ML24067A207

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3/18/2024 NRC Public Meeting Presentation for Fusion Systems Proposed Rule
ML24067A207
Person / Time
Issue date: 03/18/2024
From: Dennis Andrukat
NRC/NMSS/DREFS/RRPB
To:
References
NRC-2023-0071, RIN 3150-AL00, Rulemaking: Proposed Rule
Download: ML24067A207 (1)
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Text

Rulemaking: Regulator y Framework for Fusion Systems

NRC Public Meeting March 18, 2024 Agenda

Time To p i c Speaker

1:00 pm Welcome & Meeting Logistics Dennis Andrukat

Opening Remarks Theresa Clark NRC Presentation: Duncan White

- Stat us of Preliminary Proposed Rulemaking and Guidance

- Changes to Preliminary Proposed Rule Language

Questions & Answer Session / All Public Feedback

4:50 pm Closing Remarks & Adjourn Dennis Andrukat

Topic times are estimated and, depending on the participation level, the meeting could adjourn earlier than scheduled.

If there are concerns with a potential early meeting adjournment, please inform the point of contact for this meeting.2 Theresa Clark, Deputy Director Division of Materials Safety, Security, State, and Tribal Programs Office of Nuclear Material Safety and Safeguards US NRC

3 Changes to Preliminary Proposed Rule Language

Duncan White Division of Materials Safety, Security, State, and Tribal Programs Office of Nuclear Material Safety and Safeguards US NRC

4 Revisions:

Particle accelerator means any machine capable of Preliminar y accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant particulate or other radiation into a medium. For Proposed Rule purposes of this definition, accelerator is an equivalent term. Particle accelerators that induce plasma fusion to produce byproduct material are included in fusion systems Language: as defined in this section. [10 CFR Parts 20, 30, 110]

Fusion system means a system that, through use of byproduct material or to produce byproduct material, induces plasma fusionreactions. The term fusion system Revised includes particle accelerators that induce plasma fusion.

The term fusion system also and includes any associated radiation, radioactive material, and supporting structures, Definitions systems, and components that are used to contain, process, or control radiation and radioactive materials used in or resulting from plasma fusion. [10 CFR Parts 20, 30]

5 Preliminary Draft Licensing Guidance for Fusion Systems

Duncan White Division of Materials Safety, Security, State, and Tribal Programs Office of Nuclear Material Safety and Safeguards US NRC

6 Status of NUREG-1556, Volume 22

  • Preliminary draft version completed and Fusion shared with stakeholders
  • Additional changes to the preliminary draft Licensing guidance may be identified during NRC internal and Agreement State reviews Guidance
  • Draft will be published for formal comment in the Federal Register along with the proposed Development rule

7 Preliminary Draft N U R EG -1556 Volume 22*

Consistent with Volumes 6, 7, Fusion design Prel imi nar y NUR EG-1556 12, 21 neutral Draft Guidance Series format ML24067A227

  • Appendix A not included in this preliminary version. However, Appendix A will be part of the draft guidance document that will be published with the proposed rule for official commenting.

8 Contents of an Application

8.1 I te m 1: License Action Type 8.2 I te m 2: Name and Mailing Address of Applicant 8.2.1 Notification of Bankruptcy Proceedings 8.2.2 Timely Notification of Transfers of Control 8.3 I te m 3: Address(es) Where Licensed Material Will Be Used or Possessed 8.4 I te m 4: Person To Be Contacted About This Application 8.5 I te m 5: Radioactive Material 8.5.1 Unsealed and Sealed Byproduct Material 8.5.2 Financial Assurance and Recordkeeping for Decommissioning 8.5.3 Environmental Review

ML24067A227 9 Contents of an Application

8.6 I te m 6: Purpose(s) for Which Licensed Material Will Be Used 8.7 I te m 7: Individual(s) Responsible for Radiation Safety Program and Their Training and Experience 8.7.1 Radiation Safety Officer 8.7.2 Individuals Authorized To Handle Licensed Material 8.8 I te m 8: Training for Individuals Working in or Frequenting Restricted Areas

ML24067A227 10 Contents of an Application

8.9 Item 9: Facilities and Equipment 8.9.1 General Description of Facility and Site 8.9.2 Access Control 8.9.3 Shielding 8.9.4 Fi re Prote ct i on 8.9.5 Radiation Monitors 8.9.6 Tritium Handling System 8.9.7 Breeding Blankets 8.9.8 Heat Exchange Systems 8.9.9 Power Failures

ML24067A227 11 Contents of an Application

8.10 Item 10: Radiation Safety Program 8.10.1 Audit Program 8.10.2 Radiation Monitoring Instruments 8.10.3 Material Control and Accountability 8.10.4 Occupational Dose 8.10.4.1 Dosimetry 8.10.4.2 Bioassay Program 8.10.4.3 ALARA 8.10.4.4 Minimization of Contamination 8.10.5 Public Dose

ML24067A227 12 Contents of an Application

8.10 Item 10: Radiation Safety Program (Continued) 8.10.6 Safe Operating and Emergency Procedures 8.10.6.1 Operating Procedures 8.10.6.2 Maintenance 8.10.6.3 Eme rge n cy Proce d ures 8.10.7 Surveys and Leak Tests 8.10.8 Transportation 8.10.9 Evaluation to Determine Need for Offsite Emergency Plan 8.10.10 Environmental Sur veillance 8.10.11 Security Program

ML24067A227 13 Contents of an Application

8.11 I te m 11: Waste Management 8.12 I te m 12: License Fees 8.13 I te m 13: Certification

ML24067A227 14 Appendices

Appendix A Suggested Format for Providing Information Requested in Items 5 Through 11 of NRC Form 313 for a Possession License Appendix B Checklist for Requests to Withhold Proprietary Information from Public Disclosure (Under 10 CFR 2.390)

Appendix C Commencement of Construction at Existing and Proposed Byproduct, Source, and Special Nuclear Material Facilities Appendix D Typical Duties and Responsibilities of the Radiation Safety Officer Appendix E Radiation Safety Training Appendix F Facilities and Equipment Considerations Appendix G Sample Audit Program Appendix H Radiation-monitoring , Instrument Specifications, and Model Survey Instrument and Air-sampler Calibration Program

ML24067A227 15 Appendices

Appendix I Material Receipt and Accountability Appendix J Guidance for Demonstrating that Unmonitored Individuals are Not Likely to Exceed 10 Percent of the Allowable Occupational Dose Limits Appendix K Methodology for Determining Public Dose Appendix L Typical Notification And Reporting Requirements Appendix M General Topics for Safe Use of Radionuclides and Model Emergency Procedures Appendix N Radiation Safety Sur vey Topics Appendix O Model Leak Test Program and Procedures Appendix P Applicable U.S. Department of Transportation Regulations Appendix Q Model Waste Management Procedures

ML24067A227 16 Question & Answer Session

We encourage questions and feedback from all stakeholders during this meeting on the development of the proposed rule and preliminary draft guidance. We are not officially accepting comments today and will not provide any formal responses to any feedback provided during this meeting.

17 Upcoming Events/Milestones

Proposed Rule

  • Proposed rule and draft guidance to Commission by Schedule September 2024

18 Additional Information

Public Meeting

Information

  • Meeting Notice / Feedback Form:

https://www.nrc.gov/pmns/mtg?do=details&Code=20240278

Public

  • Rulemaking Docket ID: NRC-2023- 0071 (www.regulations.gov)

19 Thank You!

C o nta c t s Dennis Andrukat, Rulemaking Project Manager Dennis.Andrukat@nrc.gov

Duncan White, Technical Lead Duncan.White@nrc.gov

20

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