SECY-24-0020, Enclosure 1 - SRM-M170511-4 Details of Cy 2023 Advanced Reactor Program Accomplishments

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SECY-24-0020: Enclosure 1 - SRM-M170511-4 Details of Cy 2023 Advanced Reactor Program Accomplishments
ML23350A004
Person / Time
Issue date: 02/27/2024
From: O'Driscoll J
NRC/NRR/DANU/UARP
To: Commissioners
NRC/OCM
Jim O'Driscoll, NRR/DANU
Shared Package
ML23350A002 List:
References
SRM-M170511-4 SECY-24-0020
Download: ML23350A004 (11)
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Text

ADVANCED REACTOR SIGNIFICANT ACCOMPLISHMENTS FOR CALENDAR YEAR 2023

Enclosure 2

Introduction This enclosure summarizes significant accomplishments by the U. S. Nuclear Regulatory Commission (NRC) staff (the staff) to make the safe use of advanced nuclear technology possible. This enclosure covers noteworthy activities completed during calendar year (CY) 2023 in the following areas:

  • Regulatory Framework Advancement
  • Licensing
  • Analytical Tool Capabilities
  • External Coordination and Communication
  • International Collaboration
  • Oversight Regulatory Framework Advancement
  • On January 3, 2023, the staff delivered SECY-23-0001, Options for Licensing and Regulating Fusion Energy Systems (ML22273A178), providing opti ons for Commission consideration.

o In 2023, the staff held five public meetings on its efforts to implement the Commissions April 13, 2023, direction ((Agencywide Documents A ccess and Management System Accession No. ML23103A449) to prepare a limit ed-scope rulemaking to establish a regulatory framework for fusion syste ms that augments the NRC's byproduct material framework in Title 10 of the Code of Federal Regulations (10 CFR) Part 30, Rules of General Applicability to Domestic Licensing of Byproduct Material. 1

  • On January 31, 2023, the staff published NUREG-2245, Technica l Review of the 2017 Edition of ASME Code,Section III, Division 5 High Temperature Reactors (ML23030B636) and Regulatory Guide (RG) 1.87, Revision 2, Acce ptability of ASME Code,Section III, Division 5, High Temperature Reactors (ML 22101A263), which endorsed, with conditions the American Society of Mechanical En gineers (ASME) Boiler and Pressure Vessel Code Section III, Rules for the Constructi on of Nuclear Facility Components, Division 5, High Temperature Reactors.
  • On February 28, 2023, the staff published draft interim staff guidance (ISG)

DANU-ISG-2023-01, Material Compatibility for non-Light Water R eactors (ML22203A175), for public comment. The draft guidance identifie d areas of staff review that could be necessary for a submittal seeking to use material s allowed under ASME Code,Section III, Division 5.

  • On March 1, 2023, the staff delivered the draft proposed Title 10 of the Code of Federal Regulations (10 CFR) Part 53 rulemaking package as SECY-23-0021, Proposed Rule:

Risk-Informed, Technology-Inclusive Regulatory Framework for Ad vanced Reactors (RIN 3150-AK31) (ML21162A093), to the Commission for considera tion.

1 https://www.nrc.gov/materials/fusion-energy-systems.html#rule 3

  • On March 29, 2023, the staff delivered a rulemaking plan, SECY 0029, Rulemaking Plan for the Implementation of Changes to Reflect Advanced Reac tor Export Licensing Considerations (ML23037A818), to the Commission for considerat ion.
  • On April 20, 2023, the staff released draft Advanced Reactor C ontent of Application (ARCAP) DRO-ISG-2023-04, Facility Training Programs (ML23017A 130), to support discussions at the April 26, 2023, advanced reactor stakeholder meeting.
  • On May 23, 2023, the staff issued Draft Regulatory Guide DG-1 404 (RG 1.253 Rev 0),

Guidance for a Technology-Inclusive Content-of-Application Meth odology to Inform the Licensing Basis and Content-of-Applications for Licenses, Certi fications & Non-LWRs (ML22076A003), for potential endorsement of the industry--led N uclear Energy Institute (NEI) guidance document NEI 21-07, Technology Inclusive Guidan ce for Non-Light-Water Reactors (ML21250A378), dated August 2, 2021, and nine I SG documents from the NRC--led ARCAP project for public comment (ML23044A038).

o On August 31, 2023, the staff published for public comment DG-1404, Revision 1 (proposed new RG 1.253), Guidance for a Technology-Inclusive C ontent-of-Application Methodology to Inform the Licensing Basis and Co ntent of Applications for Licenses, Certifications, and Approvals for No n-Light-Water Reactors (ML23044A038), which revised the guidance for a Techn ology-Inclusive Content of Application methodology and included propo sed appendix B, providing guidance on the acceptability of a probabilistic risk assessment that supports a non-light-water-reactor (non-LWR) construction permi t application based on the Licensing Modernization Project methodology.

