Structure

  • Regulatory Development is one part of the DOEs Advanced Reactor Demonstration Program

- Advanced Reactor Demonstration Projects (funded via DOEs OCED)

- Risk Reduction for Future Demonstrations

- National Reactor Innovation Center

- Regulatory Development

- Advanced Reactor Safeguards

  • Regulatory Development has four major components:

- Regulatory Framework Modernization

- Fast Reactor Regulatory Development R&D

- Molten Salt Reactor Regulatory Development R&D

- Gas Reactor Regulatory Development R&D

10 energy.gov/ne Regulatory Framework Modernization Program Goals and Objectives

  • This portion of DOEs Advanced Reactor Demonstration Program (ARDP) directly engages and supports the industry and Nuclear Regulatory Commission (NRC) in addressing and resolving key regulatory framework issues that directly impact the critical path to advanced reactor demonstration and deployment
  • This area focuses on risk-reactor facilities, including:i nforming and adapting (modernizing) the regulatory framework for commercial

- Developing adaptations of light water reactor (LWR) based regulations for advanced non-LW Rs

- Establishing risk-informed performance-based NRC license application content and review criteria guidance

- Establishing risk-informed regulatory approaches for key parts of the plant operations phase

  • Identified scope also includes the establishment of key licensing technical requirements that have been identified by industry as areas of regulatory uncertainty when pursuing commercial facility deployments
  • These program efforts are focused on achieving formal NRC endorsement or approval, where applicable, so that these areas of regulatory uncertainty are clearly resolved
  • Its noted that the identification and prioritization of scope considers topics that may be of specific regulatory interest to DOE Advanced Reactor Demonstration Project awardees, and whose resolution would benefit both the awardees and the broader advanced reactor stakeholder community

11 energy.gov/ne Connections to DOE-NE Mission

DOE NE Mission: Advance nuclear energy science and technology to meet U.S. energy, environmental, and economic needs

Mission Goal # 2: Enable deployment of advanced nuclear reactors

Objectives:

1. Reduce risk and time needed to deploy advanced nuclear technology
2. Develop reactors that expand market opportunities for nuclear energy
3. Support a diversity of designs that improve resource utilization

Its noted that every commercial deployment of an advanced reactor will require regulatory engagement by the developer and the facilitys owner/operator(s)

12 NRCs Implementation Action Plan (IAP)

  • The IAP is an NRC initiative originated in 2015 to establish a strategy to assure NRC readiness to effectively and efficiently review non-water reactors, including consideration of their fuel cycles and waste forms
  • NRC gathered industry inputs in 2015-2017 to identify and confirm readiness needs
  • The IAP was issued in 2017, with 6 major focus areas identified

Strategy 1 Strategy 2 Strategy 3 Strategy 4 Strategy 5 Strategy 6 Knowledge, Skills Computer Codes & Flexible Review Consensus Codes Policy and Key Communication and Capability Review Tools Processes and Standards Technical Issues

  • DOE-funded programs are focused on strategy areas 2, 3, 4, & 5, and include for example:
  • 2 NEAMS Program, ART Program, Microreactor Program
  • 3 Non-LWR design criteria, Licensing Modernization Project, TICAP/ARCAP
  • 5 Functional Containment, right -sized Emergency Planning, Microreactor policy issues

13 Re gulator y Fr amewor k Moder nization Pr og r am

Advanced Non-Water Technologies Re gulator y Fr amewor k Moder nization Pr og r am

