ML22021B014
| ML22021B014 | |
| Person / Time | |
|---|---|
| Issue date: | 02/07/2022 |
| From: | Christopher Hanson NRC/Chairman |
| To: | Carper T, Markey E, Pallone F US HR (House of Representatives), US SEN, Comm on Environment & Public Works |
| Mroz S | |
| Shared Package | |
| ML22021B001 | List: |
| References | |
| CORR-20-0008 | |
| Download: ML22021B014 (40) | |
Text
STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION For the Reporting Period of October 1, 2021 through December 31, 2021
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 Inspection Hours and Percent Complete ........................................................ 4 1-3 FTE at the End of Q1 FY 2022 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 ........................................................................... 12 2-6 NuScale Small Modular Reactor Design Certification................................................................. 16 2-7 Advanced Nuclear Reactor Technologies ................................................................................... 16 2-8 Advanced Reactor Licensing Reviews ........................................................................................ 20 2-9 Reactor Oversight Process ......................................................................................................... 22 2-10 Backfit .......................................................................................................................................... 23 2-11 Risk-informed Activities ............................................................................................................... 24 2-12 Coronavirus Disease (COVID-19) Pandemic .............................................................................. 25 - Summary of Activities.....................................................................................28 3-1 Reactor Oversight Process Findings........................................................................................... 28 3-2 Licensing Actions ........................................................................................................................ 29 3-3 Licensing Amendment Request Reviews ................................................................................... 30 3-4 Research Activities ...................................................................................................................... 32 3-5 Fees Billed ................................................................................................................................... 34 3-6 Requests for Additional Information ............................................................................................ 36 3-7 Workforce Development and Management ................................................................................ 38 3-8 Inspection Activities ..................................................................................................................... 39 3-9 Backfit .......................................................................................................................................... 40
Enclosure 1 - High Level Summary 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act 100%
Average Timeliness Percentage 90%
80%
70%
(<100% = Completed Before 60%
50%
Schedule Date) 40%
30%
20%
10%
Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule 1
0F 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.
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1-2 Reactor Oversight Inspection Hours and Percent Complete 180000 90%
Cumulative Percent of Planned Direct Inspection Hours Complete 160000 80%
140000 70%
Direct Inspection Hours 120000 60%
100000 50%
80000 40%
60000 30%
40000 20%
20000 10%
0 0%
Quarter 1 Quarter 2 Quarter 3 Quarter 4 Calendar Year (CY) 2020 Total Direct ROP Inspection Hours CY 2021 Total Direct ROP Inspection Hours Percent Complete of Total CY 2021 Planned ROP Direct Inspection Hours Percent Complete of Total CY 2020 Planned ROP Direct Inspection Hours 2
1F 2 Planned direct inspection hours refers to the number of hours associated with completion of the U.S. Nuclear Regulatory Commissions (NRCs) nominal number of inspection samples established for the baseline inspection program, which is a conservative target. This contrasts with the minimum number of hours that would be necessary to complete the set of inspection activities that constitutes completion of the Reactor Oversight Process (ROP) baseline inspection program for the calendar year. In CY 2020, despite falling short of the planned/nominal number of inspection hours (due to the ongoing COVID-19 pandemic and its impact on planned inspection activities), the NRC performed the minimum number of inspection hours associated with program completion. In CY 2021, the NRC completed well above the minimum number of inspection hours needed for program completion.
Certification of the completion of the baseline inspection program for CY 2021 is underway.
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1-3 FTE at the End of Q1 FY 2022 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 2022 Budget Authority December 31, 2021 (Dollars in Thousands)
Fund Sources FY 2022 Budget 3 2F Percent Obligated Percent Expended Advanced Reactors $17,709 19% 17%
Commission Funds $12,799 10% 10%
Fee-Based Funds $789,314 19% 17%
General Funds 4 3F $1,158 12% 12%
International Activities $13,399 23% 18%
University Nuclear Leadership Program /
$2,000 98% 0%
Integrated University Program Official Representation $27 10% 10%
Total $836,406 19% 17%
NRC Control Points FY 2022 Budget Percent Obligated Percent Expended Nuclear Reactor Safety $435,212 20% 19%
3 The agency is operating under the Further Continuing Appropriations Act, 2022 (as amended); therefore, this table reflects the FY 2021 total annualized rate (i.e., the FY 2021 enacted levels). This table also includes the carryover allocated during Q1 FY 2022.
4 Consistent with previous reports, this row represents waste incidental to reprocessing activities excluded from the fee-recovery requirement.
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Fund Sources FY 2022 Budget 3 2F Percent Obligated Percent Expended Nuclear Materials and $101,898 20% 19%
Waste Safety Decommissioning and $22,580 21% 19%
Low-Level Waste Corporate Support $274,716 16% 13%
University Nuclear Leadership Program / $2,000 98% 0%
Integrated University Program 5 4F Total $836,406 19% 17%
FTE Utilization, Hiring, and Attrition Total Year to Date Projected End of Year Quarter 1 Quarter 1 YTD YTD (YTD) FTE FTE Total Utilization Hiring Attrition Hiring Attrition Utilization 629.3 2768.6 23 38 23 38 FY 2022 Fees Estimated, Fees Billed, and Fees Collected Through Q1 Total 10 CFR Part 170 Fees Billed (Dollars in Millions)
FY 2020 FY 2021 FY 2022 Q1
$205.7 $183.9 $53.7 5 This row is labeled as "University Nuclear Leadership Program / Integrated University Program" because the FY 2021 Explanatory Statement identified this control point as the Integrated University Program, but Division Z of the Consolidated Appropriations Act, 2021 replaced the Integrated University Program with the University Nuclear Leadership Program.
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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.
Over the past two years, the NRC has made significant 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.
To sustain progress and meet the agencys transformation goals, the NRC will use a variety of tools, including objectives and key results that relate to the current four focus areas (i.e., Our People, Be riskSMART, Using Technology, and Innovation). 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) Q1 Fiscal Year (FY) 2022)
Projected Transformation Activities Completion Date Completion Date Facilitated discussion on leading hybrid teams and provided resources for employees to enhance 12/31/21 12/31/21 6 knowledge and skills to perform in a hybrid 5F environment.
Completed first assessment of survey of external 12/31/21 01/05/22 7 stakeholder views on NRC transformation activities.
6F Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Transformation Activities Completion Date Conduct a series of first-line supervisor workshops to engage in dialogue on the agencys progress on transformation and identify actions they can 02/01/22 8 take to encourage use of transformation tools, while mitigating the effects 7F of change fatigue.
6 This was an emergent activity during the reporting period based on the need to prepare staff for re-entry.
7 This initial internal assessment of the survey was completed in December 2021; a briefing on those results to senior agency leadership was completed on January 5, 2022. A final assessment of the survey of external stakeholder views will be conducted after the survey closes at the end of March 2022.