  • On August 24, 2023, the staff released its draft white paper, Micro-Reactor Licensing and Deployment Considerations: Fuel Loading and Operational Tes ting at a Factory (ML23236A575), with an enclosure titled Technical, Licensing, and Policy Considerations for Factory-Fabricated Micro-Reactors, to suppo rt a stakeholder engagement meeting which took place at a September 11, 2023. 2 o On September 27, 2023, the staff released an updated version o f the paper (ML23264A802), to support an October 3, 2023, ACRS meeting. The meeting agenda and transcript are available at the ACRS public website. 3 o On January 24, 2024, the staff delivered SECY-24-0008, Factor y-Fabricated Micro Reactor Licensing and Deployment Considerations: Fuel Loa ding and Operational Testing at a Factory (ML23207A250), to provide the Commission with options for regulating certain aspects of fuel loading and operational testing of commercial factory-fabricated micro-reactors. This paper als o seeks Commission direction on whether a factory-fabricated micro-reac tor that includes features to preclude criticality would require a facility ope rating license or a combined license when loaded with fuel.
  • On October 18, 2023, the staff published DG-4034 (RG 4.7, Revi sion 4), General Site Suitability Criteria for Nuclear Power Stations (ML23123A090), for public comment. The revision included alternative approaches to the population density criterion and expanded the regulatory guidance developed for large light-wate r-reactor technology with appropriate modifications for advanced reactor designs.

2 https://www.nrc.gov/pmns/mtg?do=details&Code=20230975 3 https://www.nrc.gov/reading-rm/doc-collections/acrs/agenda/2023/index.html 4

  • On October 23, 2023, the staff released the draft white paper Development of New Reactor Application Standard Content to Support Timely, Efficie nt, and Effective Reviews of Subsequent Applications (ML23296A032), to support d iscussion at a public meeting. This white paper provides initial concepts for high-le vel guidance for the development of standard content for future applications for rea ctor licenses using the design-centered review approach.
  • On November 16, 2023, the staff published the final rule on E mergency Preparedness for Small Modular Reactor and Other New Technologies (ML23226A 019). The final rule and associated guidance amended the regulations in 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, to include a risk-informed approach to emergency preparedness for small modular reactors and other new technologies.

o On November 13, 2023, the staff issued RG 1.242, Revision 0, PerformanceBased Emergency Preparedness for Small Modular Reactors, NonLightWater Reactors, and Non-Power Production or Utilization Facilit ies (ML23226A036), which is guidance that supports the new emergenc y preparedness for small modular reactors (SMRs) and other new te chnologies rule.

  • On November 29, 2023, the staff released the draft white paper Guidelines for Risk Assessment and Severe Accident Information in a Light-Water Rea ctor Construction Permit Application (ML23326A185), for discussion at a public m eeting. This white paper provides preliminary concepts to inform development of guidance on the content of general and technical information for a preliminary safety anal ysis report (PSAR) to support the staffs review of probabilistic risk assessment (PR A) and non-PRA evaluations used in support of a construction permit applicatio n.

Other Rulemakings On August 2, 2022, the staff delivered SECY-22-0072, Proposed Rule: Alternative Physical Security Requirements for Advanced Reactors (ML21334A003), to the Commission for consideration. If approved, the rule would establish voluntary alternatives to certain physical security requirements and opportunities to credit security by d esign under the existing regulatory framework in 10 CFR Part 50 and 10 CFR Part 52, Licenses, Cert ifications, and Approvals for Nuclear Power Plants, commensurate with the potential conseque nces to public health and safety and the common defense and security. The staff anticipat es issuing the proposed rule for public comment in 2024, pending Commission approval. More infor mation on this rulemaking and the associated policy issue can be found on the NRCs advan ced reactors rulemaking and guidance website.4

