ML26033A352

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Enclosure - Fy 2025 Q3/Q4 Combined Quarterly Report
ML26033A352
Person / Time
Issue date: 02/17/2026
From: Ho Nieh
NRC/OCM/HKN
To: Capito S, Guthrie B, Lummis C
US HR (House of Representatives), US SEN (Senate), US SEN, Comm on Environment & Public Works
Shared Package
ML26033A337 List:
References
SRM-LTR-19-0383-1, CORR-26-0008
Download: ML26033A352 (0)


Text

STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION For the Reporting Period of April 1, 2025, through September 30, 2025 Table of Contents

- High Level Summary......................................................................................... 3 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act................................................................................... 3 1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete.................... 4 1-3 Full-Time Equivalent (FTE) at the End of Q4 FY 2025 vs. Budgeted FTE......................... 4 1-4 Budget Authority, FTE Utilization, and Fees..................................................................... 5 - Status of Specific Items of Interest.................................................................. 7 2-1 Organizational Management............................................................................................ 7 2-2 ADVANCE Act Updates................................................................................................... 8 2-3 Workforce Development and Management.................................................................... 11 2-4 Accident Tolerant Fuel (ATF)......................................................................................... 12 2-5 Advanced Nuclear Reactor Technologies and Fuel Cycle Facilities............................... 14 2-6 Pre-application Activities and Licensing Reviews for Nuclear Reactors............................ 16 2-7 Pre-application Activities and Licensing Reviews for Fuel Cycle Facilities..................... 26 2-8 Reactor Oversight Process............................................................................................ 27 2-9 Fusion............................................................................................................................ 29 2-10 Backfit............................................................................................................................ 31 - Summary of Activities..................................................................................... 33 3-1 Reactor Oversight Process (ROP) Findings.................................................................. 33 3-2 Licensing Actions........................................................................................................... 34 3-3 LAR Reviews................................................................................................................. 37 3-4 Research Activities........................................................................................................ 38 3-5 Fees Billed..................................................................................................................... 39 3-6 RAIs and Requests for Confirmatory Information (RCIs)................................................ 45 3-7 Workforce Development and Management.................................................................... 48 3-8 Inspection Activities....................................................................................................... 49

- High Level Summary 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act1 1 No licensing actions categorized under the Nuclear Energy Innovation and Modernization Act were completed in Quarter (Q) 3 and Q4 of fiscal year (FY) 2024 and Q2 and Q4 of FY 2025 for the new reactor business line. One activity that was completed in Q1 FY 2025 was not identified in the previous reports but is noted here. Additional details are provided in the New Reactors table in section 3-2, Licensing Actions.

10%

20%

30%

40%

50%

60%

70%

80%

90%

100%

110%

Average Timeliness Percentage

(<100% = Completed Before Schedule Date)

Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule 1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete2 1-3 Full-Time Equivalent (FTE) at the End of Q4 FY 2025 vs. Budgeted FTE 2 Planned ROP direct inspection hours refers to the number of hours associated with completion of the U.S. Nuclear Regulatory Commissions (NRCs) nominal number of inspection samples established for the baseline inspection program, which is a conservative target. This contrasts with the minimum number of hours that would be necessary to complete the set of inspection activities that constitutes completion of the ROP baseline inspection program for the calendar year. In addition, an estimated number of supplemental inspections are accounted for in the number of inspection hours, which may not be required that year.

1-4 Budget Authority, FTE Utilization, and Fees NRC FY 2025 Budget Authority September 30, 2025 (Dollars in Thousands)

Fund Sources FY 2025 Budget3 Percent Obligated Percent Expended Advanced Reactors

$28,681 75%

56%

Commission Funds

$13,360 61%

61%

Fee-Based Funds

$912,322 99%

81%

General Funds4

$1,311 51%

30%

International Activities

$17,888 92%

68%

University Nuclear Leadership Program

$7,000 100%

8%

Official Representation

$44 73%

42%

Total5

$980,604 97%

79%

NRC Control Points FY 2025 Budget Percent Obligated Percent Expended Nuclear Reactor Safety

$511,337 97%

85%

Nuclear Materials and Waste Safety

$120,593 97%

81%

Decommissioning and Low-Level Waste

$25,565 86%

76%

Corporate Support

$316,110 98%

71%

University Nuclear Leadership Program6

$7,000 100%

8%

Total7

$980,604 97%

79%

3 The FY 2025 Budget reflects the enactment of the Full-Year Continuing Appropriations and Extensions Act, 2025, and includes the enacted budget and carryover allocated.

4 Consistent with previous reports, this row represents waste incidental to reprocessing activities excluded from the fee-recovery requirement.

5 Numbers might not add correctly due to rounding.

6 The FY 2024 Explanatory Statement identified this control point as the Integrated University Program. Division Z of the Consolidated Appropriations Act, 2021, replaced the Integrated University Program with the University Nuclear Leadership Program.

7 Numbers might not add correctly due to rounding.

FTE Utilization, Hiring, and Attrition8 Total Year-to-Date (YTD)

FTE Utilization Projected End of Year FTE Total Utilization Q3 & Q4 Hiring Q3 & Q4 Attrition YTD Hiring YTD Attrition 2,813.0 2,813.8 12 175 117 290 FY 2025 Fees Estimated, Fees Billed, and Fees Collected Through Q4 Total for Title 10 of the Code of Federal Regulations (10 CFR) Part 170, Fees for Facilities, Materials, Import and Export Licenses, and Other Regulatory Services Under the Atomic Energy Act of 1954, As Amended, Fees Billed (Dollars in Millions)

FY 2023 FY 2024 FY 2025 Q1-Q4

$186.4

$204.0

$213.2 8 The NRC will update its reporting methodology starting in FY 2026 to include both permanent and temporary employees.

This refinement is intended to improve consistency and comparability across internal and external workforce reports and to align with Office of Personnel Management (OPM) guidance.

- Status of Specific Items of Interest outlines the status of key items of interest, providing for each a summary, a description of activities completed and planned during the current reporting period, and an overview of anticipated activities for the next two reporting periods.

2-1 Organizational Management The NRC is updating its performance plans for general schedule employees for fiscal year (FY) 2026 in accordance with new OPM guidance, Performance Management for Federal Employees, issued on June 17, 2025, and revised on July 17, 2025. The NRCs new GG employee performance plans will drive higher accountability by incorporating a new supervisory element for Holding Employees Accountable, performing more routine performance check-ins, and establishing clear expectations that align with the agencys mission, organizational goals, and the Administrations priorities. The new process aims to end rating inflation, better recognize high performers with meaningful bonuses and awards, and improve the agencys ability to address performance issues. The NRC is also updating Senior Executive Service performance plans to align with OPMs memorandum, Hiring and Talent Development for the Senior Executive Service, issued on May 29, 2025, and drive accountability and risk-informed decision-making across the agency.

On July 29 and 31, 2025, the NRC conducted performance management and accountability training for all supervisors in the agency. The accountability training and its accompanying methodology document establish a clear, repeatable framework for strengthening individual and organizational performance across the agency. The material translates broad accountability principles into practical expectations for supervisors and staff, providing structured guidance on setting priorities, cascading goals, monitoring progress, addressing performance gaps, and reinforcing a culture of ownership. The training sessions walked participants through real NRC scenarios, demonstrating how to apply the methodology to daily decision-making, project execution, and workforce management. Together, the methodology document and training build a shared understanding of what accountability looks like in practice and give leaders the tools to drive consistent, transparent, and mission-aligned results.

Additionally, the NRC conducted a series of internal Risk-Informed Decision Making (RIDM) workshops to highlight the agencys successes in risk-informed and performance-based regulations as well as best practices and tools to support the continued and expanded application of RIDM.

Through these ongoing knowledge management efforts, the NRC continues to increase organizational effectiveness and contribute to the organizations safety mission and overall efficiency.

Activities Planned and Completed for Q3 FY 2025 Organizational Management Activities Projected Completion Date Completion Date None N/A N/A Activities Planned and Completed for Q4 FY 2025 Organizational Management Activities Projected Completion Date Completion Date Conducted Performance Management and Accountability Training for all supervisors.

7/31/25 07/31/25 Completed Performance Management and Accountability Training in the Talent Management System [for supervisors unable to attend].

09/30/25 09/30/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Organizational Management Activities Projected Completion Date Implement more frequent performance check-ins between supervisors and staff.

12/11/25 2-2 ADVANCE Act Updates The NRC continues to make significant progress on implementing the Accelerating Deployment of Versatile, Advanced Nuclear for Clean Energy Act of 2024 (ADVANCE Act), which requires the NRC to take various actions, particularly in the areas of licensing of new reactors and fuels. On May 23, 2025, President Trump issued Executive Order (EO) 14300, Ordering the Reform of the Nuclear Regulatory Commission, directing the NRC, among other things, to take additional actions to reform the NRC to facilitate nuclear technology licensing and deployment. Consistent with the ADVANCE Act and EO 14300, the NRC is taking bold steps to embrace innovation, accelerate licensing timelines, and modernize the regulatory framework and agency culture. This section highlights accomplishments toward these goals during the Q3 and Q4 FY 2025 reporting periods.

On May 2, 2025, the NRC issued its Mission Statement Implementation Guidance (ML25106A351),

as required under Section 501(b) of the ADVANCE Act. The guidance is driving a culture change to enable the deployment of nuclear technologies, consistent with the updated mission statement, by describing best practices and examples demonstrating successful implementation of the mission.

On June 5, 2025, the NRC staff provided to the Commission SECY-25-0045, Recommendations for Revising the Reactor Oversight Process (ML25127A212), based on the assessment required by Section 507 of the ADVANCE Act. This paper seeks Commission approval for the NRC to make recommended enhancements to the Reactor Oversight Process (ROP) for greater efficiency in inspection and oversight processes to allow the NRC staff to focus time and resources on items of higher safety significance. The paper also describes planned ROP enhancements that require Commission notification before implementation. These recommendations, if approved, and planned enhancements also respond, in part, to Section 5(g) of EO 14300, which directs the NRC to revise the ROP to reduce unnecessary burdens and be responsive to credible risks.9 On June 23, 2025, the NRC established a new metric for all licensing actions for nuclear reactors and materials: schedules and resources for 80 percent of licensing actions are set at least 15 percent below the new Nuclear Energy Innovation and Modernization Act (NEIMA) milestones or the historical average, whichever is shorter. This metric creates targets for licensing reform, reducing the time and resources expended on licensing reviews while maintaining safety, consistent with Section 504 of the ADVANCE Act and Section 5(a) of EO 14300. The NRC is incorporating this metric into acceptance reviews for applications, documenting the reduced timeline and resource projection. This metric is applicable to all applications received since May 23, 2025when the new NEIMA milestones went into effectand was retroactively applied to several application reviews ongoing at the time of the new NEIMA milestones going into effect.

9 The Commission has since provided direction to the staff in SRM-SECY-0045 (ML26026A351).

On June 24, 2025, the NRC issued the FY 2025 final fee rule, establishing a reduced hourly rate for advanced nuclear reactor applicants and pre-applicants for certain activities, as required by Section 201 of the ADVANCE Act. The reduced hourly rate, which will take effect on October 1, 2025, is $148 per hour and represents an over 50 percent reduction from the full-cost professional hourly rate of

$318 per hour. The reduced hourly rate will reduce the upfront cost for applicants and pre-applicants of advanced reactor designs that can be a barrier to new technologies.

On July 10, 2025, the NRC submitted to Congress reports required by Sections 205 and 507 of the ADVANCE Act. The Section 205 report, Study on Risk-Informed, Performance-Based, Design-Specific Regulatory Frameworks to Support Licensing of Mass-Manufactured Fusion Machines (ML25120A080), provides the results of the NRCs study on potential regulatory frameworks for licensing mass-manufactured fusion machines. The Section 507 report, Improving Oversight and Inspection Programs (ML25077A251), outlines steps that the NRC has taken or could take, with Commission approval, to further improve efficiency and eliminate unnecessary burden through revisions to its reactor and materials oversight and inspection programs. The NRC has also initiated a comprehensive review of the Reactor Oversight Process to reflect improvements in industry performance and advancements in technology, consistent with direction in EO 14300.

