ML23191A892

From kanterella
Jump to navigation Jump to search
Enclosure - Status Report on the Licensing Activities and Regulatory Duties of the U.S. NRC for the Reporting Period of April 1 - June 20 2023
ML23191A892
Person / Time
Issue date: 08/14/2023
From:
NRC/Chairman
To:
Shared Package
ML23191A890 List:
References
CORR-23-0068
Download: ML23191A892 (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, 2023, through June 30, 2023 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 2023 vs. Budgeted FTE................................

1-4 Budget Authority, FTE Utilization, and Fees............................................................................. - 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 Licensing Reviews....................................................................................

2-8 Reactor Oversight Process.....................................................................................................

2-9 Backfit......................................................................................................................................

2-10 Risk-informed Activities...........................................................................................................

2-11 Coronavirus Disease (COVID-19)........................................................................................... - 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......................................................................................................................................

- High Level Summary 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act 1, 2, 3 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.

3 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.

110% ~-----------------------

100% +-----~ --------------:.:----:--:::a-------,--

CI ti C,2 90% ~ ~~l.,,-~41t6-.-------:-:;t,:s.;i~ '.=""-~~~ --\\

t) t)

~ CJ ~

80% -t----"iiF,-.,------ll---\\,------'---_-:LIi-...

==-~:,Y--_..--ll!~ ----,,~ ---~

tl'CGI Q. IP fli

l ]1 C 70% +----l---+--+--- --"'IIJ---------'-----'-----'--~-

Gl 0. QI

.: E :i 60% 'l"=""'-------1--* - ------------ -+--

..\\,;<-

!\\--

0 'C e u ~

so% +------1---------------1--+-----

1= D O IP -;/!. en 40% +-------+--"-------------1-if------

CI O cu 0

~ ii 30% +------------------- -----

<t 20% +------------------------

10% +-~~-~~~-~~~-~~~-~~~-~~~~

Operating Reactors Established Schedule

-+ - New Reactors Established Schedule

_. - Fuel Facilities Established Schedule 1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete 4

4 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.

0%

10%

20%

30%

40%

50%

60%

70%

80%

90%

0 20000 40000 60000 80000 100000 120000 140000 160000 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cumulative Percent of Planned Direct ROP Inspection Hours Complete Direct ROP Inspection Hours Reactor Oversight Process Inspection Hours and Percent Complete Calendar Year (CY) 2022 Total Direct ROP Inspection Hours CY 2023 Total Direct ROP Inspection Hours Percent Complete of Total CY 2023 Planned Direct ROP Inspection Hours Percent Complete of Total CY 2022 Planned Direct ROP Inspection Hours c::::::J 0

~

1-3 Full-time Equivalent (FTE) at the End of Q3 FY 2023 vs. Budgeted FTE5 1-4 Budget Authority, FTE Utilization, and Fees NRC FY 2023 Budget Authority June 30, 2023 (Dollars in Thousands)

Fund Sources FY 2023 Budget5 Percent Obligated Percent Expended Advanced Reactors

$27,406 44%

32%

Commission Funds

$13,036 49%

48%

Fee-Based Funds

$873,601 71%

55%

General Funds6

$1,178 32%

32%

International Activities

$19,024 61%

50%

University Nuclear Leadership Program

$36,409 46%

1%

Official Representation

$43 52%

50%

Total

$970,697 69%

52%

NRC Control Points FY 2023 Budget Percent Obligated Percent Expended Nuclear Reactor Safety

$499,748 65%

56%

Nuclear Materials and Waste Safety

$113,177 67%

56%

Decommissioning and Low-Level Waste

$24,505 71%

64%

Corporate Support

$296,857 77%

48%

5 FY 2023 Budget reflects the enactment of the Consolidated Appropriations Act, 2023 and includes the enacted budget and carryover allocated.

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

0.0 100.0 200.0 300.0 400.0 500.0 600.0 Other Office of General Counsel Office of the Chief Information Officer Office of the Chief Human Capital Officer Office of the Chief Financial Officer Office of Administration Region IV Region III Region II Region I Office of Nuclear Security and Incident Response Office of Nuclear Regulatory Research Office of Nuclear Material Safety and Safeguards Office of Nuclear Reactor Regulation FTE Budgeted FTE On Board FTE NRC Control Points FY 2023 Budget Percent Obligated Percent Expended University Nuclear Leadership Program7

$36,409 46%

1%

Total8

$970,697 69%

52%

FTE Utilization, Hiring, and Attrition Total Year-to-Date (YTD) FTE Utilization Projected End of Year FTE Total Utilization Q3 Hiring Q3 Attrition YTD Hiring YTD Attrition 1976.2 2724.6 58 40 165 145 FY 2023 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 2021 FY 2022 FY 2023 Q1-Q3

$183.9

$190.7

$139.2 7 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.

8 Numbers might not add correctly due to rounding.

vi "C

C:

5!

I 0 -=

I-C:

~

~

0 e.

E

I 0

E

<t

$800,000

$700,000

$600,000

$500,000

$400,000

$300,000

$200,000

$100,000 so 10-0ct 11~ov 12-0ec 01'-'an 02~eb 03~r 04-Apr O~y OGun 07'-'ul 08-Aug 09-Sep 2022 202.2 2022 2023 2023 2023 2023 2023 2023 2023 2023 2023 Total Estimated

$160,033 $162,478 $164,TT1 $363,691 $366,141 $369,245 $552,115 $555,206 $558,185 $605,839 $740,517 $743,563 Total Actual Billed

$159,893 $162,235 $164,650 $362,223 $364,734 $367,984 $548,544 $551,580 $554,438 Total Actual Collected $76,673 $161,116 $164,008 $268,265 $361,856 $365,727 $452,532 $544,480 $549,995

- 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; (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) 3 Fiscal Year (FY) 2023)

Transformation Activities Projected Completion Date Completion Date Conducted a Jam, an agencywide collaborative online discussion, on how to continue to best prepare for the future, focusing on sustaining transformational progress.

06/30/23 06/15/23 Conducted presentations for senior leaders and staff on results of the: (1) follow-on survey of external stakeholder views on NRC transformation activities; and (2) full reassessment of the agencys cultural norms and behaviors to ensure the agency is sustaining transformational progress.

