ML23108A268
| ML23108A268 | |
| Person / Time | |
|---|---|
| Issue date: | 05/15/2023 |
| 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 |
| Shared Package | |
| ML23108A269 | List: |
| References | |
| CORR-23-0043, SRM-LTR-19-0383-1 | |
| Download: ML23108A268 (37) | |
Text
STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION For the Reporting Period of January 1, 2023 through March 31, 2023
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 Q2 FY 2023 vs. Budgeted FTE .................................... 5 1-4 Budget Authority, FTE Utilization, and Fees ................................................................................. 5 - Status of Specific Items of Interest ................................................................... 7 2-1 Transformation .............................................................................................................................. 7 2-2 Workforce Development and Management .................................................................................. 8 2-3 Accident Tolerant Fuel .................................................................................................................. 9 2-4 Digital Instrumentation and Control ............................................................................................. 10 2-5 Vogtle Electric Generating Plant Units 3 and 4 ........................................................................... 11 2-6 Advanced Nuclear Reactor Technologies ................................................................................... 15 2-7 Advanced Reactor Licensing Reviews ........................................................................................ 18 2-8 Reactor Oversight Process ......................................................................................................... 19 2-9 Backfit.......................................................................................................................................... 20 2-10 Risk-informed Activities ............................................................................................................... 21 2-11 Coronavirus Disease (COVID-19) ............................................................................................... 23 - Summary of Activities ...................................................................................... 25 3-1 Reactor Oversight Process (ROP) Findings ............................................................................... 25 3-2 Licensing Actions ........................................................................................................................ 26 3-3 Licensing Amendment Request Reviews ................................................................................... 28 3-4 Research Activities ...................................................................................................................... 29 3-5 Fees Billed................................................................................................................................... 32 3-6 Requests for Additional Information (RAIs) ................................................................................. 34 3-7 Workforce Development and Management ................................................................................ 36 3-8 Inspection Activities ..................................................................................................................... 36 3-9 Backfit.......................................................................................................................................... 37
Enclosure 1 - High Level Summary 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act 1
Average Timeliness Percentage 0.9 0.8
(<100% = Completed Before 0.7 0.6 Schedule Date) 0.5 0.4 0.3 0.2 0.1 Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule 1, 2 1 No licensing actions categorized under the Nuclear Energy Innovation and Modernization Act were completed in Quarter (Q) 2 fiscal year (FY) 2021 for the new reactor business line.
2 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.
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1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete 3
3 Planned direct ROP 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.
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1-3 Full-time Equivalent (FTE) at the End of Q2 FY 2023 vs. Budgeted FTE Office of Nuclear Reactor Regulation Office of Nuclear Material Safety and Safeguards Office of Nuclear Regulatory Research Office of Nuclear Security and Incident Response Region I Region II Region III Region IV Office of Administration Office of the Chief Financial Officer Office of the Chief Human Capital Officer Office of the Chief Information Officer Office of General Counsel Other 0.0 100.0 200.0 300.0 400.0 500.0 600.0 FTE Budgeted FTE On Board FTE 1-4 Budget Authority, FTE Utilization, and Fees NRC FY 2023 Budget Authority March 31, 2023 (Dollars in Thousands)
Fund Sources FY 2023 Budget4 Percent Obligated Percent Expended Advanced Reactors $26,800 31% 22%
Commission Funds $13,036 31% 31%
Fee-Based Funds $863,537 45% 34%
General Funds5 $1,178 25% 25%
International Activities $18,579 46% 33%
University Nuclear
$36,409 19% 0%
Leadership Program Official Representation $43 42% 41%
Total $959,582 44% 32%
NRC Control Points FY 2023 Budget Percent Obligated Percent Expended Nuclear Reactor Safety $493,847 40% 36%
Nuclear Materials and
$112,603 45% 35%
Waste Safety Decommissioning and
$24,433 49% 44%
Low-Level Waste Corporate Support $292,290 52% 28%
4 FY 2023 Budget reflects the enactment of the Consolidated Appropriations Act, 2023 and includes the enacted budget and carryover allocated.
5 Consistent with previous reports, this row represents waste incidental to reprocessing activities excluded from the fee-recovery requirement.
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NRC Control Points FY 2023 Budget Percent Obligated Percent Expended University Nuclear
$36,409 19% 0%
Leadership Program6 Total7 $959,582 44% 32%
FTE Utilization, Hiring, and Attrition Total Year-to-Date Projected End of Year Q2 YTD YTD (YTD) FTE Q2 Hiring FTE Total Utilization Attrition Hiring Attrition Utilization 1349.2 2760.7 49 75 107 1058 FY 2023 Fees Estimated, Fees Billed, and Fees Collected Through Q2 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 2021 FY 2022 FY 2023 Q1-Q2
$183.9 $190.7 $91.8 6 The FY 2023 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 due to rounding.
8 The previous report referenced 29 staff losses for the Q1 Attrition. The YTD attrition total in this report reflects an additional staff loss that was inadvertently excluded from the previous report.
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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 The U.S. Nuclear Regulatory Commission (NRC) is becoming a more modern, risk-informed regulator, open to new technologies and ways of implementing our safety and security mission.
The NRC continues to make progress in four focus areas: (1) recruiting, developing, and retaining a strong workforce; (2) improving decision-making through the acceptance of an appropriate level of risk without compromising the NRCs mission; (3) establishing a culture that embraces innovation; and (4) adopting new and existing information technology resources. The agency has completed all but one of our initial agencywide initiatives associated with the four focus areas.
The focus areas (i.e., Our People, Be riskSMART, Using Technology, and Innovation) are interwoven into the agencys strategic goals and objectives. To sustain progress and meet the agencys transformation goals, the NRC uses a variety of tools, including objectives and key results. The NRC continues to leverage available technologies, increase opportunities for staff to gain new skills, attract talented new staff, and foster a culture of safety and innovation that accounts for differing viewpoints and risk insights in our decision-making. Planned future activities will focus on incorporating positive transformational changes into the agencys culture and processes.
Activities Planned and Completed for the Reporting Period (Quarter (Q) 2 fiscal year (FY) 2023)
Projected Transformation Activities Completion Date Completion Date Launched a follow-on survey of external stakeholder 01/31/23 01/12/23 views on NRC transformation activities.
Conducted a full reassessment of the agencys cultural norms and behaviors to ensure the agency 03/31/23 03/22/23 is sustaining transformational progress.
Conducted first-line supervisor and senior leader sessions on Organizational Health: Sustaining 03/31/23 03/31/23 Transformational Progress in a Hybrid Environment.
Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Transformation Activities Completion Date Conduct presentations for senior leaders and staff on results of the:
(1) follow-on survey of external stakeholder views on NRC transformation 05/31/23 activities; and (2) full reassessment of the agencys cultural norms and behaviors to ensure the agency is sustaining transformational progress.
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Projected Projected Transformation Activities Completion Date Conduct a Jam, which is an agencywide collaborative online discussion, on how to continue to best prepare for the future, focusing on 06/30/23 sustaining transformational progress.
Conduct presentations for senior leaders and staff on the results of the Jam on how to continue to best prepare for the future, focusing on 09/29/23 sustaining transformational progress.
2-2 Workforce Development and Management Each fiscal year, the NRC engages in a five-step Strategic Workforce Planning (SWP) process to improve workforce development to meet its near- and long-term work demands. The first step in this process is an Agency Environmental Scan that projects the amount and type of work anticipated in the next 5 years and identifies the workforce needs in order 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- 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 needed to conduct mission-critical work, the agency continued implementing strategies to recruit and onboard a significant number of new employees during this reporting period, and the agency plans to continue this recruitment effort.
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 fulfill its important safety and security mission well into the future.
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Workforce Development and Management Projected Completion Date Activities Completion Date Finalize security clearance reviews and prepare for 03/31/23 04/21/239 Summer 2023 Student Intern onboarding.
Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Workforce Development and Management Activities Completion Date Onboard Summer 2023 Student Interns. 06/30/23 Conduct an evaluation of the SWP process for effectiveness and efficiency improvements as identified in the NRCs Annual Evaluation 09/29/2310 Plan for FY 2023.
9 This activity was completed on April 21, 2023, rather than the projected completion date of March 31, 2023, due to the change of security clearance systems.
10 This activitys projected completion date was modified from March 31, 2023, to September 29, 2023, to reflect updated schedules following the completion of the development of a detailed and structured evaluation plan.
Additionally, the previous report projected a completion date of June 30, 2023, to incorporate approved recommendations from the evaluation of the SWP process into guidance documents and training materials. This activity is now anticipated to occur in FY 2024, after the evaluation is completed.
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2-3 Accident Tolerant Fuel While the NRC is ready to review and license Accident Tolerant Fuel (ATF), higher burnup, and increased enrichment submittals under the current regulatory framework, the NRC continues to take steps to make agency processes more efficient and effective. 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.
During this reporting period, the NRC did not receive any additional ATF fuel vendor topical reports. In January 2023, the NRC staff accepted for review a topical report that discusses implementation of updated nuclear methods to support increased enrichment fuels (ML23024A214). Additionally, the NRC staff issued its final safety evaluation (SE) on March 22, 2023, for a topical report that describes Framatome, Inc.s proposed increased enrichment for pressurized water reactors (ML23053A053). The NRC staff is on track to complete review of the eight ATF fuel vendor topical reports currently under review by the end of FY 2025, in time to support expected licensee submittals to use ATF. No additional LARs were submitted during this reporting period.
On January 31, 2023, the NRC received an additional certificate of compliance amendment application to transport fresh fuel with an enrichment up to 8 weight-percent uranium-235 (ML23031A213).
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Projected ATF Activities Completion Date Completion Date Held a Commission meeting to provide an update on the status and issues associated with the path to 01/24/23 01/24/23 licensing ATF concepts.
Participated in the 2023 NRC Regulatory Information Conference (RIC) by providing stakeholders an opportunity to learn about the progress of ATF licensing activities and technologies to date and the activities that support 03/14/23 03/14/23 efficient licensing of ATF concepts. At the RIC, the NRC staff communicated about ATF readiness activities, planned stakeholder engagements, the NRCs projected licensing timelines, and any challenges to ATF deployment timelines.
Approved the use of the DN30-X transportation package to transport uranium hexafluoride with an 03/31/23 03/27/23 enrichment up to 20 weight-percent uranium-235 (ML23083B977).
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Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected ATF Activities Completion Date Issue a Regulatory Issue Summary (RIS) entitled Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels. This RIS would request that 06/30/23 industry provide timelines for the submission of licensing actions to support ATF deployment, to help determine future planning and resource allocation.
In accordance with Commission direction in Staff Requirements Memorandum to SECY-21-0109 (ML22075A103), publish the regulatory basis for rulemaking, associated with the use of light water reactor fuel containing uranium enriched to greater than 5 weight-percent 09/15/23 uranium-235 for public comment. The regulatory basis will provide the technical, legal, and policy information that supports the proposed changes to the NRCs regulations.
Issue the draft final Regulatory Guide (RG) 1.183, Alternate Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, Revision 1, to expand applicability to burnup 09/23/23 extensions up to 68 gigawatt-days per metric ton and enrichments up to 8 weight-percent uranium-235, in support of the Advisory Committee on Reactor Safeguards (ACRS) full committee meeting.
Hold a fourth Higher Burnup workshop to discuss the state of development of higher burnup and increased enrichment technical and 09/29/2311 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 has transitioned to using its improved infrastructure to support the review of licensees digital instrumentation and control (I&C) modernization LARs and continues to complete 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.
Two licensees have submitted LARs to support planned digital upgrades:
- On July 30, 2022 (ML22213A045), Florida Power & Light Company (FPL) submitted LARs for Turkey Point Nuclear Plant, Units 3 and 4 (Turkey Point). The LARs, if approved, would permit the use of digital I&C for the reactor protection system, engineered safety features actuation system, and nuclear instrumentation system at Turkey Point. On October 13, 2022, the NRC staff completed its acceptance review of the Turkey Point LARs and informed FPL that the staff expects to complete its review of the LARs by June 30, 2024 (ML22280A108).
11 The projected completion date was modified from June 30, 2023, to September 29, 2023, to align with the publication of the regulatory basis for rulemaking being released for public comment.
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- On September 26, 2022 (ML22269A569), Constellation Energy Generation, LLC 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 December 9, 2022, the NRC staff completed its acceptance review of the Limerick LARs and informed Constellation that the staff expects to complete its review of the LARs by March 11, 2024 (ML22339A064).
The NRC staff provided SECY-22-0076 (ML22164B003) to the Commission for its consideration on August 10, 2022, recommending expansion of the current policy on digital I&C CCF, which is contained in the 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 the need for independent and diverse displays and manual controls in the main control room in the event of a CCF. The staffs recommendation, if approved, would allow the use of risk-informed approaches to demonstrate the appropriate level of defense-in-depth.
The NRC staff also continued the development of Draft Regulatory Guide DG-1374 to consider endorsement of Institute of Electrical and Electronics Engineers Standard 7-4.3.2-2016, Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations.
DG-1374, if finalized, will be issued as Revision 4 to RG 1.152, Criteria for Use of Computers in Safety Systems of Nuclear Power Plants. This revision to RG 1.152 will support the modernization and improvement of the digital I&C regulatory infrastructure.
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Projected Digital I&C Activities Completion Date Completion Date DG-1374 (Revision 4 to RG 1.152, Criteria for Use of Computers in Safety Systems of Nuclear Power Plants)
- Published DG-1374 for public comment 03/31/23 03/10/23 (88 FR 14957).
Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Digital I&C Activities Completion Date N/A N/A 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 to be built and operated at the Vogtle site near Augusta, GA. SNC projects the start of commercial 11
operations for Vogtle Unit 3 in Q2 CY 2023 and projects Vogtle Unit 4 to begin commercial operations in Q4 CY 2023 or Q1 CY 2024.12 On March 6, 2023, Vogtle Unit 3 achieved initial criticality. The NRC continues to perform inspections as the licensee performs power ascension testing. Vogtle Unit 4 remains under the Construction Reactor Oversight Process. The NRC continues to perform Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) inspections and review ITAAC closure notifications for Vogtle Unit 4.
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Vogtle Electric Generating Plant Units 3 and 4 Projected Completion Date Activities Completion Date Granted an emergency LAR to modify technical specifications related to the automatic N/A13 01/13/23 depressurization system prior to initial criticality (ML23013A214).
Granted an exigent LAR based on the in-containment refueling water storage tank N/A14 02/08/23 operability prior to initial criticality (ML23037A082).
Conducted a second pre-submittal meeting on a draft LAR and exemption request to remove Appendix C from the COL and provide an N/A15 02/16/23 exemption from Tier 1 and Tier 2* requirements for Vogtle Unit 3 (ML23040A295).
Conducted a public technical exchange meeting on a proposed LAR for technical specifications N/A16 03/02/23 exceptions prior to initial criticality for Vogtle Unit 4 (ML23055B033).
Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Conduct a pre-submittal meeting on a proposed LAR for technical 05/31/23 specifications exceptions prior to initial criticality for Vogtle Unit 4.
Issue safety evaluation for a request from SNC to adopt an alternative to the in-service inspection requirements for steam generator nozzle to 08/04/23 reactor coolant pump casing welds (VEGP 3&4-ISI1-ALT-17).
12 On February 16, 2023, Georgia Power Co. announced that Vogtle Unit 3 is projected to begin commercial operations between May and June 2023 and Unit 4 is projected to begin between November 2023 and March 2024.
13 This was not identified as a projected activity in the previous report because SNC submitted the emergency LAR to the NRC on January 12, 2023.
14 This was not identified as a projected activity in the previous report because SNC submitted the exigent LAR to the NRC on January 31, 2023.