On August 18, 2025, the NRC staff issued a memorandum and report describing the NRCs licensing efficiency initiatives to date (ML25191A155) in response to Section 505 of the ADVANCE Act and EO 14300. These efficiencies are reflected in recent major licensing actions, such as advanced reactor standard design approvals and safety evaluations for construction permits, being completed ahead of aggressively set review schedules and under initial budget estimates. The NRC anticipates the agency will realize further licensing efficiencies with continued implementation of the ADVANCE Act and EO 14300.

In addition, the NRC held several public meetings and workshops regarding improving nuclear licensing efficiency (ML25127A260, ML25107A283, and ML25153A016) and oversight and inspection programs (ML25161A088). The NRC maintains a public website (https://www.nrc.gov/about-nrc/governing-laws/advance-act.html) and is using social media to engage external stakeholders during implementation of the ADVANCE Act and EO 14300.

Activities Planned and Completed for Q3 FY 2025 ADVANCE Act Activities Projected Completion Date Completion Date Issued report to Congress on Licensing Considerations Relating to Use of Nuclear Energy for Nonelectric Applications, as required by Section 203 of the ADVANCE Act.

04/05/25 05/01/2510 Submitted a SECY paper to the Commission providing Mission Statement Implementation Guidance, as required by Section 501(b) of the ADVANCE Act.

05/02/25 05/02/25 Issued Information Notice 2025-03 to notify licensees and applicants of the requirements of Section 102 of the ADVANCE Act, which prohibits possession and ownership of covered fuel without specific license 05/12/25 05/12/25 10 This activity was completed on May 1, 2025, rather than the projected completion date of April 5, 2025, to support completion of internal review and approval.

ADVANCE Act Activities Projected Completion Date Completion Date authorization from the NRC.

Submitted a SECY paper to the Commission with recommendations and planned enhancements for the ROP based on the assessment required by Section 507 of the ADVANCE Act.

04/30/25 06/05/2511 Updated the NEIMA milestone schedules, as part of the implementation of the requirements of Section 504 of the ADVANCE Act and EO 14300. The new milestone schedules reflect, on average, an approximate 47 percent decrease from previous NEIMA generic milestone schedules.

06/23/25 06/23/25 Issued the FY 2025 final fee rule establishing a reduced hourly rate for advanced nuclear reactor applicants and pre-applicants for certain activities, as required by Section 201 of the ADVANCE Act.

06/24/25 06/24/25 Issued report to Congress on Engagement with the Government of Canada with Respect to Nuclear Waste Issues in the Great Lakes Basin, as required by Section 602 of the ADVANCE Act.

07/09/25 06/30/25 Activities Planned and Completed for Q4 FY 2025 ADVANCE Act Activities Projected Completion Date Completion Date Issued report to Congress on Improving Oversight and Inspection Programs, as required by Section 507 of the ADVANCE Act.

07/09/25 07/10/25 Issued report to Congress on Study on Risk-Informed, Performance-Based, Design-Specific Regulatory Frameworks to Support Licensing of Mass-Manufactured Fusion Machines, as required by Section 205(c)(2) of the ADVANCE Act.

07/09/25 07/10/25 Established a nuclear energy traineeship subprogram as part of the University Nuclear Leadership Program, as required by Section 402 of the ADVANCE Act.

07/30/25 07/23/25 Issued NRC Licensing Efficiency Initiatives Update in response to Section 505 of the ADVANCE Act.

07/31/25 08/18/25 Developed a process for implementing the reduced hourly fee established pursuant to Section 201 of the ADVANCE Act.

08/31/25 08/29/25 11 This activity was completed on June 5, 2025, rather than the projected completion date of April 30, 2025, to support completion of internal review and approval and consideration of EO 14300.

Issued report to Congress on Regulatory Issues for Nuclear Facilities at Brownfield and/or Retired Fossil Fuel Sites, as required by Section 206 of the ADVANCE Act.

09/09/25 08/25/25 Issued Draft Regulatory Issue Summary on Combined License Review Performance and Reporting, for comment as part of the implementation of the requirements of Section 207 of the ADVANCE Act.

09/30/25 09/03/25 Developed procedures to inform the Commission and to notify Congress when certain export licenses are issued to countries that meet specific criteria pursuant to Section 103 of the ADVANCE Act.

10/01/25 09/30/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected ADVANCE Act Activities Projected Completion Date Issue report to Congress on Updated Mission Statement and Guidance to Ensure Effective Performance of the Mission, as required by Section 501 of the ADVANCE Act.

11/28/2512 Develop risk-informed and performance-based strategies and guidance for the licensing and regulation of micro-reactors pursuant to Section 206 of the ADVANCE Act.

01/09/26 2-3 Workforce Development and Management The NRC continued development of the agencys Project Management Initiative to improve workforce development and management. The initiative represents a strategic, enterprise-wide effort to modernize how the agency defines, plans, executes, and oversees its project-based work. At its core, the initiative is about embedding structure, consistency, and transparency into project management practices across all business lines. By establishing standardized definitions, data requirements, and lifecycle stages for projects and activities, the initiative aims to create a common operating picture that allows for better alignment of agency priorities with available resources and capacity. The initiative includes Strategic Workforce Planning (SWP) by aligning workforce capabilities with current and future workload demands and enables proactive talent management.

Additionally, the agency continued development of the NRC Enterprise eXecution and Utilization System (NEXUS), which is an enterprise-wide application developed to unify program, project, workload, and workforce management across the agency. NEXUS leverages data from multiple authoritative sources to enable real-time visibility into agency work, resource demands, and workforce capacity.

12 The projected completion date for this activity is November 28, 2025, to support internal review and approval. The ADVANCE Act required the NRC to update its mission statement by July 9, 2025, and, upon completion of the update to its mission statement, provide a report to Congress on the updated mission statement and mission statement implementation guidance.

Activities Planned and Completed for Q3 FY 2025 Workforce Development and Management Activities Projected Completion Date Completion Date None N/A N/A Activities Planned and Completed for Q4 FY 2025 Workforce Development and Management Activities Projected Completion Date Completion Date None N/A N/A Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Workforce Development and Management Activities Projected Completion Date Post vacancy announcement to recruit for the 2026 NRAN cohort, with recruitment to occur on an annual frequency in accordance with Section 502(c) of the ADVANCE Act.

11/30/2513 Stand up the Strategic Hiring Committee in accordance with the OPM Memorandum, Guidance on Executive Order 14356, Ensuring Continued Accountability in Federal Hiring.

01/30/26 Implement the revised SWP process with information from offices on future staffing needs.

03/31/2614 2-4 Accident Tolerant Fuel (ATF)

The NRC has been developing a proposed rule associated with the use of light-water reactor fuel containing uranium enriched to greater than 5 weight-percent uranium-235. The NRC plans to combine this rulemaking, previously referred to as the Increased Enrichment rulemaking, with a rulemaking under EO 14300 titled, Modernizing Reactor Licensing, Safety Oversight, and Siting Practices. Additional information is available on the NRCs public website (https://www.nrc.gov/reading-rm/doc-collections/rulemaking-ruleforum/active/ruledetails?id=2237). In addition, the NRC staff is on track to complete the review of nine fuel vendor topical reports related to ATF by the end of FY 2026, which, if approved, could be referenced in ATF license amendment requests (LARs) for operating reactors. There were no LARs submitted during this reporting period.

13 The projected completion date for this activity was extended from September 30, 2025, to November 30, 2025, due to the government shutdown.

14 The projected completion date for this activity was extended from September 30, 2025, to March 16, 2026, due to the government shutdown and to allow for completion of additional functionality testing prior to agencywide release.

Activities Planned and Completed for Q3 FY 2025 ATF Activities Projected Completion Date Completion Date Held the first public workshop15 in a series on topics related to fuel fragmentation, relocation, and dispersal, including a Nuclear Energy Institute (NEI) draft white paper on Risk Significance of Loss of Coolant Accidents (LOCAs) and Justification for a Risk-Informed Transition Break Size (TBS)

Methodology.

06/30/25 05/21/25 Activities Planned and Completed for Q4 FY 2025 ATF Activities Projected Completion Date Completion Date Held a public workshop to discuss the status of the staffs assessment of updated accident source terms on environmental qualification of equipment and containment aerosol deposition.

09/30/25 09/24/25 Held a public workshop in the series on topics related to fuel fragmentation, relocation, and dispersal, including an Electric Power Research Institute (EPRI) draft white paper on in-core and ex-core coolability.

09/30/25 07/31/25 Held a public workshop in the series on topics related to fuel fragmentation, relocation, and dispersal, including an NEI draft white paper on Materials Degradation Research and NEI 03-08 Materials Initiative.

09/30/25 09/19/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected ATF Activities Projected Completion Date Hold subsequent public workshops in the series on topics related to fuel fragmentation, relocation, and dispersal. Future topics may include transition break size and graded approach. The staff currently plans to discuss a different draft white paper from industry at each workshop.

03/31/26 Hold tabletop exercises to test bundled power uprate licensing application pathway.

03/31/26 15 This is the same activity reported as Hold a public workshop on Alternative 4 for addressing fuel fragmentation, relocation, and dispersal in the draft proposed rule for the Increased Enrichment rulemaking in the previous report.

Deliver informational presentations on ATF initiatives at the NRCs annual Regulatory Information Conference to support stakeholder engagement and regulatory transparency.

03/31/26 2-5 Advanced Nuclear Reactor Technologies and Fuel Cycle Facilities The NRC staff held public meetings on advanced reactors focused on the following topics:

microreactor licensing and deployment considerations for mobile microreactors16 (ML25111A130);

NEI 23-01 (Rev 1), Operator Cold License Training Plan for Advanced Nuclear Reactors (ML25101A187); NEI 24-05 (Rev 0), An Approach for Risk-Informed Performance-Based Emergency Planning (ML25120A073 and ML25174A002); NEI 24-11, Fire Brigade Staffing Analysis for Advanced Reactor Technologies (ML25122A185); licensing requirements for the high-volume deployment of microreactors and other low consequence reactors (ML25192A134 and ML25196A417); draft Advanced Reactor Construction Oversight Program (ARCOP) Inspection Manual Chapters (ML25213A066); and staff feedback on NEIs White Paper Selection of a Seismic Scenario for an EPZ Boundary Determination (ML25227A092). The NRC staff also holds periodic public stakeholder meetings to discuss non-light-water reactor topics of interest. A list of those periodic meetings can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/get-involved/meetings.html).

The NRC held several public meetings on fuel cycle facilities focused on the following topics: licensing best practices and potential improvements for licensing fuel facilities, including initiatives on pre-application activities, licensing action reviews, communication and guidance, and internal NRC processes (ML25112A270 and ML25153A070). The NRC staff also holds semi-annual public stakeholder meetings with the fuel cycle industry and other stakeholders on fuel cycle regulatory activities. A list of those semi-annual meetings can be found on the NRCs public website (https://www.nrc.gov/materials/fuel-cycle-fac/regs-guides-comm.html). The last meeting was held on May 14, 2025 (ML25162A244), where the NRC staff discussed modernizing environmental reviews, environmental report pre-application guidance, the Endangered Species Act non-federal representative process, incorporation by reference as a tool for developing National Environmental Policy Act documents, and clarifying guidance on safety assessments.

In addition, the NRC staff is focused on developing strategies to streamline the licensing timelines for microreactor deployment, some of which were identified as future actions in the enclosure to SECY-24-0008, Micro-Reactor Licensing and Deployment Considerations: Fuel Loading and Operational Testing at a Factory (ML23207A252). On June 17, 2025, the Commission approved the staffs proposal in SECY 0008 (ML25168A133).