05/31/23 06/29/239 9 This activity was completed on June 29, 2023, rather than the projected completion date of May 31, 2023, due to additional supervisor and staff briefings conducted on this topic to provide a full understanding of the survey results and path forward.

Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Transformation Activities Projected Completion Date 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 sustaining transformational progress.

09/29/23 Initiate actions based on the Jam analysis which will help sustain transformational progress and enhance organizational health and performance.

12/29/23 Update public webpage on Transformation related to the results of the Jam.

12/29/23 2-2 Workforce Development and Management Each FY, 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 (Q3 FY 2023)

Workforce Development and Management Activities Projected Completion Date Completion Date Onboarded 74 Summer 2023 Student Interns.

06/30/23 06/20/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Workforce Development and Management Activities Projected Completion Date Conduct an evaluation of the SWP process for effectiveness and efficiency improvements as identified in the NRCs Annual Evaluation Plan for FY 2023.

09/29/23 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 received one additional ATF fuel vendor topical report, which is currently undergoing an acceptance review. The report discusses fuel evaluation methods and associated methodology for increased enrichment applications (ML23180A306). In April 2023, the NRC staff completed its review of a topical report for a cladding to support use of higher burnup fuel (ML23111A096). In June 2023, the NRC staff completed its review of a topical report for codes and methodology supporting increased enrichment applications (ML23167A002). The NRC staff is on track to complete review of the seven 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 operating reactor license amendment requests (LARs) were submitted during this reporting period.

On May 17, 2023, the NRC received a fuel fabrication facility LAR to extend currently approved methodology for determining the minimum margin of sub-criticality to include enrichments up to 20 weight-percent uranium-235 (ML23137A393). The NRC expects to receive additional LARs in FY 2024 from enrichment facilities and fuel fabrication facilities to directly support increased enrichment above 5 weight-percent uranium-235.

Activities Planned and Completed for the Reporting Period (Q3 FY 2023)

ATF Activities Projected Completion Date Completion Date Issued a Regulatory Issue Summary (RIS) entitled Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels (ML23123A166). This RIS requested industry provide timelines for the submission of licensing actions to support ATF deployment, to help determine future planning and resource allocation.

06/30/23 06/26/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected ATF Activities Projected Completion Date Issue for public comment the draft report, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup, which will generically evaluate the environmental impacts of the uranium fuel cycle, transportation of ATF and waste, and the decommissioning of a light water reactor utilizing ATF for up to 8 weight-percent uranium-235 and up to 80 gigawatt-days per metric ton uranium.

09/01/23 Projected ATF Activities Projected Completion Date 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 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.

09/15/23 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 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.

09/23/23 Hold a fourth Higher Burnup Workshop to discuss the state of development of higher burnup and increased enrichment technical and regulatory issues. The workshop will also provide a public forum for discussions between the NRC, industry, and other stakeholders.

09/29/23 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 for 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 June 28, 2023, FPL asked the NRC staff to temporarily suspend the review of the Turkey Point LARs (ML23179A141) for an unspecified period of time. Due to unforeseen material supply issues, FPL plans to revise the LARs and resubmit them to the NRC.

On September 26, 2022, 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 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 has changed the planned installation of the digital modification from Unit 1 in Calendar Year (CY) 2024 to Unit 2 in CY 2025 (ML23143A342). The changes by Constellation are due to design refinement iterations with the digital system original equipment manufacturer. As a result of the changes by Constellation, the NRC staff revised its review schedule, including the planned completion date for the review.

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 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 the need for 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). The NRC staff is assessing options for development of implementing guidance by May 25, 2024.

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 (Q3 FY 2023)

Digital I&C Activities Projected Completion Date Completion Date Hold a public information meeting, including a question-and-answer session, with stakeholders concerning the NRC staffs plans to develop implementing guidance for instrumentation and controls common cause failures (ML23181A068).

08/31/2310 07/11/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Digital I&C Activities Projected Completion Date DG-1374 (Revision 4 to RG 1.152, Criteria for Use of Computers in Safety Systems of Nuclear Power Plants)

Publish Revision 4 to RG 1.152.

07/28/23 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 on Vogtle Unit 3 is complete. In March 2023, Vogtle Unit 3 began generating power as part of the initial power ascension testing required before commencing commercial operations. SNC projects the start of commercial operations for Vogtle Unit 3 in Q3 CY 2023.11 10 This meeting was not identified as a projected activity in the previous report due to an error.

11 On June 16, 2023, Georgia Power Co. announced that Vogtle Unit 3 is projected to begin commercial operations as early as July 2023 and Unit 4 is projected to begin between December 2023 and March 2024.

In Q3 CY 2023, Vogtle Unit 4 remained under the Construction Reactor Oversight Process (cROP). The NRC continued to perform Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) inspections in accordance with the cROP and review ITAAC closure notifications for Vogtle Unit 4. SNC projects the start of commercial operations for Vogtle Unit 4 between Q4 CY 2023 and Q1 CY 2024.

Activities Planned and Completed for the Reporting Period (Q3 FY 2023)

Vogtle Electric Generating Plant Units 3 and 4 Activities Projected Completion Date Completion Date Conducted a pre-submittal meeting on a proposed LAR related to the timing of Unit 4 Technical Specifications effectiveness prior to initial criticality (ML23100A022).

05/31/23 04/13/23 Authorized the use of an alternative to the in-service inspection requirements for steam generator nozzle to reactor coolant pump casing welds for Vogtle Units 3 and 4 (VEGP 3&4-ISI1-ALT-17)

(ML23095A284).

08/04/23 04/14/23 Conducted a pre-submittal meeting on a proposed LAR for an exception to RG 1.163 for Vogtle Unit 3 (ML23101A120).

N/A12 04/18/23 Conducted a public meeting to discuss the NRCs Vogtle Readiness Group (VRG) activities (ML23095A264).

N/A13 04/20/23 Granted a LAR for Technical Specification Surveillance Requirement 3.0.3 for Never-Performed Surveillances for Vogtle Units 3 and 4 (ML23072A186).

01/10/2414 04/26/23 Conducted a public meeting to discuss LAR 23-006, More Restrictive Action for Technical Specification 3.1.9, for Vogtle Units 3 and 4 (ML23115A330).