  • The Regulatory Framework Modernization part of the Regulatory Development subprogram coordinates with the industry and Nuclear Regulatory Commission (NRC) to address and resolve key regulatory framework issues that directly impact the critical path to advanced reactor demonstration and deployment
  • This area focuses on risk-informing and adapting (modernizing) the regulatory framework for commercial reactor facilities, including:
  • Commission policy issue resolution,
  • Developing adaptations of light water reactor (LWR) based regulations for advanced non-LWR s
  • Establishing risk-informed performance-based NRC license application content and review criteria guidance
  • Establishing risk-informed regulatory approaches for key parts of the plant operations phase
  • These program efforts are focused on achieving formal NRC endorsement or approval, where applicable, so that these areas of regulatory uncertainty are clearly resolved
  • Its noted that the identification and prioritization of scope considers topics that are specific regulatory challenges to ARDP Demonstration Project awardees, and whose resolution would benefit both the awardees and the broader advanced reactor stakeholder community

15 Examples & Outcomes of Completed Pr og r am Ef for ts

Regulatory Framework Modernization Program efforts have resulted in elimination of regulatory uncertainties in key areas supporting advanced reactor deployments. This involved the development of regulatory proposals, coordinated with industry, that have been formally approved or endorsed by NRC for industry use, such as:

  • Licensing Modernization Project (LMP)
  • Established a risk-i nformed and performance-based approach to advanced reactor design and licensing
  • Technology Inclusive Content of Application Project (TICAP) - NRC endorsement is pending
  • Provides guidance to both industry and NRC staff on LMP-b ased license application content expectations
  • Being utilized by the two DOE-ARDP awardees (TerraPower & X-energy) for commercial licensing
  • Use of historical DOE experimental databases to support NRC licensing
  • NRC Safety Evaluation approving Argonne National Laboratory QA program to qualify certain EBR-II historical data
  • Use of DOE R&D program results to support industry fuel qualification efforts
  • NRC Safety Evaluation of EPRI topical report that establishes an accepted foundation for TRISO particle fuel qualification

16 Examples of Cur r ent Fr amewor k Moder nization Wor k

  • Further Development of Risk-I nformed and Performance-Based (RIPB) Approach
  • Developed Technology Inclusive Risk Informed Change Evaluation (TIRICE) guidance for non-LWRs to evaluate changes to the facility that meets the intent of the 10 CFR 50.59 regulation for those licensees that have used the Licensing Modernization Project approach
  • The Technology Inclusive Management of Safety Case (TIMaSC) project is looking at the full picture of the licensing basis for a plant with an LMP-based safety case provide for integration of the various activities associated with the risk -informed change management o f a license.
  • Risk-Informed and Performance-Based Emergency Planning
  • Developing a consensus technology-inclusive RIPB approach to establishing the plume exposure EPZ and associated emergency plan
  • Hazards
  • Developing an approach for the assessment of low frequency external events as part of a RIPB licensing approach
  • Liquid Fuel Qualification
  • Piloting the MSR-specific NUREG/CR-7299 approach to assess and identify any specific challenges with achieving liquid fuel quali fication by addressing the key considerations reflected in NUREG-2246, Fuel Qualification for Advanced Reactors
  • Sodium Fast Reactor Fire Protection - Industry Standard
  • Assist with industry efforts to draft an updated version of ANSI/ANS Standard 54.8 - Liquid Metal Fire Protection
  • International Collaborations
  • Continued GIF-RSWG & IAEA participation focused primarily on development of advanced reactor safety design approaches and criteria

17 Advanced Reactor Pr og r am R&D &

Re gulator y Connections

Advanced Non-Water Technologies Fast Reactor R&D Fast Reactor Pr og r am

Ongoing research to support licensing:

  • Archival of rich U.S. fast reactor operation and testing legacy and data from other test facilities in modern web-accessible databases:
  • EBR-I I, FFTF, TREAT, and ZPR test databases
  • EBR-II and FFTF fuels irradiation and physics databases
  • Sodium component reliability database
  • Maintenance, quality assurance, continued development, and validation Experimental Breeder Reactor-II (EBR-II) of fast reactor physics and systems/safety analysis software to support their use in fast reactor license applications
  • Argonne Reactor Computation (ARC) suite: MC 2-3, DIF3D/Variant, REBUS, PERSENT, etc.