The staff also continued to address topics discussed in the Integrated Microreactor Activities Plan.

The Integrated Microreactor Activities Plan includes the topical focus areas from Section 208 of the ADVANCE Act, which requires the NRC to develop and implement risk-informed and performance-based strategies and guidance to license and regulate microreactors. The plan outlines actions the staff has identified to enhance the flexibility of the regulatory framework to support the diverse technologies and deployment models being considered by microreactor developers and potential applicants. Subsequently, EO 14300, Section 5(e), directed the staff to establish a process for high-volume licensing of microreactors and modular reactors. The staff is using the Microreactor Activities Plan to inform its efforts to meet the direction in the EO.

16 The staff uses the term mobile microreactor to refer to a microreactor that is intended to be operated at more than one fixed location on an as-needed, where-needed basis.

On August 8, 2025, the NRC published draft Regulatory Guide (DG), DG-1439, Guidance for Technology-Inclusive Risk-Informed Change Evaluation in the Federal Register with a 30-day public comment period (90 FR 38516), which closed on September 8, 2025. The staff is preparing responses to the comments received and continuing to develop the final regulatory guide.

On October 31, 2024, the NRC published the Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors in the Federal Register with a 60-day public comment period (89 FR 86918). The public comment period closed on February 28, 2025, and the agency received over 900 unique comments on the proposed rule. The staff is preparing responses to the comments received and continuing to develop the draft final rule. After the NRC staff completes this work, the draft final rule package, including key guidance, will be submitted to the Commission for consideration. The NRCs rulemaking is on target to be completed in advance of NEIMAs required deadline of December 31, 2027. Further details about the rulemaking schedule can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/modernizing/rulemaking/part-53.html).

Activities Planned and Completed for Q3 FY 2025 Advanced Nuclear Reactor Technologies and Fuel Cycle Facilities Activities Projected Completion Date Completion Date Submitted a SECY paper to the Commission with the status of advanced reactor activities.

04/30/25 05/09/2517 Submitted a SECY paper to the Commission on Microreactor Licensing and Deployment Considerations for Nth-of-a-Kind Licensing.

05/30/25 06/18/2518 Activities Planned and Completed for Q4 FY 2025 Advanced Nuclear Reactor Technologies and Fuel Cycle Facilities Activities Projected Completion Date Completion Date Published Draft Regulatory Guide on Technology-Inclusive Risk-Informed Change Evaluation Process for public comment.

08/29/25 08/08/25 17 This activity was completed on May 9, 2025, rather than the projected completion date of April 30, 2025, to support completion of internal review and approval.

18 This activity was completed on June 18, 2025, rather than the projected completion date of May 30, 2025, to support completion of internal review and approval and consideration of EO 14300.

Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Advanced Nuclear Reactor Technologies and Fuel Cycle Facilities Activities Projected Completion Date Issue Draft Regulatory Guide Technology Inclusive Risk Informed, and performance Based Methodology for Seismic Design of Commercial Nuclear Plants and Draft Regulatory Guide Seismically Isolated Nuclear Power plants to support ACRS interaction.

TBD19 Submit a SECY paper to the Commission on Update on Development of the U.S. Nuclear Regulatory Commissions Advanced Reactor Construction Oversight Program.

11/30/2520 2-6 Pre-application Activities and Licensing Reviews for Nuclear Reactors21 Advanced Reactors Information on the reactor designers that formally notified the NRC of their intent to engage in pre-application regulatory interactions can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/who-were-working-with/pre-application-activities.html).

TerraPower Natrium Reactor Plant Construction Permit Application Review On March 28, 2024, TerraPower, LLC (TerraPower), on behalf of US SFR Owner, LLC (USO),

submitted a construction permit (CP) application for Kemmerer Power Station Unit 1 (Kemmerer Unit 1) (ML24088A059), which would be sited in Lincoln County, Wyoming. The NRC staff accepted the application for review on May 21, 2024 (ML24135A109). On February 26, 2025, the NRC staff issued a letter (ML25055A019) informing USO of the completion of the draft safety evaluation (SE) with open items ahead of schedule, allowing the scheduled review to be shortened by 4 months. On May 7, 2025, the staff issued an exemption from the definition of construction (ML25119A333) in 10 CFR 50.10 that allows USO to proceed with the construction of the energy island without the need for a limited work authorization while the staff continues its construction permit application review. The associated environmental assessment and finding of no significant impact were published concurrently in the Federal Register. On June 18, 2025, the staff issued the draft Environmental Impact Statement (EIS) (ML25154A651) for the Kemmerer Unit 1 CP application. On July 1, 2025, the staff issued an updated schedule and resource letter indicating that the staff plans to complete its review by December 31, 2025 (ML25181A764). The acceleration of the review is facilitated by the streamlined Advisory Committee on Reactor Safeguards (ACRS) interactions directed by EO 14300.

Application documents and information regarding the review are available on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/who-were-working-with/applicant-projects/terrapower.html).

19 The projected completion date for this activity was extended from May 30, 2025, to support completion of internal review and approval and consideration of EO 14300.

20 The projected completion date for this activity was extended from June 30, 2025, to November 30, 2025, to support internal review and approval.

21 Pre-application activity tables are not provided for license renewal, reactor restarts, or power uprates. Any pre-application activities for license renewal, reactor restarts, and power uprates are addressed in the narrative portion of the respective section. The first licensing activity for these licensing actions is the acceptance review, which would appear in the licensing review activities tables of the respective section.

Long Mott Generating Station Construction Permit Application Review On March 31, 2025, Long Mott Energy, LLC submitted a construction permit application for Long Mott Generating Station (LMGS) (ML25090A057). LMGS would be sited at the Dow Seadrift Site in Calhoun County, Texas, and would consist of a four-module, X-Energy Xe-100 nuclear power facility. On May 12, 2025, the NRC staff accepted the LMGS application for review (ML25115A247).

On June 10, 2025, the staff issued a letter providing the staffs expected review schedule and resources (ML25155B841). The staff expects to complete its review of the LMGS application by November 2026 (18-month review). Application documents and information regarding the review are available on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/who-were-working-with/applicant-projects/long-mott.html).

Fermi America Combined License Application Review On June 17, 2025, Fermi America submitted Part 1 of a combined licensee application (COLA)

(ML25169A395) for four AP1000 reactors. The reactors are proposed to be located at the President Donald J. Trump Advanced Energy and Intelligence Campus in Carson County, Texas, adjacent to the U.S. Department of Energys (DOE) Pantex facility. Part 1 of the application included general, financial, and environmental information. On August 20, 2025, Fermi America submitted Part 2 of the COLA (ML25232A199), which included non-site-specific technical chapters of the Final Safety Analysis Report and other supplemental information. Fermi America has identified additional future submittals, including an applicant-prepared draft EIS and site-specific information, that it plans to submit to complete its application. On September 5, the NRC staff accepted Part 1 and Part 2 of the COLA (ML25240A918). Upon receipt of Part 3 of the COLA, the NRC staff will be able to complete its acceptance review of the remaining portion of the COLA and, if the completed application is accepted, issue a formal notice of opportunity for hearing in the Federal Register. Application documents and information regarding the review are available on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/large-lwr/col/fermi-energy-intel-campus).

Tennessee Valley Authority (TVA) Construction Permit Application Review On April 28, 2025, Tennessee Valley Authority (TVA) submitted Part 1 of a two-part construction permit application (CPA) to build a GVH (former GE Vernova Hitachi Nuclear Energy) BWRX-300 at the Clinch River Nuclear Site in Roane County, Tennessee (ML25118A209). Part 2 of the CPA was submitted to the NRC on May 20, 2025 (ML25140A062). On July 9, 2025, the NRC staff accepted TVAs CPA for review (ML25182A151) and issued a resource and schedule letter to TVA on July 25, 2025 (ML25205A005). The staff expects to complete its review of TVAs application by November 2026. Application documents and information regarding the review are available on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/who-were-working-with/applicant-projects/clinch-river.html).

Atomic Alchemy Construction Permit Application Review On September 12, 2025, Atomic Alchemy, Inc. (AAI) submitted parts of its CPA, consisting of general information and the preliminary safety analysis report (PSAR). The AAI CPA requests NRC approval to construct four Versatile Isotope Production Reactors (VIPRs) at the Idaho National Laboratory desert site in Bingham County, Idaho. The VIPRs will be light-water non-power reactors used for irradiating targets to commercially produce various radioisotopes. As part of its submission, AAI requested an exemption that would allow it to submit the environmental report within 6 months of the PSAR submittal. The NRC staff is performing an acceptance review of the PSAR and the exemption request. Pre-application documents are available on the NRCs public website (https://www.nrc.gov/reactors/non-power/new-facility-licensing/atomic-alchemy).

Activities Planned and Completed for Q3 FY 2025 Advanced Reactor Licensing Review Activities Projected Completion Date Completion Date Completed acceptance review of Long Mott Generating Station construction permit application.

05/30/25 05/12/25 Issued final SE for the NuScale US460 standard design approval application.

07/31/25 05/22/25 Issued draft EIS for Kemmerer Unit 1.

06/30/25 06/18/25 Advanced Reactor Pre-application Review Activities Projected Completion Date Completion Date Issued final SE to TerraPower for its topical report on human factors program plan methodology.

04/30/25 04/22/25 Issued final SE to TerraPower for its topical report on reactor stability methodology.

06/27/25 04/22/25 Issued final SE to TerraPower for its topical report on design basis accident without radiological release methodology.

07/11/25 04/22/25 Issued final SE to TerraPower for its topical report on radiological release methodology.

06/27/25 05/13/25 Issued final SE to TerraPower for its topical report on radiological source term methodology.

06/27/25 06/16/25 Activities Planned and Completed for Q4 FY 2025 Advanced Reactor Licensing Review Activities Projected Completion Date Completion Date None N/A N/A Advanced Reactor Pre-application Review Activities Projected Completion Date Completion Date Issued final SE to TerraPower for its topical report on digital instrumentation and control methodology.

11/30/2522 08/08/25 Issued final SE to TerraPower for its topical report on partial flow methodology.

11/30/25 08/19/25 Issued final SE to TerraPower for its topical report on design basis accident with radiological release methodology.

11/30/25 08/19/25 22 The projected completion date for this activity was extended from June 13, 2025, to November 30, 2025, to allow the ACRS review for the topical report and the Kemmerer Unit 1 construction permit application to occur at the same time.

Issued readiness assessment report to Oklo for the Aurora Powerhouse combined license application.

07/11/25 07/07/25 Issued final SE to Terrestrial for its topical report on principal design criteria.

09/30/2523 07/18/25 Issued final SE to X-energy for its topical report on transient and safety analysis methodology 09/30/25 08/11/25 Issued final SE to X-energy for its topical report on Gothic and Flownex Analysis Code Qualification.

09/30/25 08/11/25 Issued final SE to X-energy for its topical report on training programs methodology.

10/31/2524 09/05/25 Issued final SE to X-energy for its topical report on reactor core analysis and methods.

10/31/25 08/20/25 Issued final SE to X-energy for its topical report on mechanistic source term approach 10/31/25 08/11/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Advanced Reactor Licensing Review Activities Projected Completion Date Issue final SE for Kemmerer Unit 1 construction permit application.

12/31/25 Issue final EIS for Kemmerer Unit 1 construction permit application.

12/31/25 Projected Advanced Reactor Pre-Application Review Activities Projected Completion Date Issue final SE to Kairos for its Core Design Methodology Topical Report.

11/30/2525 Issue final SE to X-energy for its Principal Design Criteria Topical Report for the XENITH design.

TBD26 Issue final SE to Westinghouse Electric Company, LLC (Westinghouse) for its Nuclear Design Criteria Topical Report for the eVinci design.

12/31/2527 Issue final SE to X-energy for its Analytical Methods Topical Report for the XENITH design.28 TBD Issue final SE to Westinghouse for its TRISO Fuel Design Methodology Topical Report for the eVinci design.