15, 16 These meetings were not identified as projected activities in the previous report because the meeting requests were submitted after the previous reports issuance.
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Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Issue safety evaluation for a request from SNC to adopt an alternative for use of Code Case N-648-2 for in-service inspection of the reactor vessel 08/04/23 nozzle inner radius sections (VEGP 3&4-ISI1-ALT-18).
A COL allows a licensee to construct a plant and to operate it once construction is complete if certain standards identified in the COL are satisfied. These standards are called ITAAC. The majority of ITAAC are from the design certification for the particular reactor technology that a plant uses. Throughout the construction process, NRC inspectors will perform inspections based on Inspection Manual Chapter 2503, Construction Inspection Program: Inspections of Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) Related Work, and the NRCs Construction Inspection Program at the plant site to confirm that the licensee has successfully completed the ITAAC.
Additional information on the ITAAC process as well as closure for Vogtle Units 3 and 4 is available at https://www.nrc.gov/reactors/new-reactors/oversight/itaac.html.
Number of ITAAC ITAAC Total Inspections ITAAC Unit Remaining Requiring Inspections Completed17 Inspected18 Inspection Closed19 Vogtle 4 77 28 20 37 ITAAC Reviews Completed for the Reporting Period (Q2 FY 2023)20 The table below provides ITAAC closure notification reviews completed during the reporting period for Vogtle Unit 4, including the date when the NRC received the ITAAC closure notice and the date when the review was completed.
Unit ITAAC No. Received Date Approval Date Vogtle 4 2.2.01.01 12/27/22 01/03/23 Vogtle 4 2.1.02.08d.ii 12/21/22 01/06/23 Vogtle 4 2.7.01.05.i 01/05/23 01/06/23 Vogtle 4 2.3.02.14 01/10/23 01/11/23 Vogtle 4 2.3.13.05.i 01/12/23 01/13/23 Vogtle 4 2.1.02.12a.iv 01/13/23 01/17/23 Vogtle 4 2.1.02.01 01/16/23 01/19/23 17 This column includes all inspections related to Vogtle Unit 4 completed during the reporting period; the column is not limited to ITAAC (e.g., quality assurance inspections).
18 ITAAC Inspected refers to the number of ITAAC that were inspected as part of ongoing inspections and does not indicate that all inspections were completed for those ITAAC. Only targeted ITAAC - ITAAC selected for inspection by the NRC staff - are included in this count.
19 ITAAC Inspection Closed refers to the number of ITAAC for which all associated inspections have been completed during the reporting period.
20 This table accounts for the total number of ITAAC that SNC provided closure notifications for and that the NRC verified. This includes both ITAAC that were selected for inspection by the NRC staff (targeted ITAAC) and ITAAC that were not selected for inspection by the NRC staff (non-targeted ITAAC). This differs from the previous table, where the ITAAC Inspected column is the number of targeted ITAAC that were inspected during the designated reporting period.
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Unit ITAAC No. Received Date Approval Date Vogtle 4 3.3.00.02a.i.c 01/13/23 01/19/23 Vogtle 4 3.3.00.02a.i.d 01/13/23 01/19/23 Vogtle 4 2.2.02.11a.i 01/23/23 01/24/23 Vogtle 4 2.2.03.12a.iv 01/13/23 01/26/23 Vogtle 4 2.2.04.01 01/26/23 01/27/23 Vogtle 4 2.2.02.06b 01/27/23 01/31/23 Vogtle 4 2.2.04.12a.i 01/20/23 01/31/23 Vogtle 4 2.3.08.02.i 01/31/23 02/02/23 Vogtle 4 2.2.03.09a.i 01/20/23 02/02/23 Vogtle 4 3.3.00.02h 01/31/23 02/06/23 Vogtle 4 2.2.03.08c.i.04 01/19/23 02/06/23 Vogtle 4 2.4.06.02 02/07/23 02/09/23 Vogtle 4 2.3.02.02a 02/02/23 02/10/23 Vogtle 4 2.3.05.03c.ii 02/10/23 02/13/23 Vogtle 4 2.3.10.12 02/13/23 02/14/23 Vogtle 4 2.2.03.08c.ii 02/03/23 02/15/23 Vogtle 4 2.3.04.05 02/16/23 02/17/23 Vogtle 4 2.3.07.07c 02/10/23 02/17/23 Vogtle 4 2.3.05.03d.ii 02/10/23 02/17/23 Vogtle 4 2.3.09.02a 02/16/23 02/20/23 Vogtle 4 2.3.07.05.i 02/17/23 02/21/23 Vogtle 4 2.2.03.08c.i.03 01/20/23 02/21/23 Vogtle 4 2.1.02.08d.i 02/03/23 02/21/23 Vogtle 4 3.3.00.07d.i 02/24/23 02/27/23 Vogtle 4 2.2.05.05a.i 02/17/23 02/28/23 Vogtle 4 2.6.03.05d.i 03/01/23 03/02/23 Vogtle 4 2.7.07.02 03/01/23 03/03/23 Vogtle 4 2.3.09.02b 03/02/23 03/03/23 Vogtle 4 2.3.13.02 03/03/23 03/07/23 Vogtle 4 3.3.00.02a.i.b 03/03/23 03/08/23 Vogtle 4 2.1.02.09c 03/08/23 03/09/23 Vogtle 4 2.1.02.13a 03/10/23 03/13/23 Vogtle 4 2.2.04.09a.ii 03/14/23 03/15/23 Vogtle 4 2.6.03.07 03/14/23 03/20/23 Vogtle 4 3.2.00.05 03/17/23 03/20/23 Vogtle 4 2.7.06.02.ii 03/16/23 03/21/23 Vogtle 4 2.1.02.13b 03/14/23 03/21/23 Vogtle 4 2.1.02.09b.ii 03/21/23 03/21/23 Vogtle 4 2.1.02.15 03/20/23 03/21/23 Vogtle 4 2.6.02.02b 03/17/23 03/22/23 Vogtle 4 2.6.02.02a 03/20/23 03/22/23 Vogtle 4 3.3.00.07d.ii.c 03/16/23 03/24/23 14
Unit ITAAC No. Received Date Approval Date Vogtle 4 3.3.00.07c.i.b 03/16/23 03/24/23 Vogtle 4 2.5.06.02 03/24/23 03/29/23 Vogtle 4 2.7.03.03 03/30/23 03/31/23 Vogtle Units 3 and 4 LAR Reviews Completed (Q2 FY 2023)
Number of LAR Reviews Forecast to be Number of LAR Reviews that Were Completed in the Reporting Period Completed in the Reporting Period 0 221 2-6 Advanced Nuclear Reactor Technologies The NRC continues to make significant progress in enhancing its efforts to review non-light-water-reactor (non-LWR) designs, consistent with the NRC staffs vision and strategy (ML16356A670) and implementation action plans to achieve non-LWR safety review readiness.22 During this reporting period, the NRC staff continued its extensive stakeholder engagement, including holding several public meetings and workshops regarding various advanced reactor topics, such as digital I&C systems.
On March 1, 2023, the NRC staff provided SECY-23-0021, Proposed Rule: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (RIN 3150-AK31), to the Commission for its consideration. Once the Commission votes, the staff will revise the draft proposed rule to reflect Commission direction and then issue the resulting proposed rule for public comment. After the staff receives, considers, and addresses the public comments, the draft final rule package, including key guidance, will be submitted to the Commission for consideration by December 2024. The NRC anticipates issuing the final rule by July 2025.
Further details about the Part 53 rulemaking schedule can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/rulemaking-and-guidance/part-53.html).
The NRC holds periodic public stakeholder meetings to discuss advanced reactor topics of interest. A list of the meetings that the NRC has conducted to date can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/stakeholder-engagement).
The NRC is also actively engaged with stakeholders regarding the Advanced Reactor Content of Application Project (ARCAP). A list of these meetings and related preliminary draft guidance documents to support the meetings can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/rulemaking-and-guidance/
advanced-reactor-content-of-application-project.html).