8 In the last report, the projected completion date for this activity was reported as January 31, 2022. The workshops are scheduled and the final one is now anticipated to be completed on February 1, 2022.
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Projected Projected Transformation Activities Completion Date Launch the Mission Analytics Portal Event Reporting module. This module will provide NRC licensees an alternative electronic submission 02/28/22 9 method for reports required under Title 10 of the Code of Federal 8F Regulations (10 CFR) 50.72.
Establish calendar year 2022 Objectives and Key Results. 02/28/22 Conduct final assessment of survey of external stakeholder views on 05/31/22 NRC transformation activities.
Brief the Commission on the staffs transformation activities (public 06/30/22 meeting).
Implement a staff-led effort to recognize NRC employees who make notable and innovative contributions towards attaining agency goals through business improvements, applying risk insights, using data in 07/31/22 decision-making, realizing culture, enhancing the work environment, or advancing knowledge management practices.
2-2 Workforce Development and Management The NRC implemented a 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 five 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. The SWP process occurs each FY.
During the reporting period, the agency began recruitment efforts for our Summer Student Intern program and anticipates having 75 - 80 new and returning students onboard during summer 2022. Additionally, recruitment efforts began for the second Nuclear Regulator Apprenticeship Network (NRAN) cohort, and 25 recent graduates majoring in engineering and science are expected to join the agency in Q4 FY 2022.
Additionally, during this reporting period, the Chief Human Capital Officer began developing a strategy for a significant recruitment effort to occur throughout FY 2022. The strategy will directly address staffing challenges and ensure that the agency continues to fulfill its important safety and security mission well into the future.
Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Workforce Development and Management Projected Completion Date Activities Completion Date Completed updates to the Agency Environmental Scan to support FY 2022 SWP activities. 12/31/21 12/31/21 9 The projected completion date for this activity has been extended from December 31, 2021, to February 28, 2022, due to additional time needed to complete actions that must be taken prior to launch of the portal.
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Workforce Development and Management Projected Completion Date Activities Completion Date Utilized insights from the SWP process to inform recruitment activities for the 2022 NRAN and 12/31/21 12/31/21 Summer Student Intern programs and made initial selections.
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Workforce Development and Management Activities Completion Date Complete Steps 2 (Workload Forecasting and Workforce Demand) and 3 03/31/22 (Workforce Supply Analysis) to support 2022 SWP activities.
Continue pre-employment hiring activities for NRAN and Summer 03/31/22 Student Intern program selectees.
Onboard Summer 2022 Student Interns. 06/30/22 Complete Steps 4 (Gap Analysis and Risk Assessment) and 5 06/30/22 (Strategies and Action Plans) to support 2022 SWP activities.
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 (ADAMS)
Accession No. ML21243A298), which was revised to include an increased focus on higher burnup and increased enrichment fuels. The NRC has not received any additional ATF fuel vendor topical reports for review since the last reporting period, and the NRC staff continues to review five ATF fuel vendor topical reports. The first topical report is on a new type of doped fuel pellet called Westinghouse Advanced Doped Pellet Technology (ADOPTTM) Fuel (ADAMS Accession No. ML20132A014). The second covers increased burnup limits for a fuel cladding material (ADAMS Package No. ML20003E125). The third discusses a slight increase in burnup limits for existing Westinghouse fuel designs (ADAMS Package No. ML20350B834), and the fourth involves increased fuel enrichment (ADAMS Package No. ML21035A073). The fifth report discusses the use of chromia-doped fuel for pressurized water reactors (ADAMS Accession No. ML21187A198). The NRC staff is on track to complete review of these topical reports by FY 2025.
The NRC staff also continues to review a request from Framatome to amend the certificate of compliance for the MAP transportation package. The amendment seeks to authorize shipment of 17x17 fuel assemblies with enrichments above 5 weight percent uranium-235 (ADAMS Package No. ML21090A321). Further, the NRC staff is reviewing two additional transportation package amendments (ADAMS Accession Nos. ML21216A322 and ML21181A001), that are seeking increased enrichment above 5 weight percent uranium-235; the NRC staffs review of these applications is expected to be completed between early- to mid-calendar year (CY) 2022.
The NRC expects to receive a number of license amendment requests (LARs) in CY 2022 from enrichment facilities and fuel fabricators to directly support increased enrichment above 5 weight percent uranium-235.
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Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Projected ATF Activities Completion Date Completion Date Issued a research information letter documenting the current state of knowledge regarding the phenomena of fuel fragmentation, relocation, and 03/31/22 12/17/21 dispersal in higher burnup fuel (ADAMS Accession No ML21313A145).
Provided to the Commission a rulemaking plan evaluating changes to regulations associated with the potential use of light-water-reactor fuel 12/31/21 12/20/21 containing uranium enriched to greater than 5.0 weight percent uranium-235 (ADAMS Accession No. ML21232A232).
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected ATF Activities Completion Date Issue the Regulatory Framework Applicability Assessment and associated Licensing Pathways. The Regulatory Framework Applicability Assessment contains the NRC staffs analysis of the applicability of regulations and guidance for coated cladding, doped 02/28/22 10 pellets, higher burnup, and increased enrichment fuels. The Licensing 9F Pathways are intended to illustrate the remaining informational needs or tasks that should be completed to thoroughly and efficiently review ATF topical reports and plant-specific LARs.
Host an NRC Regulatory Information Conference session on ATF. The public session will provide stakeholders an opportunity to learn about the progress of ATF licensing activities and technologies to date and the activities that support efficient licensing of ATF concepts. The panel 03/09/22 discussion will focus on completed ATF readiness activities, plans for the remaining stakeholder activities as well as the NRCs projected licensing timelines, and challenges to ATF deployment timelines.
Hold a third Higher Burnup workshop. This workshop will discuss the state of development of higher burnup and increased enrichment 06/30/22 technical and regulatory issues. It will also provide a public forum for discussions between the NRC, industry, and other stakeholders.
2-4 Digital Instrumentation and Control The NRC staff continues to complete digital instrumentation and control (digital I&C) infrastructure improvements to address commercial grade dedication of digital equipment and protection against common cause failure (CCF). Further, the NRC staff continues to review and prepare for anticipated digital modernization LARs. While some infrastructure improvement activities continue, the staff is transitioning to using the improved infrastructure to 10 The projected completion date was modified from December 31, 2021, to February 28, 2022, to accommodate additional public engagement with stakeholders on their comments, which was completed on December 7, 2021.
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support the review of licensees digital I&C modernization LARs. These activities support the NRCs vision to establish a modern, risk-informed regulatory structure with reduced uncertainty that will enable the expanded safe use of digital technologies.
During the reporting period, the NRC staff continued to review the Nuclear Energy Institutes (NEI) NEI 17-06, Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications.
