ML24215A382
| ML24215A382 | |
| Person / Time | |
|---|---|
| Issue date: | 09/12/2024 |
| From: | Christopher Hanson NRC/Chairman |
| To: | Carper T, Markey E, Rodgers C US HR (House of Representatives), US HR, Comm on Energy & Commerce, US SEN (Senate), US SEN, Comm on Environment & Public Works, US SEN, Subcomm on Clean Air, Climate Change & Nuclear Safety |
| Ramu Bishwakarma, OEDO | |
| References | |
| CORR-24-0079, SRM-LTR-19-0383 | |
| Download: ML24215A382 (1) | |
Text
STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION
For the Reporting Period of April 1, 2024, through June 30, 2024
Table of Contents
- High Level Summary................................................................................... 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act............................................................................................. 1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete. 1-3 Full-time Equivalent (FTE) at the End of Q3 FY 2024 vs. Budgeted FTE................................ 1-4 Budget Authority, FTE Utilization, and Fees............................................................................. Enclosure 2 - Status of Specific Items of Interest............................................................. 2-1 Transformation.......................................................................................................................... 2-2 Workforce Development and Management.............................................................................. 2-3 Accident Tolerant Fuel.............................................................................................................. 2-4 Digital Instrumentation and Control......................................................................................... 2-5 Vogtle Electric Generating Plant Units 3 and 4....................................................................... 2-6 Advanced Nuclear Reactor Technologies............................................................................... 2-7 Advanced Reactor Pre-application and Licensing Reviews................................................... 2-8 Reactor Oversight Process..................................................................................................... 2-9 Backfit...................................................................................................................................... 2-10 Risk-informed Activities........................................................................................................... Enclosure 3 - Summary of Activities................................................................................ 3-1 Reactor Oversight Process (ROP) Findings........................................................................... 3-2 Licensing Actions.................................................................................................................... 3-3 Licensing Amendment Request Reviews............................................................................... 3-4 Research Activities.................................................................................................................. 3-5 Fees Billed............................................................................................................................... 3-6 Requests for Additional Information (RAIs)............................................................................. 3-7 Workforce Development and Management............................................................................ 3-8 Inspection Activities................................................................................................................. 3-9 Backfit......................................................................................................................................
Enclosure 1 - High Level Summary
1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act 1
110%
100%
90%
80%
70%
60%
50%
40%
30%
20%
10%
Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule
1 No licensing actions categorized under the Nuclear Energy Innovation and Modernization Act were completed in Quarter (Q) 2 FY 2021 for the new reactor business line. There was one activity completed in Q3 FY 2022 for the new reactor business line, and it was completed significantly ahead of the established schedule. Because the one activity was completed in 28 percent of the established schedule, this resulted in the Q3 FY 2022 average timeliness percentage for the new reactor business line being 28 percent. There were three activities completed in Q3 FY 2023 for the new reactor business line, and they were completed significantly ahead of the established schedule. Because the three activities were completed in 50 percent of the established schedule, this resulted in the Q3 FY 2023 average timeliness percentage for the new reactor business line being 50 percent. The NRC staff identified errors in some data values previously reported for Operating Reactors Established Schedule from Q1 FY 2023 through Q1 FY 2024. Those errors have now been corrected.
1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete2
1-3 Full-time Equivalent (FTE) at the End of Q3 FY 2024 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.
1-4 Budget Authority, FTE Utilization, and Fees
NRC FY 2024 Budget Authority June 30, 2024 (Dollars in Thousands)
Fund Sources FY 2024 Budget3 Percent Obligated Percent Expended Advanced Reactors $34,200 42% 31%
Commission Funds $12,083 48% 47%
Fee-Based Funds $919,914 69% 55%
General Funds4 $1,011 44% 44%
International Activities $18,716 60% 52%
University Nuclear $34,714 55% 0%
Leadership Program Official Representation $44 41% 41%
Total5 $1,020,681 67% 52%
NRC Control Points FY 2024 Budget Percent Obligated Percent Expended Nuclear Reactor Safety $526,819 66% 58%
Nuclear Materials and $124,735 62% 54%
Waste Safety Decommissioning and $26,767 58% 52%
Low-Level Waste Corporate Support $307,646 72% 47%
University Nuclear Leadership Program 6 $34,714 55% 0%
Total $1,020,681 67% 52%
FTE Utilization, Hiring, and Attrition
Total Year-to-Date Projected End of Year Q3 YTD YTD (YTD) FTE FTE Total Utilization Q3 Hiring Attrition Hiring Attrition Utilization 2143.9 2795.5 69 54 176 169
3 FY 2024 Budget reflects the enactment of the Consolidated Appropriations Act, 2024 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.
FY 2024 Fees Estimated, Fees Billed, and Fees Collected Through Q3
Total for Title 10 of the Code of Federal Regulations 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 2022 FY 2023 FY 2024 Q1-Q3
$190.7 $186.3 $146.5
Enclosure 2 - Status of Specific Items of Interest provides the status of specific items of interest including a summary of the item, the activities planned and accomplished under each item within the reporting period, and projected activities under each item for the next two reporting periods.
2-1 Transformation
As a modern, risk-informed regulator, the U.S. Nuclear Regulatory Commission (NRC) has demonstrated an ability to adopt new technologies and ways of implementing its safety and security mission. The NRC continues to make progress in four focus areas: (1) recruiting, developing, and retaining a strong workforce (Our People); (2) improving decision-making through the acceptance of an appropriate level of risk without compromising the NRCs mission (Be riskSMART); (3) establishing a culture that embraces innovation (Innovation); and (4) adopting new and existing information technology resources (Using Technology). These focus areas are now interwoven into the agencys strategic goals and objectives.
The agency has completed all but one of the initial formal agencywide initiatives associated with the four focus areas. The remaining initiative centers on fostering a culture that embodies the NRC Values and Leadership Model, which supports the agencys strategic goal of fostering a healthy organization. Further, based on analysis of data from the 2023 Jam, an agencywide collaborative online discussion, the NRC is focusing on areas to support our organizational health strategic goal.
Projected Activities for the Next Reporting Period (Q4 FY 2024)
Projected Transformation Activities Projected Completion Date The agencys Culture Leader Retreat. 07/25/2024 Provide agencywide communications on the Jam actions related to knowledge management and how those actions are helping to enhance 07/31/24 organizational health and performance.
Conduct an internal pulse survey to gain data on whether recent actions 09/30/247 are helping to enhance organizational health and performance.
Provide final agencywide communications on the Jam actions related to workload prioritization and management and how those actions are 09/30/24 helping to enhance organizational health and perform ance.
7 This activity was originally expected to be completed by June 28, 2024. The NRC pushed back the completion date for this activity so that staff would not experience survey fatigue by taking the pulse survey and FEVS 2024 during the same timeframe. The new completion date for the pulse survey is September 30, 2024.
2-2 Workforce Development and Management
The NRC is in the process of re-engineering its Strategic Workforce Planning (SWP) process.
The goal of this initiative is to improve workforce development to meet its near-term and long-term work demands.8 The first step in this process is an Agency Environmental Scan to assess and project the amount and type of work anticipated in the next 5 years and identify the workforce needs to perform that work. By analyzing the current workforce and comparing it to future needs, skill gaps can be identified. In the final step of the process, both short-term and long-term strategies are developed to enable the agency to recruit, retain, and develop a skilled and diverse workforce with the competencies and agility to address both current and emerging needs and workload fluctuations.