Consistent with the Nuclear Energy Innovation and Modernization Act (NEIMA), the NRC staff presented these options to support the development of a regulatory framework for fusion energy systems by 2027 (ML22273A178). On April 13, 2023, the Commission approved the option to license and regulate fusion energy systems under NRCs byproduct material framework 21 The two LARs issued on January 13, 2023, and February 08, 2023, respectively, were unplanned. They met the agencys conditions for emergency and exigent processing to support the completion of pre-critical testing activities for Vogtle Unit 3.
22 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).
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contained in 10 CFR Part 30 and associated regulations (ML23103A449). Under the limited-scope rulemaking approved under this option, the Commission directed the staff to take into account the existence of fusion systems that already have been licensed and are being regulated by the Agreement States, as well as those that may be licensed prior to the completion of the rulemaking. Further, the Commission directed the staff to develop 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 Commission also directed the staff to evaluate whether controls-by-design approaches, export controls, or other controls are necessary for near-term fusion energy systems. Finally, the Commission directed that, if in the future, the staff, in consultation with the Agreement States, determines that an anticipated fusion design presents hazards sufficiently beyond those of near-term fusion technologies, the staff should notify the Commission and make recommendations for taking appropriate action as needed.
To support development of the options for a regulatory framework for fusion energy systems, the NRC staff conducted several public meetings in 2021 and 2022 to engage stakeholders on fusion energy technology and views on developing a regulatory framework. The meeting agendas, presentations, and summaries for these interactions can be found on the NRCs public website (https://www.nrc.gov/reactors/new-reactors/advanced/policy-development/
fusion-energy.html). The NRC staff plans to continue to engage stakeholders on fusion energy systems.
Additionally, the NRC staff is preparing, 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 resolution of technical and policy issues that could affect licensing. Information on the reactor designers that have 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).
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Projected Advanced Nuclear Reactor Technologies Completion Completion Date Activities Date Published the final RG (RG 1.87, Revision 2) endorsing, with conditions, the American Society of Mechanical Engineers Boiler and Pressure Vessel 03/31/23 01/31/23 Code Section III, Division 5, High Temperature Reactors (ML22101A263).
Submitted the draft proposed rule providing the 10 CFR Part 53 requirements for advanced reactors to the Commission for its consideration 02/23/23 03/01/2323 (ML21162A093).
Issued final SE to Kairos for its topical report on fuel qualification methodology (ML23048A326). 02/28/23 03/02/2324 23 This activity was completed on March 1, 2023, rather than the projected completion date of February 23, 2023, to accommodate additional time for administrative processing.
24 This activity was completed on March 2, 2023, rather than the projected completion date of February 28, 2023, to accommodate additional time for the staff to address comments received from the ACRS.
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Projected Advanced Nuclear Reactor Technologies Completion Completion Date Activities Date Published draft interim staff guidance on material compatibility, DANU-ISG-2023-01, for public 04/28/23 03/07/23 comment (ML22203A175, 88 FR 14186).
Issued final SE to X-energy for its topical report on pebble fuel qualification methodology 02/24/23 03/09/2325 (ML22327A198).
Issued final SE to Kairos for its topical report on 03/31/23 03/13/23 graphite materials qualification (ML23062A733).
Issue final SE to Kairos for its topical report on metallic material qualification program 03/31/23 03/13/23 (ML23062A727).
Issued final SE to X-energy for its topical report on transient and safety analysis methodologies 04/07/23 03/29/23 framework (ML23037A943)
Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Completion Projected Advanced Nuclear Reactor Technologies Activities Date Issue draft RG (DG-1404) for potential endorsement of industry-led Nuclear Energy Institute (NEI) 21-07, Technology Inclusive Guidance for Non-Light Water Reactors, and nine 04/30/2326 NRC-led ARCAP interim staff guidance documents for public comment.
Issue draft white paper on alternative approaches to address 04/26/23 population-related siting considerations.
Issue final SE to X-energy for its topical report on control room 04/28/2327 staffing analysis methodology.
Submit a paper to the Commission on the vision for the NRC's 05/15/23 Advanced Reactors Construction Oversight Program.
Release draft interim staff guidance on facility training programs 05/31/2328 to support stakeholder engagement.
Issue draft white paper on expectations for PRAs supporting construction permit applications for non-LWRs implementing the Effort Discontinued29 Licensing Modernization Project.
25 This activity was completed on March 9, 2023, rather than the projected completion date of February 24, 2023, to accommodate additional time for resolution of internal comments.
26, 28 The projected completion dates for these activities were extended due to the need to prioritize work on the Part 53 draft proposed rule.
27 A draft of the SE was completed on February 27, 2023. The projected completion date for the final SE was modified from March 31, 2023, to April 28, 2023, to provide additional time for X-energy to comment on the draft SE and for the staff to resolve any comments received from X-energy before issuing the final SE.
29 The projected completion date for this activity was modified from April 30, 2023, to Effort Discontinued and this activity will not be included in future reports because the staff is reevaluating its approach to addressing PRA for non-LWR construction permit applications and the staff no longer plans to prepare a draft white paper focused on 17
Projected Completion Projected Advanced Nuclear Reactor Technologies Activities Date Issue final SE to General Atomics-Electromagnetic Systems for 07/06/23 its topical report on principal design criteria.
Issue final SE to X-energy for its topical report on principal design 09/08/23 criteria.
2-7 Advanced Reactor Licensing Reviews Kairos Hermes Construction Permit Application Review Kairos Power LLC (Kairos) submitted an application for a construction permit for the Kairos Power Fluoride Salt-Cooled, High Temperature Non-Power Reactor (Hermes). Kairos submitted application documents to the NRC by letters dated September 29, 2021 (submitting the Preliminary Safety Analysis Report) (ML21272A375), and October 31, 2021 (submitting the Environmental Report) (ML21306A131).
The NRC staff performed an acceptance review of the Hermes construction permit application and docketed the application on November 29, 2021 (ML21319A354). The NRC staff is currently conducting a detailed technical review of the safety of the Hermes design, which will lead to a SE. The final SE will not be issued until after the ACRS completes its review of the SE.
The final SE is expected to be issued in September 2023. Application documents and information on the review are available on the NRCs public website (https://www.nrc.gov/reactors/non-power/hermes-kairos.html).
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).
The NRC staff performed an acceptance review of the MSRR construction permit application and docketed the application on November 18, 2022 (ML22313A097). The NRC staff is currently conducting a detailed technical review of the safety of the MSRR design, which will lead to a SE. The NRC staff plans to prepare an environmental assessment for this application.
The NRC staff anticipates issuing the final SE by May 2024. 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).
this topic. The staff plans to incorporate activities related to expectations for PRAs supporting construction permit applications for non-LWRs into other future work products.
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Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Advanced Reactor Licensing Review Activities Projected Completion Date Completion Date Completed development of the Kairos Hermes advanced SE, with all sections completed and 02/23/23 02/13/23 assembled.
Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Advanced Reactor Licensing Review Activities Completion Date Complete review and NRC staff approval of Kairos Hermes SE.30 05/04/23 Complete regulatory audits and evaluate any additional docketed 08/30/23 information necessary for the preparation of the ACU SE.
Completion of ACRS meetings and ACRS review of Kairos Hermes 09/01/23 SE.
Issue final Kairos Hermes SE. 09/11/23 Issue final Kairos Hermes Environmental Impact Statement. 09/15/23 2-8 Reactor Oversight Process The ROP is a risk-informed, performance-based oversight program that contains provisions for continuous self-assessment and improvement.
During this reporting period, the Commission issued several SRMs approving the staffs recommended options related to the greater-than-green inspection findings and performance indicators (SECY-22-0086, ML23069A093), Problem Identification and Resolution inspection frequency (SECY-22-0087, ML23062A686), and Emergency Preparedness Significance Determination Process (SECY-22-0089, ML23040A378), and providing additional direction for the staff. In accordance with the Commissions direction, the staff is making changes to inspection, assessment, and significance determination process ROP documents.