On June 6, 2022, the staff delivered SECY-22-0052, Proposed Ru le: Alignment of Licensing Processes and Lessons Learned from New Reactor Licensing (ML21 159A055), to the Commission for consideration. If approved, the rule would ensur e the consistency of technical requirements between reactor licensing processes in Parts 50 an d 52 and would incorporate lessons learned from new reactor licensing into the regulations. The staff anticipates issuing the proposed rule for public comment in 2024, pending Commission ap proval. More information on this rulemaking can be found on the NRCs rulemaking public web site.5

4 https://www.nrc.gov/reactors/new-reactors/advanced/modernizing/rulemaking-and-guidance/physical-security.html 5 https://www.nrc.gov/reading-rm/doc-collections/rulemaking-ruleforum/active/ruledetails.html?id=27 5

Licensing Non-Light-Water Reactors Kairos Hermes 1

  • On June 13, 2023, the staff issued Safety Evaluation Related to the Kairos Power LLC Construction Permit Application for the Hermes Test Reactor (M L23158A265).
  • On August 17, 2023, the staff issued Environmental Impact Sta tement for the Construction Permit for the Kairos Hermes Test Reactor (ML2321 4A269).
  • On September 13, 2023, the staff delivered SECY 23-0080, Envi ronmental Review Approach for the Kairos Power, LLC, Hermes 2 Construction Permi t Application (ML23214A165) to the Commission for consideration. This paper d escribes the staffs intent to prepare an environmental assessment to determine whet her a finding of no significant impact is justifi ed or whether an environmental imp act statement is necessary, fulfilling the NRCs National Environmental Policy A ct obligations as part of the Hermes 2 environmental review.
  • On October 19, 2023, an uncontested hearing was held regarding the Hermes 1 test reactor construction permit application (ML23342A148).
  • On December 12, 2023, the Commission issued Commission Memoran dum and Order CLI-23-05 (ML23346A068), which authorized issuance of the Herme s 1 test reactor construction permit and the associated record of decision.
  • On December 14, 2023, the staff issued Kairos Power LLC Hermes Test Reactor Construction Permit No. CPTR-6 (ML23338A258) and the associated record of decision (ML23338A257).

Abilene Christian University Research Reactor

  • On March 9, 2023, the staff issued Abilene Christian Universi tyEnvironmental Audit Plan for the Molten Salt Research Reactor Construction Permit A pplication Technical Topics (ML23061A126), in which the staff identified initial in formation needs that would promote a better understanding of the detailed analysis and bas es underlying the construction permit application.
  • On June 22, 2023, the staff issued its Interim Report on Regu latory Audits of the Abilene Christian University Preliminary Safety Analysis Report (ML23157A064), in which the staff anticipated that the scope of planned changes t o the PSAR for the molten salt research reactor will be significant and that many of the revisions discussed with Abilene Christian University will affect multiple areas or chap ters of the PSAR.
  • On September 14, 2023, the staff issued Abeline Christian Uni versityUpdate to the Construction Permit Application Technical Review Schedule (ML2 3249A095), which informed the applicant of the staffs need to reassess the appl ication review schedule.
  • On December 21, 2023, the staff issued Abilene Christian Univ ersity - Transmittal of Requests for Additional Information (ML23348A196), which reque sted information pertaining to the application of ASME Boiler and Pressure Vesse l Code,Section VIII, and surveillance procedures for materials degradation mechanism s. Additionally, the staff communicated its intent to issue a revised schedule and l evel of effort estimate for the remainder of the review once responses are provided.

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Kairos Hermes 2

  • On September 11, 2023, the staff issued Acceptance for Docket ing of the Hermes 2 Test Reactor Facility Construction Permit Application submitted by Kairos Power LLC (ML23233A167), which documented the staffs acceptance of the H ermes 2 construction permit application for review.
  • On October 11, 2023, the staff issued Kairos Power LLCHermes 2 Construction Permit Application Review Schedule and Resource Estimate (ML23 269A176), outlining the schedule and resource estimates for the Hermes 2 constructi on permit application review.

X Energy, LLC

  • On March 9, 2023, the staff issued X Energy, LLCFinal Safety Evaluation for Xe-100 Topical Report: TRISO-X Pebble Fuel Qualification Methodology (Revision 3) cover letter (ML22327A198), and redacted safety evaluation (ML22327A2 01).
  • On March 29, 2023, the staff issued X Energy, LLCSafety Eval uation of Xe-100 Topical Report: Transient and Safety Analysis Methodologies Fra mework, Revision No. 1 (ML23037A943).
  • On May 17, 2023, the staff issued X Energy, LLCFinal Safety Evaluation of Topical Report Xe-100 Licensing Topical Report: Control Room Staffing A nalysis Methodology, Revision 2 and Associated Implementation Plans (ML23107A044).