12/31/25 23 The projected completion date for this activity was extended from June 1, 2025, to September 30, 2025, to support internal review and approval.

24 The projected completion date for this activity was extended from June 15, 2025, to October 31, 2025, to support internal review and approval.

25 The projected completion date for this activity was extended from September 30, 2025, to November 30, 2025, to allow for the completion of an onsite audit used to acquire additional information to support the topical report.

26 The projected completion date for this activity is TBD while the review is on hold by request of the vendor.

27 The projected completion for this activity was extended from September 30, 2025, to December 31, 2025, to support internal review and input received by the applicant.

28 The title of this activity was updated from nuclear design methodology to analytical methods.

Projected Advanced Reactor Pre-Application Review Activities Projected Completion Date Issue final SE to Kairos for its Hermes Safety Analysis Methods Topical Report.

10/31/25 Issue final SE to TerraPower for its Reactor Seismic Isolation System Qualification Topical Report.

11/30/25 Issue final SE to Energy Northwest New Nuclear for its Quality Assurance Program Description Topical Report.

12/12/25 Issue final SE to X-energy for its Graphite Core Assembly Material Qualification and Design Methodologies Topical Report.

12/31/25 Issue final SE to Westinghouse for its Advanced Logic System v2 Platform Elimination of Technical Specification Surveillance Requirements Topical Report.

02/27/26 Issue final SE to Aalo Atomics for its Quality Assurance Program Description Topical Report.

12/31/25 Issue final SE to X-energy for its Plume Exposure Pathway Emergency Planning Zone Sizing Methodology Topical Report.

01/30/26 License Renewal Information on upcoming license renewal application submittals can be found on the NRCs public website at:

License Renewal Applications Subsequent License Renewal Applications Activities Planned and Completed for Q3 FY 2025 License Renewal Licensing Review Activities Projected Completion Date Completion Date Issued Draft Supplemental Environmental Impact Statement (SEIS) for Clinton Power Station, Unit 1 license renewal application.

04/30/25 04/11/25 Issued Draft Supplement to the Draft SEIS for Point Beach Nuclear Plant, Units 1 and 2 subsequent license renewal application.

04/30/25 04/16/25 Completed acceptance review for H.B. Robinson Steam Electric Plant, Unit 2 subsequent license renewal application.

05/30/25 04/28/25 Issued Final SEIS for Perry Nuclear Power Plant, Unit 1 license renewal application.

04/30/25 04/30/25 Issued Final SEIS for Virgil C. Summer Nuclear Station, Unit 1 subsequent license renewal application.

06/30/25 05/08/25 Issued Draft SEIS for Browns Ferry Nuclear Plant, Units 1, 2, and 3 subsequent license renewal application.

05/30/25 05/21/25 License Renewal Licensing Review Activities Projected Completion Date Completion Date Issued Final SEIS for Peach Bottom Atomic Power Station, Units 2 and 3 subsequent license renewal application.

06/30/25 05/21/25 Issued Draft SEIS for Dresden Nuclear Power Station, Units 2 and 3 subsequent license renewal application.

06/30/25 05/21/25 Issued Final Safety Evaluation Report (SER) for Perry Nuclear Power Plant, Unit 1 license renewal application.

05/30/25 05/29/25 Completed acceptance review for Edwin I. Hatch Nuclear Plant, Units 1 and 2 subsequent license renewal application.

06/30/25 06/13/25 Issued subsequent renewed license for Virgil C.

Summer Nuclear Station, Unit 1.

08/29/25 06/30/25 Activities Planned and Completed for Q4 FY 2025 License Renewal Licensing Review Activities Projected Completion Date Completion Date Issued Final SER for Browns Ferry Nuclear Plant, Units 1, 2, and 3 subsequent license renewal application.

07/30/25 07/18/25 Issued decision on Perry Nuclear Power Plant, Unit 1 license renewal application.

07/31/25 07/7/25 Issued Final SER for Clinton Power Station, Unit 1 license renewal application.

08/29/25 8/29/25 Issued Final SER for Dresden Nuclear Power Station, Units 2 and 3 subsequent license renewal application.

09/30/25 9/9/25 Issued Final SEIS for Point Beach Nuclear Plant, Units 1 and 2 subsequent license renewal application.

10/31/25 8/8/25 Issued Final SEIS for Dresden Nuclear Power Station, Units 2 and 3 subsequent license renewal application.

10/31/25 9/3/25 Issued Final SEIS for Clinton Power Station, Unit 1 license renewal application.

10/31/25 8/1/25 Issued Final SEIS for Browns Ferry Nuclear Plant, Units 1, 2, and 3 subsequent license renewal application.

11/28/25 8/21/25 Issued decision on Point Beach Nuclear Plant, Units 1 and 2 subsequent license renewal application.

12/31/25 9/29/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected License Renewal Licensing Review Activities Projected Completion Date Issue decision on Diablo Canyon Power Plant, Units 1 and 2 license renewal application.

TBD29 Issue Draft SEIS for St. Lucie Plant, Units 1 and 2 subsequent license renewal application.

12/31/2530 Issue decision on Browns Ferry Nuclear Plant, Units 1 and 2 subsequent license renewal application.

12/12/2530 Issue decision on Dresden Nuclear Power Station, Units 2 and 3 subsequent license renewal application.

12/16/2530 Issue decision on Clinton Power Station, Unit 1 license renewal application.

12/16/2530 Issue Draft SEIS for H.B. Robinson Steam Electric Plant, Unit 2 subsequent license renewal application.

12/31/2530 Complete draft of Supplemental Environmental Assessment for Edwin I.

Hatch Nuclear Plant, Units 1 and 2 subsequent license renewal application.

01/31/26 Issue Final SEIS for St. Lucie Plant, Units 1 and 2 subsequent license renewal application.

03/31/26 Issue Supplemental Environmental Assessment for Edwin I. Hatch Nuclear Plant, Units 1 and 2 subsequent license renewal application.

03/31/26 Reactor Restarts Palisades Nuclear Plant Restart Review Palisades Nuclear Plant, in Covert, Michigan, ceased operations on May 20, 2022. On February 1, 2023, and March 13, 2023, Holtec Decommissioning International (Holtec) submitted letters to the NRC expressing interest in returning Palisades to operations (ML23032A399 and ML23072A404).

The NRC staff held two initial pre-application meetings in March and May 2023 to discuss the regulatory path (ML23107A121 and ML23171B122). On September 28, 2023, Holtec submitted the first in a series of requests for licensing actions to reauthorize power operations (ML23271A140). On July 1, 2025, the licensee submitted a letter notifying the NRC of their readiness to transition to an operational status on August 25, 2025 (ML25182A066). On July 24, the NRC issued the bundle of licensing actions necessary to restore the plants operational licensing basis. On August 25, 2025, the licensee implemented the bundle of licensing actions and re-entered the Reactor Oversight Process (ML25237A317). The NRC has additional reviews and inspections to complete, and the licensee has additional actions to take to restore the plant equipment, before fuel can be loaded in the reactor 29 While the NRC staff has completed its safety and environmental reviews, the applicant has not obtained two Federal certifications that are required for the NRC to move forward with its licensing decision (i.e., Coastal Zone Management Act

[CZMA] and Clean Water Act [CWA] Section 401). The current projected timeline for State completion of the CWA 401 certification review is February 2026. The California Coastal Commission has not shared a schedule associated with its CZMA review.

30 In August 2025, the NRC revised the schedules for ongoing license renewal reviews (Browns Ferry, Clinton, Dresden, H.B. Robinson, Point Beach, and St. Lucie), accelerating the schedules to meet the EO 14300 timeline for completion within 12 months.

vessel and the plant resumes commercial operation. Requests and information regarding the review are available on the NRCs public website (https://www.nrc.gov/info-finder/reactors/pali.html).

Christopher M. Crane Clean Energy Center Restart Review The Christopher M. Crane Clean Energy Center, formerly Three Mile Island Nuclear Station, Unit 1, in Middletown, Pennsylvania, ceased operations on September 20, 2019. On October 25, 2024, the NRC staff held an initial pre-application meeting with Constellation Energy Generation, LLC to discuss their regulatory path and intent to rename the plant (ML24346A418). On November 4, 2024, Constellation submitted a letter to the NRC expressing interest in plant restart in 2027 (ML24310A104). On November 19, 2024, Constellation submitted the first in a series of requests for licensing actions to reauthorize power operations (ML24324A048). On March 6, 2025, the NRC staff issued a charter establishing the Crane Restart Panel (ML25013A196). On June 27, 2025, Constellation submitted a license amendment request to receive new fuel prior to transitioning to an operational status (ML25178A294). On July 31, 2025, Constellation submitted a license amendment request to restore the license and technical specification back to an operational status (ML25212A076). Requests and information regarding the review are available on the NRCs public website (https://www.nrc.gov/info-finder/reactors/ccec.html).

Duane Arnold Energy Center Restart Review The Duane Arnold Energy Center (DAEC), in Palo, Iowa, permanently ceased operations on August 10, 2020. On January 23, 2025, NextEra Energy Duane Arnold, LLC submitted a letter to the NRC expressing interest in plant restart in 2028 (ML25023A265) and the first in a series of requests for licensing actions to reauthorize power operations (ML25023A270). In March 2025, the NRC staff held an initial pre-application meeting to discuss their regulatory path (ML25099A149). On April15, 2025, the NRC staff issued a charter establishing the DAEC Restart Panel (ML25069A731). Requests and information regarding the review are available on the NRCs public website (https://www.nrc.gov/info-finder/reactors/duan.html).

Activities Planned and Completed for Q3 FY 2025 Reactor Restart Activities Projected Completion Date Completion Date Completed acceptance review for relief request for the Christopher M. Crane Clean Energy Center to use specific provisions of a later edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI.

05/06/25 05/06/25 Issued a license amendment to change facility name from Three Mile Island Nuclear Station, Unit 1 to Christopher M. Crane Clean Energy Center.

05/13/25 05/13/25 Issued environmental assessment and finding of no significant impact for Holtecs request to return Palisades to operation.

05/30/25 05/30/25 Activities Planned and Completed for Q4 FY 2025 Reactor Restart Activities Projected Completion Date Completion Date Completed acceptance review for Palisades LAR to modify license condition associated with completion of NFPA-805 modifications.

07/15/25 05/06/25 Issued decision on Palisades request for exemption from portions of 10 CFR 50.82 to support reauthorization of power operations.

07/31/25 07/24/25 Issued decision on Palisades license transfer request to support reauthorization of power operations.

07/31/25 07/24/25 Issued decision on Palisades LAR to update the license and technical specifications to support reauthorization of power operations.

07/31/25 07/24/25 Issued decision on Palisades LAR to update the administrative section of the technical specifications to support reauthorization of power operations.

07/31/25 07/24/25 Issued decision on Palisades LAR to restore the operational emergency plan to support reauthorization of power operations.

07/31/25 07/24/25 Issued decision on Palisades LAR to modify the main steam line break analysis to support reauthorization of power operations.

07/31/25 07/24/25 Issued decision on Palisades LAR to include leak-before-break methodology for primary coolant hot and cold leg piping.

08/15/25 08/26/25 Issued decision on Palisades LAR to authorize sleeving to repair steam generator tubes.

09/30/25 10/15/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Reactor Restart Activities Projected Completion Date Issue decision on Palisades LAR to modify license condition associated with completion of NFPA-805 modifications.

10/24/25 Issue decision on Palisades exemption request related to Part 26 work hour requirements.

10/24/2531 Complete acceptance review for Crane LAR to restore the operational security plan to support reauthorization of power operations.

12/03/2532 Complete acceptance review for Crane LAR to restore the operational emergency plan to support reauthorization of power operations.

12/10/25 Complete acceptance review for DAEC LAR to update the license and technical specifications to support reauthorization of power operations.

12/29/2533 Complete acceptance review for DAEC LAR and license transfer request to support reauthorization of power operations.