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Projected ROP Activities Completion Date Completion Date Submitted a paper to the Commission recommending that the Alert and Notification 03/31/23 01/30/23 System Performance Indicator be retired (ML23004A013).
Completed an effectiveness review of the 03/31/23 03/20/23 incorporation of safety culture oversight into the ROP.
30 The final SE will not be issued until after the ACRS completes its review of the SE.
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Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected ROP Activities Completion Date Complete CY 2022 ROP Self-Assessment and submit a paper to the 04/15/23 Commission.
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. The backfitting rules define backfitting as the modification of or addition to systems, structures, components, or design of a facility; or the design approval or manufacturing license for a facility; or the procedures or organization required to design, construct or operate a facility; any of which may result from a new or amended provision in the Commissions regulations or the imposition of a regulatory staff position interpreting the Commissions regulations that is either new or different from a previously applicable staff position.31 The rules require, in the absence of an applicable exception, an analysis showing that the backfit would result in a substantial increase in the overall protection of the public health and safety or the common defense and security and that the increased protection warrants the direct and indirect costs of implementation. 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.
The Commission changed its backfitting and issue finality policy as well as its policy on forward fits, which it defined as requirements or staff interpretations of requirements imposed as a condition of agency approval of a licensee request that result in the modification of or addition to systems, structures, components, or design of a facility, 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 FR 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). This revised document is currently before the Commission for its consideration.
Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Projected Backfit Activities Completion Date Completion Date N/A N/A N/A 31 10 CFR 50.109(a)(1). Substantially similar definitions are provided in Sections 70.76, Backfitting, 72.62, Backfitting, and 76.76, Backfitting, for non-reactor facilities.
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Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Backfit Activities Completion Date N/A32 N/A 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.33 The NRC staff continues to implement and monitor the use of the agencywide Be riskSMART risk-informed decision-making framework to inform a broad range of decisions spanning technical, legal, and corporate arenas.
For example, the NRC staff continues to review and approve applications to adopt advanced risk management programs such as 10 CFR Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, and Risk-Informed Technical Specifications Initiative 4b,34 that provide for operational flexibilities that enhance safety by ensuring that power reactor licensees and the NRC prioritize the most risk significant issues. In addition, the staff has successfully completed its reviews and approved the applications submitted by all operating reactor licensees to adopt a risk-informed surveillance frequency control program, Risk-Informed Technical Specifications Initiative 5b.
Beginning in December 2022, the NRC staff embarked on increased use of risk insights in the review of new reactor applications. Specifically, in preparation for the submittal of the NuScale standard design approval application, the NRC staff collected preliminary risk insights in support of a graded review of the NuScale VOYGR 460 standard design. These risk insights were leveraged by the NRC staff in its early review of the standard design approval application by:
(1) identifying focus areas for the review; (2) grading the review scope and schedule; and (3) supporting decision-making during the acceptance review of the application. This NRC staff initiative is aligned with the implementation of the lessons learned from the NuScale design certification application review (ML22294A144) and is an example of being a more modern risk-informed regulator.
32 The previous report included the following in the projected activity table: Publish, for public comment, a proposed rule that contains a proposed change to NRC regulations that would constitute backfitting if issued as a final rule: Alignment of Licensing Processes and Lessons Learned from New Reactor Licensing. The proposed rule is with the Commission for its consideration; therefore, it has been removed from the projected activity table.
33 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.
34 A description of these and other operating reactors risk-informed initiatives is available at https://www.nrc.gov/about-nrc/regulatory/risk-informed/rpp/reactor-safety-operating.html. To date, the NRC has approved 28 applications enabling licensees to adopt 10 CFR Section 50.69 and 19 applications enabling licensees to adopt Risk-Informed Technical Specifications Initiative 4b.
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Activities Planned and Completed for the Reporting Period (Q2 FY 2023)
Projected Risk-Informed Activities Completion Completion Date Date Provided the new seminar to new staff with an overview of the Risk Tool and its use to risk-inform 02/28/23 03/08/2335 technical reviews for spent nuclear fuel dry storage.
Held a technical session at the 2023 NRC RIC entitled, Building on a Strong Foundation: A Voyage through Risk Informed Decision-Making.
This session included representatives from the NRC, Electric Power Research Institute (EPRI),
and industry, including NEI. The session highlighted novel and innovative approaches to leveraging risk-informed decision-making (RIDM) across operating, new, and advanced reactors and addressed the advancement of the RIDM 03/14/23 03/14/23 infrastructure to support increased adoption of more complex risk-informed applications, advancements in PRA technology and risk tools, and the emergence of new designs and operational concepts. It also facilitated discussion on where challenges exist and how to address them. In addition, the staff offered two digital displays at the 2023 NRC RIC on the importance of leveraging integrated review teams and the safety benefits of risk-informed initiatives.
Issued an Information Notice, IN-2023-01, to share international and domestic operating experience relating to high energy arcing faults (HEAFs),
including qualitative and quantitative risk insights derived from operating experience using the NRCs Office of Nuclear Reactor Regulation Office Instruction LIC-504, Integrated Risk-Informed 06/30/23 03/10/23 Decisionmaking Process for Emergent Issues, Revision 5. This information notice also provides information about the availability of an updated HEAF PRA methodology developed by the NRCs Office of Nuclear Regulatory Research in coordination with EPRI (ML22326A204).
35 This activity was completed on March 8, 2023, rather than the projected completion date of February 28, 2023, because of conflicts with other higher priority efforts and a desire to maximize staff attendance and benefits of the seminar.
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Projected Activities for the Next Two Reporting Periods (Q3 and Q4 FY 2023)
Projected Projected Risk-Informed Activities Completion Date Complete the revision of four materials Inspection Procedures (IPs) associated with Inspection Manual Chapter 2800 (specifically, IP 87121, Industrial Radiography Programs; IP 87122, Irradiator Programs; IP 87125, Materials Processor/Manufacturer Programs; 04/30/23 and IP 87127, Radiopharmacy Programs). The NRC staff is developing risk modules in each IP, with each module focusing on the risks of the relevant types of radioactive materials and their usage.
2-11 Coronavirus Disease (COVID-19)
The NRC continues to implement precautionary measures, as needed, in response to COVID-19 to help protect the health and safety of our workforce consistent with guidance provided by the Federal Government, including the Centers for Disease Control and Prevention (CDC), as well as considerations of State and local conditions around NRC facilities. The NRC is monitoring the effects of COVID-19 on NRC-licensed activities as well as actions taken in response to State, local, and site-specific conditions. The NRC is poised to take additional steps as warranted without compromising its public health and safety mission.
NRC Occupancy of Facilities During this reporting period, the NRC continued to operate in a hybrid work environment at all locations, combining telework and in-office staff presence. The guidance for inspection program implementation remains in effect in accordance with memorandum, Implementation of Inspection Programs Following Re-Entry from the Public Health Emergency for the Reactor Safety Program (ML21295A302). The agency continues to closely monitor guidance from the Federal Governments Safer Federal Workforce Taskforce, the CDC, and the Occupational Safety and Health Administration to facilitate a healthy and safe physical workspace.
Licensing and Oversight Items of Interest The NRC staff took steps to identify areas of our regulations that proved challenging during the pandemic, and the areas where temporary flexibilities, such as exemptions, would not compromise the ability of licensees to maintain the safe and secure operation of NRC-licensed facilities. The NRC staff has communicated the processes available to licensees for requesting these flexibilities in a transparent way through public communications, such as teleconferences, webcasts, and letters. In addition, these processes and the approved flexibilities are posted and updated on the NRC public website (https://www.nrc.gov/about-nrc/covid-19/).
The NRC has also developed portions of its website devoted to the regulatory activities taken in response to the COVID-19 pandemic. Specific posts related to nuclear power plant licensees, nuclear materials licensees, and security and emergency preparedness are available to keep the public informed on how the NRC adapted its regulatory approach during the pandemic.