To cover anticipated attrition and address skill gaps, the agency continued implementing strategies to recruit and onboard a significant number of new employees during this reporting period; the agency plans to continue this recruitment effort going forward. Senior leaders are collaborating to develop agencywide priorities to concentrate hiring on those positions with the greatest mission impact. This recruitment effort is positioning the agency to continue to fulfill its important safety and security mission well into the future.
Activities Planned and Completed for this Reporting Period (Q3 FY 2024)
Workforce Development and Management Projected Completion Date Activities Completion Date Update SWP Guidance and share Final Evaluation 06/30/24 04/14/24 Report with all NRC offices.
NRC held its second Annual Career Expo also 05/09/24 05/09/24 known as the NRC Hiring Expo Finalize security clearance reviews and onboard 06/30/24 06/17/24 Summer 2024 Student Interns.
Finalize security clearance reviews and prepare to 06/30/24 06/30/24 onboard NRAN 2024 cohort members.
Projected Activities for the Next Two Reporting Periods (Q4 FY 2024 and Q1 FY 2025)
Projected Workforce Development and Management Projected Activities Completion Date There are no specific activities currently planned for the reporting N/A periods.
The NRC continues to take steps to make agency processes more efficient and effective for the review of Accident Tolerant Fuel (ATF), higher burnup, and increased enrichment submittals.
The NRC staff is executing the ATF project plan (Agencywide Documents Access and Management System Accession No. ML21243A298), which was revised to include an increased focus on higher burnup and increased enrichment fuels.
8 In FY 2023, the NRC paused its SWP process, as the agency initiated an in-depth evaluation to review and consider potential improvements to the process. The NRC is currently considering the recommendations from this evaluation and plans to take action to implement necessary changes and re-initiate the SWP process in FY 2024.
During this reporting period, the NRC received one additional ATF fuel vendor topical report which is currently undergoing acceptance review. On April 30, 2024, Electric Power Research Institute, Inc. submitted a topical report regarding its alternate licensing strategy for loss of coolant accident induced fuel fragmentation, relocation, and dispersal ( ML24121A203). The NRC staff is currently on track to complete review of eight ATF fuel vendor topical reports by the end of FY 2026, in time to support expected licensee submittals to use ATF. No additional ATF-related operating reactor license amendment requests (LARs) were submitted during this reporting period.
Activities Planned and Completed for this Reporting Period (Q3 FY 2024)
ATF Activities Projected Completion Date Completion Date Held a public meeting to discuss the staffs efforts associated with a revision to Regulatory Guide (RG) 1.183, Revision 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Plants. This revision would serve as 05/01/24 05/01/24 one of the implementing guidance documents for the increased enrichment rulemaking, if promulgated, and would incorporate updates to enhance the guidance that applies to radiological consequence analyses.
Issued a report documenting a phenomena identification and ranking table exercise related to higher burnup fuel fragmentation, relocation, and dispersal and its potential consequences 05/31/24 05/31/24 (ML24155A058). The report will be used by the NRC to support changes to the regulatory infrastructure for higher burnup fuel.
Held a public meeting on Draft Guide (DG) 1425, to discuss proposed changes to the main control room design criteria in Regulatory Guide 1.183, Revision 2, Alternative Radiological Source Terms for 06/12/24 06/12/24 Evaluating Design Basis Accidents at Nuclear Power Reactors. Staff continues to offer opportunities to obtain early stakeholder feedback on the draft guidance document.
Projected Activities for the Next Reporting Period (Q4 FY 2024)
Projected ATF Activities Projected Completion Date Issue NUREG-2266, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels, which will generically evaluate the environmental impacts of a light-water reactor using ATF for up to 10 weight-percent uranium-235 for uranium fuel 09/30/24 cycle and decommissioning, for up to 8 weight-percent uranium-235 for transportation of ATF and wastes, and for burnups of up to 80 gigawatt-days per metric ton uranium for all three topic areas.
Hold the fifth Higher Burnup Workshop to discuss the state of development of higher burnup fuel and increased enrichment technical 09/30/24 and regulatory issues. The workshop will also provide a public forum for discussions between the NRC, industry, and other stakeholders.
2-4 Digital Instrumentation and Control
The NRC staff is using its improved infrastructure to review licensees digital instrumentation and control (I&C) modernization LARs. The staff also continues digital I&C infrastructure improvements to address protection against common cause failure (CCF) and consider endorsement of updated consensus standards. These activities support the NRCs vision to establish a more modern, risk-informed regulatory structure with reduced uncertainty that will enable the expanded safe use of digital technologies.
On September 26, 2022, Constellation Energy Generation, LLC (CEG) submitted LARs for Limerick Generating Station, Units 1 and 2 (Limerick) to revise the licensing and design basis to incorporate proposed digital modifications. The LARs also request other changes to plant functions and the reactivity control system. On May 23, 2023, Constellation informed the NRC staff that it is delaying submittal of information needed to complete the Limerick LARs by seven months and that it changed the planned installation of the digital modification from Unit 1 in Calendar Year (CY) 2024 to Unit 2 in CY 2025 (ML23143A342). CEG states that it is engaging in design refinement iterations with the digital system original equipment manufacturer and understands that this will affect the NRC staffs review schedule. On April 17, 2024, the NRC staff notified CEG (ML24093A091) of the changes to the estimated review completion date. In this letter, the NRC staff also stated that this estimate is subject to change if there are additional delays in submitting information.
On April 23, 2024, CEG submitted a letter ( ML24114A322) to the NRC stating that it is further delaying the digital modification initial installation at Limerick. The licensee stated that the delay is due to identification of additional new design considerations/issues that had to be addressed/resolved, and current final design and manufacturing schedules that do not meet the CEG internal 2025 Refueling Outage. Because of the delay, CEG changed its planned installation for Unit 1 to CY 2026, and the Unit 2 installation to CY 2027.
On June 19, 2024, Florida Power & Light submitted a letter requesting withdrawal of the Turkey Point digital instrumentation and controls license amendment request (ML24171A005). This review has been on hold since June 2023 (i.e., 12 months) at the licensees request ( ML23179A141 and ML23188A124). The amendment request was
submitted by the licensee on July 30, 2022 ( ML22213A045). The licensee stated it continues to evaluate the replacement project but has decided not to proceed with it at this time. Consistent with its internal processes, the NRC staff informed the licensee on June 28, 2024, that its request is being treated as withdrawn ( ML24173A190).
Regarding improvement to related guidance, on August 10, 2022, the NRC staff recommended to the Commission, SECY-22-0076 ( ML22164B003), expansion of the current policy on digital I&C CCF that was approved in the Staff Requirements Memorandum (SRM) to SECY-93-087 (ML003708056). On January 23, 2023, the NRC staff provided a supplement to SECY-22-0076 (ML22357A037) to the Commission as a result of stakeholder views received; the supplement included additional discussion on independent and diverse displays and manual controls in the main control room in the event of a CCF. The Commission approved the NRC staffs recommendation subject to revisions in SRM-SECY-22-0076 on May 25, 2023 ( ML23145A176).
Consequently, the NRC staff issued final implementing guidance on May 1, 2024, with Revision 9 to Branch Technical Position (BTP) 7-19, which provides guidance for the review of risk-informed approaches to digital I&C CCF. The NRC staff also plans to revise guidance for non-light-water reactors (non-LWRs), including the Design Review Guide ( ML21011A140), after obtaining additional stakeholder perspectives on the implementation of the revised policy through pre-application engagement and ongoing advanced reactor I&C workshops.