and PyARC as the user interface and workflow management tool)

  • SAS4A/SASSYS-1, SRT (source term assessments), SPCA -ANL (sodium fire analysis)
  • Generating mechanical properties and sodium compatibility data to support ASME code case for Alloy 709 for structural material use 3rd heat of Alloy 709 stainless steel

20 Fast Reactor Pr og r am

Current priorities in programs regulatory R&D:

  • Extension of NRC approved FIPD quality assurance program plan (QAPP) to other fast reactor databases and their implementation to support their use in upcoming license applications
  • Provision of software and database access is included in programmatic scope, but resources for user support, training, and expertise to help utilize the software and data are also needed Recommend path forward:
  • Given limited resources, QAPP and SQA implementation is currently limited to the highest priority databases and software, leading to differing levels of quality assurance
  • Direct industry support and other DOE grants (GAIN, TCF) are leveraged, when possible, to accelerate implementation

conducted in the past for the NRC to help inform new staff

21 Molten Salt Reactor R&D Accelerating Advanced Reactors Demonstration &

Marvel Deployment in the U.S.

design is a Molten Chloride Fast Reactor (only liquid fueled Na-K cooled design supported under ARDP - w ill not produce microreactor, electricity) - 150 kWth 100 kWth, 20kWe

Project Pele, design, build MCFR Full and commercial demonstrate operation - 500-a prototype 1200 MWe mobile Natrium - 840 nuclear MWth, 345 MWe reactor, (variable output (up TRISO fuel, to 500 MWe short-5 MWth, 1 term with molten M We salt storage) - ARDP Kairos KP-FHR fluoride salt-awa rd cooled, TRISO pebble fueled MSRR, Low power (up to 1 MWth, to MSR, will not produce support academic research) electricity, 35 MWth

23 Technical Ar eas of Str ate gic R&D in the US MSR Pr og r am

24 Modeling Radionuclide Tr anspor t and Bulk Salt Behavior for Sour ce Ter m Assessments

  • Required thermochemical and thermophysical properties data
  • Viscosity
  • Thermal conductivity
  • Density
  • Heat capacities
  • Liquidus/solidus temperatures
  • Salt boiling temperatures
  • Volume expansion coefficients
  • Surface tension
  • Radiation emissivity
  • Process contributions require experimental validation

Courtesy Melissa Rose, MSR Developer Workshop, Oct 2020

25 Multi-faceted A ppr oach to Investigation of Technologies for MSR of f-Gas Systems

Sensors/ salt chemistry

  • Salt composition
  • Redox state
  • Salt level

26 Gas Cooled Reactor R&D Gas Cooled Reactor Pr og r am

Summary of current R&D activities that support industry regulatory engagements TRISO Fuel

- Return on 20-year & $300M+ DOE -N E Investment:

  • It reflects a major accomplishment, largely funded by a series of DOE projects (NGNP QA Program, AGR Program) in close coordination with industry (DOE-EPRI topical report), NRC (QA Program), and NRC's cooperation with CNSC.
  • This significantly reduces North American regulatory uncertainty for TRISO-fueled reactors.

- Main focus in FY24oxidation testing in FACS and AMIX, and compilation of AGR datasets -27 is on completion of AGR -5/ 6/7 PIE, safety and in NDMAS database for use by reactor designers.

- FY25+: Develop strategy on how to best support nonforms (larger kernels, SiC matrix, UN, etc.). -AGR coated fuel

https://art.inl.gov/ndmas/SitePages/Home.aspx 28 Gas Cooled Reactor Pr og r am

Metallics and Graphite

- Qualify and incorporate Alloy 709 into the ASME Code as high temperature construction material for SFR, HTGR and MSR applications

- Complete high-dose graphite (HDG) experiments to provide baseline vs. irradiation performance data.

- Develop and implement high temperature design methodology needed for advanced reactor designs into the ASME Code. Data is being collected in NDMAS and GIF Handbook databases.