Between January 1 and March 31, 2023, the NRC did not receive any requests for COVID-19-related flexibilities from nuclear materials or nuclear reactor licensees. A complete list of licensing requests approved by the NRC in response to the COVID-19 pandemic is available on the NRC public website at https://www.nrc.gov/about-nrc/covid-19/.
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Regulatory Activities Taken in Response to the COVID-19 Pandemic During the Reporting Period Licensee Type Number of COVID-19 Average Number of Requests Approved During Days to Review the Reporting Period COVID-19 Requests36 Power Reactor 0 N/A Non-Power Reactor 0 N/A Other (e.g., topical reports) 0 N/A Decommissioning of Nuclear 0 N/A Facilities and Uranium Recovery Storage and Transportation of 0 N/A Spent Nuclear Fuel Fuel Cycle Facilities 0 N/A Medical, Industrial and Academic Uses of Nuclear Materials and 0 N/A Agreement States 36 This average is calculated based on the dates the request is received and the review is completed; review time may be longer in cases where a supplement to a request is received after the initial submission date.
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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.37 Number of Location CY 2020 CY 2021 CY 2022 CY 2023 Findings Nationally Total 291 278 399 85 Green 50 61 83 16 White 0 1 2 0 Yellow 0 0 0 0 Red 0 0 0 0 Greater-Than-Green Region I 0 0 0 (GTG) Security 0 Total 50 62 85 16 No. of Units Operating During 2238 2139 2040 20 CY Green 77 69 90 21 White 2 0 1 0 Yellow 0 0 0 0 Red 0 0 0 0 Region II GTG Security 1 0 0 1 Total 80 69 91 22 No. of Units Operating During 33 33 33 3441 CY Green 51 65 89 21 White 0 0 2 0 Yellow 0 0 0 0 Red 0 0 0 0 Region III GTG Security 0 1 1 0 Total 51 66 92 21 No. of Units Operating During 23 2242 22 2143 CY 37 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.
38 The reduction of two units for CY 2020 reflects the permanent shutdown of Pilgrim Nuclear Station on May 31, 2019, and Three Mile Island Unit 1 on September 20, 2019.
39 The reduction of one unit for CY 2021 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 2 on April 30, 2020.
40 The reduction of one unit for CY 2022 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 3 on April 30, 2021.
41 The increase of one unit for CY 2023 reflects Vogtle Unit 3 entering the ROP on August 3, 2022.
42 The reduction of one unit for CY 2021 reflects the permanent shutdown of Duane Arnold on August 10, 2020.
43 The reduction of one unit for CY 2023 reflects the permanent shutdown of Palisades on May 20, 2022.
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Number of Location CY 2020 CY 2021 CY 2022 CY 2023 Findings Green 110 81 130 25 White 0 0 1 1 Yellow 0 0 0 0 Red 0 0 0 0 Region IV GTG Security 0 0 0 0 Total 110 81 131 26 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 U.S. Nuclear Regulatory Commission (NRC) staff issues a final safety evaluation (SE). These totals do not include license amendment requests (LARs), as they are addressed separately in section 3-3. 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 of Percentage of Licensing Licensing Licensing 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 Period44 Milestone Schedule45 Schedule Quarter (Q) 3 fiscal year 136 41 43 100% 100%
(FY) 2022 Q4 FY 2022 124 28 32 100% 81%46 Q1 FY 2023 128 53 36 100% 58%47 44 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.
45 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
46 This percentage is due to a smaller number of actions in the quarter and the disproportionate weight of a Dominion Fleet request involving six actions that required verification of referenced topical reports.
47 This percentage is due to 2 fleet actions involving 11 requests for relief from in-service inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code to extend the period of performance beyond the end of the current 10-year inspection interval (in some cases up to the end of the operating life of the plant). The review of these requests required coordination of over 25 similar relief requests 26
Percentage of Percentage of Licensing Licensing Licensing 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 Period44 Milestone Schedule45 Schedule Q2 FY 2023 130 35 38 99% 90%48 New 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 Period49 Milestone Schedule Schedule Q3 FY 2022 1 1 1 100% 100%
Q4 FY 2022 1 1 1 100% 100%
Q1 FY 2023 2 2 1 100% 100%
Q2 FY 2023 4 4 2 100% 100%
Fuel Facilities Percentage of Percentage of Licensing Licensing Licensing Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Prior Completed Period Inventory During the During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule Q3 FY 2022 6 6 6 100% 100%
Q4 FY 2022 8 8 6 100% 60%50 from multiple licensees, additional time to resolve policy and technical issues, public meetings, and multiple rounds of requests for additional information. The previous report stated that the review of the remaining requests was expected to be completed in Q2 FY 2023. The review is now expected to be completed by Q4 FY 2023 due to additional internal deliberations.
48 There were 5 requests that exceeded the established schedule by 180 days. These requests involved 13 licensing actions requesting relief from in-service inspection requirements of the ASME Boiler and Pressure Vessel Code to extend the period of performance beyond the end of the current 10-year inspection interval (in some cases up to the end of the operating life of the plant). One request was completed in Q2 FY 2023, and the remaining four requests are expected to be completed by Q4 FY 2023.
49 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.
50 Two fuel cycle licensing actions exceeded the established schedule by approximately 1 month due to prioritizing other work.
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Percentage of Percentage of Licensing Licensing Licensing Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Prior Completed Period Inventory During the During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule Q1 FY 2023 4 6 10 100% 60%51 Q2 FY 2023 9 4 4 100% 79%52 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).
Operating Reactors LAR Percentage of Percentage of LARs Reviews LAR Reviews LAR Reviews Submitted Reporting Total Completed Completed Prior Completed During the Period Inventory During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule53 Q3 FY 2022 289 78 93 100% 91%
Q4 FY 2022 269 65 84 100% 93%
Q1 FY 2023 247 74 89 100%54 90%55 Q2 FY 2023 236 76 88 100% 77%56 51 Four out of 10 fuel cycle licensing actions exceeded the established schedule by approximately 1 month due to prioritizing other work.
52 Two fuel cycle licensing actions exceeded the established schedule due in part to delays in receiving information from the applicant and in part due to staff prioritization of other work.
53 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
54 One review of a complex LAR exceeded the 2-year date for issuance of a final SE set in the NRCs generic milestone schedule. As required by Section 102(c)(3) of NEIMA, the NRC submitted a report regarding this LAR to the House Committee on Energy and Commerce and the Senate Committee on Environment and Public Works on August 5, 2022 (ML22217A145 and ML22173A160, respectively). The applicant notified the NRC in October 2022 that its supplement to the LAR is now expected in March 2023. This exceedance of a generic milestone schedule will be reflected in the percentage for the quarter in which the final SE is issued.
55 One review of an LAR that proposed two first-of-a-kind methodologies exceeded the established schedule by 180 days. The NRC staff identified complex technical issues with the application that resulted in requests for additional information, multiple public meetings, and the licensee modifying its request. The staff expects to complete its review in May 2023.
56 Reviews for 2 LARs, involving 14 actions, exceeded the established schedule, one by approximately 3.5 months and the other by approximately 3 months, due to time needed for Commission consideration and approval prior to issuance.