Activities Planned and Completed for the Reporting Period (Q3 FY 2024)
Digital I&C Activities Projected Completion Date Completion Date
Issue Revision 9 to BTP 7-19 05/25/24 05/01/24
Projected Activities for the Next Two Reporting Periods (Q4 FY 2024 and Q1 FY 2025)
Projected Digital I&C Activities Projected Completion Date Brief the Advisory Committee on Reactor Safeguards (ACRS) Digital 10/25/24 I&C Subcommittee on the review of the Limerick Digital I&C LAR s.
Brief the ACRS full committee on the review of the Limerick Digital I&C 11/15/24 LARs.
Issue Limerick Digital I&C LAR 12/09/24
2-5 Vogtle Electric Generating Plant Units 3 and 4
The NRC issued two combined licenses (COLs) to Southern Nuclear Operating Company (SNC) and its financial partners on February 10, 2012, for two AP1000 units (Units 3 and 4) to be built and operated at the Vogtle site near Augusta, GA. Construction of Vogtle Units 3 and 4 is complete, and inspection activities for both units are being conducted under the ROP. Vogtle Units 3 and 4 are currently in the Licensee Response Column of the ROP action matrix.
On April 29, 2024, Vogtle Unit 4 entered commercial operation. Since July 31, 2023, Vogtle Unit 3 has been operating commercially.
LARs Planned and Completed for this Reporting Period (Q3 FY 2024)
Number of LAR Reviews Forecast to be Number of LAR Reviews that Were Completed in the Reporting Period Completed in the Reporting Period 1 1
2-6 Advanced Nuclear Reactor Technologies
The NRC continues to make progress in enhancing its efforts to review non-LWR designs, consistent with the NRC staffs vision and strategy ( ML16356A670) and implementation action plans to achieve non-LWR safety review readiness. 9 During this reporting period, the NRC staff continued its extensive stakeholder engagement, including holding several public meetings regarding various advanced reactor topics, such as the advanced reactor construction oversight process (ML24129A079), micro-reactor licensing and deployment considerations (ML24135A033), and Technology-Inclusive Maintenance of Safety Case ( ML24156A029).
On March 4, 2024, in SRM-SECY-23-0021 (ML24064A047) the Commission directed the staff to publish a proposed rule and draft guidance to establish a voluntary risk-informed, performance-based, and technology-inclusive regulatory framework for commercial nuclear plants, commonly referred to as Part 53. The Commission approved, in part, the draft proposed rule proposed by the staff in SECY-23-0021, Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN 3150-AK31)
(ML21162A093), and directed the staff to make changes throughout the rule. The staff is revising the draft proposed rule to reflect the Commissions direction and, consistent with the Commissions direction, will provide the Federal Register (FR) notice for the proposed rule to the Commission before it is published for public comment. After the NRC staff receives, considers, and addresses the public comments, 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 the Nuclear Energy Innovation and Modernization Act (NEIMA) 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/rulemaking-and-guidance/part-53.html ).
On January 24, 2024, the staff submitted to the Commission for its consideration SECY 0008, Micro-Reactor Licensing and Deployment Considerations: Fuel Loading and Operational Testing at a Factory (ML23207A250) with options for addressing certain aspects of fuel loading and operational testing of commercial factory-fabricated micro-reactors. This paper also seeks Commission direction on whether a factory-fabricated micro-reactor that includes features to preclude criticality would require a facility operating license or a COL when loaded with fuel.
The NRC staff is currently focusing on developing strategies to streamline the licensing timelines for nth-of-a-kind micro-reactor deployment, some of which were identified as future actions in the enclosure to SECY-24-0008. These efforts may identify additional policy and rulemaking opportunities and potential legislative proposals for Commission consideration.
9 The NRCs public website lists the implementation action plans and is updated periodically to show the status of these activities (https://www.nrc.gov/reactors/new-reactors/advanced/details.html#visStrat).
The NRC holds periodic public stakeholder meetings to discuss advanced reactor topics of interest. A list of the meetings that the NRC conducted to date can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/get-involved/meetings.html ).
On April 13, 2023, the Commission directed the staff to license and regulate near-term fusion energy systems under a byproduct material framework ( ML23103A449). The Commission also directed staff to develop a limited scope rulemaking and a new volume of NUREG-1556, Consolidated Guidance About Materials Licenses, dedicated to fusion energy systems to provide consistent guidance across the National Materials Program. The NRC staff is implementing this direction and has been holding public meetings on the rule language and guidance revisions since July 2023. The NRC staff has released preliminary proposed rule language and preliminary draft guidance as part of the meeting handouts to support stakeholder engagement in 2023 and 2024. During this reporting period, the NRC staff provided a copy of the draft Federal Register notice that contains the draft regulatory language and compatibility designations and the draft guidance to the Agreement States for review and held a government-to-government meeting with the States on June 4, 2024. The draft proposed rule and draft guidance are scheduled to be provided to the Commission for its consideration in October 2024.
Activities Planned and Completed for the Reporting Period (Q3 FY 2024)
Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date Conducted a public workshop on codes and 04/04/24 04/04/24 standards for new and advanced reactors.
Presented the Status Update on Computer Code and Model for Non-Light-Water 04/30/24 05/01/2410 Reactors (ML24069A003) to the ACRS.
Projected Activities for the Next Two Reporting Periods (Q4 FY 2024 and Q1 FY 2025)
Projected Advanced Nuclear Reactor Projected Completion Date Technologies Activities Publish the Proposed Rule: Alternative Physical 08/16/24 Security Requirements for Advanced Reactors Conduct a public workshop on the SCALE/MELCOR non-LWR fuel cycle demonstration project for a 08/30/24 molten salt reactor.
Submit to the Commission a draft proposed rule on 10/15/24 Licensing and Regulating Fusion Energy Systems Publish the Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for 10/18/24 Advanced Reactors
10 An initial presentation was given on April 3, 2024, to the ACRS subcommittee. The ACRS full committee deliberated on the staff presentation on May 1, 2024.
Projected Advanced Nuclear Reactor Projected Completion Date Technologies Activities Publish the Proposed Rule: Generic Environmental Impact Statement for Licensing of New Nuclear 11/15/24 Reactors Issue Draft Regulatory Guide on Technology-Inclusive Risk-Informed Change Evaluation Process 12/31/24 for Public Comment Deliver SECY on Micro-Reactor Licensing and Deployment Considerations for Nth-of-a-Kind 12/31/24 Licensing to the Commission Publish DG-1410 (proposed new RG 1.251),
Technology Inclusive, Risk-Informed, and Performance-Based Methodology for Seismic 12/31/24 Design of Commercial Nuclear Plants, for public comment.
Publish DG-1307 (proposed new RG 1.252),
Seismically Isolated Nuclear Power Plants, for 12/31/24 public comment.
2-7 Advanced Reactor Pre-application and Licensing Reviews
The NRC staff continues to prepare, through early interactions with reactor designers, to review specific advanced reactor designs. These pre-application interactions provide predictability in the licensing process through early identification and, where appropriate, resolution of technical and policy issues that could affect licensing. Information on the reactor designers that formally notified the NRC of their intent to engage in regulatory interactions can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/ongoing-licensing-activities/pre-application-activities.html).
