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
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281 020 73
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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 Coordination Plan NRC 10:15 am - 11:00 am Department of Energys Advanced Reactor Regulatory Development Program Department of Energy/INL 11:00 pm - 11:30 am Federal Consultations During the Environmental Review Process: Lessons Learned and Best Practices NRC 11:30 am - 12:00 pm United States and Canada Cooperation on SMR Design Reviews - Successes in Collaboration NRC 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 Advanced Reactors NEI 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.

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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-24-0020: Advanced Reactor Program Status - released March 12, 2024

SECY-24-0008: 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.

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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 NRCs codes and standards program that could increase the efficiency of NRCs 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 NRCs 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.

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New & Advanced Reactors: Codes & Standards Workshop Desired Outcomes:

Near-term actions for development or endorsement of specific codes and standards; New or novel approaches to the development of regulatory guidance, aligned with the agencys Principles of Good Regulation; An NRC action plan with milestones and dates for implementation of proposed changes to improve the effectiveness and efficiency of the NRCs codes and standards program.

8 Thursday, April 4, 2024 Time Topic Opening Theme: Purpose for meeting 9:00 - 9:30 am Welcome and Introductions 9:30 - 10:15 am Opening Remarks: NRC Chair and INL Director 10:15 - 10:25 am Break Morning Theme: What codes & standards are needed to foster efficiencies (and their timeline)?

10:25 - 10:40 am Summary of DOE-NE Codes and Standards Activities 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) 11:20 - 11:45 am Discussion 11:45 am - 1:15 pm Lunch Break Afternoon Theme: How can NRC's codes and standards program be enhanced?

1:15 - 1:30 pm NRC support to standards orgs and preparations for future reactors.

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 Agenda:

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

energy.gov/ne 10

  • 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 Overview of Regulatory Development Structure

energy.gov/ne 11 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-informing and adapting (modernizing) the regulatory framework for commercial reactor facilities, including:

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

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
  • 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 Strategy 1 Knowledge, Skills and Capability Strategy 2 Computer Codes &

Review Tools Strategy 3 Flexible Review Processes Strategy 4 Consensus Codes and Standards Strategy 5 Policy and Key Technical Issues Strategy 6 Communication 13

Regulatory Framework Modernization Program Advanced Non-Water Technologies

Regulatory Framework Modernization Program

  • 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-LWRs
  • 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 Program Efforts 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-informed 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-based 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 Current Framework Modernization Work Further Development of Risk-Informed 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 of 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 qualification 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 Program R&D &

Regulatory Connections Advanced Non-Water Technologies

Fast Reactor R&D

Fast Reactor Program 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-II, FFTF, TREAT, and ZPR test databases EBR-II and FFTF fuels irradiation and physics databases Out-of-pile transient fuel testing database Sodium component reliability database Maintenance, quality assurance, continued development, and validation of fast reactor physics and systems/safety analysis software to support their use in fast reactor license applications Argonne Reactor Computation (ARC) suite: MC2-3, 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 Experimental Breeder Reactor-II (EBR-II) 3rd heat of Alloy 709 stainless steel 20

Fast Reactor Program 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 Modern software quality assurance (SQA) practices to support commercial grade dedication of fast reactor software by the vendors 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 Labs are open to refreshing the in-person Fast Reactor Technology Training conducted in the past for the NRC to help inform new staff https://frdb.ne.anl.gov/

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Molten Salt Reactor R&D

23 Marvel design is a Na-K cooled microreactor, 100 kWth, 20kWe Project Pele, design, build and demonstrate a prototype mobile nuclear

reactor, TRISO fuel, 5 MWth, 1 MWe MSRR, Low power (up to 1 MWth, to support academic research)

Molten Chloride Fast Reactor (only liquid fueled design supported under ARDP - will not produce electricity) - 150 kWth Kairos KP-FHR fluoride salt-cooled, TRISO pebble fueled MSR, will not produce electricity, 35 MWth Natrium - 840 MWth, 345 MWe (variable output (up to 500 MWe short-term with molten salt storage) - ARDP award MCFR Full commercial operation - 500-1200 MWe Accelerating Advanced Reactors Demonstration &

Deployment in the U.S.