N/A15 04/27/23 Authorized the use of Code Case N-648-2 for in-service inspection of the reactor vessel nozzle inner radius sections for Vogtle Units 3 and 4 (VEGP 3&4-ISI1-ALT-18) (ML23109A067).

08/04/23 05/04/23 Conducted a public meeting to discuss NRC staffs acceptance review of LAR 23-006, More Restrictive Action for Technical Specification 3.1.9, for Vogtle Units 3 and 4 (ML23129A798).

N/A16 05/11/23 12 This meeting was not identified as a projected activity in the previous report because the meeting request was submitted after the previous reports issuance.

13 This meeting was not identified as a projected activity in the previous report because the VRG public meeting was added to the annual assessment meeting for Vogtle Units 1-4, which was also scheduled for April 20, 2023, after the previous reports issuance.

14 The LAR was originally scheduled for completion in Q2 FY 2024; however, the NRC staff was able to complete the review and issue the LAR ahead of schedule.

15, 16, 17, 18 These meetings were not identified as projected activities in the previous report because the meeting requests were submitted after the previous reports issuance.

Vogtle Electric Generating Plant Units 3 and 4 Activities Projected Completion Date Completion Date Conducted a public meeting to discuss the NRCs late filed allegations process for Vogtle Unit 4 (ML23129A801).

N/A17 05/25/23 Conducted a public meeting to discuss the NRC staffs acceptance review of LAR 23-003, Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources, for Vogtle Units 3 and 4 (ML23139A239).

N/A18 05/25/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Projected Completion Date Complete the review of a LAR to revise the timing of Vogtle Unit 4 Technical Specifications effectiveness prior to initial criticality.

07/19/23 Conduct a pre-submittal meeting on a proposed request for exemptions from Tier 1 and Tier 2* requirements for Vogtle Units 3 and 4.

08/31/23 If the NRC determines that all acceptance criteria in the ITAAC for Vogtle Unit 4 are met, issue the finding that all acceptance criteria contained in the license are met in accordance with 10 CFR 52.103(g). After this finding, the licensee may operate the facility in accordance with the license.

08/31/23 Issue a letter regarding Vogtle Unit 4s transition to the operating reactor assessment program.

08/31/23 Conduct a pre-submittal meeting on a draft LAR to revise Technical Specification 3.7.6 for Vogtle Units 3 and 4.

09/30/23 Complete the review of a LAR to adopt WCAP-17661-P-A as part of the overall Southern Nuclear fleet-wide revision to Technical Specifications.

10/14/23 Issue a lessons learned summary report on Part 52 construction oversight for Vogtle Unit 3.

12/30/23 A COL allows a licensee to construct a plant and to operate it once construction is complete if the NRC determines that certain standards identified in the COL are met. These standards are called ITAAC. After this NRC finding, the licensee may operate the facility in accordance with the license. 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/how-we-regulate/oversight/itaac.html.

Vogtle Unit 4 Summary of ITAAC Inspections Completed (Q3 FY 2023)

Unit Number of ITAAC Remaining Requiring Inspection Total Inspections Completed19 ITAAC Inspected20 ITAAC Inspections Closed21 Vogtle 4 44 67 32 33 ITAAC Reviews Completed for the Reporting Period (Q3 FY 2023)22 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 2.2.01.11b 03/29/23 04/05/23 Vogtle 4 3.3.00.14 03/17/23 04/06/23 Vogtle 4 2.2.02.02a 04/03/23 04/10/23 Vogtle 4 2.2.01.07.ii 04/21/23 04/24/23 Vogtle 4 2.5.04.03 04/21/23 04/24/23 Vogtle 4 2.2.01.09 04/21/23 04/25/23 Vogtle 4 2.3.04.02.ii 04/26/23 04/27/23 Vogtle 4 2.5.02.08a.ii 04/13/23 04/27/23 Vogtle 4 2.5.02.09d 04/13/23 04/27/23 Vogtle 4 2.4.01.02 04/28/23 05/02/23 Vogtle 4 2.6.06.01.i 04/27/23 05/03/23 Vogtle 4 2.1.02.14 04/28/23 05/04/23 Vogtle 4 2.2.03.11a.i 05/05/23 05/08/23 Vogtle 4 2.2.02.01 05/08/23 05/09/23 Vogtle 4 2.3.03.04 05/04/23 05/10/23 Vogtle 4 2.1.02.08b 05/05/23 05/11/23 Vogtle 4 2.1.02.11a.ii 04/13/23 05/11/23 Vogtle 4 2.3.06.11a 05/05/23 05/11/23 Vogtle 4 3.2.00.01e 04/27/23 05/11/23 Vogtle 4 2.3.07.02a 05/11/23 05/12/23 Vogtle 4 2.2.05.02a 05/12/23 05/15/23 Vogtle 4 2.2.01.02a 05/11/23 05/16/23 19 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).

20 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.

21 ITAAC Inspection Closed refers to the number of ITAAC for which all associated inspections have been completed during the reporting period.

22 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.

Unit ITAAC No.