01/07/26 31 This exemption request was unplanned, and therefore, it was not forecasted in the previous report. The licensee submitted the request and the NRC staff reviewed and granted the exemption within the licensees requested timeframe.

32 The Crane LARs are new applications from the licensee.

33 DAEC recently announced it was formally moving forward with the plan to restart the site and signed a power purchase agreement. Given that new agreement, the licensee has sent in, or plans to send, the majority of the licensing requests by the end of CY 2025.

Complete acceptance review for DAEC LAR to restore the operational security plan to support reauthorization of power operations.

02/27/26 Complete acceptance review for DAED LAR to restore the operational emergency plan to support reauthorization of power operations.

02/27/26 Power Uprates The NRC continues to make agency processes more efficient and effective for the review of power uprate submittals. The NRC staff are executing the power uprate project plan (ML24110A141),

identifying efficiencies to exceed review targets identified in the May 2024 letter to NEI (ML24106A068), and implementing process improvements (ML24239A394). On February 7, 2025, the NRC issued a regulatory issue summary to request information on planned power uprate submittals to support NRC budgeting and resource allocation. Responses to the February 7, 2025, regulatory issue summary requesting schedule information are available at https://www.nrc.gov/reactors/operating/licensing/power-uprates/status-power-apps/expected-applications. On June 26, 2025, the NRC staff held a closed meeting with GE Hitachi Nuclear Energy (GEH) to discuss GEHs strategy for a combined safety analysis for future submissions of extended power uprates combined with use of maximum extended load line limit analysis plus (MELLLA+)

(ML25153A482). In July 2025, the NRC staff scheduled a public workshop to discuss industry recommendations, the staffs approach, and associated schedules.

On September 23, 2025, the NRC staff held a public meeting with PSEG Nuclear LLC, to discuss a measurement uncertainty recapture (MUR) using EPRI data validation and reconciliation (DVR) methodology at Salem Nuclear Generating Station. On July 23 and September 30, 2025, the NRC staff held closed meetings with Constellation Energy Generation LLC to discuss potential power uprates for unnamed plants. There are currently no power uprate applications under review.

Additional information can be found on the NRCs public website (https://www.nrc.gov/reactors/operating/licensing/power-uprates.html).

Activities Planned and Completed for Q3 FY 2025 Power Uprate Licensing Review Activities Projected Completion Date Completion Date None N/A N/A Activities Planned and Completed for Q4 FY 2025 Power Uprate Licensing Review Activities Projected Completion Date Completion Date None N/A N/A Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Power Uprate Licensing Review Activities Projected Completion Date None N/A 2-7 Pre-application Activities and Licensing Reviews for Fuel Cycle Facilities34 Westinghouse Electric Company, LLC Pre-Application Engagement Westinghouse had a pre-application meeting with the NRC staff on May 16, 2024, regarding a proposed LAR for the Columbia Fuel Fabrication Facilitys (CFFF) low enriched uranium plus (LEU+)

facility and a pre-application meeting focused on natural phenomena hazards on November 21, 2024.

On February 26, 2025, Westinghouse submitted a white paper about Natural Phenomena Hazard Criteria to support a future LAR aimed at increasing enrichment in a new building at their site that will fabricate fuel with increased enrichment (ML25057A093). The NRC staff provided observations as early feedback on the white paper to Westinghouse on June 25, 2025 (ML25160A287). On June 23, 2025, the NRC staff held a virtual partially closed public meeting with Westinghouse CFFF staff, who requested the meeting to discuss the criticality safety program for the planned LEU+ facility expansion (ML25197A519).

Paducah Laser Enrichment Facility Application Acceptance Review On June 30, 2025, Global Laser Enrichment, LLC (GLE) submitted a license application (ML25179A001) for the Paducah Laser Enrichment Facility (PLEF). GLE plans to construct and operate the proposed facility adjacent to the decommissioned Paducah Gaseous Diffusion Plant site in McCraken County, Kentucky. The proposed facility is anticipated to be deployed as part of an agreement between GLE and the U.S. Department of Energy (DOE) to purchase and re-enrich certain DOE inventories of depleted uranium hexafluoride (UF6). The proposed facility will utilize laser-based isotope separation technology to enrich UF6 up to 8 weight-percent uranium-235. On August 4, 2025, the staff accepted the license application for the PLEF (ML25202A201). The license application review has a projected completion date of January 2027.

TRISO-X Fuel Fabrication Facility License Application Review:

In September 2022, the NRC staff received an application from TRISO-X, a subsidiary of X-energy, to operate a TRISO fuel fabrication facility (ML22101A200 and ML22266A269). The application was accepted for review on November 18, 2022 (ML22320A110). TRISO-X submitted supplemental information for the application on February 29, 2024 (ML24060A239). TRISO-X later revised the license application and environmental report to account for a modified facility design via letters dated December 30, 2024, January 31, 2025, and March 28, 2025. The NRC staff issued a revised schedule letter on March 14, 2025 (ML23005A193), which modified the projected completion date from June 2025 to May 2026. In September 2025, the NRC staff issued the draft EIS (ML25267A128) for comment, and is working to develop the safety evaluation report and final EIS.

Activities Planned and Completed for Q3 FY 2025 Fuel Facility Licensing Review Activities Projected Completion Date Completion Date None N/A N/A 34 Pre-application activity tables are not provided for fuel cycle facilities. Any pre-application activities for fuel cycle facilities are addressed in the narrative portion of the respective section. The first licensing activity for these licensing actions is the acceptance review, which would appear in the licensing review activities tables of the respective section.

Activities Planned and Completed for Q4 FY 2025 Fuel Facility Licensing Review Activities Projected Completion Date Completion Date Completed the acceptance review for the Paducah Laser Enrichment Facility license application.

09/30/25 08/04/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Fuel Facility Licensing Review Activities Projected Completion Date None N/A 2-8 Reactor Oversight Process In response to Section 507 of the ADVANCE Act, the NRC completed an assessment to identify specific improvements to the nuclear reactor and materials oversight and inspection programs that the NRC may implement to maximize the efficiency of these programs through, where appropriate, the use of risk-informed, performance-based procedures, expanded incorporation of information technologies, and staff training. This assessment identified specific, near-term changes to the NRCs oversight and inspection programs to improve efficiency and reduce redundancy. Further, as a result of this assessment, the NRC staff determined that a broad, comprehensive review of the ROP is necessary to reflect improvements in industry performance and advancements in technology.

Further, Section 5(g) of EO 14300 directs the NRC specifically to [r]evise the Reactor Oversight Processto reduce unnecessary burdens and be responsive to credible risks. The comprehensive review of the ROP will provide the NRC with a mechanism to further revise the ROP consistent with the direction in EO 14300. During the reporting period, the staff discussed the status of its review and sought feedback on its proposed resolutions to recommendations from internal and external stakeholders at the ROP bimonthly public meeting (ML25155A001) and a public workshop to discuss preliminary concepts for the review and revision of the ROP performance indicator program (ML25161A073). Following a subsequent public workshop to further discuss the review and revision of the ROP performance indicator program (ML25174A351), the staff decided to prioritize revising the ROP Baseline Inspection Program. The staff discussed the ROP Baseline Inspection Program revision and sought feedback on the proposed changes at two public meetings (ML25237A001 and ML25267A199). Targeted revisions to the performance indicator program will be resumed after revision of the ROP Baseline Inspection Program is completed.

The NRC staff is revising Inspection Manual Chapter 0609, Appendix E, Part I, Baseline Security Significance Determination Process for Power Reactors (ML22178A222), to further risk-inform the process and improve its clarity and consistency. The SECY and revised inspection manual documents were provided to the Commission for review and approval in October 2025.

In May 2024, the Commission approved the NRC staffs proposed revision to the Force-on-Force (FOF) inspection program in SRM-COMSECY-19-0006, Revised Security Inspection Program Framework (Option 3) in Response to SRM-17-0100 (ML24138A045). Most notably, the revised framework will include a reduction from two NRC-conducted FOF exercises to one, reducing direct inspection time by 118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br />. The revised inspection procedures and inspection manual chapters were issued September 23, 2025, with implementation scheduled to begin at the start of the eighth triennial FOF inspection cycle on January 1, 2026 (ML25232A186 and ML25232A185).

Additionally, the staff developed interim guidance to implement inspection of minimum samples for the security baseline inspection program (non-public - contains security-related information). This interim guidance was developed to ensure consistency with revisions to IMC 2515, Light-Water Reactor Inspection Program - Operations Phase, (ML25072A254) effective July 1, 2025, and to capture efficiencies in security inspection and oversight. This interim guidance lists samples for each baseline security inspection procedure and provides flexibility for inspectors to tailor the remaining inspection requirements as necessary, prioritizing the most risk-significant aspects. The staff plans to revise and reissue IMC 2201, Security Inspection Program for Operating Commercial Nuclear Power Reactors, (ML23074A024) and other impacted inspection manual documents consistent with this interim guidance.

Activities Planned and Completed for Q3 FY 2025 ROP Activities Projected Completion Date Completion Date Issued a revision to IMC 0612 for the revised guidance on the Very Low Safety Significance Issue Resolution (VLSSIR) process.

05/31/25 05/28/25 Revised and clarified the guidance for inspection preparation. Conducted inspector training on inspection document requests and use of the NRC inspector library to ensure that documents are not requested that the NRC already holds.

06/03/25 06/03/25 Submitted a SECY paper to the Commission with recommendations and planned enhancements for the ROP based on the ROP assessment required by Section 507 of the ADVANCE Act.

04/30/25 06/05/2535 Issued revisions to IMC 0308 and 2515 for the revised guidance on minimum and nominal sample criteria.

05/31/25 06/20/2536 Activities Planned and Completed for Q4 FY 2025 ROP Activities Projected Completion Date Completion Date Revised the security issues forum charter to ensure consistency in dispositioning physical security inspection findings.

07/01/25 07/01/25 Issued interim guidance to IMC 2201 to implement minimum samples for the security baseline inspection program.

07/01/25 06/25/25 35 This activity was completed on June 5, 2025, rather than the projected completion date of April 30, 2025, to support completion of internal review and approval and consideration of EO 14300.

36 This activity was completed on June 20, 2025, rather than the projected completion date of May 31, 2025, because these actions required Commission notification, which occurred in SECY-25-0045, which was submitted to the Commission on June 5, 2025. There is a 14-day hold after Commission notification.

ROP Activities Projected Completion Date Completion Date Held a follow-on public workshop related to the ROP performance indicator program review.

07/22/25 06/26/25 Held a public meeting to discuss the ROP re-baseline proposed inspection plan.

08/20/25 08/20/25 Revised the requirement to review and close event reports through a specific inspection procedure when the underlying issue was previously inspected through a different ROP inspection.

12/31/25 09/03/25 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected ROP Activities Projected Completion Date Submit a SECY paper to the Commission on proposed revisions to the Baseline Security Significance Determination Process.

10/31/25 Submit a SECY paper to the Commission with recommendations and planned enhancements for the FOF inspection program consistent with Section 507 of the ADVANCE Act.

11/28/25 Submit a SECY paper to the Commission on proposed revisions to the ROP baseline inspection program.

01/31/26 Reduce documentation of Green and severity level IV non-cited violations, which will involve revisions to the Reactor Program System (RPS)

(projected to be implemented in January 2026).

01/31/26 Revise the More-than-minor criteria for documenting very low safety significance issues (Green) 01/31/26 Issue CY25 ROP Self-Assessment Metrics report 03/13/26 Issue annual assessment letters 03/13/26 2-9 Fusion The NRC is developing regulations and guidance for fusion machines to support licensing activities.