Kairos Construction Permit Application Reviews for Hermes 2
In September 2021, Kairos Power LLC (Kairos) submitted a construction permit application for a non-power fluoride salt-cooled, high-temperature reactor (Hermes 1). The NRC staff issued the construction permit for the Hermes 1 test reactor facility on December 14, 2023 (ML23338A258). Application documents and information regarding the review are available on the NRCs public website ( https://www.nrc.gov/reactors/non-power/hermes-kairos.html ).
On July 14, 2023, Kairos submitted a second construction permit application for a two-unit test reactor facility (Hermes 2) that would be located on the same site as the Hermes 1 test reactor (ML23195A121). The Hermes 2 test reactors would use the same fluoride salt-cooled, high-temperature reactor technology as the Hermes 1 reactor but would incorporate some additional features, such as intermediate salt loops and a shared turbine generator system. The NRC staff accepted the Hermes 2 construction permit application for review on September 11, 2023 (ML23233A167). On October 11, 2023, the NRC staff issued a letter to Kairos outlining the estimated schedule and resources needed to complete the safety and environmental reviews for the Hermes 2 construction permit application ( ML23269A176). The NRC published the draft environmental assessment (EA) and draft Finding of No Significant Impact (FONSI) on April 19,
2024, for the Hermes 2 construction permit application. The notice of availability of and a 30 day request for comment on the draft EA and draft FONSI was published in the Federal Register on April 26, 2024 (89 FR 32462). The NRC staff continues its review of the Hermes 2 construction permit application and remains on schedule to publish the final EA/FONSI and issue the final safety evaluation. Application documents and information regarding the review are available on the NRCs public website ( https://www.nrc.gov/reactors/non-power/new-facility-licensing/hermes2-kairos.html ). It is anticipated that this application will be the first one subject to the simplified procedures for mandatory hearings on licensing decisions for commercial nuclear power plants approved by the Commission (staff requirements memo on SECY 0032).
Abilene Christian University Molten Salt Research Reactor Construction Permit Application Review
On August 12, 2022, Abilene Christian University (ACU) submitted an application for a construction permit for a molten salt research reactor (MSRR) (less than 1 megawatt thermal power) to be located on the ACU campus in Abilene, TX ( ML22227A201). On October 20, 2022, ACU supplemented its application to provide additional instrumentation and control design information (ML22293B817).
On March 14, 2024, the NRC staff issued the final EA and FONSI ( 89 FR 18678). On March 28, 2024 (ML24094A332), and April 30, 2024 (ML24121A272), ACU provided its responses to the two requests for additional information. On June 12, 2024, the NRC staff sent ACU a letter (ML24162A093) in which it provided its revised review schedule and indicated that the NRC staff expects that the original estimate of NRC staff hours to complete the review remains valid.
The NRC staff is currently conducting a detailed technical review of the safety of the MSRR design, which will result in a SE. Application documents and information on the review are available on the NRCs public website ( https://www.nrc.gov/reactors/non-power/new-facility-licensing/msrr-acu.html ).
TerraPower Natrium Demonstration Reactor Construction Permit Application Review
On March 28, 2024, TerraPower, LLC (TerraPower), on behalf of US SFR Owner, LLC, a wholly owned subsidiary of TerraPower, submitted a construction permit application for Kemmerer Power Station Unit 1 (Kemmerer Unit 1) (ML24088A059). Kemmerer Unit 1 would be sited in Lincoln County, WY, and would be used to demonstrate the Natrium sodium fast reactor technology under DOEs Advanced Reactor Demonstration Program. The NRC staff accepted the TerraPower application on May 21, 2024 ( ML24135A109). On June 12, 2024, the NRC staff issued a letter to TerraPower outlining the estimated schedule and resources needed to complete the safety and environmental reviews for the construction permit application (ML24162A063). On June 12, 2024, the NRC also published in the Federal Register a Notice of Intent to conduct scoping and prepare an Environmental Impact Statement ( 89 FR 49917).
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)
Activities Planned and Completed for the Reporting Period (Q3 FY 2024)
Advanced Reactor Licensing Review Activities Projected Completion Date Completion Date Published draft EA and FONSI for Kairos Hermes 04/19/24 04/19/24 2.
Made determination of whether to prepare an Environmental Impact Statement or a FONSI for 05/31/24 05/31/24 Kairos Hermes 2.
Completed development of Kairos Hermes 2 advanced SE, with all sections completed and 06/24/24 06/05/24 assembled.
Completed review and NRC staff approval of 08/05/24 06/27/24 Kairos Hermes 2 SE. 11
Advanced Reactor Pre-application Review Projected Completion Date Activities Completion Date Issued final SE to Kairos for its topical report on 04/05/24 04/04/24 instrument setpoint methodology.
Projected Activities for the Next Two Reporting Periods (Q4 FY 2024 and Q1 FY 2025)
Projected Advanced Reactor Licensing Projected Completion Date Review Activities Issue Final EA and FONSI for Kairos Hermes 2. 08/30/24 Complete regulatory audits and evaluate any additional docketed information necessary for 09/20/2412 the preparation of the ACU SE.
Completion of ACRS meetings and ACRS 09/30/24 review of Kairos Hermes 2 SE.
Issue the Final Safety Evaluation and 09/30/24 Construction Permit for the ACU MSRR.
Projected Advanced Reactor Pre-Application Projected Completion Date Review Activities Issue final SE to University of Illinois at Urbana-Champaign for its topical report on regulatory 07/26/24 applicability analysis.
Issue final SE to Westinghouse for its topical 07/26/24 report on the Advanced Logic System v2.
Issue final SE to Terrestrial Energy for its TBD13 topical report on principal design criteria.
Issue final SE to X-energy for its topical report on atmospheric dispersion and dose 09/30/24 consequence methodology.
11 The final SE will not be issued until after the ACRS completes its review of the SE.
12 On September 14, 2023, the NRC staff notified ACU that it was unable to complete the regulatory audits by August 30, 2023, because ACU needed additional time to provide necessary information to the staff and for the staff and ACU to bring the remaining technical topics to resolution. On December 21, 2023, the NRC staff requested additional information needed to complete its review of the application. ACU provided its responses to the request for additional information on March 28, 2024 (ML24094A332), and April 30, 2024 (ML24121A272). On June 12, 2024, the NRC staff sent a letter to ACU to provide its revised review schedule (ML24162A093).
13 The projected completion date for this activity is now to be determined. The NRC staff identified additional information needed to support its review during an audit that will be completed on July 2, 2024. The NRC staff will issue a revised schedule after receipt of the additional information from Terrestrial Energy.
Projected Advanced Reactor Pre-Application Projected Completion Date Review Activities Issue final SE to TerraPower for its topical report on fuel and control assembly 09/30/24 qualification.
Issue final SE to TerraPower for its topical 09/30/24 report on principal design criteria.
Issue final SE to TerraPower for its topical 09/30/24 report on the assessment of volcanic hazards.
Issue final SE to Westinghouse for its topical 10/31/2414 report on principal design criteria.
Issue final SE to TerraPower for its topical report on Plume Exposure Pathway Emergency 11/04/24 Planning Zone Methodology Issue final SE to X-energy for its topical report 11/29/24 on principal design criteria.
2-8 Reactor Oversight Process
The ROP is the NRCs program to inspect, measure, and assess the safety and security performance of operating commercial nuclear power plants, and to respond to any decline in their performance. The ROP is also a risk-informed, performance-based oversight program that contains provisions for continuous self-assessment and improvement.