29 Gas Cooled Reactor Pr og r am

HTGR Core Simulation and Methods Development + V&V

- We utilize the new codes developed in the DOE-(e.g., Griffin, Pronghorn, Bison) to perform various verification and N E NEAMS program validation benchmarks

- Current efforts include the NEA HTTR LOFC and HTTF benchmarks

- FY25+: Assess potential for creating nonfacility at ANL as successor to NSTF. -nuclear pebble bed test

- International collaborations provide valuable data: (Coordinated Research Projects (IAEA), bi-lateral agreements (Civil Nuclear Working Group (CNWG) with JAEA), Generation-IV Forum (GIF)

- Example: HTR-China within GIF VHTR Computation Methods Validation and PM first start -up core physics benchmark shared by Benchmarks (CMVB) activity.

- Outcome: Validated highuse for comparisons against legacy tools for safety-fidelity codes that industry and NRC can, margin and uncertainty assessments

- FY25+: Complete NEA HTTF and HTTR LOFC Benchmarks and start GIF CMVB validation

- NSTF at ANL: current water-Assessing future use of this facility (pebble bed or microbas ed RCCS testing will end in FY25. -reactor validation data support) ?

30 Stakeholder Enga gement &

Coor dination Re gulator y Enga gement Consider ations

  • DOE program outputs have a number of connections to industry regulatory engagements -

close coordination is critical:

  • Currently ongoing NRC licensing reviews (Kairos-Hermes 2, Abilene Christian-NEXT)
  • Design and commercial license application development is underway (incl. DOE ARDP awardees)
  • NRC pre-application interactions by various industry advanced reactor technology stakeholders is underway
  • General types of regulatory engagement directly supported by DOE NE-5 programs:
  • Completion of R&D that provides experimental results, data, and validated methods that are reflected in DOE national laboratory reports (OSTI) that can be directly referenced by industry stakeholders in support of their license applications and associated regulatory interactions
  • Completion of R&D and development of associated industry proposals that are submitted to NRC for formal endorsement, and can then be utilized by multiple industry stakeholders without additional up-front regulatory approach evaluation

32 Questions?

Federal Consultations in the Environmental Review Process:

Lessons Learned and Best Practices

Michelle Rome, Branch Chief Environmental Technical Branch 1, Environmental Center of Expertise Office of Nuclear Material and Safety Safeguards U.S. Nuclear Regulatory Commission National Environmental Policy Act NRC Implementing Regulations in 10 CFR Environmental Part 51 Reviews for Amended through the Fiscal Responsibility Advanced Act in June 2023 Reactors New page and time limit requirements Additional streamlining opportunities The staff formed a working group and is assessing options to:

reduce time and resources, while balancing meaningful public engagement, and codify new requirements and remove any inconsistencies.

35 N E PA National Environmental Policy Act (NEPA):

The "Umbrella Act "National Historic Endangered Species Act and other Federal Preser vation Act Consultations Coastal Zone Clean Water Act Management Act

Clean Air Act Environmental Justice (E.O. 12898)

Marine Mammal Protection Act Magnuson Stevens Act

36 Why are other Federal Consultations important to consider?

Requires close coordination: Ro l e of other Federal Risk mitigation:

Applicant data NRC-lead with agencies: If lessons learned and best other Federal agencies and Data completeness, timelines, practices are not incorporated, consultation with Federally and effect determinations could pose schedule risks.

recognized Tribes Early coordination is key!