Received Date Approval Date Vogtle 4 2.3.13.08 05/12/23 05/16/23 Vogtle 4 2.3.06.09b.ii 05/12/23 05/16/23 Vogtle 4 2.2.02.05a.i 05/13/23 05/17/23 Vogtle 4 2.1.02.11a.i 05/10/23 05/18/23 Vogtle 4 2.2.03.11b.i 05/05/23 05/18/23 Vogtle 4 2.1.02.11b.i 05/09/23 05/19/23 Vogtle 4 2.1.02.12a.iii 05/11/23 05/22/23 Vogtle 4 2.5.02.06a.i 05/15/23 05/22/23 Vogtle 4 2.3.01.03.ii 05/19/23 05/23/23 Vogtle 4 2.5.05.04 05/19/23 05/23/23 Vogtle 4 3.2.00.07 05/20/23 05/23/23 Vogtle 4 2.2.03.01 05/23/23 05/24/23 Vogtle 4 2.5.02.08b.ii 05/08/23 05/24/23 Vogtle 4 2.3.02.08a.i 05/25/23 05/25/23 Vogtle 4 3.3.00.07d.ii.b 05/22/23 05/26/23 Vogtle 4 3.3.00.07c.i.a 05/20/23 05/28/23 Vogtle 4 3.3.00.02a.i.a 05/19/23 05/30/23 Vogtle 4 2.2.05.09c 05/12/23 05/30/23 Vogtle 4 2.3.09.03.ii 05/30/23 05/31/23 Vogtle 4 2.5.03.02 05/30/23 05/31/23 Vogtle 4 2.1.03.13 05/18/23 06/01/23 Vogtle 4 2.2.03.08c.vii 05/26/23 06/01/23 Vogtle 4 E.3.9.01.01.01 05/24/23 06/01/23 Vogtle 4 2.2.03.08c.x 05/23/23 06/02/23 Vogtle 4 2.2.03.08b.01 05/23/23 06/04/23 Vogtle 4 2.2.01.11a.iii 05/22/23 06/05/23 Vogtle 4 3.3.00.05b 06/05/23 06/07/23 Vogtle 4 2.5.02.02.i 05/12/23 06/08/23 Vogtle 4 3.5.00.01.i 05/31/23 06/08/23 Vogtle 4 2.2.03.08c.xiii 06/08/23 06/09/23 Vogtle 4 3.2.00.09 06/07/23 06/12/23 Vogtle 4 2.7.04.03 06/09/23 06/12/23 Vogtle 4 C.2.6.09.06 05/24/23 06/13/23 Vogtle 4 C.2.6.09.09 05/24/23 06/13/23 Vogtle 4 C.2.6.09.02 05/26/23 06/13/23 Vogtle 4 C.2.6.09.03a 05/31/23 06/13/23 Vogtle 4 2.3.05.02.i 06/13/23 06/14/23 Vogtle 4 E.3.9.05.01.03 06/14/23 06/15/23 Vogtle 4 2.2.02.07f.i 06/14/23 06/15/23 Vogtle 4 3.1.00.03 06/13/23 06/16/23 Vogtle 4 E.3.9.03.00.01 06/15/23 06/16/23 Vogtle 4 2.3.29.02 06/15/23 06/16/23 Vogtle 4 2.2.01.08 06/13/23 06/20/23 Unit ITAAC No.

Received Date Approval Date Vogtle 4 2.1.03.12 06/15/23 06/20/23 Vogtle 4 2.2.03.08c.viii 06/15/23 06/20/23 Vogtle 4 2.2.03.08c.ix 06/16/23 06/20/23 Vogtle 4 E.3.9.05.02.02 06/16/23 06/21/23 Vogtle 4 E.3.9.03.00.02 06/16/23 06/21/23 Vogtle 4 2.3.03.03c 06/17/23 06/21/23 Vogtle 4 E.3.9.07.01.02 06/16/23 06/22/23 Vogtle 4 2.3.10.05a.i 06/20/23 06/22/23 Vogtle 4 2.2.02.07b.i 06/16/23 06/23/23 Vogtle 4 2.3.19.02a 06/24/23 06/26/23 Vogtle 4 2.6.09.06 06/24/23 06/28/23 Vogtle 4 2.6.03.04i 06/17/23 06/29/23 Vogtle Units 3 and 4 LAR Reviews Completed (Q3 FY 2023)

Number of LAR Reviews Forecast to be Completed in the Reporting Period Number of LAR Reviews that Were Completed in the Reporting Period 0

123 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.24 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)

(ML21162A093), to the Commission for its consideration. Once the SRM is issued the staff will revise the draft proposed rule to reflect Commission direction and then issue the resulting proposed rule 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 to establish a risk-informed, performance-based, and technology-inclusive regulatory framework for commercial nuclear plants is on target to be completed significantly in advance of the Nuclear Energy Innovation and Modernization Act (NEIMA) required deadline of December 31, 2027.

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).

23 One LAR was planned for completion in Q2 FY 2024, but the NRC staff was able to complete the review and issue the LAR ahead of schedule.

24 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).

A significant recent accomplishment was publication, for public comment, of a draft RG (DG-1404), Guidance for a Technology-Inclusive Content-of-Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors, for potential endorsement of industry-led Nuclear Energy Institute (NEI) 21-07, Technology Inclusive Guidance for Non-Light Water Reactors Safety Analysis Report Content for Applicants Using the NEI 18-04 Methodology, and nine NRC-led Advanced Reactor Content of Application (ARCAP) draft interim staff guidance documents (ML23044A038). These draft documents, if finalized, will provide non-LWR applicants guidance for preparing applications and guidance to the NRC staff for review of such applications.

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 ARCAP. A list of these meetings and related 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 NEIMA, the NRC staff presented three 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 the NRCs byproduct material framework 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. The NRC staff has initiated the rulemaking and plans to continue to engage stakeholders during the rulemaking and guidance development process. For example, the NRC staff held a public meeting on July 12, 2023, to discuss the development of the draft proposed rule and guidance under NUREG-1556.

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, where appropriate, 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 (Q3 FY 2023)

Advanced Nuclear Reactor Technologies Activities Projected Completion Date Completion Date Released a draft white paper on alternative approaches to address population-related siting considerations to support stakeholder engagement (ML23102A326).

04/26/23 04/13/23 Released a draft white paper on facility training programs to support stakeholder engagement (ML23017A130).

05/31/2023 04/20/23 Issued final safety evaluation (SE) to X-energy for its topical report on control room staffing analysis methodology (ML23107A044).

04/28/23 05/17/2325 Published a draft RG (DG-1404) for potential endorsement of industry-led NEI 21-07, Technology Inclusive Guidance for Non-Light Water Reactors Safety Analysis Report Content for Applicants Using the NEI 18-04 Methodology, and nine NRC-led ARCAP draft interim staff guidance documents for public comment (ML23044A038).

04/30/23 05/25/2326 Submitted a paper (SECY-23-0048) to the Commission on the vision for the NRCs Advanced Reactors Construction Oversight Program (ML23061A086).

05/15/23 06/06/2327 Issue final SE to General Atomics-Electromagnetic Systems for its topical report on principal design criteria (ML23174A176).

07/06/23 07/06/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Advanced Nuclear Reactor Technologies Activities Projected Completion Date Release a draft white paper on Technical, Licensing, and Potential Policy Issues for Factory-Fabricated Transportable Micro-Reactors to support stakeholder engagement.

08/31/23 Publish Draft Regulatory Guide 4.7, General Site Suitability Criteria for Nuclear Power Stations, Revision 4, for public comment.