Consistent with the Commissions direction in SRM-SECY-23-0010 ( ML23244A282), which was issued in the fourth quarter of FY 2023, the staff is revising procedures and processes to implement an emergency response facility and equipment readiness performance indicator to measure licensee emergency preparedness. Final implementation of the indicator is planned for Q2 FY 2025.
The NRC staff evaluated Inspection Manual Chapter 0609, Appendix E, Part I, Baseline Security Significance Determination Process for Power Reactors ( ML22178A222) to determine whether the Baseline Security Significance Determination Process (BSSDP) can be improved or further risk-informed. Upon receiving input from both internal and external stakeholders, the staff decided to revise the BSSDP; this will occur over the course of several months. The evaluation/revision of the BSSDP is part of the 2024 ROP Self-Assessment Process, which directs the staff to perform focused assessments of specific ROP program areas.
14 The projected completion date for this activity was extended from August 30, 2024, to October 31, 2024, because on May 15, 2024, Westinghouse submitted Revision 1 to its principal design criteria topical report. The revised date reflects the additional time needed for the staff to complete its review of the revised submittal, including a presentation to the ACRS.
The NRC staff is revising Inspection Manual Chapter 0609, Appendix B, Emergency Preparedness Significance Determination Process ( ML15128A462), dated September 22, 2015, in accordance with the Commissions direction. In SRM-SECY-22-0089, Recommendation for Enhancing the Emergency Preparedness Significance Determination Process for the Reactor Oversight Process ( ML23040A378), the Commission approved the staffs recommendation to revise the risk-informed methodology such that only the planning standards that are either risk-significant or considered significant for effective implementation of the site-specific emergency plan, will have greater-than-green significance for EP inspection findings.
In 2019, the NRC staff submitted COMSECY-19-0006, Revised Security Inspection Program Framework (Option 3) (ML19058A094) to the Commission in response to SRM-SECY-17-0100, Security Baseline Inspection Program Assessment Results and Recommendations for Program Efficiencies (ML18283A072). In COMSECY-19-0006, the staff proposed a revised framework to modify the Force-on-Force (FOF) inspection program to include one NRC-conducted FOF exercise and an enhanced NRC inspection of a licensee-conducted annual FOF exercise. In May 2024, the Commission approved the staffs proposed approach in SRM-COMSECY 0006, Revised Security Inspection Program Framework (Option 3) in Response to SRM 0100 (ML24138A045). The staff is developing a plan to implement the Commissions direction and will engage with external stakeholders periodically for feedback.
The NRC staff continues to assess the ROP as part of its normal work practices through the NRCs Be RiskSMART framework, stakeholder correspondence, feedback from ROP public meetings, and the ROP self-assessment program. If potential changes are identified, the staff will seek Commission approval of changes to the ROP, or provide the Commission with notification of changes, as appropriate, in accordance with Management Directive/Directive Handbook 8.13, Reactor Oversight Process ( ML17347B670).
Activities Planned and Completed for this Reporting Period (Q3 FY 2024)
ROP Activities Projected Completion Date Completion Date Complete CY 2023 ROP Self-Assessment and 04/15/24 04/09/24 submit an information paper to the Commission.
Projected Activities for the Next Reporting Period (Q4 FY 2024)
Projected ROP Activities Projected Completion Date Submit a paper to the Commission on planned revisions of Inspection Manual Chapters and Inspection Procedures (IPs) regarding safety 07/31/24 culture.
2-9 Backfit
The NRCs backfitting rules are codified in 10 CFR Sections 50.109, Backfitting, 70.76, Backfitting, 72.62, Backfitting, and 76.76, Backfitting. There are similar requirements, referred to as issue finality, that apply when there are new or amended requirements for licenses, permits, and design approvals and certifications issued under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.
In September 2019, the Commission changed its backfitting and issue finality policy as well as its policy on forward fits, in NRC Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests ( ML18093B087). The NRC completed draft NUREG-1409, Backfitting Guidelines, Revision 1, in March 2020 and issued a notice of availability in the Federal Register for public comment ( ML18109A498). The NRC received approximately 250 individual comments from members of the public, licensees, and industry representatives. The NRC staff evaluated the comments, updated the draft NUREG, and provided the Commission with the staffs proposed NUREG-1409, Revision 1 (Final Report)
(ML21006A431), in March 2021. In its direction to the staff on the final rule for non-power production or utilization facility (NPUFs) license renewal (SECY-19-0062), the Commission returned this document to the staff for updates to clarify the applicability of Part 50.109 to commercial NPUFs through an interpretive rule process. The staff should revise the backfilling analysis portion of the draft Federal Register notice for the rulemaking to reflect that as an ongoing effort in a policy neutral way.
Activities Planned and Completed for this Reporting Period (Q3 FY 2024)
Backfit Activities Projected Completion Date Completion Date There are no activities planned for the reporting N/A N/A period.
Projected Activities for the Next Reporting Period (Q4 FY 2024)
Projected Backfit Activities Projected Completion Date Publication of the Regulatory Improvements for Production and 08/30/24 Utilization Facilities Transitioning to Decommissioning final rule.
2-10 Risk-informed Activities
The NRC staff continues to make progress to advance the use of risk insights more broadly to inform decision-making. There are numerous activities ranging in scope from agencywide initiatives, such as the Be riskSMART initiative, which is part of the transformation efforts discussed in Section 2-1, to the advanced reactor risk-informed activities listed in Section 2-6, to individual undertakings in program and corporate offices. 15
The NRC staff also continues to increase the use of risk insights, where appropriate, in the review of new reactor applications. For example, the staff is leveraging risk insights in its detailed technical review of the NuScale standard design approval application for the NuScale VOYGR 460 standard design. This use of risk insights in the NuScale VOYGR 460 review is aligned with the implementation of the lessons learned from the NuScale design certification application review ( ML22294A144). In March 2024, the NRC staff developed a Standardized Plant Analysis Risk model for the NuScale SDAA review with the goal of having more accessible and granular risk insights to support the review.
15 The NRC maintains a listing of risk-informed activities that is updated annually at https://www.nrc.gov/about-nrc/regulatory/risk-informed/rpp.html.
Activities Planned and Completed for this Reporting Period (Q3 FY 2024)
Projected Completion Risk-Informed Activities Completion Date Date The staff held a public meeting to gather feedback related to the staff's development of a balanced and performance-based approach for the oversight of Probabilistic Risk Assessment (PRA) configuration control (CC) ( ML24137A229). The meeting offered an opportunity to continue the dialogue and gather additional feedback from industry and the public on the 04/18/24 04/18/24 staff's proposed significance determination process for the OpE smart sample for PRA CC, as well as minor and more than minor criteria examples. Staff considered the industrys feedback to support the development of recommendations for future oversight in this area.
The staff issued the PRA Configuration Control OpESS 2023- 06/30/24 06/14/24 02 Cross Regional Panel Charter ( ML24081A131) on June 4, 2024. The Smart Sample for Probabilistic Risk Assessment Configuration Control (ML23255A006) was first implemented during the Comprehensive Engineering Team Inspection at Turkey Point during the week of June 10, 2024.