37 Today s Focus

  • National Historic Preser vation Act

- Section 106 Consultation

- Section 7 Consultation

38 Section 106 of the National Historic Preser vation Act: Over view

Purpose Who is involved? Consulting Parties Individuals and

  • Identify historic properties,* State/Tribal Historic Preser vation organizations with a
  • Assess adverse impacts, andO ff ic e legal or economic
  • Resolve or mitigate adverse
  • Tribes with ancestral or historical interest in the project impacts. times to the project area or their concern with
  • Advisory Council on Historic Preser vation the effects on historic
  • Interested parties including the properties.

public [36 CFR § 800.2(c)(5)]

39 40 Section 106: Best Practices for NRC

Early and frequent coordination with Tribes and SHPOs

Incorporate lessons learned from completed Section 106 consultations

Implementation of process and operational changes

  • Organizational realignment for ECOE-wide project-management and incorporation of lessons learned
  • Increased capacity and greater agility to meet workload surges and develop increased capacity in priority areas
  • Continue building st ro n ge r working relationships with Tribes and SHPOs

41 Section 106: Best Practices for Applicants

Early and often coordination with NRC during pre -application phase Ensure consistent understanding of data needs, which may be informed by NRC s consultation with SHPO/THPO, Tribes, and other interested parties.

Awareness that tribal and cultural resources may still exist on brownfield sites. Include Secretary of Interior qualified professionals on your team.

Conduct fieldwork and reports prior to application submittal..

42 Section 106: Best Practices for Applicants (cont.)

Early and often coordination with Tribes, SHPOs, and A ffe c te d Communities Who are the Tribal communities affected by the proposed project? What are their concerns?

What are the best approaches for meaningful engagement and building trust?

Some Tribes or SHPOs will only engage with Federal agencies.

Ultimately, Section 106 responsibilities remain with the NRC.

43 Section 7 of the Endangered Species Act:

Over view

Purpose:

  • To protect and recover imperiled species and the ecosystems upon which they depend

Requirements:

  • Ensure actions does not jeopardize the continued existence of listed species or crtical habitat

44 Endangered Species Act: What is the consultation process?

No Effect No consequences

May Affect Project impacts are beneficial, negligible, discountable, or greater 45 Endangered Early and often coordination during pre-Species Act: application Best Practices and Lessons Ensure consistent understanding of data needs Learned

  • Data needs are often site and action-specific
  • Fish and Wildlife Service's Information for Planning and Consultation (IPAC) Tool Consider multiple approaches for Section 7 consultation
  • For example, combine with the NEPA process or parallel tracks

46 Questions?

47 UNITED STATES AND CANADA COOPERADESIGN REVIEWS -TION ON SMR SUCCESSES IN COLLABORATION

M a r c h 27, 202 4

48 WHY A MEMORANDUM OF COOPERATION? United Kingdom

U. S.Canada

49 HOW THE MOC WORKS

Design certification Construction permit Pre-application interactions Combined license Operating license

White paper Joint Vendor design review Topical report report License to construct

License to operate

Generic design assessment nuclear site license

50 DESIGNS UNDER COOPERATIVE REVIEWS

51 GENERIC TOPICS

52 ORGANIZATION

Advanced Reactor and SMR Subcommittee

Strategic Working Group

Work Plan leads Work Plan leads Work Plan leads SMEs SMEs SMEs 53 BEST PRACTICES

Frequent meetings

Strategic working group

balanced workload training

54 QUESTIONS?

55 Advanced Reactor Stakeholder Public Meeting

Lunch Break Meeting will resume at 1:00 pm EST

Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 281 020 73#

Advanced Reactor Stakeholder Public Meeting

Nuclear Energy Institute Input on Regulatory Priorities for New and Advanced Reactors

Marcus Nichol Executive Director, New Nuclear Nuclear Energy Institute Future Meeting Planning

  • The next periodic stakeholder meeting is scheduled for M ay 23, 2024.
  • If you have sug gested topics, please contact Katie Wagner at Katie.Wagner@nrc. gov or Ossy Font at Ossy.Font@nrc. gov.

58 How Did We Do?

  • Click link to NRC public meeting information:

https://www.nrc. gov/pmns/mtg?do=details&Code=20240086

  • Then, click link to NRC public feedback form:

59

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