On December 3, 2021, NEI provided a substantial revision to the proposed guidance in NEI 17-
- 06. NEI 17-06 is intended to clarify how licensees can use Safety Integrity Level (SIL) certification in their commercial grade dedication programs. These commercial dedication programs would provide increased access to safety critical digital equipment not specifically developed for the nuclear industry. In September 2021, NEI provided a major revision of its proposed additional CCF guidance contained in NEI 20-07, Guidance for Addressing Software Common Cause Failure in High Safety-Significant Safety-Related Digital I&C Systems, for NRC review. The NRC staff is currently considering the policy implications of new approaches and plans to hold a public meeting with external stakeholders in the near term to inform its thinking on how best to consider addressing digital I&C CCF. Additionally, the NRC staff is planning a public workshop with external stakeholders to discuss the lessons learned from the first application of the alternate review process for digital I&C LARs described in interim staff guidance DI&C-ISG-06, Revision 2, Licensing Process.
Several licensees are now planning for digital upgrades. The NRC staff has communicated to industry that pre-application engagement can be vital to enabling efficient and effective reviews of LARs, and the staff continues to conduct pre-application meetings to better understand the scope and schedule for LARs for two upcoming major digital modifications: 1) Turkey Point Power Plant Units 3 and 4 planned for February 2022, and 2) Limerick Generating Station Units 1 and 2 planned for September 2022.
Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Projected Digital Instrumentation and Control Activities Completion Date Completion Date Review NEI 17-06, Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, and consider endorsement through issuance of a regulatory guide (RG).
- Conducted public meeting to discuss proposed revision to NEI 17-06 and 11/09/21 11/09/21 proposed NRC draft guidance (ADAMS Accession No. ML21323A140).
Digital Modernization LAR Using the Improved Digital Regulatory Infrastructure 11 10F
- Conducted fourth pre-application meeting with Exelon for a digital modernization 10/20/21 10/20/21 project at Limerick Generating Station (ADAMS Accession No. ML21300A277).
11 Activities reported in this section are related to planned or submitted digital changes for which the licensee is using some portion of the modernized digital regulatory infrastructure.
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Projected Digital Instrumentation and Control Activities Completion Date Completion Date
- Conducted fifth pre-application meeting with Exelon for a digital modernization project at 12/07/21 12/07/21 Limerick Generating Station (ADAMS Accession No. ML21330A045).
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Digital Instrumentation and Control Activities Completion Date Review NEI 17-06, Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, and consider endorsement through issuance of an RG.
Digital Modernization LAR Using the Improved Digital Regulatory Infrastructure 12 11F
- Conduct sixth pre-application meeting with Exelon for a digital 01/11/22 modernization project at Limerick Generating Station.
- Conduct sixth pre-application meeting with NextEra for digital 01/31/22 modernization project at Turkey Point Units 3 and 4.
- Issue a staff decision on acceptability of the NextEra submittal for digital modernization project at Turkey Point Units 3 and 4 03/31/22 1312F within 60 days of submission by licensee.
Consideration of Current CCF Policy in SECY-93-08
- Conduct public meeting with external stakeholders to discuss 02/28/22 CCF policy in SECY-93-08 Alternate Review Process Lessons Learned Workshop
- Conduct workshop with external stakeholders on lessons learned from the first application of the alternate review 03/31/22 process.
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. SNCs public milestone for Vogtle Electric Generating Plant (Vogtle) Unit 3 entering service. The NRC staff adjusted the agencys activities and associated milestone dates to reflect the revised schedule.
During this reporting period, the NRC staff focused significant inspection activities on the licensees response to quality issues. On November 17, 2021, the NRC issued a Final Significance Determination letter (ADAMS Accession No. ML21312A412) to SNC regarding the findings discussed in the Special Inspection Report dated August 26, 2021 (ADAMS Accession No. ML21236A057). The NRC staff issued two White findings after careful evaluation of the inspection findings and SNCs response to the Special Inspection Report, which the NRC 12 Activities reported in this section are related to planned or submitted digital changes for which the licensee is using some portion of the modernized digital regulatory infrastructure.
13 The projected completion date changed because the licensee is delaying the submittal of this LAR.
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received on October 5, 2021 (ADAMS Accession No. ML21278A354). The first White finding was associated with the failure to promptly identify and correct conditions adverse to quality for the installation of Class 1E cables and associated raceways. The second White finding was associated with the failure to accomplish separation for Class 1E system field installations in accordance with applicable instructions, procedures, and drawings. Both findings were determined to have low to moderate safety significance. The NRC staff currently plans to conduct a supplemental inspection at Vogtle Units 3 and 4 during Q2 FY 2022 to oversee SNCs resolution of the cable installation issues.
Due to the COVID-19 public health emergency, the NRC staff performed mission-critical inspections through a combination of remote inspections and targeted onsite inspections. The NRC maintains its inspection agility through consistent communication with the licensee and resource planning to ensure that the NRC can adapt to changes in the dynamic construction schedule.
Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Vogtle Electric Generating Plant Units 3 and 4 Projected Completion Date Activities Completion Date Issued a decision regarding SNCs request for a license amendment and exemption to revise inspections, tests, analyses, and acceptance criteria (ITAAC) associated with inspection of specific 10/11/21 10/15/21 1413F components that cannot be placed in their final location until after core fuel load (ADAMS Package No. ML21237A205).
Issued a decision regarding SNCs request for a limited scope exemption from certain operator testing requirements for reactor operators licensed 11/30/21 11/22/21 to operate Unit 3 who are qualified to operate Unit 4 (ADAMS Package No. ML21279A185).
Issued a decision regarding SNCs request for an exemption to implement certain physical protection and personnel access authorization requirements 12/01/21 11/23/21 15 after the Commission finds that the acceptance 14F criteria in the COL are met and prior to initial fuel load (ADAMS Package No. ML21320A041).
Issued a decision regarding SNCs request for an exemption to delay establishment of the full fitness for duty program from the time of the 10 CFR 12/20/21 12/21/21 1615F 52.103(g) finding to prior to fuel load (ADAMS Package No. ML21334A417).
14 The safety evaluation was issued after the projected completion date to ensure all technical concerns were fully resolved. The license amendment was issued in time to support Vogtle Units 3 and 4 construction activities.
15 This was a new emergent activity identified during the reporting period based on an exemption request submitted by SNC to delay establishment of the protected area from the time of the 10 CFR 52.103(g) finding to prior to initial fuel load.
16 This was a new emergent activity identified during the reporting period based on an exemption request submitted by SNC to delay establishment of the full fitness for duty program from the time of the 10 CFR 52.103(g) finding to prior to initial fuel load. The exemption was issued 1 day after the projected completion date to allow time to resolve technical concerns. It was issued in time to support Vogtle Units 3 and 4 construction activities.
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Vogtle Electric Generating Plant Units 3 and 4 Projected Completion Date Activities Completion Date Conducted a public meeting to discuss Vogtle Readiness Group activities (ADAMS Accession No. 11/18/21 12/02/21 17 16F ML21337A003).