On December 11, 2024, the staff submitted SECY-24-0085, Proposed Rule: Regulatory Framework for Fusion Machines (3150-AL00; NRC-2023-0071) (ML24019A064), to the Commission for its approval. The enactment of the ADVANCE Act resulted in the staff incorporating conforming changes to the fusion machine proposed rule package. On March 12, 2025, the NRC staff publicly released updated draft consolidated guidance associated with the fusion machine proposed rule (Draft NUREG-1556, Vol. 22; ML24295A002). The proposed fusion rule and guidance is currently in the interagency review process with the Office of Management and Budgets Office of Information and Regulatory Affairs pursuant to EO 12866. If the proposed rule is approved, the NRC staff will submit the proposed rules Federal Register notice to the Office of the Federal Register for publication. This notice will provide an opportunity for the public to submit formal comments on the proposed rule and draft guidance.

As required by Section 205(c)(2) of the ADVANCE Act, the NRC completed a study of internal and external design certification processes that may be leveraged in the development of a licensing framework for scaled fusion machine production, deployment, and operation. The study was conducted in consultation with the Agreement States, fusion industry, public, and other Federal agencies, including the Federal Aviation Administration. The NRC staff held two public meetings and a Government-to-Government meeting to gather feedback from external stakeholders on this effort.

The NRC provided a final report to Congress summarizing the study on July 10, 2025 (ML25120A080).

To support continued external engagement, the staff chartered a standing committee on fusion oversight that is made up of NRC and Agreement State staff (ML25183A025). This committee will serve in an advisory role to the NRCs fusion program. They will develop and share lessons learned and best practices, provide technical assistance on licensing and inspection issues, track the status of commercial fusion technology development, and provide input on qualification and refresher training for licensing reviewers, inspectors, and standard device designs reviewers. The committees first meeting was held on August 7, 2025, and future meetings will be held on a bi-monthly basis.

Further, the NRC is incorporating fusion technology into its existing technical training program for both NRC and Agreement State staff. In the near term, the NRC staff is developing a self-guided training course that will provide an introduction to basic science, physics, and technology associated with fusion machines. On July 28, 2025, the NRC released web-based fusion training materials provided by the Massachusetts Institute of Technology Plasma Science and Fusion Center to NRC and Agreement State personnel. This provided an immediate pathway for staff to learn about fusion basics, fusion machines, and the latest research shaping the future of fusion while the NRC continues development of its formal fusion training program. Additionally, following the publication of the proposed rule and associated guidance discussed earlier in this section, the staff will develop and provide training on its implementation for NRC and Agreement State licensing and inspection staff.

Looking forward, as the fusion industry matures and the first commercial fusion machines are successfully deployed, the staff will work to develop an instructor-led fusion technology course similar to other technology courses designed for various byproduct material operations licensed under the 10 CFR Part 30 framework (e.g., radiography, irradiators, and well-logging).

Lastly, on June 27, 2025, the NRC revamped its public website on fusion to increase transparency for external stakeholders on the status of current fusion activities conducted by the NRC. Some updates include information on rulemaking, ADVANCE Act activities, public meetings, and frequently asked questions regarding fusion energy. The NRC staff will periodically update this website with new information on fusion activities.

Activities Planned and Completed for Q3 FY 2025 Fusion Activities Projected Completion Date Completion Date None N/A N/A Activities Planned and Completed for Q4 FY 2025 Fusion Activities Projected Completion Date Completion Date Issued report to Congress summarizing the NRCs study of regulatory frameworks as potential models for 07/09/2025 07/10/2025 the licensing of mass-manufactured fusion machines in response to Section 205(c) of the ADVANCE Act.

Conducted the first meeting with the Standing Committee for Fusion Machine Oversight.

N/A 08/07/2025 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Fusion Activities Projected Completion Date Publish the NRCs Fusion Program Roadmap to visually represent the path to successful deployment of commercial fusion technology.

11/3/2025 Release Part 1 of the NRCs web-based fusion fundamentals training course to NRC and Agreement State staff.

12/31/2025 Issue revision of Vision and Strategy: Regulating Fusion Machines Across the National Materials Program (ML25069A706) that incorporates lessons learned from the NRCs study performed in response to Section 205(c) of the ADVANCE Act.

01/30/2026 2-10 Backfit In September 2024, in its affirmation of the final rule for non-power production or utilization facility license renewal, the Commission returned NUREG-1409, Backfitting Guidelines, Revision 1 to the staff and directed the staff to clarify the applicability of 10 CFR 50.109 to commercial non-power production or utilization facilities through an interpretive rule process.37 The staff is working to address the Commissions direction. The staff plans to publish a notice of interpretation in Q1 FY 2026 to clarify the applicability of the NRCs backfitting regulations to commercial non-power production or utilization facilities.

Activities Planned and Completed for Q3 FY 2025 Backfit Activities Projected Completion Date Completion Date None N/A N/A Activities Planned and Completed for Q4 FY 2025 Backfit Activities Projected Completion Date Completion Date None N/A N/A 37 SRM-M240904, Affirmation Session - SECY-19-0062: Final Rule: Non-power Production or Utilization Facility License Renewal (RIN 3150-AI96, NRC-2011-0087) (ML24248A208).

Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2026)

Projected Backfit Activities Projected Completion Date Publish notice of interpretation to clarify the applicability of the NRCs backfitting regulations to commercial non-power production or utilization facilities.

12/31/2538 Backfit Challenges The agency did not receive any backfit appeals or written concerns during this reporting period.

During a closed meeting between the Nuclear Energy Institute (NEI) and the NRC staff on April 22, 2025, NEI raised a concern that the scope of force-on-force inspections could potentially raise backfit concerns. The concern is not publicly available because it contains security related information. The NRC staffs resolution of the concern is currently under review.

38 The projected completion date for this activity was extended from August 29, 2025, to December 31, 2025, because of prioritization of work and furlough impacts.

- Summary of Activities 3-1 Reactor Oversight Process (ROP) Findings The table below provides the CY ROP findings for the year-to-date and 3-year rolling metrics.39 Location Number of Findings CY 2022 CY 2023 CY 2024 CY 2025 Nationally Total 399 466 489 239 Region I Green 83 88 96 47 White 2

1 1

3 Yellow 0

0 0

0 Red 0

0 0

0 Greater-Than-Green (GTG) Security 0

0 1

0 Total 85 89 98 50 No. of Units Operating During CY 20 20 20 20 Region II Green 90 135 130 74 White 1

3 3

0 Yellow 0

0 0

0 Red 0

0 0

0 GTG Security 0

5 0

0 Total 91 143 133 74 No. of Units Operating During CY 33 3440 3541 35 Region III Green 89 103 105 56 White 2

0 0

0 Yellow 0

0 0

0 Red 0

0 0

0 GTG Security 1

0 0

0 Total 92 103 105 56 No. of Units Operating During CY 22 21 21 42 21 Region IV Green 130 126 149 57 White 1

5 0

2 Yellow 0

0 0

0 Red 0

0 0

0 GTG Security 0

0 0

0 Total 131 131 149 59 No. of Units Operating During CY 18 18 18 18 39 For the purposes of this report, the total number of findings per CY is based on the year in which an inspection report was issued instead of the year in which a finding was identified.

40 The increase of one unit for CY 2023 reflects Vogtle Unit 3 entering the ROP on August 3, 2022.

41 The increase of one unit for CY 2024 reflects Vogtle Unit 4 entering the ROP on July 28, 2023.

42 The reduction of one unit for CY 2023 reflects the permanent shutdown of Palisades on May 20, 2022.

3-2 Licensing Actions The tables below provide the status of licensing actions organized by licensing program. Consistent with Section 102(c) of NEIMA, the licensing actions referenced in this section include requested activities of the Commission for which the NRC staff issues a final SE. These totals do not include LARs, as they are addressed separately in Section 3-3 of this report (e.g., licensing actions here comprise exemptions, relief requests, license transfers, or plant-specific topical reviews). Total Inventory refers to the total number of licensing actions that are open and accepted by the NRC at the end of the quarter. Licensing Actions Initiated During the Reporting Period are the number of licensing actions (regardless of acceptance) that are received by the NRC during the reporting period.

Operating Reactors Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period43 Percentage of Licensing Actions Completed Prior to the NEIMA Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule44 Q1 FY 2025 132 41 67 100%

80.6%

Q2 FY 2025 157 72 47 100%

90.0%

Q3 FY 2025 173 70 54 100%

96.3%

Q4 FY 2025 119 39 91 100%

95.6%

Subsets of Licensing Actions for Q3 FY 2025 Exemptions 33 8

3 100%

100%

Relief Requests 124 59 50 100%

96.0%

License Transfers 2

0 0

N/A N/A Plant-specific Topical Reviews 0

0 0

N/A N/A Other Licensing Actions 14 3

1 100%

100%

Subsets of Licensing Actions for Q4 FY 2025 Exemptions 22 8

19 100%

84.2%

Relief Requests 83 31 69 100%

100%

License Transfers 2

0 2

N/A 100%

Plant-specific Topical Reviews 0

0 0

N/A N/A Other Licensing Actions 1445 0

1 100%

100%

43 Requested activities included in the initiated actions total but subsequently withdrawn are not included in the completed actions total because no final SE was issued.

44 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.

45 Includes applications for license renewal and subsequent license renewal.

New Reactors Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period46 Percentage of Licensing Actions Completed Prior to the NEIMA Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule Q1 FY 202547 2

0 1

100%

100%

Q2 FY 2025 2

0 0

N/A N/A Q3 FY 2025 2

1 1

100%

100%

Q4 FY 2025 4

2 0

N/A N/A Subsets of Licensing Actions for Q3 FY 2025 Exemptions 0

0 0

N/A N/A Relief Requests 0

0 0

N/A N/A License Transfers 0

0 0

N/A N/A Plant-specific Topical Reviews 0

0 0

N/A N/A Other Licensing Actions 2

1 1

100%

100%

Subsets of Licensing Actions for Q4 FY 2025 Exemptions 0

0 0

N/A N/A Relief Requests 0

0 0

N/A N/A License Transfers 0

0 0

N/A N/A Plant-specific Topical Reviews 0

0 0

N/A N/A Other Licensing Actions 448 2

0 N/A N/A 46 Requested activities included in the initiated actions total but subsequently withdrawn are not included in the completed actions total because no final SE was issued.

47 In April 2024, Request for Exemption from Annual Reporting Requirements for the U.S. EPR Standard Design Certification Application was submitted. In December 2024, the NRC staff issued the exemption. This report corrects the line item for Q1 FY 2025 to account for this licensing action.

48 Includes applications for construction permits and combined licenses.

Fuel Facilities Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period Percentage of Licensing Actions Completed Prior to the NEIMA Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule Q1 FY 2025 6

2 1

100%

100%

Q2 FY 2025 4

2 4

100%

100%

Q3 FY 2025 2

1 3

100%

66.7%49 Q4 FY 2025 1

2 3

100%

100%

Subsets of Licensing Actions for Q3 FY 2025 Exemptions 0

0 0

N/A N/A Relief Requests 0

0 0

N/A N/A License Transfers 0

0 0

N/A N/A Plant-specific Topical Reviews 0

0 0

N/A N/A Other Licensing Actions 250 1

3 100%

66.7%

Subsets of Licensing Actions for Q4 FY 2025 Exemptions 0

1 1

100%

100%

Relief Requests 0

0 0

N/A N/A License Transfers 0

0 0

N/A N/A Plant-specific Topical Reviews 0

0 0

N/A N/A Other Licensing Actions 246 1

1 100%

100%

49 One fuel cycle licensing action was completed 3 days after the established schedule due to pressing workload.

50 Includes reviews for periodic decommissioning cost estimates.

3-3 LAR Reviews The tables below provide the status of LARs organized by licensing program. Consistent with Section 102(c) of NEIMA, the LARs referenced in this section include requested activities of the Commission for which the NRC staff issues a final SE. The total inventory is the number of open LARs at the end of the quarter. LARs are included in the total inventory after they have been accepted by the NRC (the acceptance review period is generally 30 days after the application is submitted).

LARs Submitted During the Reporting Period are the number of LARs (regardless of acceptance) that are received by the NRC during the reporting period.