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New Reactors LAR Percentage of Percentage of LARs Reviews LAR Reviews LAR Reviews Submitted Reporting Total Completed Completed Prior Completed During the Period Inventory During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule Q3 FY 2022 0 0 0 N/A N/A Q4 FY 2022 1 1 0 N/A N/A Q1 FY 2023 0 0 1 100% 100%
Q2 FY 2023 2 4 2 100% 100%
Fuel Facilities Percentage of LAR Percentage of LARs LAR Reviews Reviews LAR Reviews Submitted Completed Reporting Total Completed Completed Prior During the Prior to the Period Inventory During the to the Reporting Generic Reporting Established Period Milestone Period Schedule Schedule Q3 FY 2022 10 4 5 100% 60%57 Q4 FY 2022 7 1 4 100% 75%58 Q1 FY 2023 9 3 1 100% 100%
Q2 FY 2023 9 4 4 100% 75%59 3-4 Research Activities60 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:
Extravasation Dosimetry Modeling and Medical Event Regulatory Guide Support (NMSS-2023-003)
This work supports reporting requirements to the NRC for medical events where a licensee administers byproduct material for a medical treatment Importance to that exceeds a safety threshold. The Commission directed the NRC staff the NRC to amend the NRCs regulations to include certain nuclear medicine Mission injection extravasations as reportable medical events and to create guidance regarding medical event reporting.
57 Reviews for two LARs exceeded the established schedule, one by 5 days and the other by 7 days, due to prioritizing other work.
58 One review of an LAR exceeded the established schedule by 26 days due to prioritizing other work.
59 One review of an LAR exceeded the established schedule due in part to delays in receiving information from the applicant and in part due to staff prioritization of other work.
60 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.
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Consistent with the Commission direction, the staff plans to develop a dosimetry model to characterize safety significant extravasations and incorporate this dosimetry model into the NRCs VARSKIN+ computer Planned code as part of this rulemaking effort. The Commission directed the staff Activities to create guidance that comprehensively explains and illustrates the medical event reporting criteria for evaluating and reporting all medical events, including but not limited to extravasation events.
Requesting Nuclear Materials Users Business Line Estimated FY 2027 Completion Estimate of Total Research 1 Full-Time Equivalent (FTE) and $1.25M over a 4-year period Resources Licensing Support for Advanced Reactors (NRR-2023-001)
The Office of Nuclear Reactor Regulation (NRR) is seeking support to perform confirmatory analyses and licensing review activities related to Importance to incoming first-of-a-kind advanced reactor applications. These incoming the NRC applications will require that NRR staff have the technical resources to Mission better understand the technology presented to inform their regulatory safety determinations.
RES staff will provide technical support for pre-licensing and licensing reviews of advanced reactor submittals in the areas of: (1) materials, component performance, performance monitoring, structural, and seismic Planned analysis; (2) systems, fuels, source term, severe accident, consequence, Activities and radiation protection analysis; and (3) probabilistic risk assessment, external hazards, fire risk, and human factors analysis. The support will include reviews of technical white papers and topical reports and analytical assessment of proposed methodologies and approaches.
Requesting New Reactors Business Line Estimated FY 2026 Completion Estimate of Total Research 3 FTE over a 3-year period Resources Environmental Materials Degradation for Reactor Coolant Pressure Boundary Components (NRR-2023-003)
This user need request develops data and analyses to support regulatory treatment of the generic aspects of flaw analysis, including probabilistic analysis support, and primary water stress corrosion cracking (PWSCC)
Importance to identified at several domestic and overseas plants. The deliverables will the NRC provide NRR staff with information needed to enhance the evaluation of Mission industry generic assessments and licensee plant-specific relief request activities, and to support long-term regulatory actions that provide reasonable assurance of public health and safety. PWSCC in nickel-base alloy primary pressure boundary components is a significant safety 30
concern due to the potential for reactor pressure boundary loss of structural integrity and the associated potential of boric acid corrosion of low alloy steels. Also, recent operating experience and international research have raised concerns for aging effects on Ni-alloys and thermal fatigue effects on stainless steel materials in the reactor coolant pressure boundary.
The activities planned include PWSCC initiation testing of Alloy 600/182 Planned and Alloy 690/52/152, evaluation of long-term aging of Alloy 690/52/152, Activities and assessments of operating experience and research to address thermal aging of stainless steel weldments and thermal fatigue.
Requesting Operating Reactors Business Line Estimated FY 2028 Completion Estimate of Total Research 4 FTE and $3.71M over a 5-year period Resources Summary of Completed Research Projects61 During the reporting period, the following research projects were completed:
Research Assistance Request NMSS-2019-003, Development a Risk Tool for Design Reviews of Storage Cask and Transportation Packages (ML19274C788).
RES assisted NMSS by developing tools to use risk insights to inform the use of resources and focus reviewer and inspector resources on items of Importance to higher risk significance. The RES support was used to develop tools to the NRC risk-inform dry cask storage licensing and oversight activities.
Mission Development of these tools enhanced the NRC review process in these areas.
This project resulted in issuance of two interim reports and one final report (INL/EXT-20-58896, Development of Dry Cask Risk Tools, Rev. 1, ML22353A565). The report presents a tool that allows NRC reviewers to efficiently conduct a preliminary risk determination of typical Research LARs, such as dry storage system design changes, changes in the Results or approved spent nuclear fuel content or evaluation methods, or editorial Findings changes. Further, the tool provides the user with a rationale behind the risk estimation of each specific change. The risk estimation could be used to define specific, actionable review recommendations for each individual LAR.
Duration of the 3 years Project Estimate of Total Research 0.4 FTE and $263K over the 3-year period Resources 61 The research project resources are estimates of staff hours and program support costs based on inspection of project records, including staffing plans and contract spending plans.
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3-5 Fees Billed The tables below provide information on Part 170 fees billed for each fee class. For each fee class, the NRC staff compared the fees billed to the receipts estimated in the annual fee rule.62 FY 2023 Part 170 Total Part 170 -
Receipts Estimated Part 170 Billed in Q2 Fee Class Billed in FY 2023
- Proposed Fee FY 2023 ($M)
($M)
Rule ($M)
Fuel Facilities $9.0 $2.9 $4.2 Generic
$3.2 $0.6 $0.8 Decommissioning Materials Users63 $1.2 $0.2 $0.564 Operating Power
$160.2 $53.2 $75.0 Reactors Non-Power Production or
$5.8 $1.9 $2.9 Utilization Facilities Spent Fuel Storage / Reactor $11.7 $4.8 $6.8 Decommissioning Rare Earth $0.3 $0.1 $0.1 Transportation $3.5 $0.8 $1.2 Uranium
$0.6 $0.1 $0.2 Recovery Significant Ongoing Licensing Actions The following table includes a comparison of the fees billed to projected resources for subsequent license renewal application reviews, the SHINE Medical Technologies, LLC (SHINE) operating license application review, and the Kairos Hermes construction permit application review.
62 The FY 2023 Proposed Fee Rule estimated collections are being used until the FY 2023 Final Fee Rule is published. The FY 2023 Proposed Fee Rule was published in the Federal Register (FR) on March 3, 2023 (88 FR 13357).
63 Materials UsersBilled as flat fee applications and included in the estimates and billed.
64 Total Part 170 - Billed in FY 2023 ($M) for Materials Users may not add due to rounding: $0.267M reported in Q1 plus $0.234M in Q2 totals $0.501M.
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Projected Fees Billed Docket Project Name Resources to Date
($M)65 ($M)66 Point Beach Units 1 and 2 Point Beach Units 1 and 2 Subsequent License Renewal $5.067 $3.5 05000266/05000301 Application Safety Review Point Beach Units 1 and 2 Point Beach Units 1 and 2 Subsequent License Renewal
$1.4 $1.6 05000266/05000301 Application Environmental Review North Anna Units 1 and 2 North Anna Units 1 and 2 Subsequent License Renewal $5.068 $3.8 05000338/05000339 Application Safety Review North Anna Units 1 and 2 North Anna Units 1 and 2 Subsequent License Renewal
$1.4 $1.5 05000338/05000339 Application Environmental Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 05000269/05000270/ Subsequent License Renewal $5.069 $3.5 05000287 Application Safety Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 Subsequent License Renewal 05000269/05000270/ $1.4 $0.7 Application Environmental 05000287 Review SHINE Medical Isotope SHINE Medical Production Facility Operating Technologies, LLC License Application Review $6.570 $7.471 05000608 Safety and Environmental Reviews St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 Subsequent License Renewal $5.072 $3.7 05000335/05000389 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 -
Kairos Hermes 05007513 Construction Permit - Safety $5.573 $3.4 and Environmental Reviews 65 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.