Technical Areas of Strategic R&D in the US MSR Program 24

Modeling Radionuclide Transport and Bulk Salt Behavior for Source Term 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 Approach to Investigation of Technologies for MSR off-Gas Systems 26 Sensors/ salt chemistry Salt composition Redox state Salt level

Gas Cooled Reactor R&D

Gas Cooled Reactor Program Summary of current R&D activities that support industry regulatory engagements TRISO Fuel

- Return on 20-year & $300M+ DOE-NE 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 FY24-27 is on completion of AGR-5/6/7 PIE, safety and oxidation testing in FACS and AMIX, and compilation of AGR datasets in NDMAS database for use by reactor designers.

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

https://art.inl.gov/ndmas/SitePages/Home.aspx 28

Gas Cooled Reactor Program 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.

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Gas Cooled Reactor Program HTGR Core Simulation and Methods Development + V&V

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

- Current efforts include the NEA HTTR LOFC and HTTF benchmarks

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

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

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

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

- NSTF at ANL: current water-based RCCS testing will end in FY25.

Assessing future use of this facility (pebble bed or micro-reactor validation data support) ?

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Stakeholder Engagement &

Coordination

Regulatory Engagement Considerations

  • 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

Environmental Reviews for Advanced Reactors National Environmental Policy Act NRC Implementing Regulations in 10 CFR Part 51 Amended through the Fiscal Responsibility Act in June 2023

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.

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National Environmental Policy Act (NEPA):

The "Umbrella Act" and other Federal Consultations 36 National Historic Preservation Act Clean Water Act Clean Air Act Marine Mammal Protection Act Endangered Species Act Coastal Zone Management Act Environmental Justice (E.O. 12898)

Magnuson Stevens Act NEPA

Why are other Federal Consultations important to consider?

37 Requires close coordination:

Applicant data NRC-lead with other Federal agencies and consultation with Federally recognized Tribes Role of other Federal agencies:

Data completeness, timelines, and effect determinations Risk mitigation:

If lessons learned and best practices are not incorporated, could pose schedule risks.

Early coordination is key!

Todays Focus

  • National Historic Preservation Act

- Section 106 Consultation

- Section 7 Consultation

Section 106 of the National Historic Preservation Act: Overview 39 Purpose

  • Identify historic properties,
  • Assess adverse impacts, and
  • Resolve or mitigate adverse impacts.

Who is involved?

  • State/Tribal Historic Preservation Office
  • Tribes with ancestral or historical times to the project area
  • Advisory Council on Historic Preservation
  • Interested parties including the public Consulting Parties Individuals and organizations with a legal or economic interest in the project or their concern with the effects on historic properties.

[36 CFR § 800.2(c)(5)]

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Section 106: Best Practices for NRC 41 Early and frequent coordination with Tribes and SHPOs Incorporate lessons learned from completed Section 106 consultations

  • 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 stronger working relationships with Tribes and SHPOs Implementation of process and operational changes

Section 106: Best Practices for Applicants 42 Early and often coordination with NRC during pre-application phase Ensure consistent understanding of data needs, which may be informed by NRCs 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..

Section 106: Best Practices for Applicants (cont.)

43 Early and often coordination with Tribes, SHPOs, and Affected 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.

Section 7 of the Endangered Species Act:

Overview 44

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

Purpose:

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

Endangered Species Act: What is the consultation process?

45 May Affect Project impacts are beneficial, negligible, discountable, or greater No Effect No consequences

Endangered Species Act:

Best Practices and Lessons Learned 46 Early and often coordination during pre-application Ensure consistent understanding of data needs

  • 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

Questions?

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UNITED STATES AND CANADA COOPERATION ON SMR DESIGN REVIEWS -

SUCCESSES IN COLLABORATION March 27, 2024 48

WHY A MEMORANDUM OF COOPERATION?

United Kingdom Canada U.S.

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HOW THE MOC WORKS White paper Topical report Design certification Construction permit Combined license Operating license Joint report License to construct Generic design assessment Pre-application interactions Vendor design review nuclear site license License to operate 50

DESIGNS UNDER COOPERATIVE REVIEWS 51

GENERIC TOPICS 52

ORGANIZATION Advanced Reactor and SMR Subcommittee Work Plan leads SMEs Work Plan leads SMEs Work Plan leads SMEs Strategic Working Group 53

BEST PRACTICES training Frequent meetings Strategic working group balanced workload 54

QUESTIONS?

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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 Advanced Reactor Stakeholder Public Meeting

Future Meeting Planning

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

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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:

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