Operating Reactors Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period51 Percentage of LAR Reviews Completed Prior to the NEIMA Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule52 Q1 FY 2025 201 77 68 100%

85.3%

Q2 FY 2025 239 99 61 100%

82%

Q3 FY 2025 216 52 72 100%

87.5%

Q4 FY 2025 192 98 111 100%

94.6%

New Reactors Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the NEIMA Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule Q1 FY 2025 0

0 0

N/A N/A Q2 FY 2025 0

0 0

N/A N/A Q3 FY 2025 0

0 0

N/A N/A Q4 FY 2025 0

0 0

N/A N/A 51 Requested activities included in the submitted LARs total but subsequently withdrawn are not included in the completed LARs total because no final SE was issued.

52 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.

Fuel Facilities Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the NEIMA Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule Q1 FY 2025 9

3 3

100%

66.7%53 Q2 FY 2025 10 4

3 100%

50%54 Q3 FY 2025 6

3 7

100%

100%

Q4 FY 2025 11 6

1 100%

100%

3-4 Research Activities55 Summary of New Research Projects During the reporting period, the Office of Nuclear Regulatory Research (RES) initiated research on or substantially revised the following projects:

Research Assistance Request VARSKIN+ Computer Code Development & Maintenance (NRR-2024-041)

Importance to the NRC Mission 10 CFR 20.1201, Occupational dose limits for adults, specifies the annual dose limits for internal and external exposures, lens of the eye, skin of the whole body, and skin of the extremities for occupational workers. To demonstrate compliance with these dose limits, licensees must perform surveys or other radiation measurements and, when appropriate, monitor the radiation exposure and calculate the resultant doses. The NRCs VARSKIN+ computer code is used by licensees to calculate skin doses for demonstration of compliance with 10 CFR 20.1201(c), as it relates to the dose averaged over the contiguous 10 cm2 of the skin receiving the highest exposure, and by the NRC staff to verify the licensees results and conclusion. Licensees are also required to evaluate and, to the extent practical, account for intakes through wounds or skin absorption for compliance with 10 CFR 20.1202(d). Additionally, the VARSKIN+ computer code can also be used by licensees to calculate the dose to the lens of the eye for demonstration of compliance with 10 CFR 20.1201(a)(2)(i). The VARSKIN+ computer code (version 2.0 and later) can also be used by licensees to calculate the doses to the patient in instances of medical extravasations involving radiopharmaceuticals for demonstration of compliance with 10 CFR Part 35, Medical Use of Byproduct Material.

53 One of the LARs exceeded the established schedule by 33 days due to additional time needed to resolve requests for additional information. This extension was communicated and agreed to by the licensee.

54 Two of the LARs exceeded the established schedule by approximately 2 months due to higher priority licensing actions and an issue identified late in the review. This extension was communicated and agreed to by the licensee.

55 This section provides information about projects that were started or completed during the reporting period that exceeded 2 FTE or $650K of program support for the total duration of the project. For new research starts, a final reporting of research findings and results will be provided as part of the research project closure within the quarterly reports.

Planned Activities The purpose of this research project is to: 1) maintain and provide technical support, code error fixing, and updates to the VARSKIN+ computer code; 2) distribute VARSKIN+ and provide Radiation Protection Computer Code Analysis and Maintenance Program (RAMP) support; and 3) provide and develop the ExtravDose module.

Requesting Business Line Operating Reactors Estimated Completion FY 2028 Estimate of Total Research Resources 3 FTE and $430K over a 3-year period Summary of Completed Research Projects56 No research projects were completed during the reporting period.

3-5 Fees Billed The tables below provide information on 10 CFR Part 170 fees billed for each fee class. For each fee class, the NRC staff compared the fees billed to the receipts estimated in the annual fee rule.57 Fee Class New Reactors58 FY 2025 Part 170 Receipts Estimated

- Final Fee Rule

($M)59 Part 170 Billed in Q3 FY 2025 ($M)

Part 170 Billed in Q4 FY 2025 ($M)

Total Part 170

- Billed in FY 2025 ($M)

Operating Power Reactors (Total)

$174.1

$39.2

$48.3

$178.9 Operating Power Reactors Combined Licenses

$1.0

$0.0

$0.1

$0.1 Design Certifications and Standard Design Approvals

$6.2

$1.0

$0.4

$4.4 Early Site Permits

$0.0

$0.0

$0.0

$0.0 Construction Permits and Operating Licenses

$5.2

$1.6

$2.2

$6.7 Fuel Facilities

$10.0

$2.1

$3.2

$9.9 Non-Power Production or Utilization Facilities

$0.6

$0.2

$0.2

$0.8 Generic Decommissioning

$2.7

$0.4

$0.8

$2.1 Spent Fuel Storage/Reactor Decommissioning

$12.3

$3.2

$5.2

$14.2 Materials Users60

$0.8

$0.7

$0.2

$1.8 Rare Earth

$0.0

$0.0

$0.0

$0.0 56 The research project resources are estimates of staff hours and program support costs based on inspection of project records, including staffing plans and contract spending plans for the duration of the project.

57 The FY 2025 Final Fee Rule was published in the Federal Register on June 24, 2025 (90 FR 26730).

58 As requested in the May 1, 2025, letter, starting with this report, the NRC has expanded the table to provide additional information on Part 170 fees billed for specific activities for new reactors.

59 The New Reactors subset is not itemized in the FY 2025 Final Fee Rule. The NRC fee estimates system is the source of the New Reactors Part 170 Receipts Estimated.

60 Materials Users - Billed as flat fee applications and included in the estimates and billed.

Fee Class New Reactors58 FY 2025 Part 170 Receipts Estimated

- Final Fee Rule

($M)59 Part 170 Billed in Q3 FY 2025 ($M)

Part 170 Billed in Q4 FY 2025 ($M)

Total Part 170

- Billed in FY 2025 ($M)

Transportation

$3.3

$0.8

$1.2

$3.9 Uranium Recovery

$1.6

$0.4

$0.5

$1.6 Significant Ongoing Pre-Application Activities and Licensing Actions The following table includes a comparison of the fees billed to projected resources for initial and subsequent license renewals; power uprates; reactor restarts; new fuel facility license applications; construction permits and operating licenses for new reactors; design certifications and standard design approvals for new reactors; early site permits for new reactors; combined licenses for new reactors; and significant pre-application activities, which for the purposes of this table includes only topical report reviews.

Docket Project Name Projected Resources ($M)61 Fees Billed to Date

($M)62 Point Beach Units 1 and 2 -

05000266/05000301 Point Beach Units 1 and 2 Subsequent License Renewal Application - Safety Review

$5.0

$3.5 Point Beach Units 1 and 2 -

05000266/05000301 Point Beach Units 1 and 2 Subsequent License Renewal Application -

Environmental Review

$1.4

$1.8 Oconee Units 1, 2, and 3 -

05000269/05000270/05000287 Oconee Units 1, 2, and 3 Subsequent License Renewal Application - Safety Review

$5.0

$3.9 Oconee Units 1, 2, and 3 -

05000269/05000270/05000287 Oconee Units 1, 2, and 3 Subsequent License Renewal Application -

Environmental Review

$1.4

$1.8 St. Lucie Units 1 and 2 -

05000335/05000389 St. Lucie Units 1 and 2 Subsequent License Renewal Application - Safety Review

$5.0

$4.2 61 Projected resources are calculated based on the FTE estimates provided to applicants in the acceptance letters. Dollar amounts are obtained by multiplying the hours estimate by the professional hourly rate.

62 The NRC bills its licensees/applicants in the first month of the quarter following the timeframe in which the work was performed. For example, NRC work performed in April, May, and June would be invoiced to the licensee/applicant in July. NRC work performed in July, August, and September would be invoiced to the licensee/applicant in October. Therefore, the total billed amounts listed in Table 3-5 reflect costs for NRC work performed through June 2025.

Docket Project Name Projected Resources ($M)61 Fees Billed to Date

($M)62 St. Lucie Units 1 and 2 -

05000335/05000389 St. Lucie Units 1 and 2 Subsequent License Renewal Application -

Environmental Review

$1.4

$0.78 Kemmerer Unit 1 -

05000613 Kemmerer Unit 1 Construction Permit Application - Safety and Environmental Reviews

$13.0

$6.4 Long Mott Generating Station 05000614 Long Mott Generating Station Construction Permit Application - Safety and Environmental Reviews

$10.4

$0.39 Monticello Unit 1 -

05000263 Monticello Unit 1 Subsequent License Renewal Application

- Safety Review

$5.1

$2.4 Monticello Unit 1 -

05000263 Monticello Unit 1 Subsequent License Renewal Application

- Environmental Review

$2.1

$2.0 Browns Ferry Units 1, 2, and 3 -

05000259/05000260/05000296 Browns Ferry Units 1, 2, and 3 Subsequent License Renewal Application - Safety Review

$3.5

$2.9 Browns Ferry Units 1, 2, and 3 -

05000259/05000260/05000296 Browns Ferry Units 1, 2, and 3 Subsequent License Renewal Application -

Environmental Review

$1.9

$1.4 Dresden Units 2 and 3 -

05000237/05000249 Dresden Units 2 and 3 Subsequent License Renewal Application -

Safety Review

$2.4

$2.1 Dresden Units 2 and 3 -

05000237/05000249 Dresden Units 2 and 3 Subsequent License Renewal Application -

Environmental Review

$1.8

$1.2 Docket Project Name Projected Resources ($M)61 Fees Billed to Date

($M)62 Perry Unit 1 -

05000440 Perry Unit 1 License Renewal Application -

Environmental Review

$1.9

$1.2 Perry Unit 1 -

05000440 Perry Unit 1 License Renewal Application Review - Safety Review

$4.4

$3.7 Diablo Canyon Units 1 and 2 -

05000275/05000323 Diablo Canyon Units 1 and 2 License Renewal Application -

Environmental Review

$2.0

$1.6 Diablo Canyon Units 1 and 2 -

05000275/05000323 Diablo Canyon Units 1 and 2 License Renewal Application -

Safety Review

$3.2

$2.5 Clinton Unit 1 -05000461 Clinton Unit 1 License Renewal Application -

Environmental Review

$1.9

$1.4 Clinton Unit 1 -05000461 Clinton Unit 1 License Renewal Application -

Safety Review

$3.5

$2.0 Palisades -

05000255/99902112 Palisades Restart

- Safety and Environmental Review

$3.2

$2.8 Crane Clean Energy Center63 -

05000289 Crane Clean Energy Center Restart - Safety and Environmental Review

$0.8064

$0.01 63 On May 13, 2025, the NRC staff issued an amendment approving the name change from Three Mile Island Nuclear Station, Unit 1, to the Christopher M. Crane Clean Energy Center (ML25100A006).

64 Projected resources will be updated, as Constellation submits the remaining requests in the series of requests for licensing actions outlined in the Regulatory Path to Potential Reauthorization of Power Operations (ML24310A104).

Projected resources included in the table are for requests for licensing actions received prior to the end of the reporting period.

Docket Project Name Projected Resources ($M)61 Fees Billed to Date

($M)62 Duane Arnold Energy Center -

05000331 Duane Arnold Energy Center Restart - Safety and Environmental Review

$0.6665

$0.01 TRISO-X LLC 07007027 TRISO-X Fuel Fabrication Facility -

Safety and Environmental Reviews

$7.4

$4.9 Aalo Holdings Inc 99902128 Quality Assurance Program Topical Report

$0.07

$0.01 General Atomics 99902098 Quality Assurance program Description Topical Report

$0.06

$0.05 Kairos Power LLC -

99902069 Core Design Methodology Topical Report

$0.44

$0.36 Kairos Power LLC -

99902069 Hermes Safety Analysis Methods Topical Report

$0.35

$0.30 Oklo -

99902095 Product Based Operator Licensing Topical Report

$0.13

$0.04 Project Long Mott -

99902117 Quality Assurance Program Description Topical Report

$0.06

$0.02 TerraPower -

99902100 Reactor Seismic Isolation System Qualification Topical Report

$0.19

$0.12 65 Projected resources will be updated, as NextEra submits the remaining requests in the series of requests for licensing actions outlined in the Duane Arnold Energy Center: Regulatory Path to Potential Reauthorization of Power Operations (ML25023A265). Projected resources included in the table are for requests for licensing actions received prior to the end of the reporting period.