Projected Activities for the Next Reporting Period (Q4 FY 2024)
Projected Risk-Informed Activities Projected Completion Date Continue to offer internal workshops to the NRC staff to highlight recent accomplishments in leveraging RIDM and to discuss appropriate 09/30/24 application of the key principles of RIDM, as well as to highlight best practices and tools that have been developed to support RIDM.
Enclosure 3 - Summary of Activities
3-1 Reactor Oversight Process (ROP) Findings
The table below provides the calendar year (CY) ROP findings for the year-to-date and 3-year rolling metrics.16
Location Number of CY 2021 CY 2022 CY 2023 CY 2024 Findings Nationally Total 278 399 466 214
Green 61 83 88 43 White 1 2 1 0 Yellow 0 0 0 0 Red 0 0 0 0 Greater-Than-Green Region I (GTG) Security 0 0 0 1
Total 62 85 89 44 No. of Units Operating During 2117 2018 20 20 CY Green 69 90 135 63 White 0 1 3 0 Yellow 0 0 0 0 Red 0 0 0 0 Region II GTG Security 0 0 5 0 Total 69 91 143 63 No. of Units Operating During 33 33 3419 3520 CY Green 65 89 103 43 White 0 2 0 0 Region III Yellow 0 0 0 0 Red 0 0 0 0 GTG Security 1 1 0 0 Total 66 92 103 43
16 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.
17 The reduction of one unit for CY 2021 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 2 on April 30, 2020.
18 The reduction of one unit for CY 2022 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 3 on April 30, 2021.
19 The increase of one unit for CY 2023 reflects Vogtle Unit 3 entering the ROP on August 3, 2022.
20 The increase of one unit for CY 2024 reflects Vogtle Unit 4 entering the ROP on July 28, 2023.
Location Number of CY 2021 CY 2022 CY 2023 CY 2024 Findings No. of Units Operating During 2221 22 2122 21 CY Green 81 130 126 67 White 0 1 5 0 Yellow 0 0 0 0 Red 0 0 0 0 Region IV GTG Security 0 0 0 0 Total 81 131 131 63 No. of Units Operating During 18 18 18 18 CY
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. 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
Percentage Percentage Licensing Licensing of Licensing of Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period23 Milestone Schedule24 Schedule Q4 FY 2023 114 48 64 99% 100%
Q1 FY 2024 206 14525 43 100% 91%
21 The reduction of one unit for CY 2021 reflects the permanent shutdown of Duane Arnold on August 10, 2020.
22 The reduction of one unit for CY 2023 reflects the permanent shutdown of Palisades on May 20, 2022.
23 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.
24 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
25 The significant inventory increase is due to 105 licensing actions submitted in Q1 FY 2024 that request additional time to address emergent issues identified with a security rule that licensees are required to implement by January 8, 2024. The reviews are being expedited, and the NRC issued decisions on 94 of the licensing actions in Q2 FY 2024. The NRC expects to issue decisions on the remaining 5 requests, involving 11 licensing actions, in Q3 FY 2024.
Percentage Percentage Licensing Licensing of Licensing of Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period23 Milestone Schedule24 Schedule Q2 FY 2024 149 54 111 100% 99%26 Q3 FY 2024 [Pending Final Data]
New Reactors
Licensing Percentage Percentage of Actions Licensing of Licensing Licensing Initiated Actions Actions Actions Reporting Total During Completed Completed Completed Period Inventory the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period27 Milestone Schedule Schedule Q4 FY 202328 4 4 0 N/A N/A Q1 FY 202429 1 0 1 100% 0%30 Q2 FY 2024 1 0 0 N/A N/A Q3 FY 2024 2 1 0 N/A N/A
26 One request for a proposed alternative to implement a risk-informed categorization and treatment for repair or replacement activities exceeded the established schedule by 180 days. The NRC received two requests to implement the same alternative within a short time and identified several complex technical issues while reviewing the first request. The decision on the first request was issued in December 2023. The NRC expects to follow the same approach to complete the review of the second request and to issue its decision in Q3 FY 2024.
27 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.
28 For Q4 FY 2023, the total inventory and the licensing actions initiated were changed from 5 to 4 to correct a reporting error from the previous report. The item that was removed is no longer included in the table since it was not a requested activity of the Commission.
29 For Q1 FY 2024, the total inventory was changed from 3 to 1 and the licensing actions initiated was changed from 1 to 0 to correct a reporting error from the previous report. The total inventory decreased from 4 to 1 to reflect the termination and withdrawal of the Carbon Free Power Project (CFPP) Limited Work Authorization (LWA) application and exemption request, requested by the applicant, as well as the completion of one licensing action. The CFPP LWA application and exemption request are no longer included in the table, starting with Q1 FY 2024, since they are no longer requested activities of the Commission.
30 One licensing action exceeded the established schedule by 19 days because additional time was needed for SNC to review the safety evaluation for proprietary information.
Fuel Facilities
Licensing Licensing Percentage of Percentage of Actions Actions Licensing Licensing Reporting Total Initiated Completed Actions Actions Period Inventory During the During the Completed Prior Completed Reporting Reporting to the Generic Prior to the Period Period Milestone Established Schedule Schedule Q4 FY 2023 3 5 6 100% 67%31 Q1 FY 2024 7 4 0 100% 100%
Q2 FY 2024 10 7 4 100% 100%
Q3 FY 2024 6 0 4 100% 25%32
3-3 Licensing Amendment Request 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).
31 Two out of six fuel cycle licensing actions exceeded the established schedule because these reviews were deferred while the NRC staff worked on higher-priority reviews.
32 Two of the three fuel cycle licensing actions exceeded the established schedule due to the need to complete environmental assessments and publish Federal Register notices that were not anticipated.
The extension was communicated and agreed to by the licensee. The third late fuel cycle licensing action exceeded the established schedule due to an extension requested by the applicant and granted by the NRC to complete requests for additional information.
Operating Reactors
LARs LAR Percentage Submitted Reviews Percentage of LAR of LAR Reporting Total During Completed Reviews Completed Reviews Period Inventory the During the Prior to the Generic Completed Reporting Reporting Milestone Schedule Prior to the Period Period33 Established Schedule34 Q4 FY 2023 223 59 75 100% 81%35 Q1 FY 2024 190 39 68 100% 93%
Q2 FY 2024 168 36 54 99% 85%
Q3 FY 2024 [Pending Final Data]
New Reactors LARs LAR Percentage of Percentage of Submitted Reviews LAR Reviews LAR Reviews Reporting Total During the Completed Completed Prior Completed Period Inventory Reporting During the to the Generic Prior to the Period Reporting Milestone Established Period Schedule Schedule Q4 FY 2023 6 2 2 100% 100%
Q1 FY 2024 1 0 5 100% 100%
Q2 FY 2024 0 0 1 100% 100%
Q3 FY 2024 [Pending Final Data]
33 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.
34 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
35 One review of a LAR that proposed a first-of-a-kind security-related methodology exceeded the established schedule by 180 days. The complex technical issues resulted in requests for additional information, multiple closed public meetings, a site visit, and the licensee submitting supplements, including one that superseded the previous LAR. The last public meeting was on September 19, 2023, and the licensee indicated that it would discuss the options for moving forward internally and reengage with the NRC staff. The licensee withdrew the request in October 2023. The two associated licensing actions are no longer included in the table, starting with Q1 FY 2024, since they are no longer requested activities of the Commission.