66 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 January, February, and March would be invoiced to the licensee/applicant in April. Therefore, the total billed amounts listed in Table 3-5 reflect costs for NRC work performed through December 2022.
67 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.
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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 only 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 Inventory of Total Number Total Number Number of Open RAIs of RAIs of RAIs Type of Facility or Activity RAIs as of the Issued in Responded to Type Closed in End of Reporting in Reporting Reporting Reporting Period Period Period74 Period Operating Reactors 169 56 39 72 Non-Power Production and 165 1 5 283 Utilization Facilities75 Design Certifications for N/A N/A N/A N/A New Reactors76 Early Site Permits for New N/A N/A N/A N/A Reactors77 Combined Licenses for 0 0 0 0 New Reactors 68 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.
69 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.
70 The update to the projected resource estimate for this application review was provided to SHINE by letter dated February 17, 2022 (ML22047A179).
71 Increases in the scope of the review related to the phased construction approach, unexpected design modifications, and novel technical and licensing challenges for this first-of-a-kind facility resulted in increased resource expenditures relative to the estimate.
72 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.
73 The projected resource estimate was provided to Kairos Power LLC by letter dated December 15, 2021 (ML21343A214).
74 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.
75 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, including the ongoing review of the SHINE operating license application.
76 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.
77 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.
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Total Total Inventory of Total Number Total Number Number of Open RAIs of RAIs of RAIs Type of Facility or Activity RAIs as of the Issued in Responded to Type Closed in End of Reporting in Reporting Reporting Reporting Period Period Period74 Period Construction Permits for New Reactors or 0 0 0 0 Non-Power Production and Utilization Facilities Fuel Facilities 40 1 15 28 Power Reactor 88 1578 19 10 Decommissioning Research and Test Reactor 12 0 0 0 Decommissioning Spent Fuel 744 90 22 51 Materials 0 0 0 0 Pre-Application Activities for 0 0 4 4 Advanced Reactors 78 This total includes the 15 RAIs issued to Ft. Calhoun on December 30, 2022, which the NRC staff inadvertently excluded from the previous report.
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3-7 Workforce Development and Management FY 2023 Staffing by Office79 Delta (Q2 End of Year FTE FTE FTE FTE Delta (EOY FTE (EOY)80 FY 2023 Utilization Utilization Utilization Utilization Utilization -
Utilization - Projection w/
Budget 01/01/23 - 01/29/23 - 02/26/23 - as of FY 2023 FY 2023 Personnel 01/28/23 02/25/23 03/25/23 03/25/23 Budget)
Budget) Actions Totals 2888.1 206.7 206.2 206.9 1349.2 -1538.9 2760.7 -127.4 COMM 42.0 2.6 2.6 2.6 16.3 -25.7 34.4 -7.6 OIG 73.0 4.0 3.9 3.8 26.1 -46.9 54.5 -18.5 Totals Other 2773.1 200.0 199.8 200.5 1306.8 -1466.3 2671.8 -101.3 Offices OCFO 93.0 6.8 6.9 7.0 44.2 -48.8 90.4 -2.6 OGC 90.4 7.0 6.8 7.0 45.6 -44.8 89.8 -0.6 OCA 10.0 0.8 0.8 0.9 5.1 -4.9 11.1 1.1 OCAA 7.0 0.4 0.4 0.4 2.9 -4.1 6.0 -1.0 OPA 13.0 1.0 1.0 1.0 6.7 -6.3 13.9 0.9 SECY 17.0 1.2 1.3 1.3 8.1 -8.9 16.5 -0.5 OIP 35.0 2.4 2.4 2.7 16.0 -19.0 33.7 -1.3 ASLBP 23.3 1.5 1.4 1.5 9.6 -13.7 19.8 -3.5 ACRS 25.1 1.7 1.8 1.9 11.6 -13.5 24.6 -0.5 OEDO 26.0 1.7 1.7 2.0 12.4 -13.6 25.4 -0.6 NRR 568.0 38.4 38.5 38.6 249.9 -318.1 523.3 -44.7 NMSS 310.8 22.0 22.2 22.6 143.1 -167.7 295.5 -15.3 RES 202.1 14.0 13.6 13.6 91.0 -111.1 188.5 -13.6 NSIR 155.6 11.3 11.0 10.3 71.7 -83.9 146.7 -8.9 R-I 169.8 12.5 12.5 12.4 81.9 -87.9 166.6 -3.2 R-II 192.7 15.8 15.7 15.9 104.4 -88.3 206.8 14.1 R-III 167.1 12.4 12.3 12.4 82.3 -84.8 165.0 -2.1 R-IV 162.9 12.9 12.9 12.5 83.9 -79.0 167.0 4.1 OE 31.3 2.2 2.2 2.2 14.5 -16.8 29.2 -2.1 OI 35.0 2.3 2.3 2.4 15.1 -19.9 31.1 -3.9 OCIO 172.0 11.9 11.8 11.9 78.4 -93.6 159.3 -12.7 ADM 117.0 8.8 8.9 9.1 58.7 -58.3 118.6 1.6 SBCR 13.0 1.0 1.0 1.0 6.5 -6.5 13.4 0.4 OCHCO 133.0 10.0 9.9 9.9 62.3 -70.7 127.8 -5.2 CSU 3.0 0.2 0.2 0.2 0.9 -2.1 1.9 -1.1 3-8 Inspection Activities The table below shows the average number of hours of direct inspection per plant in CY 2023.
79 Some numbers might not add due to rounding.
80 Based on FTE utilization as of March 25, 2023.
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Average ROP Direct Inspection Hours Column 1 of Column 2 of Column 3 of Column 4 of Nationwide Per ROP Action ROP Action ROP Action ROP Action Plant (unit)
Matrix Matrix Matrix Matrix No Plants in No Plants in 356 Hours 352 Hours 423 Hours81 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 2022 (Hours) CY 2023 (Hours)
- i. Baseline Inspection 213,363 48,126 ii. Plant-Specific Inspection 7,946 1,500 iii. Generic Safety Issue Inspections 83 0 iv. Performance Assessment 3,062 1,643
- v. Other Activities 97,511 21,452 vi. Total Staff Effort 321,964 72,721 vii. Total Staff Effort Per Operating Site 5,85482 1,32283 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.84 81 Callaway Plant was in Column 2 of the ROP Action Matrix (ROP Action Matrix) in Q1 FY 2022, and moved to Column 1 on May 6, 2022 (ML22123A227). Davis-Besse Nuclear Power Station, Unit 1 moved to Column 2 in Q1 FY 2022 (ML22055B117). Waterford Steam Electric Station, Unit 3 moved to Column 2 in Q3 FY 2022 (ML22241A143). Quad Cities Nuclear Power Station, Unit 2 moved to Column 2 in Q4 FY 2022 (ML22313A150).
Peach Bottom Atomic Power Station, Unit 2 moved to Column 2 in Q4 FY 2022 (ML22314A098). Calvert Cliffs Nuclear Power Plant, Unit 1 moved to Column 2 in Q4 FY 2022 (ML22314A100). Virgil C. Summer Nuclear Station moved to Column 2 in Q2 FY 2022 (ML22287A184).
82 Total staff effort is divided by 55 sites for CY 2022, due to Indian Point Unit 3 permanently ceasing operations in April 2021.
83 Total staff effort is divided by 55 sites for CY 2023, due to Palisades permanently ceasing operations in June 2022 and Vogtle Unit 3 transitioning to the ROP in August 2022.
84 By letter dated September 20, 2022 (ML22263A440), Constellation Energy Generation, LLC provided the NRC with forward fitting concerns associated with the NRC staffs communications during review of a requested licensing action for a proposed alternative. By letter dated February 8, 2023 (ML22287A069), the NRC staff responded that the staff action proposed in a communication with the licensee would not constitute a forward fit.
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