Docket Project Name Projected Resources ($M)61 Fees Billed to Date

($M)62 TerraPower -

99902100 Instrumentation and Control Architecture and Design Basis Topical Report

$0.15

$0.15 TerraPower -

99902100 Design Basis Accident Methodology with Radiological Release Topical Report

$0.14

$0.08 TerraPower -

99902100 Partial Flow Blockage Methodology Topical Report

$0.17

$0.11 Terrestrial Energy USA, Inc. -

99902076 Principal Design Criteria Topical Report

$0.23

$0.27 Terrestrial Energy USA, Inc. -

99902076 Postulated Initiating Events Topical Report

$0.11

$0.03 Westinghouse eVinci Micro Reactor -

99902079 TRISO Fuel Design Methodology Topical Report

$0.25

$0.15 Westinghouse eVinci Micro Reactor -

99902079 Advanced Logic System v2 Platform Elimination of Technical Specification Surveillance Requirements Topical Report

$0.18

$0.15 Westinghouse eVinci Micro Reactor -

99902079 Nuclear Design Criteria Topical Report

$0.12

$0.14 X-Energy LLC -

99902071 Graphite Core Assembly Material Qualification and Design Methodologies Topical Report

$0.42

$0.29 X-Energy LLC -

99902071 Training Programs Methodology Topical Report

$0.08

$0.04 Docket Project Name Projected Resources ($M)61 Fees Billed to Date

($M)62 X-Energy LLC -

99902071 Reactor Core Analysis and Methods Topical Report

$0.12

$0.10 X-Energy LLC -

99902071 Transient and Safety Analysis Methodology Topical Report

$0.11

$0.12 X-Energy LLC -

99902071 Mechanistic Source Term Approach Topical Report

$0.12

$0.11 X-Energy LLC -

99902071 GOTHIC and Flownex Analysis Code Qualification Topical Report

$0.20

$0.20 X-Energy LLC -

99902071 Plume Exposure Pathway Emergency Planning Zone Sizing Methodology

$0.18

$0.08 XENITH Microreactor -

99902118 Principal Design Criteria Topical Report

$0.14

$0.16 XENITH Microreactor -

99902118 Analytical Methods Topical Report

$0.19

$0.14 Energy Northwest -

99902130 Quality Assurance Program Description Topical Report

$0.06

$0.04 NuScale US460 Standard Design Approval Application -

05200050 NuScale US460 Standard Design Approval Application -

Phase A -

Advanced Safety Evaluation Report Without Open Items

$15.7

$13.9 3-6 RAIs and Requests for Confirmatory Information (RCIs)

The table below provides information on RAIs, including RCIs, associated with licensing actions that are considered requested activities of the Commission for which the NRC staff issues a final SE, consistent with Section 102(c) of NEIMA. An RCI is a type of RAI where the response is expected to be limited to providing confirmation, on the docket, of staff-identified information related to the requested activity. While Section 102(c) of NEIMA applies to licensing actions accepted after July 13, 2019, the RAI data also includes licensing actions accepted prior to July 13, 2019, to provide a complete inventory.

Type of Facility or Activity Type Total Inventory of Open RAIs as of the End of Reporting Period Total Number of RAIs Issued in Reporting Period Total Number of RAIs Responded to in Reporting Period Total Number of RAIs Closed in Reporting Period66 All67 RCIs All RCIs All RCIs All RCIs Operating Reactors 182 30 219 48 135 46 300 18 Non-Power Production and Utilization Facilities68 122 0

0 0

0 0

0 0

Design Certifications and Standard Design Approvals for New Reactors69 0

0 0

0 0

0 0

0 Early Site Permits for New Reactors70 0

0 0

0 0

0 0

0 Combined Licenses for New Reactors 0

0 0

0 0

0 0

0 Construction Permits for New Reactors or Non-Power Production and Utilization Facilities 0

0 0

0 0

0 0

0 Fuel Facilities 218 1

59 1

89 1

18 0

66 RAIs are considered closed once the final SE, environmental assessment, or environmental impact statement is finalized, except for RAIs associated with new reactor application reviews. Due to the phased approach taken over several years for new reactor application reviews, RAIs are closed throughout the review process once the staff has determined that no additional information is needed to resolve the issue.

67 The All columns include data on all RAIs, including RCIs. The RCIs columns include data on the subset of RCIs.

68 For the purposes of RAI reporting, non-power production and utilization facilities include all operating research and test reactors and medical radioisotope facilities licensed under Title 10 of the Code of Federal Regulations Part 50, Domestic Licensing of Production and Utilization Facilities.

69 No design certification applications or standard design approval applications are currently under review by the NRC; therefore, there will be no RAI data to report until an application is submitted and accepted by the NRC for review.

70 No early site permit applications are currently under review by the NRC; therefore, there will be no RAI data to report until an application is submitted and accepted by the NRC for review.

Type of Facility or Activity Type Total Inventory of Open RAIs as of the End of Reporting Period Total Number of RAIs Issued in Reporting Period Total Number of RAIs Responded to in Reporting Period Total Number of RAIs Closed in Reporting Period66 All67 RCIs All RCIs All RCIs All RCIs Power Reactor Decommissioning 11 0

3 0

0 0

0 0

Research and Test Reactor Decommissioning 0

0 0

0 0

0 0

0 Spent Fuel 79 0

32 0

22 0

111 0

Materials 14 0

14 0

14 0

0 0

Uranium Recovery Licensed/

Operating 44 0

0 0

0 0

0 0

Pre-Application Activities for Advanced Reactors 0

0 0

0 0

0 0

0 3-7 Workforce Development and Management FY 2025 Staffing by Office71 FY 2025 Budget72 FTE Utilization 06/29/25-07/26/25 FTE Utilization 07/27/25-08/23/25 FTE Utilization 08/24/25-09/30/25 FTE Utilization as of 09/30/25 (Q1-Q4)

Delta (Q4 FTE Utilization

- FY 2025 Budget)

End of Year (EOY)

Projection w/

Personnel Actions Delta (EOY Utilization

- FY 2025 Budget)

Totals 2,920.6 210.2 208.5 279.8 2,813.0

-107.6 2,813.8

-106.8 COMM 42.0 1.9 1.8 2.1 26.2

-15.8 26.9

-15.1 OIG 63.0 3.9 3.8 4.9 51.7

-11.3 51.8

-11.2 Totals Other Offices 2,815.6 204.4 202.9 272.8 2,735.2

-80.4 2,735.2

-80.4 ACRS 29.1 1.7 1.7 2.3 24.6

-4.5 24.3

-4.8 ADM 117.0 8.1 8.0 10.9 107.7

-9.3 107.8

-9.2 ASLBP 22.6 1.5 1.6 2.2 20.6

-2.0 20.4

-2.2 NMSS 320.0 24.0 24.3 33.2 318.7

-1.3 317.2

-2.8 NRR 551.2 41.0 40.5 54.0 549.2

-2.0 549.3

-1.9 NSIR 162.0 11.5 11.3 15.2 151.6

-10.4 151.4

-10.6 OCA 10.0 0.9 0.9 1.2 11.7 1.7 11.8 1.8 OCAA 7.0 0.4 0.4 0.6 5.2

-1.8 5.0

-2.0 OCFO 93.0 6.2 6.2 8.4 85.2

-7.8 85.4

-7.6 OCHCO 139.0 11.0 11.0 14.8 140.7 1.7 140.8 1.8 OCIO 174.0 12.3 12.1 16.3 168.0

-6.0 168.0

-6.0 OE 30.9 2.1 2.0 2.5 29.9

-1.0 30.8

-0.1 OEDO 27.0 1.2 1.2 1.8 22.5

-4.5 21.7

-5.3 OGC 96.6 7.3 7.2 9.8 94.4

-2.2 94.0

-2.6 OI 36.0 2.9 2.8 3.8 36.9 0.9 37.1 1.1 OIP 37.0 2.3 2.5 3.5 34.9

-2.1 34.7

-2.3 OPA 13.0 1.0 1.0 1.3 14.0 1.0 14.0 1.0 RES 200.9 14.1 13.7 17.9 189.2

-11.7 190.9

-10.0 RI 175.4 13.1 13.0 17.5 170.8

-4.6 171.1

-4.3 RII 196.7 15.3 15.0 20.2 205.1 8.4 205.7 9.0 RIII 182.1 12.5 12.3 16.4 163.5

-18.6 163.7

-18.4 RIV 163.1 12.3 12.3 16.5 164.1 1.0 164.0 0.9 SBCR 15.0 0.7 0.8 1.2 11.6

-3.4 11.4

-3.6 SECY 17.0 1.1 1.1 1.6 15.1

-1.9 14.8

-2.2 71 Some numbers might not add exactly due to rounding.

72 The values in the FY 2025 Budget column reflect adjustments to ensure compliance with the Full-Year Continuing Appropriations and Extensions Act, 2025.

3-8 Inspection Activities The table below shows the average number of hours of direct inspection per plant in CY 2025. The ROP Action Matrix can be found on the NRCs public website (https://www.nrc.gov/reactors/operating/oversight/actionmatrix-summary.html#am_summary).

Average ROP Direct Inspection Hours Nationwide Per Plant (unit)

Column 1 of ROP Action Matrix (unit)

Column 2 of ROP Action Matrix (unit)

Column 3 of ROP Action Matrix (unit)

Column 4 of ROP Action Matrix 1,156 Hours 1,132 Hours 1,335 Hours73 No Plants in Column 3 No Plants in Column 4 The table below shows the staff hours spent on inspection-related efforts at operating power reactor sites by CY.

Items Description CY 2024 (Hours)

CY 2025 (Hours)

i.

Baseline Inspection 210,254 150,007 ii.

Plant-Specific Inspection 6,512 7,815 iii.

Generic Safety Issue Inspections 0

15 iv.

Performance Assessment 2,225 2,275

v.

Other Activities 100,374 73,742 vi.

Total Staff Effort 319,365 233,854 vii.

Total Staff Effort Per Operating Site 5,807 4,252 73 Calvert Cliffs Nuclear Power Plant, Unit 2 moved to Column 2 in Q4 FY 2024 (ML24309A247) and returned to Column 1 in Q3 FY 2025 (ML25149A055). Columbia Generating Station moved to Column 2 in Q1 FY 2022 (ML23111A237) and returned to Column 1 in Q2 FY 2025 (ML25073A062). James A. FitzPatrick Nuclear Power Plant entered Column 2 in Q4 FY 2024 (ML24299A214) and entered Column 1 in Q2 FY 2025 (ML25065A041). Vogtle Electric Generating Plant, Unit 3 entered Column 2 in Q4 FY 2024 (ML24313A063) and returned to Column 1 in Q2 FY 2025 (ML25099A013). Browns Ferry Nuclear Plant, Unit 2 entered Column 2 in Q4 FY 2024 (ML24310A203) and returned to Column 1 in Q2 FY 2025 (ML25079A182). Catawba Nuclear Station, Unit 2 entered Column 2 in Q2 FY 2024 (ML24234A291) and returned to Column 1 in Q2 FY2025 (ML25113A269). Susquehanna Steam Electric Station, Units 1 and 2 moved to Column 2 in Q1 FY 2025 (ML25016A306) and returned to Column 1 in Q3 FY 2025 (ML25163A059). South Texas Project Electric Generating Station, Unit 2 moved to Column 2 in Q1 FY 2025 (ML25007A210). Waterford Steam Electric Station, Unit 3 moved to Column 2 in Q3 FY 2025 (ML25149A059). Hope Creek Generating Station moved to Column 2 in Q4 of FY2025 (ML25237A290).