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Publish a notice of the licensees intent to operate Vogtle Unit 4 in the Federal Register (FR) to announce the opportunity for the public to 02/02/22 19 request a hearing on the licensees conformance with acceptance 18F criteria in the COL. 18 17F Issue a letter regarding Vogtle Unit 3s transition to the operating reactor 03/31/22 20 assessment program.
19F Once the NRC determines that all ITAAC have been met, issue the finding that all acceptance criteria contained in the Vogtle Unit 3 license 03/31/22 21 have been met and that the licensee may operate the facility, in 20F accordance with 10 CFR 52.103(g).
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 Completed 22 Inspected 23 Inspection Closed 24 21F 22F 23F 17 The public meeting was delayed until December 2, 2021, based on schedule conflicts.
18 This activity was previously reported in error for Unit 3 and is being corrected in this report.
19 The timing of FR notice was adjusted because of updates to the licensees schedule for commercial operations for Vogtle Unit 4.
20 The projected completion date was modified from December 31, 2021, to March 31, 2022, due to changes in the licensees construction schedule for Vogtle Unit 3.
21 The projected completion date was modified from January 31, 2022, to March 31, 2022, due to changes in the licensees construction schedule for Vogtle Unit 3.
22 This column includes all inspections related to Vogtle Unit 3 and 4 completed during the reporting period; the column is not limited to ITAAC (e.g., quality assurance inspections).
23 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.
24 ITAAC Inspection Closed refers to the number of ITAAC for which all associated inspections have been completed during the reporting period.
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Vogtle 3 66 25 5 23 Vogtle 4 127 2 2 1 ITAAC Reviews Completed for the Reporting Period (Q1 FY 2022) 25 24F The table below provides ITAAC closure notification reviews completed during the reporting period for Vogtle Units 3 and 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 2.5.05.03b 10/27/21 10/28/21 Vogtle 3 2.2.03.01 10/22/21 10/25/21 Vogtle 3 2.3.07.02a 10/22/21 10/25/21 Vogtle 3 2.5.01.03e 10/18/21 10/22/21 Vogtle 3 2.5.05.03b 10/20/21 10/21/21 Vogtle 3 2.6.06.01.i 10/12/21 10/20/21 Vogtle 3 3.3.00.07d.v.b 10/18/21 10/20/21 Vogtle 3 3.3.00.07d.v.c 10/18/21 10/20/21 Vogtle 3 3.3.00.07d.v.a 10/18/21 10/20/21 Vogtle 3 2.3.07.07c 10/13/21 10/18/21 Vogtle 3 2.3.03.04 10/08/21 10/14/21 Vogtle 3 2.2.01.08 10/08/21 10/14/21 Vogtle 3 3.3.00.07d.iv.a 10/07/21 10/12/21 Vogtle 3 3.3.00.07d.iv.b 10/07/21 10/12/21 Vogtle 3 3.3.00.07d.iv.c 10/07/21 10/12/21 Vogtle 3 2.2.04.12a.i 10/05/21 10/07/21 Vogtle 3 2.2.03.08c.viii 10/01/21 10/05/21 Vogtle 3 3.3.00.02a.i.c 09/24/21 10/05/21 Vogtle 3 2.2.03.08b.01 09/24/21 10/04/21 Vogtle 3 2.1.01.04 11/10/21 11/30/21 Vogtle 3 2.5.05.02.i 11/24/21 11/29/21 Vogtle 3 3.3.00.10.ii 11/11/21 11/22/21 Vogtle 3 2.7.04.03 11/17/21 11/18/21 Vogtle 3 3.3.00.01 11/08/21 11/16/21 Vogtle 3 3.3.00.02a.i.d 11/12/21 11/15/21 Vogtle 3 2.2.03.08c.ix 11/11/21 11/15/21 Vogtle 3 3.3.00.10.i 11/04/21 11/15/21 Vogtle 3 C.2.6.09.03b 10/08/21 11/15/21 Vogtle 3 2.2.01.11a.iii 11/05/21 11/15/21 Vogtle 3 2.3.13.05.i 11/03/21 11/05/21 25 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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Vogtle 3 E.3.9.06.00.04 10/27/21 11/01/21 Vogtle 3 2.3.06.05a.i 10/29/21 11/01/21 Vogtle 3 2.2.04.02a 12/02/21 12/06/21 Vogtle Units 3 and 4 License Amendment Request Reviews Completed (Q1 FY 2022)
Number of License Amendment Request Number of License Amendment Request Reviews Forecast to be Completed in the Reviews that Were Completed in the Reporting Reporting Period Period 2 4 2-6 NuScale Small Modular Reactor Design Certification On March 15, 2017, the NRC accepted the NuScale Power, LLC (NuScale) application for a small modular reactor (SMR) design certification review. The NRC staff completed the final Safety Evaluation Report on August 28, 2020 (ADAMS Package No. ML20023A318), and issued a standard design approval to NuScale on September 11, 2020 (ADAMS Accession No. ML20247J564). On January 14, 2021, the NRC staff provided the Commission with a draft proposed rule that proposes certifying the design for its consideration (ADAMS Package No.
ML19353A003). On May 6, 2021, the Commission approved the publication of the proposed rule (ADAMS Package No. ML21126A153), and on July 1, 2021, the proposed rule was published for public comment in the FR (86 FR 34999) with a comment period ending August 30, 2021. During the public comment period, the staff received a request, submitted on behalf of two public interest groups, to extend the public comment period (ADAMS Accession No. ML21209A763). On August 24, 2021, the NRC staff published a FR notice extending the public comment period by 45 days to October 14, 2021 (86 FR 47251). The NRC staff is scheduled to provide the draft final rule for its consideration by March 25, 2022.
Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
NuScale Small Modular Reactor Design Projected Completion Date Certification Activities Completion Date Public comment period ended for proposed rule for 10/14/21 10/14/21 26 NuScale SMR design certification.
25F Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY2022)
Projected NuScale Small Modular Reactor Design Certification Projected Activities Completion Date Provide the Commission the draft final rule for its consideration. 03/25/22 2-7 Advanced Nuclear Reactor Technologies The NRC continues to make significant progress in preparation for reviewing non-light-water-reactor (non-LWR) designs, consistent with the NRC staffs vision and strategy (ADAMS Accession No. ML16356A670) and implementation action plans to achieve non-LWR safety review readiness. 27 During this reporting period, the NRC staff issued several draft guidance 26F documents. The staff also continued its extensive stakeholder engagement, including holding 26 In the last report, this was erroneously reported as a projected activity, even though it was already completed.