Fuel Facilities
LARs LAR Reviews Percentage of Percentage of Submitted Completed LAR Reviews LAR Reviews Reporting Total During the During the Completed Prior Completed Period Inventory Reporting Reporting to the Generic Prior to the Period Period Milestone Established Schedule Schedule Q4 FY 2023 12 6 4 100% 50%36 Q1 FY 2024 9 4 7 100% 71%37 Q2 FY 2024 11 4 2 100% 50%38 Q3 FY 2024 6 1 6 100% 100%
3-4 Research Activities39
Summary of New Research Projects During the reporting period, the Office of Nuclear Regulatory Research (RES) did not initiate research on or substantially revise any projects.
Summary of Completed Research Projects 40 During the reporting period, RES did not complete research projects above the reporting resource levels.
3-5 Fees Billed
The tables below provide information on 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. 41
FY 2024 Part 170 Total Part 170 -
Fee Class Receipts Estimated Part 170 Billed in Billed in FY 2024
- Final Fee Rule Q3 FY 2024 ($M) ($M)
($M)
Fuel Facilities $8.7 $2.0 $6.7 Generic $6.2 $0.3 $0.8 Decommissioning Materials Users 42 $0.8 $0.1 $0.743
36 Two out of four LARs exceeded the established schedule because these reviews were deferred while the NRC staff worked on higher-priority reviews.
37 Two out of seven LARs exceeded the established schedule. The first review involved multiple NRC licenses and required additional coordination. The second review was delayed one week as the NRC and licensee coordinated on how to characterize proprietary information in the publicly available SE.
38 One out of two LARs exceeded the established schedule by 12 days due to limited staff availability.
This extension was communicated and agreed to by the licensee.
39 This section provides information about projects that were started or completed during the reporting period that exceeded 300 staff hours or $500K of program support for the total duration of the project.
40 The research project resources are estimates of staff hours and program support costs based on inspection of project records, including staffing plans and contract spending plans.
41 The FY 2024 Final Fee Rule was published in the Federal Register on June 20, 2024 (89 FR 51789).
42 Materials Users - Billed as flat fee applications and included in the estimates and billed.
43 Total Part 170 - Billed in FY 2024 ($M) for Materials Users reflects an update. Specifically, Q2 is reported as $0.265M instead of $0.214M in the previous report. Additionally, Total Part 170 - Billed in
FY 2024 Part 170 Total Part 170 -
Fee Class Receipts Estimated Part 170 Billed in Billed in FY 2024
- Final Fee Rule Q3 FY 2024 ($M) ($M)
($M)
Operating Power $168.3 $39.0 $125.5 Reactors Non-Power Production or $3.0 $1.0 $2.444 Utilization Facilities Spent Fuel Storage/
Reactor $12.3 $2.2 $8.645 Decommissioning Rare Earth $0.2 $0.0 $0.0 Transportation $2.4 $0.5 $1.6 Uranium Recovery $0.4 $0.1 $0.3
Significant Ongoing Licensing Actions
The following table includes a comparison of the fees billed to projected resources for subsequent license renewal application reviews and the Kairos Hermes 1 and Kairos Hermes 2 construction permit application reviews.
Projected Fees Billed Docket Project Name Resources to Date
($M)46 ($M)47 Point Beach Units 1 and 2 Point Beach Units 1 and 2 05000266/05000301 Subsequent License Renewal $5.048 $3.5 Application Safety Review Point Beach Units 1 and 2 Point Beach Units 1 and 2 Subsequent License Renewal $1.4 $1.5 05000266/05000301 Application Environmental Review
FY 2024 ($M) for Materials Users may not add due to rounding: $0.249M reported in Q1 plus
$0.265M in Q2 plus $0.140M in Q3 totals $0.654M.
44 Total Part 170 - Billed in FY 2024 ($M) for Non-Power Production or Utilization Facilities may not add due to rounding: $0.615M reported in Q1 plus $0.871M in Q2 plus $0.956M in Q3 totals $2.442M.
45 Total Part 170 - Billed in FY 2024 ($M) for Spent Fuel Storage/ Reactor Decommissioning may not add due to rounding: $3.090M reported in Q1 plus $3.229M in Q2 plus $2.238M in Q3 totals
$8.557M.
46 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.
47 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. Therefore, the total billed amounts listed in Table 3-5 reflect costs for NRC work performed through March 2024.
48 When the formal acceptance letter for the Point Beach subsequent license renewal application was sent to the licensee on January 15, 2021 (ML21006A417), the NRC estimated that it would take approximately $6.4M to complete the application review.
Projected Fees Billed Docket Project Name Resources to Date
($M)46 ($M)47 North Anna Units 1 and 2 North Anna Units 1 and 2 05000338/05000339 Subsequent License Renewal $5.049 $3.0 Application Safety Review North Anna Units 1 and 2 North Anna Units 1 and 2 Subsequent License Renewal $1.4 $2.3 05000338/05000339 Application Environmental Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 05000269/05000270/ Subsequent License Renewal $5.050 $3.8 05000287 Application Safety Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 05000269/05000270/ Subsequent License Renewal $1.4 $1.7 05000287 Application Environmental Review St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 05000335/05000389 Subsequent License Renewal $5.051 $4.1 Application Safety Review St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 Subsequent License Renewal $1.4 $0.4 05000335/05000389 Application Environmental Review Kairos Hermes 2 Units 1 Kairos Hermes 2 Units 1 and 2 and 2 Construction Permit - Safety $3.152 $1.2 05000611/05000612 and Environmental Reviews Monticello Unit 1 Monticello Unit 1 Subsequent 05000263 License Renewal Application $5.153 $2.4 Safety Review Monticello Unit 1 Monticello Unit 1 Subsequent 05000263 License Renewal Application $2.1 $1.3 Environmental Review
49 When the formal acceptance letter for the North Anna subsequent license renewal application was sent to the licensee on October 13, 2020 (ML20258A284), the NRC estimated that it would take approximately $6.4M to complete the application review.
50 When the formal acceptance letter for the Oconee subsequent license renewal application was sent to the licensee on July 22, 2021 (ML21194A245), the NRC estimated that it would take approximately
$6.4M to complete the application review.
51 When the formal acceptance letter for the St. Lucie subsequent license renewal application was sent to the licensee on September 24, 2021 (ML21246A091), the NRC estimated that it would take approximately $6.4M to complete the application review.
52 The projected resource estimate was provided to Kairos Power LLC by letter dated October 11, 2023 (ML23269A176).
53 When the formal acceptance letter for the Monticello subsequent license renewal application was sent to the licensee on February 23, 2023 (ML23047A175), the NRC estimated that it would take approximately $7.2M to complete the application review.
Projected Fees Billed Docket Project Name Resources to Date
($M)46 ($M)47 V.C. Summer Unit 1 V.C. Summer Unit 1 05000395 Subsequent License Renewal $5.054 $1.3 Application Safety Review V.C. Summer Unit 1 V.C. Summer Unit 1 Subsequent License Renewal $1.4 $0.1 05000395 Application Environmental Review
3-6 Requests for Additional Information (RAIs)
The table below provides information on RAIs 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. While Section 102(c) of NEIMA applies to licensing actions accepted after July 13, 2019, the RAI data also include licensing actions accepted prior to July 13, 2019, to provide a complete inventory.