09/29/23 Hold a public workshop on SCALE/MELCOR non-LWR fuel cycle demonstration project for a sodium cooled fast reactor.

09/30/23 25 This activity was completed on May 17, 2023, rather than the projected completion date of April 28, 2023, to provide additional time for X-energy to comment on the draft SE.

26 This activity was completed on May 25, 2023, rather than the projected completion date of April 30, 2023, because the NRC staff prioritized work on the Part 53 draft proposed rule during prior reporting periods.

27 This activity was completed on June 6, 2023, rather than the projected completion date of May 15, 2023, to accommodate additional time for resolution of internal comments.

Projected Advanced Nuclear Reactor Technologies Activities Projected Completion Date Enter into a Memorandum of Understanding with Department of Energy (DOE) on Roles and Responsibilities for National Environmental Policy Act (NEPA) Implementation Requirements for Reactor Demonstration Projects Supported by DOE.

09/30/23 Issue final SE to TerraPower for its topical report on Nuclear Island/Energy Island interface.

10/12/23 Submit a paper to the Commission on Technical, Licensing, and Potential Policy Issues for Factory-Fabricated Transportable Micro-Reactors.

10/31/23 Issue final guidance, DANU-ISG-2023-01, Material Compatibility.

10/31/23 Issue final SE to University of Illinois at Urbana-Champaign for its topical report on regulatory applicability analysis.

12/31/23 Publish DG 1410 (proposed new RG 1.251), Technology Inclusive, Risk Informed, and Performance Based Methodology For Seismic Design Of Commercial Nuclear Plants, for public comment.

12/31/23 Publish DG 1307 (proposed new RG 1.252), Seismically Isolated Nuclear Power Plants, for public comment.

12/31/23 Issue final SE to X-energy for its topical report on principal design criteria.

03/13/2428 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 completed its detailed technical review of the safety of the Hermes design and issued the final SE on June 13, 2023 (ML23158A265). The NRC staff plans to complete the final environmental impact statement (EIS) for this application by September 15, 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).

28 This activity is included in this table, even though the projected completion date is beyond Q1 FY 2024, because this activity was included in the previous report and the projected completion date was extended from September 8, 2023, to March 13, 2024, to allow the applicant to provide an updated revision of the topical report. The updated revision is expected to include a significant amount of new information for the NRC staff to review.

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 and the environmental assessment by April 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).

Activities Planned and Completed for the Reporting Period (Q3 FY 2023)

Advanced Reactor Licensing Review Activities Projected Completion Date Completion Date Complete review and NRC staff approval of Kairos Hermes SE.

05/04/23 04/18/23 Completion of ACRS meetings and ACRS review of Kairos Hermes SE.

09/01/23 05/16/23 Issue final Kairos Hermes SE (ML23158A265).

09/11/23 06/13/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Advanced Reactor Licensing Review Activities Projected Completion Date Complete regulatory audits and evaluate any additional docketed information necessary for the preparation of the ACU SE.

08/30/23 Issue final Kairos Hermes EIS.

09/15/23 Complete draft ACU environmental assessment.

10/31/23 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 the second quarter of FY 2023, 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 revised Inspection Manual Chapter 0305, Operating Reactor Assessment Program, dated May 4, 2023 (ML23093A184), and Inspection Procedure (IP) 71111.24, Testing and Maintenance of Equipment Important to Risk, dated March 7, 2023 (ML23062A724). The NRC staff is also in the process of revising Inspection Manual Chapter 0609, Appendix B, Emergency Preparedness Significance Determination Process (ML15128A462), dated September 22, 2015, in accordance with the Commissions direction.

The NRC staff continues to assess and improve 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. The staff will seek Commission approval of changes to the ROP, or provide the Commission with notification of changes, in accordance with Management Directive/Directive Handbook 8.13, Reactor Oversight Process (ML17347B670).

Activities Planned and Completed for the Reporting Period (Q3 FY 2023)

ROP Activities Projected Completion Date Completion Date Completed CY 2022 ROP self-assessment and submitted SECY-23-0032 (ML23026A346) to the Commission.

04/15/23 04/07/23 Briefed the Commission on the results of the Agency Action Review Meeting.

06/20/23 06/20/23 Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected ROP Activities Projected Completion Date Begin first implementation of IP 71111.21N.04, Age-Related Degradation, focused engineering inspections at a reactor site.

08/31/23 Complete ROP Implementation Audit of Region II.

12/31/23 Assess the baseline security significance determination process for power reactors (ML22178A222) as part of the ROP program area evaluations under the ROP self-assessment program.

12/31/23 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.29 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.

29 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.

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 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). This revised document is currently before the Commission for its consideration.

Activities Planned and Completed for the Reporting Period (Q3 FY 2023)

Backfit Activities Projected Completion Date Completion Date N/A N/A N/A Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Backfit Activities Projected Completion Date N/A 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.30 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,31 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.

30 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.

31 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.

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. The NRC staff will continue to seek and leverage risk insights during the technical review of the NuScale VOYGR 460 standard design approval 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.

Activities Planned and Completed for the Reporting Period (Q3 FY 2023)

Risk-Informed Activities Projected Completion Date Completion Date N/A N/A N/A Projected Activities for the Next Two Reporting Periods (Q4 FY 2023 and Q1 FY 2024)

Projected Risk-Informed Activities Projected Completion Date Conduct an NRC Risk Forum, which will be held as a public meeting, to provide an opportunity to discuss and provide awareness of the various risk-informed initiatives that have been leveraged for operating, new, and advanced reactors. This forum will facilitate engagement and dialogue between the NRC, industry, other external stakeholders, and the public about the successes and path forward of current risk activities and to seek feedback regarding future risk-informed activities that may be pursued.

09/12/23 Complete the revision of four materials IPs associated with Inspection Manual Chapter 2800 (specifically, IP 87121, Industrial Radiography Programs; IP 87122, Irradiator Programs; IP 87125, Materials Processor/Manufacturer Programs; 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.

09/30/2332 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. President Biden declared that the COVID-19 public health emergency ended effective May 11, 2023. Following the presidential announcement regarding the end of the public health emergency, on April 21, 2023, the NRC canceled a November 2, 2021, memorandum providing supplemental guidance on implementation of inspection programs during the pandemic (ML21295A302). The NRC 32 The projected completion date for this activity was extended from April 30, 2023, to September 30, 2023, due to the need to prioritize other work.

returned to implementation of the inspection programs in accordance with the inspection manual and procedures effective May 11, 2023 (ML23082A106).