27 The NRCs public Web site 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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several public meetings and workshops regarding various advanced reactor topics, development of the 10 CFR Part 53 proposed rule, and development of guidance for the content of advanced reactor licensing applications. Additionally, the staff provided to the Commission for its consideration the draft Advanced Nuclear Reactors Generic Environmental Impact Statement and draft proposed rule that would codify the generic findings of the Generic Environmental Impact Statement (ADAMS Accession No.ML21222A053), as well as the draft final rule on emergency preparedness requirements for SMRs and other new technologies (ADAMS Accession No. ML21200A059).
In addition, the NRC staff continues to release for public comment various subparts for the 10 CFR Part 53 preliminary proposed rule, including technical, licensing, and administrative requirements on an iterative basis. During the reporting period, the NRC staff released additional sections of the preliminary proposed rule language for 10 CFR Part 53 (ADAMS Accession Nos. ML21267A006, ML21267A004, ML21348A123, ML21148A173, ML21270A005, ML21308A028, ML21308A026, and ML21319A135). The NRC staff discussed portions of the released preliminary proposed rule language with stakeholders during public meetings on October 26 and October 28, 2021 (ADAMS Accession Nos. ML21288A403 and ML21288A407).
The NRC staff briefed the Advisory Committee on Reactor Safeguards (ACRS) on topics related to the Part 53 preliminary proposed rule on November 18 and December 16-17, 2021. Details of these ACRS meetings can be found on the NRCs public Web site (https://www.nrc.gov/reading-rm/doc-collections/acrs/agenda/index.html).
In October 2021, the NRC staff requested a 9-month extension to the current schedule for the Part 53 rulemaking. The NRC staff requested the extension based on consideration of stakeholder requests for an option for a more traditional, deterministic licensing framework for advanced reactors. In addition, the NRC staff recognized that more time would support further engagement with stakeholders, as well the ACRS, before sending a draft proposed rule to the Commission. The Commission approved the NRC staffs extension request. The NRC staff now anticipates providing the Commission the Part 53 draft proposed rule package by February 2023 and the draft final rule package, including key guidance, to the Commission by December 2024. The NRC staff is expecting to issue the final rule by July 2025. Further details about the staffs basis for the schedule extension can be found on the NRCs public Web site (https://www.nrc.gov/reactors/new-reactors/advanced/rulemaking-and-guidance/part-53.html).
The NRC holds periodic stakeholder meetings to discuss non-LWR topics of interest. A list of the meetings that the NRC has conducted to date can be found on the NRCs public Web site (https://www.nrc.gov/reactors/new-reactors/advanced/details.html#stakeholder). The NRC also holds frequent public meetings 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 Web site (https://www.nrc.gov/reactors/new-reactors/advanced/details.html#advRxContentAppProj).
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 Web site (https://www.nrc.gov/reactors/new-reactors/advanced/ongoing-licensing-activities/pre-application-activities.html).
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Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date Made public a preliminary draft version of RG 1.247 on the acceptability of non-LWR probabilistic risk 12/31/21 10/05/21 28 assessments and presented it to the ACRS 27F (ADAMS Accession No. ML21246A216).
Issuance of a scalable human factors engineering technical review strategy report by Brookhaven 10/31/21 10/12/21 National Laboratory under contract with the NRC (ADAMS Accession No. ML21287A088).
Issued several draft white papers on specific chapters or topics of information to be included in 10/21/21, an advanced reactor application to support the 10/31/21 11/04/21 30 ARCAP (ADAMS Accession Nos. ML21294A266 29F and ML21309A020). 29 28F Issued final safety evaluation for Kairos topical report on quality assurance (ADAMS Accession No. 11/30/21 11/12/21 ML21308A599).
Submitted draft Advanced Nuclear Reactors Generic Environmental Impact Statement and associated draft proposed rule to the Commission 11/30/21 11/29/21 for its consideration (ADAMS Package No.
Issued an updated draft white paper regarding use of the industry-led Technology-inclusive Content of Application Project (TICAP) guidance to inform 10/31/21 12/02/21 31 specific portions of the safety analysis report 30F included as part of an advanced reactor license application (ADAMS Accession No. ML21336A697).
Issued an updated draft white paper on ARCAP guidance regarding the content of an advanced 10/31/21 12/02/21 3231F reactor application and a roadmap to support NRC 28 The original activity to publish the trial use RG 1.247 was projected to be completed by December 31, 2021. The activity shown here indicates that a preliminary draft version was made publicly available. Final publishing of the draft RG was delayed in order to incorporate stakeholder feedback.
29 The NRCs public Web site (https://www.nrc.gov/reactors/new-reactors/advanced/details.html#advRxContentAppProj) provides a complete listing of the draft white papers that the staff has issued to date as well as industry guidance documents. The listing of these draft documents provides a reference that is used to support stakeholder interactions during public meetings on the topic.
30 Issuance delayed from the previous projected date of October 31, 2021, to provide additional time for the staff to incorporate concepts into these documents based on stakeholder interactions at public meetings in October and November. Additional future updates to these draft white papers prior to issuance for formal public comment are possible.
31 Issuance delayed from the previous projected date of October 31, 2021, to provide additional time for the staff to incorporate concepts into these documents based on stakeholder interactions at public meetings in October and November. Additional future updates to these draft white papers prior to issuance for formal public comment are possible.
32 Issuance delayed from the previous projected date of October 31, 2021, to provide additional time for the staff to incorporate concepts into these documents based on stakeholder interactions at public meetings in October and November. Additional future updates to these draft white papers prior to issuance for formal public comment are possible.
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Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date staff review (ADAMS Accession No. ML21336A702).
Released preliminary proposed rule language for 10 CFR Part 53 technical requirements (ADAMS 10/15/21, Accession Nos. ML21267A004, ML21270A005, 10/31/21 12/21/21, ML21267A006, ML21148A173, and 12/29/21 33 32F ML21348A123).
Submit a paper to the Commission providing the Emergency Preparedness Requirements for Small Modular Reactors and Other New Technologies 12/30/21 01/03/22 draft final rule for its consideration (ADAMS Accession No. ML21200A055).
Issuance of a report by the Center for Nuclear Waste Regulatory Analyses under contract with NRC addressing information gaps and potential 03/31/22 12/15/21 information needs associated with transportation and storage of fresh and spent advanced reactor fuel types (ADAMS Accession No. ML21349A914).
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Completion Projected Advanced Nuclear Reactor Technologies Activities Date Issue final safety evaluation to Abilene Christian University for its 01/31/22 34 topical report on quality assurance program description.
33F Release consolidated preliminary proposed rule language for 10 01/31/22 CFR Part 53.
Issue annual paper to the Commission on the status of advanced 02/28/22 reactor readiness activities Issue final safety evaluation to TerraPower for its topical report on 02/28/22 35 34F quality assurance program description.
Publish final NUREG-2246, Fuel Qualification for Advanced Reactors, with fuel qualification methodology to provide guidance 02/28/22 for non-LWR developers on qualification of fuel under the Nuclear Energy Innovation and Modernization Act.