Total Total Total Inventory of Number Number of Total Number Type of Facility or Open RAIs as of of RAIs RAIs of RAIs Closed Activity Type the End of Issued in Responded in Reporting Reporting Period Reporting to in Period55 Period Reporting Period Operating Reactors 322 165 135 114 Non-Power Production and 113 0 0 2 Utilization Facilities56 Design Certifications 0 0 0 0 for New Reactors 57 Early Site Permits for N/A N/A N/A N/A New Reactors 58 Combined Licenses 0 0 0 0 for New Reactors
54 When the formal acceptance letter for the V.C. Summer subsequent license renewal application was sent to the licensee on October 11, 2023 (ML23275A014), the NRC estimated that it would take approximately $6.4M to complete the application review.
55 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.
56 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.
57 No design certification 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.
58 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.
Total Total Total Inventory of Number Number of Total Number Type of Facility or Open RAIs as of of RAIs RAIs of RAIs Closed Activity Type the End of Issued in Responded in Reporting Reporting Period Reporting to in Period55 Period Reporting Period Construction Permits for New Reactors or Non-Power 23 13 14 28 Production and Utilization Facilities Fuel Facilities 186 0 1 37 Power Reactor 70 18 18 5 Decommissioning Research and Test Reactor 0 0 0 0 Decommissioning Spent Fuel 247 80 93 59 Materials 25 0 0 0 Pre-Application Activities for 16 15 15 0 Advanced Reactors
3-7 Workforce Development and Management
FY 2024 Staffing by Office 59
End of FTE FTE FTE FTE Delta (Q2 Year Delta FY Utilization Utilization Utilization Utilization FTE (EOY) (EOY 2024 3/24/24 - 4/21/24 - 5/19/24 - as of Utilization Projection Utilization Budget 4/20/24 5/18/24 6/29/24 6/29/24 - FY 2024 w/ - FY 2024 Budget) Personnel Budget)
Actions Totals 2937.8 212.5 212.4 327.2 2143.9 -793.9 2795.5 -142.3 COMM 42.0 2.0 2.0 3.0 20.8 -21.2 27.0 -15.0 OIG 63.0 4.0 4.0 6.1 39.2 -23.8 50.9 -12.1 Totals Other 2832.8 206.5 206.4 318.1 2083.9 -748.9 2717.6 -115.2 Offices OCFO 93.0 6.8 6.8 10.6 69.1 -23.9 91.1 -1.9 OGC 94.2 6.7 6.7 10.1 67.9 -26.3 88.1 -6.1 OCA 10.0 0.9 0.9 1.3 8.7 -1.3 11.3 1.3 OCAA 7.0 0.5 0.5 0.8 4.8 -2.2 6.3 -0.7 OPA 13.0 0.9 1.0 1.5 9.8 -3.2 12.8 -0.2 SECY 17.0 1.3 1.3 2.0 12.7 -4.3 16.2 -0.8 OIP 37.0 3.1 3.1 4.7 29.8 -7.2 38.7 1.7 ASLBP 25.6 1.4 1.5 2.3 14.7 -10.9 18.9 -6.7 ACRS 27.1 1.8 2.0 3.0 19.6 -7.5 25.4 -1.7 OEDO 30.0 2.3 2.4 3.3 22.1 -7.9 28.8 -1.2 NRR 580.3 42.1 42.4 65.5 418.9 -161.4 548.4 -31.9 NMSS 324.4 24.1 24.2 36.7 238.9 -85.5 310.7 -13.7 RES 207.4 14.5 14.7 23.7 146.1 -61.3 191.6 -15.8 NSIR 166.4 11.4 11.2 17.4 115.7 -50.7 150.4 -16.0 R-I 169.8 13.0 13.0 19.5 129.4 -40.4 167.5 -2.3 R-II 190.7 16.1 15.9 24.3 161.2 -29.5 209.9 19.2 R-III 168.9 12.6 12.5 19.1 126.8 -42.1 165.0 -3.9 R-IV 163.1 11.9 11.9 18.7 123.2 -39.9 160.5 -2.6 OE 30.9 2.2 2.3 3.5 22.5 -8.4 29.2 -1.7 OI 35.0 2.4 2.4 3.8 23.7 -11.3 31.5 -3.5 OCIO 172.0 12.6 12.4 19.2 125.8 -46.2 164.6 -7.4 ADM 119.0 8.5 8.5 13.0 87.6 -31.4 113.4 -5.6 SBCR 15.0 1.0 1.0 1.5 10.4 -4.6 13.4 -1.6 OCHCO 133.0 8.3 7.7 12.5 93.4 -39.6 122.4 -10.6 CSU 3.0 0.1 0.1 0.1 1.1 -1.9 1.5 -1.5
59 Some numbers might not add exactly due to rounding.
3-8 Inspection Activities
The table below shows the average number of hours of direct inspection per plant in CY 2024.
Average ROP Direct Inspection Hours
Nationwide Column 1 of Column 2 of Column 3 of Column 4 of Per Plant ROP Action ROP Action ROP Action ROP Action (unit) Matrix (unit) Matrix (unit) Matrix (unit) Matrix 375 Hours 366 Hours 564 Hours60 No Plants in No Plants in Column 3 Column 4
The table below shows the staff hours expended for inspection-related effort at operating power reactor sites by CY.
Items Description CY 2023 (Hours) CY 2024 (Hours)
- i. Baseline Inspection 213,426 51,636 ii. Plant-Specific Inspection 8,080 1,389 iii. Generic Safety Issue Inspections 0 0 iv. Performance Assessment 2,548 1,640
- v. Other Activities 101,059 22,747 vi. Total Staff Effort 325,114 77,412 vii. Total Staff Effort Per Operating 5,911 1,407 Site61
3-9 Backfit
Facility-Specific Backfits
No facility-specific backfits were issued during the reporting period.
Generic Backfits
No generic backfits were issued during the reporting period.
Backfit Appeals Filed by Licensees and Applicants
There were no backfit appeals submitted to the NRC during the reporting period.
60 Quad Cities Nuclear Power Station, Unit 2 moved to Column 2 in Q4 FY 2022 (ML22313A150) and returned to Column 1 in Q3 FY 2023 (ML23173A003). Calvert Cliffs Nuclear Power Plant, Unit 1 moved to Column 2 in Q4 FY 2022 (ML22314A100) and returned to Column 1 in Q2 FY 2024 (ML24101A261). Virgil C. Summer Nuclear Station moved to Column 2 in Q2 FY 2022 (ML22287A184), returned to Column 1 in Q3 FY 2023 (ML23195A196), and then returned to Column 2 in Q1 FY 2024 (ML23342A000). Sequoyah Nuclear Plant, Units 1 and 2 moved to Column 2 in Q1 FY 2023 (ML23103A395) and returned to Column 1 in Q1 FY 2024 (ML24011A077). Columbia Generating Station moved to Column 2 in Q1 FY 2022 (ML23111A237). Shearon Harris Nuclear Plant, Unit 1 moved to Column 2 in Q3 FY 2023 (ML23249A279) and returned to Column 1 in Q1 FY 2024 (ML24011A121). River Bend Station moved to Column 2 in Q3 FY 2023 (ML23201A132) and returned to Column 1 in Q2 FY 2024 (ML24074A476). Watts Bar Nuclear Plant, Units 1 and 2 moved to Column 2 in Q4 FY 2023 (ML23352A395).
61 Total staff effort is divided by 55 sites for both CY 2023 and CY 2024, due to Palisades permanently ceasing operations in June 2022 and Vogtle Unit 3 transitioning to the ROP in August 2022.