TerraPower, LLC

  • On November 17, 2023, the staff issued TerraPower, LLCU.S. N uclear Regulatory Commission Staff Feedback Regarding White Paper: Natrium Human Factors Engineering Concept of Operations, Revision 0, letter and enc losure (ML23321A086, and ML23321A087, respectively), which provided feedback on the ways users interact with the human system interfaces and with one another to monito r, control, and maintain the Natrium plant.
  • On August 14, 2023, the staff issued TerraPower, LLCU.S. Nuc lear Regulatory Commission Staff Feedback and Observations Regarding Nat-3049, Nascent Thermal Hydraulic Model White Paper (ML23229A541), which provided fee dback on the Natrium Simplified Coolant Energy Transport (Nascent) model. Th is model will be used to predict steady-state coolant temperatures within Natrium fue l assembly subchannels.
  • On September 28, 2023, the staff issued TerraPower, LLCFinal Safety Evaluation for Topical Report NATD-LIC-RPRT-0001, Regulatory Management of Na trium Nuclear Island and Energy Island Design Interfaces, Revision (ML23257 A260). This topical report evaluates the applicability of several regulations relev ant to the interface between the Natrium designs nuclear and energy islands.
  • On November 15, 2023, the staff issued TerraPower, LLCU.S. N uclear Regulatory Commission Staff Feedback Regarding White Paper: Preliminary C onsensus Codes and Standards, Revision 0 (ML23319A338), which provided feedb ack on the use of codes and standards that TerraPower intends to use for the Natr ium reactor design.

Small Modular Reactor Licensing NuScale Power, LLC

  • On January 19, 2023, the NuScale small modular reactor design certification final rule was published in the Federal Register (88 FR 3287).

7

  • On April 25, 2023, the staff issued its safety evaluation repo rt on Topical Report TR-107522, Revision 1, Applicability Range Extension of NSP4 C ritical Heat Flux Correlation, Supplement 1 to TR-0116-21012-P-A, Revision 1 (ML 23115A008).
  • On July 31, 2023, the staff completed the acceptance review an d issued a docketing and resource estimate letter (ML23198A163), to finalize acceptance for docketing of NuScales standard design approval application for the NuScale US460 SMR design.

The staffs goal is to conduct an efficient, high-quality safet y review to support issuance of a final safety evaluation report by July 31, 2025.

  • On December 28, 2023, the staff issued its final safety evalua tion report on Topical Report MN-122626, Revision 1, NuScale Power, LLC Quality Assur ance Program Description (ML23361A122).

Carbon Free Power Project

  • On April 7, 2023, the staff issued its safety evaluation repor t on Topical Report TR-121173NP, Revision 3, Carbon Free Power Project (CFPP) Qual ity Assurance Program Description (ML23094A061).
  • On April 24, 2023, the staff issued a letter providing feedbac k on the CFPPs proposed decommissioning cost estimate methodology (ML23114A047).
  • On September 5, 2023, the staff completed the acceptance revie w and issued a docketing and resource estimate letter (ML23236A263) for the CF PP limited work authorization application.
  • On December 1, 2023, the staff published a notice in the Federal Register (88 FR 83977), granting the request of CFPP and NuScale, dated Novembe r 10, 2023, to withdraw a limited work authorization application and an associ ated exemption request, which had sought to conduct certain early construction activiti es at the CFPP site at the Idaho National Laboratory, near Idaho Falls, Idaho (ML23318A512 ).
  • On November 10, 2023, CFPP and NuScale submitted a letter and informed the NRC staff that the CFPP project has been terminated and requested t o withdraw the limited work authorization application, exemption request, and the topi cal reports associated with the CFPP combined license application (COLA). Accordingly, effective November 13, 2023, the NRC staff suspended its review of the CFPP submit tals in support of its COLA.

Tennessee Valley Authority

  • On September 15, 2023, the staff issued observations resulting from an audit of an annotated outline of a construction permit application for the Clinch River Nuclear Site (ML23236A476).
  • On November 21, 2023, the staff issued an exemption from certa in requirements of NRC regulations pertaining to the submission of a construction perm it application (ML23320A261). Specifically, the NRC will permit a portion of t he PSAR, required to be included in the first part of a two-part application, to be def erred to the second part of the application.
  • On December 12, 2023, the staff issued its safety evaluation r eport on Topical Report NNP-TR-001-NP, Revision 2, Quality Assurance Program Descripti on for TVA New Nuclear (ML23254A052).