Issue NRC staff technical letter report documenting the technical basis regarding potential endorsement of American Society of 02/28/22 Mechanical Engineers (ASME)Section III, Division 5 Code Cases N-872 and N-898 for Alloy 617.
33 This activity was previously projected for completion by October 31, 2021, but consistent with the Commission approved 9-month schedule extension for the Part 53 rulemaking, additional time was needed to develop the first iteration of preliminary proposed rule language for fitness for duty and decommissioning requirements. Release of the preliminary proposed rule language for decommissioning requirements completed the initial release for all 10 CFR Part 53 technical requirements. The NRC staff expects to release consolidated preliminary proposed rule language for 10 CFR Part 53 in the next quarter (Q2 FY 2022) and will continue to release preliminary proposed rule language on an iterative basis.
34 The projected completion date was changed from October 28, 2021, to January 31, 2022, to provide additional time for internal review.
35 The projected completion date was changed from December 31, 2021, to provide additional time for internal review.
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Projected Completion Projected Advanced Nuclear Reactor Technologies Activities Date Issue final safety evaluation to Kairos for its topical report on 03/31/22 36 regulatory analysis.
35F Issue final safety evaluation to Kairos for its topical report on 03/31/22 metallic material qualification program.
Issue final safety evaluation to Kairos for its topical report on 03/31/22 mechanistic source term.
Issue final safety evaluation to Kairos for its topical report on fuel 03/31/22 performance methodology.
Issue final safety evaluation to Kairos for its topical report on fuel 03/31/22 qualification methodology.
Publish trial use RG 1.247 for potential endorsement of the ASME/American Nuclear Society standard on non-LWR 03/31/22 probabilistic risk assessments.
Publish Revision 1 to draft Regulatory Guide DG-1380 for potential endorsement of ASME Section III, Division 5 Code 03/31/22 Cases N-872 and N-898 for Alloy 617.
Submit draft proposed rule providing the alternative physical security requirements for advanced reactors to the Commission 06/28/22 for its consideration.
Publish the final RG (RG 1.246) for potential endorsement of the ASME Boiler and Pressure Vessel Code Section XI, Division 2, 06/30/22 Reliability and Integrity Management standard.
2-8 Advanced Reactor Licensing Reviews 37 36F Oklo Aurora Custom COL Application Review Oklo Inc. (Oklo) submitted a custom COL application 38 for the Aurora advanced reactor design 37F on March 11, 2020 (ADAMS Package No. ML20075A000). The NRC staff planned to complete the review of the Oklo COL application using an innovative two-step process (ADAMS Accession No. ML20149K616). On November 17, 2020, the NRC staff issued a letter to Oklo (ADAMS Accession No. ML20308A677), extending the Step 1 review schedule in the areas of maximum credible accident methodology, safety classification of structures, systems, and components (SSCs), and scope of the quality assurance program. Because Oklos quality assurance program is closely tied to its safety classification of SSCs, these issues were combined and were no longer tracked separately. In the letter, the NRC staff stated that Oklos responses to requests for additional information (RAIs), audit documents, and audit discussions enhanced the staffs understanding of Oklos novel approach to the Aurora safety case but did not provide sufficient information to define the scope of the full Step 2 technical review. The NRC staff completed its review of one of the key aspects of the licensing basis, the applicability of regulations, and issued a letter documenting Step 1 closure on this topic on November 17, 36 This activity was previously projected for completion by December 31, 2021, but additional time is needed because the vendor has decided to submit a revision to the topical report.
37 This section was previously titled Oklo Power LLC Combined License Application for the Aurora Compact Fast Reactor. It is being broadened to allow for a more thorough discussion of the status of advanced reactor application reviews. Applications will be added to this section once they are accepted by the NRC.
38 A custom COL application provides both the design information that would be provided by a certified design and the site-specific information provided with a COL application.
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2020 (ADAMS Accession No. ML20300A593). To close the Step 1 review, Oklo proposed to leverage two topical reports, Maximum Credible Accident Methodology and Performance-Based Licensing Methodology, to support the staffs review of methodologies for the maximum credible accident and classification of SSCs. Oklo submitted the topical reports on July 2, 2021 (Letter Submitting the Reports (ADAMS Accession No. ML21184A001), Topical Report on Maximum Credible Accident Methodology (ADAMS Accession No. ML21184A002), and Topical Report on Performance-Based Licensing Methodology (ADAMS Accession No. ML21187A001)). The NRC staff performed threshold reviews of the topical reports and determined that they lacked sufficient information to initiate the detailed technical reviews. On August 5, 2021, the staff provided Oklo written descriptions of the needed supplemental information and requested that Oklo submit it within 60 days (ADAMS Package Nos.
ML21201A010 and ML21201A104). On October 5, 2021, Oklo submitted a revision to the Maximum Credible Accident Methodology topical report (ADAMS Accession Nos.
ML21278B097 and ML21278B098). On October 19, 2021, Oklo submitted a revision to the Performance-Based Licensing Methodology topical report (ADAMS Accession Nos.
ML21292A326 and ML21292A327). The NRC staff performed subsequent threshold reviews of the revised topical reports and supplemental information and found that Oklo had not provided sufficient technical information to resolve the previously identified deficiencies in the topical reports or to respond to specific questions in the RAIs. The topical reports lacked sufficient information in key areas necessary for the NRC staff to determine whether the methodologies will support regulatory findings of reasonable assurance of adequate protection of public health and safety. On January 6, 2022, the staff notified Oklo that the topical reports did not contain sufficiently complete information for the NRC staff to initiate detailed technical reviews (ADAMS Accession No. ML21307A108). Also, on January 6, 2022, the staff ended its review of the Oklo COL application and denied the COL application, without prejudice (ADAMS Accession No. ML21357A034), based on Oklos failure on a number of occasions to provide necessary technical information to support developing a review schedule or reaching findings on the safety of the facility that the NRC must make before issuing a license.
The NRC staff held periodic public meetings to discuss the review of the COL application for the Oklo Aurora design. A list of the meetings can be found on the NRCs public Web site (https://www.nrc.gov/reactors/new-reactors/col/aurora-oklo/public-meetings.html).
Because the staff denied this COL application, this project will no longer be included in this report as an ongoing advanced reactor licensing action.
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 applications documents to the NRC by letters dated September 29, 2021 (submitting the Preliminary Safety Analysis Report) (ADAMS Package No. ML21272A375) and October 31, 2021 (submitting the Environmental Report) (ADAMS Accession No. ML21306A131).
The NRC staff performed an acceptance review of the Hermes construction permit application and docketed the application on November 29, 2021 (ADAMS Accession No. ML21319A354).