Licensing and Oversight Items of Interest The NRC 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 April 1 and June 30, 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/index.html.

Regulatory Activities Taken in Response to the COVID-19 Pandemic During the Reporting Period Licensee Type Number of COVID-19 Requests Approved During the Reporting Period Average Number of Days to Review COVID-19 Requests33 Power Reactor 0

N/A Non-Power Reactor 0

N/A Other (e.g., topical reports) 0 N/A Decommissioning of Nuclear Facilities and Uranium Recovery 0

N/A Storage and Transportation of Spent Nuclear Fuel 0

N/A Fuel Cycle Facilities 0

N/A Medical, Industrial and Academic Uses of Nuclear Materials and Agreement States 0

N/A 33 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.

- 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.34 Location Number of Findings CY 2020 CY 2021 CY 2022 CY 2023 Nationally Total 291 278 399 212 Region I Green 50 61 83 34 White 0

1 2

0 Yellow 0

0 0

0 Red 0

0 0

0 Greater-Than-Green (GTG) Security 0

0 0

0 Total 50 62 85 34 No. of Units Operating During CY 22 2135 2036 20 Region II Green 77 69 90 67 White 2

0 1

1 Yellow 0

0 0

0 Red 0

0 0

0 GTG Security 1

0 0

3 Total 80 69 91 71 No. of Units Operating During CY 33 33 33 3437 Region III Green 51 65 89 44 White 0

0 2

0 Yellow 0

0 0

0 Red 0

0 0

0 GTG Security 0

1 1

0 Total 51 66 92 44 No. of Units Operating During CY 23 2238 22 2139 Region IV Green 110 81 130 61 White 0

0 1

2 Yellow 0

0 0

0 Red 0

0 0

0 34 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.

35 The reduction of one unit for CY 2021 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 2 on April 30, 2020.

36 The reduction of one unit for CY 2022 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 3 on April 30, 2021.

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

38 The reduction of one unit for CY 2021 reflects the permanent shutdown of Duane Arnold on August 10, 2020.

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

I l

I I

I l

I I

I I

I I

I I

I I

Location Number of Findings CY 2020 CY 2021 CY 2022 CY 2023 GTG Security 0

0 0

0 Total 110 81 131 63 No. of Units Operating During CY 18 18 18 18 3-2 Licensing Actions The tables below provide the status of licensing actions organized by licensing program.

Consistent with Section 102(c) of Nuclear Energy Innovation and Modernization Act (NEIMA),

the licensing actions referenced in this section include requested activities of the Commission for which the 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 Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period40 Percentage of Licensing Actions Completed Prior to the Generic Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule41 Q4 FY 2022 124 28 32 100%

81%42 Q1 FY 2023 128 53 36 100%

58%43 Q2 FY 2023 130 35 38 99%

90%44 Q3 FY 2023 132 55 59 100%

95%

40 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.

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

42 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.

43 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 from multiple licensees, additional time to resolve policy and technical issues, public meetings, and multiple rounds of requests for additional information. The review is expected to be completed by Q4 FY 2023.

44 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.

New Reactors Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period45 Percentage of Licensing Actions Completed Prior to the Generic Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule Q4 FY 2022 1

1 1

100%

100%

Q1 FY 2023 2

2 1

100%

100%

Q2 FY 202346 2

0 0

100%

100%

Q3 FY 2023 0

0 2

100%

100%

Fuel Facilities Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period Percentage of Licensing Actions Completed Prior to the Generic Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule Q4 FY 2022 8

8 6

100%

60%47 Q1 FY 2023 4

6 10 100%

60%48 Q2 FY 2023 9

4 4

100%

79%49 Q3 FY 2023 4

4 4

100%

100%

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).

45 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.

46 For Q2 FY 2023, the total inventory was changed from 4 to 2, the licensing actions initiated was changed from 4 to 0, and the licensing actions completed was changed from 2 to 0 to correct a reporting error from the previous report.

47 Two fuel cycle licensing actions exceeded the established schedule by approximately 1 month due to prioritizing other work.

48 Four out of 10 fuel cycle licensing actions exceeded the established schedule by approximately 1 month due to prioritizing other work.

49 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.

Operating Reactors Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period50 Percentage of LAR Reviews Completed Prior to the Generic Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule51 Q4 FY 2022 269 65 84 100%

93%

Q1 FY 2023 247 74 89 100%52 90%53 Q2 FY 2023 236 76 88 100%

77%54 Q3 FY 2023 244 68 61 100%

97%

New Reactors Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the Generic Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule 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%

Q3 FY 2023 6

655 1

100%

100%

50 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.

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

52 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 provided its supplement to the LAR in April 2023, and the NRC staff is assessing its impact on the review schedule. This exceedance of a generic milestone schedule will be reflected in the percentage for the quarter in which the final SE is issued.

53 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 completed the review and issued its decision in May 2023.

54 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.

55 The six LARs submitted during Q3 FY 2023 include one LAR submitted by SNC on April 5, 2023, but withdrawn on May 17, 2023; and five LARs submitted and accepted by the NRC staff for review. This results in six LARs for the total inventory for Q3 FY 2023 (five LARs submitted and accepted plus one LAR outstanding from Q2 FY 2023).

Fuel Facilities Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the Generic Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule Q4 FY 2022 7

1 4

100%

75%56 Q1 FY 2023 9

3 1

100%

100%

Q2 FY 2023 9

4 4

100%

75%57 Q3 FY 2023 10 6

5 100%

100%

3-4 Research Activities58 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:

There are no research starts or substantial revisions to report for this period.

Summary of Completed Research Projects59 During the reporting period, the following research projects were completed:

Support and Evaluation of SHINE Medical Technologies (SHINE) Facility Applications (NRR-2013-011)

Importance to the NRC Mission RES provided technical assistance for the review and evaluation of the SHINE construction permit and operating license applications in accordance with the provisions of 10 CFR Part 50.

Research Results or Findings RES provided neutronic, thermal-hydraulic, and accident analyses support of the evaluation and review of the SHINE construction permit and operating license applications. This support included:

Performing technical reviews and evaluations.