8

SMR, LLC, a subsidiary of Holtec International

  • Throughout 2023, the staff held 30 public meetings with SMR, L LC (Holtec) and provided feedback on 12 white papers related to design features, regulatory compliance, and licensing approaches. The staff also responded to 20 clarif ication questions on guidance and the SMR design through routine correspondence. 6 Fuel Cycle Licensing TRISO-X, LLC
  • On April 28, 2023, the NRC approved an exemption that supports TRISO-X's new fuel facility application review and allows for storage and transpor tation of fabricated fuel in shipping containers as Category III material (ML23187A629).

Framatome, Inc.

  • On November 27, 2023, the staff approved the Framatome facilit ys minimum margins of subcriticality up to 20 weight percent uranium-235 (U-235) for its Richland, Washington fuel fabrication facility (ML23313A077), which will support fut ure licensing actions to fabricate advanced reactor fuels.

ORANO NCS GmbH

  • On March 27, 2023, the staff issued a revision to the Certific ate of Compliance for the Model DN30-X transportation package (ML23083B977). This first o f a kind package allows for shipment of uranium hexafluoride enriched up to 20 w eight percent U-235.

NAC International

  • On December 14, 2023, the staff issued a revision to the OPTIM US-L transportation package (ML23345A093) to authorize shipment of unirradiated TRI -structural ISOtropic (TRISO) fuel particle compacts enriched up to 20 weight percent U-235.

Analytical Tool Capabilities

  • On February 28, 2023, the staff issued technical letter report (TLR) TLR-RES/DE/REB-2023-02, State-of-Technology and Technical Challenges in Advan ced Sensors, Instrumentation, and Communication to Support Digital Twin for Nuclear Energy Application (ML23058A085). The TLR addressed challenges in int egrating advanced sensor, instrumentation, and communication technologies with di gital twin technologies.
  • On March 3, 2023, the staff completed the MELCOR Accident Con sequence Code System (MACCS) Consequence Analysis Demonstration Calculations for an Example Heat Pipe Reactor Source Term (ML23045A044), which concluded t hat the MACCS accident consequence analysis code is flexible in analyzing the offsite consequences of an example postulated heat pipe reactor accident release.
  • On May 17, 2023, the staff issued TLR-RES/DE/REB-2023-04, Eva luating Static Isothermal Molten Salt Compatibility with Structural Alloys (M L23129A786). The report enhances understanding of molten salt compatibility with struct ural materials and offers guidance for molten salt reactor licensees.
  • On September 7, 2023, the staff issued its Assessment of the Current State of Knowledge on Storage and Transportation of Molten Salt Reactor WasteFinal Report

6 https://www.nrc.gov/reactors/new-reactors/smr/licensing-activities/pre-application-activities/holtec/documents.html#questions 9

(ML23188A168), which analyzed molten salt reactor designs and s alt waste streams, highlighting challenges in waste storage, transportation, and p rocessing.

  • On September 30, 2023, the staff issued TLR-RES/DE/REB-2023-08, Digital Twins for Nuclear Safeguards and Security: Assessment of Challenges, Oppo rtunities, and Current State-of-Practice (ML23271A055), which explored the ap plication of digital twins in nuclear safeguards and security.
  • On October 19, 2023, the staff issued TLR-RES/DE/REB-2023-07, Reliability Integrity Management Scoping Study (ML23285A233), which examined the sys tems-based code concept and reliability and integrity management for non-LWRs.
  • On October 20, 2023, the staff completed its Comparison of Tr itium Dose Calculations from MACCS, UFOTRI, and ETMOD (ML23292A364), which documented the capabilities of the MACCS accident consequence analysis code fo r assessing tritium release consequences. The report concluded that the MACCS accid ent consequence analysis code is flexible enough to model inhalation doses aris ing from tritium releases to the atmosphere but is not currently suited to modeling doses from the ingestion of tritium.
  • Throughout 2023, the staff hosted four public workshops on the following research topics: SCALE/MELCOR non-LWR fuel cycle demonstration project f or a high temperature gas-cooled reactor (ML23012A085), SCALE/MELCOR non-LWR fuel cycle demonstration project for a sodium-cooled fast reactor (ML23202 A091), condition monitoring and structural health management for nuclear power p lants (more information can be found on the NRCs public website7), and the integration of safety, security, and safeguards (3S) (more information can be found on the NRCs pub lic website8).
  • Throughout 2023, the staff completed several research activiti es to support reactor systems and design-basis analyses, which advance the capability of the NRCs BlueCRAB suite of codes to model the operation and upset condit ions for many non-LWR designs (ML23354A274).
  • Throughout 2023, the staff identified areas of enhancement to the U.S. Department of Energys (DOEs) Nuclear Energy Advanced Modeling and Simulatio n codes, which included the need for coupling between the two thermal fluids c odes, Nuclear Energy Advanced Modeling and Simulati on (NEAMS) Pronghorn and SAM (ML23354A276).