On December 15, 2021, the staff issued a letter to Kairos (ADAMS Accession No. ML21343A214) providing the schedule and resource estimates for the review. The NRC staff is currently conducting a detailed technical review of the safety of the Hermes design which will lead to a safety evaluation report. The NRC staff is also conducting a review of the effects of Hermes design on the environment and will document the review in a draft environmental 21
impact statement. Application documents and information on the review are available on the NRCs public Web site (https://www.nrc.gov/reactors/non-power/hermes-kairos.html).
Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Advanced Reactor Licensing Review Activities Projected Completion Date Completion Date Completed acceptance review of the Kairos Hermes construction permit application (ADAMS Accession N/A 39 38F 11/29/21 No. ML21319A354).
Issued letter to Kairos providing the schedule and resource estimate for the review of the Hermes N/A 40 12/15/21 construction permit application (ADAMS Accession 39F No. ML21343A214).
Completed acceptance review of two Oklo topical reports submitted in July 2021 and revised in 01/10/22 01/06/22 41 October 2021 (ADAMS Package Nos.
40F ML21201A010 and ML21201A104).
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Advanced Reactor Licensing Review Activities Completion Date Complete draft safety evaluation report for the Kairos Hermes 2/28/22 construction permit application.
Identify if any need for additional information on the Kairos Hermes TBD depending construction permit application, prepare RAIs, and issue RAIs to Kairos. on need 2-9 Reactor Oversight Process The Reactor Oversight Process (ROP) is a risk-informed, performance-based oversight program that contains provisions for continuous self-assessment and improvement. The NRC staff developed recommendations for proposed changes to the ROP in SECY-18-0113, Recommendations for Modifying the Reactor Oversight Process Engineering Inspections (ADAMS Accession No. ML18144A567), and SECY-19-0067, Recommendations for Enhancing the Reactor Oversight Process (ADAMS Accession No. ML19070A050). The staff requested to withdraw these papers, and on August 5, 2021, the Commission approved the staffs proposed withdrawal. The staff intends to evaluate the basis for the previous recommendations in light of new information and is engaging internal and external stakeholders, including regional inspection staff, members of the public, and the nuclear industry, on these and any other proposed changes to the ROP, as appropriate. The staff also continues to assess and improve the ROP as part of its normal work practices through the NRCs transformation activities, stakeholder correspondence, feedback from ROP public meetings, and the ROP self-assessment program. Significant changes to the ROP will be submitted to the Commission for either approval or notification in accordance with Management Directive 8.13, Reactor Oversight Process.
39 This activity was not previously reported due to the expansion of this section.
40 This activity was not previously reported due to the expansion of this section.
41 The projected completion date was changed from November 30, 2021 to provide additional time for internal review.
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Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Projected Reactor Oversight Process Activities Completion Date Completion Date Completed Comprehensive Baseline Inspection Program Review focused on lessons learned from 10/31/21 11/05/21 42 the COVID-19 public health emergency and issued 41F report (ADAMS Accession No. ML21252A154).
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Reactor Oversight Process Activities Completion Date Complete CY 2021 ROP Self-Assessment and send information paper to 04/15/22 the Commission.
2-10 Backfit The NRCs backfitting rules are codified in 10 CFR 50.109, 70.76, 72.62, and 76.76. 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. 43 The rules require, in the absence of an 42F 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.
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 (ADAMS Accession No. 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 (ADAMS Accession No. ML18109A498). This revision would provide additional guidance for the NRC staff on how to implement the Commissions backfitting and issue finality regulations and policies and forward fitting policy, including how to process violations that are contested based on claims of unjustified backfitting. 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) (ADAMS Package 42 The projected completion date was changed from October 31, 2021, to November 5, 2021, to provide additional time for internal review.
43 10 CFR 50.109(a)(1). Substantially similar definitions are provided in § 70.76, Backfitting, § 72.62, Backfitting, and § 76.76, Backfitting, for non-reactor facilities.
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No. ML21006A431). This revised document is currently before the Commission for its consideration.
Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Projected Backfit Activities Completion Date Completion Date Completed determination (ADAMS Accession No. ML21064A350) that a proposed technical specification, pertaining to degraded voltage protection at the Oconee Nuclear Station, is not 07/31/21 07/26/21 required under 10 CFR 50.36(c)(3), in accordance with the NRCs backfit rule (ADAMS Accession No. ML21047A241). 44 43F Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Backfit Activities Completion Date Publish proposed rule that contains a proposed change to NRC regulations that would constitute backfitting if issued as a final rule:
Regulatory Improvements for Production and Utilization Facilities 03/04/22 Transitioning to Decommissioning (ADAMS Package No.
2-11 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 2-7, to individual undertakings in program and corporate offices. 45 The NRC staff continues to 44F implement and track 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 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors and Risk-Informed Technical Specifications Initiative 4b, 46 that provide for operational flexibilities that enhance 45F safety by ensuring that power reactor licensees and the NRC prioritize the most risk significant issues.
44 This activity was previously reported as completed for development of a recommendation. This should have been reported as completion of a determination and therefore is being included again for correction.
45 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.
46 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 24 and 17 applications enabling licensees to adopt 10 CFR 50.69 and Risk-Informed Technical Specifications Initiative 4b, respectively.
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Activities Planned and Completed for the Reporting Period (Q1 FY 2022)
Projected Risk-Informed Activities Completion Date Completion Date Completed the license termination process for General Atomics TRIGA Mark I and Mark F non-power research reactors, License No. R-38 and 12/31/21 12/07/21 License No. R-67, respectively (ADAMS Accession No. ML21281A171).
Completed participation in an expert panel exercise to characterize the safety impacts of spent fuel cladding gross ruptures. The Phenomena Identification and Ranking Table panel report, published by the Electric Power Research Institute 09/30/21 12/22/21 47 46F (EPRI), will provide the technical basis for engagements with external stakeholders to identify operational and licensing efficiencies for spent fuel storage systems.
Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2022)
Projected Projected Risk-Informed Activities Completion Date Complete pilot program of risk tool to risk-inform technical reviews for 01/31/22 48 spent fuel dry storage (ADAMS Accession No. ML20318A269).
47F Complete the acceptance review for the first-of-a-kind Risk-informed Process for Evaluations (RIPE) submittal regarding the diverse auxiliary 02/04/22 feedwater actuation system for Palo Verde Nuclear Generating Station.
Complete report summarizing the Office of Nuclear Reactor Regulation (NRR) activities regarding the use of risk-informed decision-making (RIDM) for licensing reviews. The report will detail NRRs efforts to 02/28/22 49 increase the use of RIDM and will provide recommendations on how to 48F proceed into the next phase of realizing NRRs goal to enhance process efficiency and effectiveness.
Complete the revision of 10 materials inspection procedures (IPs) associated with Inspection Manual Chapter 2800. The NRC staff 03/31/22 50 developed risk modules in each IP, with each module focusing on the 49F risks of the relevant types of radioactive materials and their usage.