Documenting review conclusions.

Meeting with the Office of Nuclear Reactor Regulation (NRR) staff and the applicant.

Recommending requests for additional information (RAIs).

Reviewing the applicants responses to RAIs.

Providing support to the Advisory Committee on Reactor Safeguards (ACRS) meetings.

Duration of the Project 10 years 56 One review of an LAR exceeded the established schedule by 26 days due to prioritizing other work.

57 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 NRC staff prioritization of other work.

58 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.

59 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.

Support and Evaluation of SHINE Medical Technologies (SHINE) Facility Applications (NRR-2013-011)

Estimate of Total Research Resources 2.5 Full-Time Equivalent (FTE) over the 10-year period Alternative Framework for Postulating Pipe Break Locations (NRR-2021-004)

Importance to the NRC Mission The work delivered a risk-informed approach for postulating pipe rupture locations to demonstrate compliance with General Design Criterion 4 requirements. This approach enhances the NRCs ability to assess new reactor applications and offers greater flexibility to operating plant licensees.

Research Results or Findings RES produced a technical letter report that presents a risk-informed methodology for pipe rupture analysis. The project involved developing a framework and the necessary technical basis for a risk-informed alternative to the current pipe design criteria. Additionally, RES conducted a sensitivity study to evaluate the methodology described in the technical letter report. The outcomes of this work provide a solid technical foundation for advancing the current guidance on postulating pipe break locations.

Duration of the Project 2 years Estimate of Total Research Resources 1 FTE and $250K over the 2-year period 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.60 Fee Class FY 2023 Part 170 Receipts Estimated

- Final Fee Rule

($M)

Part 170 Billed in Q3 FY 2023 ($M)

Total Part 170 -

Billed in FY 2023

($M)

Fuel Facilities

$9.2

$2.3

$6.5 Generic Decommissioning

$4.5

$0.5

$1.461 Materials Users62

$1.2

$0.1

$0.863 Operating Power Reactors

$158.9

$39.6

$114.6 Non-Power Production or Utilization Facilities

$4.9

$0.9

$3.8 60 The FY 2023 Final Fee Rule was published in the Federal Register (FR) on June 15, 2023 (88 FR 39120).

61 Total Part 170 - Billed in FY 2023 ($M) for Generic Decommissioning may not add due to rounding: $0.248M reported in Q1 plus $0.573M in Q2 plus $0.532M in Q3 totals $1.353M.

62 Materials UsersBilled as flat fee applications and included in the estimates and billed.

63 Total Part 170 - Billed in FY 2023 ($M) for Materials Users reflects a correction. Specifically, Q2 should have been reported as $0.383M instead of $0.234M in the previous report. Additionally, Total Part 170 - Billed in FY 2023 ($M) for Materials Users may not add due to rounding: $0.267M reported in Q1 plus $0.383M in Q2 plus

$0.147M in Q3 totals $0.797M.

Fee Class FY 2023 Part 170 Receipts Estimated

- Final Fee Rule

($M)

Part 170 Billed in Q3 FY 2023 ($M)

Total Part 170 -

Billed in FY 2023

($M)

Spent Fuel Storage/

Reactor Decommissioning

$12.4

$2.9

$9.7 Rare Earth

$0.3

$0.1

$0.2 Transportation

$3.4

$0.8

$2.0 Uranium Recovery

$0.3

$0.0

$0.2 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 operating license application review, and the Kairos Hermes construction permit application review.

Docket Project Name Projected Resources

($M)64 Fees Billed to Date

($M)65 Point Beach Units 1 and 2 05000266/05000301 Point Beach Units 1 and 2 Subsequent License Renewal Application Safety Review

$5.066

$3.5 Point Beach Units 1 and 2 05000266/05000301 Point Beach Units 1 and 2 Subsequent License Renewal Application Environmental Review

$1.4

$1.467 North Anna Units 1 and 2 05000338/05000339 North Anna Units 1 and 2 Subsequent License Renewal Application Safety Review

$5.068

$3.069 North Anna Units 1 and 2 05000338/05000339 North Anna Units 1 and 2 Subsequent License Renewal Application Environmental Review

$1.4

$1.970 64 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.

65 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 2023.

66 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.

67 The Fees Billed to Date for this review reflects a correction. Specifically, the Fees Billed to Date for Q2 should have been reported as $1.4M instead of $1.6M in the previous report.

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 The Fees Billed to Date for this review reflects a correction. Specifically, the Fees Billed to Date for Q2 should have been reported as $3.0M instead of $3.8M in the previous report.

70 The Fees Billed to Date for this review reflects a correction. Specifically, the Fees Billed to Date for Q2 should have been reported as $1.6M instead of $1.5M in the previous report.

Docket Project Name Projected Resources

($M)64 Fees Billed to Date

($M)65 Oconee Units 1, 2, and 3 05000269/05000270/

05000287 Oconee Units 1, 2, and 3 Subsequent License Renewal Application Safety Review

$5.071

$3.872 Oconee Units 1, 2, and 3 05000269/05000270/

05000287 Oconee Units 1, 2, and 3 Subsequent License Renewal Application Environmental Review

$1.4

$0.8 SHINE Medical Technologies, LLC 05000608 SHINE Medical Isotope Production Facility Operating License Application Review Safety and Environmental Reviews

$6.573

$7.574 St. Lucie Units 1 and 2 05000335/05000389 St. Lucie Units 1 and 2 Subsequent License Renewal Application Safety Review

$5.075

$3.9 St. Lucie Units 1 and 2 05000335/05000389 St. Lucie Units 1 and 2 Subsequent License Renewal Application Environmental Review

$1.4

$0.4 Kairos Hermes 05007513 Kairos Hermes -

Construction Permit - Safety and Environmental Reviews

$5.576

$4.3 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.

71 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.

72 The Fees Billed to Date for this review reflects a correction. Specifically, the Fees Billed to Date for Q2 should have been reported as $3.8M instead of $3.5M in the previous report.

73 The update to the projected resource estimate for this application review was provided to SHINE by letter dated February 17, 2022 (ML22047A179).

74 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.

75 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.