External Coordination and Communication

  • On July 5, 2023, the NRC signed Addendum No. 7 to the Memoran dum of Understanding between the United States Department of Energy an d Nuclear Regulatory Commission on Nuclear Energy Innovation; Establishin g Roles and Responsibilities for National Environmental Policy Act Implemen tation Requirements for Reactor Demonstration Projects Supported by DOE (ML23213A147), which seeks to establish functional coordination between the DOE and the NRC regarding National Environmental Policy Act and National Historic Preservation Act section 106 requirements associated with the demonstration and deployment o f advanced reactors (to include both light-water reactors and non-LWRs) in the Unit ed States receiving DOE

7 https://www.nrc.gov/public-involve/conference-symposia/structural-health-management.html 8 https://www.nrc.gov/public-involve/conference-symposia/adv-reactors-fuel-fab.html 10

support for design, license, construction, and operation of adv anced reactors at U.S.

sites.

  • In CY 2023, the staff held over 140 public meetings on advance d reactor topics such as pre-application and licensing documents, staff-developed guidan ce, and industry-led guidance initiatives.

International Collaboration

o On June 21, 2023, the staff, in collaboration with the CNSC, i ssued U.S. NRC CNSC Memorandum of Cooperation Interim Joint Report Concerning Classification and Assignment of Engineering Design Rules to St ructures, Systems and Components (ML23172A201), which addressed the simi larities and differences in the safety classification process, including scope and outcomes, and two areas involving application of engineering de sign rules:

reliability assurance programs and pressure-retaining component s and supports.

o On June 21, 2023, the staff, in collaboration with the CNSC, i ssued Joint Report on GEH BWRX-300 Steel-Plate Composite (SC) Containment Vessel ( SCCV) and Reactor Building Structural Design White Paper (ML23100A03 2), which addressed a request from GE-Hitachi Nuclear Energy Americas for feedback on its design.

o On June 30, 2023, the staff, in collaboration with the CNSC, i ssued U.S. NRC CNSC Memorandum of Cooperation FINAL REPORT concerning Tristruc tural Isotropic (TRISO) Fuel Qualification (ML23172A242), which summ arized data, criteria, and approaches that can help support fuel-related reg ulatory findings for TRISO-fueled reactor designs.

o On July 31, 2023, the staff, in collaboration with the CNSC, i ssued Joint Report on GEH BWRX-300 Safety Strategy White Paper (ML23135A151), whi ch addressed a request from GE-Hitachi Nuclear Energy Americas for feedback on its safety strategy white paper.

These and previous reports can be found on the Joint Reports o f the Canadian Nuclear Safety Commission (CNSC) and the NRC website.9 Oversight

  • On June 6, 2023, the staff delivered to the Commission for con sideration an information paper, SECY-23-0048, Vision for the Nuclear Regulatory Commiss ions Advanced Reactor Construction Oversight Program, (ML23061A086), which f ocused on the development of a framework for an effective and efficient const ruction oversight program for advanced reactors.
  • On July 3, 2023, the staff issued the TRISO-X At-Risk Constru ction Letter (ML23121A151), which communicated regulations relevant to certa in construction activities related to their proposed fuel fabrication facility under 10 CFR Part 70, that would be considered construction at-risk. The letter provided possible risks related to

9 https://www.nrc.gov/reactors/new-reactors/advanced/who-were-working-with/international-cooperation/nrc-cnsc-moc/joint-reports.html 11

construction at-risk and communicated the staffs intent to con duct oversight of these activities.

  • In 2023, the staff assessed the need to have a resident inspec tor stationed at Category II fuel facilities during construction and operation activities. In January 2024, the staff issued memoranda, which documented the staffs assessment and d etermination that resident inspectors are not needed at the TRISO-X and Centrus American Centrifuge Plant Category II fuel facilities during construction or operat ions (ML23355A245, ML23356A124).
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