76 The projected resource estimate was provided to Kairos Power LLC by letter dated December 15, 2021 (ML21343A214).

Type of Facility or Activity Type Total Inventory of Open RAIs as of the End of Reporting Period Total Number of RAIs Issued in Reporting Period Total Number of RAIs Responded to in Reporting Period Total Number of RAIs Closed in Reporting Period77 Operating Reactors 43878 142 233 133 Non-Power Production and Utilization Facilities79 16478 0

0 4

Design Certifications for New Reactors80 N/A N/A N/A N/A Early Site Permits for New Reactors81 N/A N/A N/A N/A Combined Licenses for New Reactors 0

0 0

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

0 0

3182 Fuel Facilities 83 37 47 16 Power Reactor Decommissioning 87 17 0

1883 Research and Test Reactor Decommissioning 12 0

0 0

Spent Fuel 303 18 58 467 Materials 0

0 0

0 Pre-Application Activities for Advanced Reactors 0

0 0

0 77 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.

78 The Total Inventory of Open RAIs for Operating Reactors and Non-Power Production and Utilization Facilities reflect a correction. Specifically, the total number of open RAIs should have been reported as 458 and 429 for Operating Reactors for Q1 and Q2 FY 2023, respectively, and as 168 for Non-Power Production and Utilization Facilities for Q2 FY 2023.

79 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.

80 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.

81 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 82 31 RAIs were inadvertently excluded from the previous report and have been included here for completeness.

The final SE was issued for the Kairos Hermes construction permit application on June 13, 2023 (ML23158A265).

83 The total number of RAIs closed include 3 Three Mile Island Unit 2 RAIs that were closed on March 31, 2023.

3-7 Workforce Development and Management FY 2023 Staffing by Office84 FY 2023 Budget FTE Utilization 03/26/23 -

04/22/23 FTE Utilization 04/23/23 -

05/20/23 FTE Utilization 05/21/23 -

06/17/23 FTE Utilization as of 06/17/23 Delta (Q3 FTE Utilization -

FY 2023 Budget)

End of Year (EOY)86 Projection w/

Personnel Actions Delta (EOY Utilization -

FY 2023 Budget)

Totals 2868.585 206.7 207.1 213.5 1976.2

-892.3 2724.6

-143.9 COMM 42.0 2.6 2.7 2.7 24.3

-17.7 33.9

-8.1 OIG 63.0 3.7 3.5 3.7 37.0

-26.0 51.1

-11.9 Totals Other Offices 2763.5 200.3 200.9 207.1 1914.9

-848.6 2639.6

-123.9 OCFO 93.0 7.0 6.7 7.2 65.0

-28.0 90.3

-2.7 OGC 87.7 6.7 6.6 6.7 65.5

-22.2 89.3 1.6 OCA 10.0 0.8 0.7 0.8 7.4

-2.6 10.0 0.0 OCAA 7.0 0.4 0.4 0.4 4.0

-3.0 5.4

-1.6 OPA 13.0 1.1 1.1 1.1 10.0

-3.0 13.5 0.5 SECY 17.0 1.2 1.2 1.2 11.8

-5.2 16.0

-1.0 OIP 35.0 2.6 2.5 2.6 23.7

-11.3 33.3

-1.7 ASLBP 20.1 1.4 1.4 1.4 13.9

-6.2 19.1

-1.0 ACRS 25.1 1.8 1.9 1.8 17.1

-8.0 24.0

-1.1 OEDO 29.0 1.7 1.9 2.0 17.9

-11.1 25.3

-3.7 NRR 555.1 38.8 38.5 39.8 367.0

-188.1 506.9

-48.2 NMSS 308.0 22.8 23.3 23.4 212.6

-95.4 294.3

-13.7 RES 198.6 13.4 13.8 15.1 133.4

-65.2 185.8

-12.8 NSIR 156.1 11.2 11.3 11.7 105.8

-50.3 146.8

-9.3 R-I 169.8 12.1 12.2 12.7 118.8

-51.0 163.4

-6.4 R-II 204.7 15.8 15.6 16.0 151.8

-52.9 207.4 2.7 R-III 167.1 12.5 12.2 12.6 119.6

-47.5 163.7

-3.4 R-IV 162.9 12.2 12.3 12.8 121.2

-41.7 164.9 2.0 OE 31.3 2.2 2.1 2.1 21.0

-10.3 28.6

-2.7 OI 35.0 2.4 2.4 2.3 22.2

-12.8 30.8

-4.2 OCIO 172.0 12.1 12.3 12.3 115.2

-56.8 157.5

-14.5 ADM 117.0 9.0 9.0 9.6 86.3

-30.7 118.7 1.7 SBCR 13.0 1.0 1.0 1.0 9.5

-3.5 13.0 0.0 OCHCO 133.0 9.9 10.2 10.4 92.8

-40.2 129.6

-3.4 CSU 3.0 0.2 0.2 0.1 1.4

-1.6 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.

84 Some numbers might not add due to rounding.

85 FY 2023 budget number reflects the FY 2023 Enacted Budget.

86 Based on FTE utilization as of June 17, 2023.

Average ROP Direct Inspection Hours Nationwide Per Plant (unit)

Column 1 of ROP Action Matrix Column 2 of ROP Action Matrix Column 3 of ROP Action Matrix Column 4 of ROP Action Matrix 818 Hours 799 Hours 963 Hours87 844 Hours88 No Plants in 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 213,363 107,046 ii.

Plant-Specific Inspection 7,946 4,918 iii.

Generic Safety Issue Inspections 83 0

iv.

Performance Assessment 3,062 2,098

v.

Other Activities 97,511 49,779 vi.

Total Staff Effort 321,964 164,098 vii.

Total Staff Effort Per Operating Site 5,85489 2,97990 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.

87 Davis-Besse Nuclear Power Station, Unit 1 moved to Column 2 in Q4 FY 2021 (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). Sequoya Nuclear Plant, Units 1 and 2 moved to Column 2 in Q1 FY 2023 (ML23103A395).

Columbia Generating Station moved to Column 2 in Q1 FY 2022 (ML23111A237). Browns Ferry Nuclear Plant, Unit 1 moved to Column 2 in Q2 FY 2023 (ML23115A000).

88 Farley Nuclear Plant, Units 1 and 2 moved to Column 3 in Q4 FY 2022 (ML23089A399).

89 Total staff effort is divided by 55 sites for CY 2022, due to Indian Point Unit 3 permanently ceasing operations in April 2021.

90 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.