Develop guidance for use of RIPE in Technical Specification LARs. 06/30/22 2-12 Coronavirus Disease (COVID-19) Pandemic 47 This activity was erroneously listed as completed in the previous report. While the panel was completed, the report was not issued until December 22, 2021. The report is available on EPRIs Web site:
https://www.epri.com/research/products/000000003002020929.
48 The projected completion date was changed from December 31, 2021, to January 31, 2022, because additional time is needed to consider feedback from risk tool users for the next steps of development.
49 The projected completion date was changed from December 31, 2021, to February 28, 2022, because additional time is needed for the staff to finalize the recommendations in the report on the next phase of enhancing RIDM process efficiency and effectiveness.
50 The projected completion date was changed from December 31, 2021, to March 31, 2022, to allow for additional time to address stakeholder comments and revisions.
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The NRC COVID-19 Coordination Team (including a COVID-19 Task Force and Working Group) continues to develop and implement precautionary measures in response to the pandemic 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. In addition, the NRC continues to protect public health and safety and the environment. The NRC is monitoring the effects of the COVID-19 pandemic 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.
NRC Re-Occupancy of Facilities During this reporting period, the NRC executed its re-entry plans on November 7, 2021 and shifted to a hybrid environment at all locations, combining telework and in-office staff presence. Coinciding with re-entry, the NRC staff issued updated guidance for implementation of inspection programs following re-entry (ADAMS Accession No. 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. The NRC has been proactive in responding as circumstances warrant. Namely the agency recently decided in response to the omicron variant to allow employees maximum flexibilities to telework through February 26, 2022.
Licensing and Oversight Items of Interest The NRC staff has taken steps to identify areas of our regulations that are 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 continues to communicate 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 Web site (https://www.nrc.gov/about-nrc/covid-19/).
The NRC has also developed portions of its Web site 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 have been developed to keep the public informed on how the NRC is adapting its regulatory approach during the pandemic. Between October 1 and December 30, 2021, the NRC approved ten licensing actions granting temporary flexibilities to maintain the safe and secure operation of nuclear reactor and nuclear materials licensees. A complete list of licensing requests approved by the NRC in response to the COVID-19 pandemic is available on the NRC public Web site 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 Number of COVID-19 Average Number of Licensee Type Requests Approved During Days to Review the Reporting Period COVID-19 Requests 51 50F Power Reactor 3 10 Non-Power Reactor 0 N/A Other (e.g., topical reports) 0 N/A Decommissioning of Nuclear 0 Facilities and Uranium Recovery N/A Storage and Transportation of 0 Spent Nuclear Fuel N/A Fuel Cycle Facilities 6 20 Medical, Industrial and Academic Uses of Nuclear Materials and 1 14 Agreement States 51 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 Findings The table below provides the calendar year (CY) Reactor Oversight Process (ROP) findings for the year-to-date (YTD) and 3-year rolling metrics.
Location Number of Findings CY 2018 CY 2019 CY 2020 CY2021 Nationally Total 478 440 291 269 52 51F Green 107 95 50 58 White 1 0 0 1 Yellow 0 0 0 0 Red 0 0 0 0 Region I Greater Than Green 0 0 0 0
Security Total 108 95 50 59 No. of Units 25 24 21 53 21 Operating During CY 52F Green 113 110 77 66 White 0 1 2 0 Yellow 0 0 0 0 Red 0 0 0 0 Region II Greater Than Green 0 0 1 0 Security Total 113 111 80 66 No. of Units 33 33 33 33 Operating During CY Green 110 96 51 64 White 2 1 0 0 Yellow 0 0 0 0 Region III 0 0 0 0 Red Greater Than Green 0 0 0 1 Security Total 112 97 51 65 52 The inspection reports for the fourth quarter of CY 2021 will continue to be finalized through February 15, 2022.
The report for the next reporting period will be updated to include any additional findings from the fourth quarter of CY 2021.
53 The reduction of three units for CY 2020 reflects the permanent shutdown of Pilgrim Nuclear Station on May 31, 2019; Three Mile Island, Unit 1, on September 20, 2019; and Indian Point Nuclear Generating Unit 2 on April 30, 2020.
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Location Number of Findings CY 2018 CY 2019 CY 2020 CY2021 No. of Units 23 23 22 54 22 Operating During CY 53F Green 145 137 110 79 White 0 0 0 0 Yellow 0 0 0 0 Red 0 0 0 0 Region IV Greater Than Green 0 0 0 0 Security Total 145 137 110 79 No. of Units 18 18 18 18 Operating During 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. 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 Percentage of Licensing Licensing of Licensing Licensing Reporting Total Actions Actions Actions Actions Period Inventory Initiated Completed Completed Completed During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule 5655F Schedule 5554F Q2 FY 2021 264 135 105 100% 96%
Q3 FY 2021 223 58 76 100% 100%
Q4 FY 2021 207 83 95 100% 94%
Q1 FY 2022 132 33 107 100% 94%
54 The reduction of one unit for CY 2020 reflects the permanent shutdown of Duane Arnold on August 10, 2020.
55 Consistent with previous reports, this excludes unusually complex and Fukushima-related licensing actions accepted or initiated prior to July 13, 2019.
56 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
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New Reactors Percentage Percentage Licensing Licensing of Licensing of Licensing Reporting Total Actions Actions Actions Actions Period Inventory Initiated Completed Completed Completed During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule Schedule Q2 FY 2021 2 0 0 N/A N/A Q3 FY 2021 2 1 1 100% 100%
Q4 FY 2021 2 1 1 100% 100%
Q1 FY 2022 2 3 3 100% 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 Q2 FY 2021 2 4 4 100% 75% 57 56F Q3 FY 2021 4 3 1 100% 100%
Q4 FY 2021 4 3 3 100% 0% 58 57F Q1 FY 2022 2 11 13 100% 92% 59 58F 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, 60 the LARs referenced in this section include requested activities of 59F the Commission for which the NRC staff issue a final safety evaluation. 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).
57 One licensing action was complex, which resulted in it exceeding the established schedule by 27 days. The licensing action was completed within the generic milestone schedule.
58 One licensing action was complex; the other three actions were completed within 13 days of the established schedule. All the licensing actions were completed within the generic milestone schedule.
59 One licensing action was complex due to security issues, which resulted in it exceeding the established schedule by 17 days.
60 Consistent with Section 102(c) of NEIMA, the NRC is focusing this section on the total inventory of LARs and will not be providing separate information on unusually complex LARs in this report and future reports. Should data on unusually complex LARs be available, it would instead be incorporated into the existing section 3-3 tables.
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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 61 60F Schedule 62 61F Q2 FY 2021 276 36 107 100% 90%
Q3 FY 2021 286 103 82 100% 98% 63 62F Q4 FY 2021 293 106 102 100% 91%
Q1 FY 2022 317 105 81 99% 95% 6463F 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 Q2 FY 2021 1 0 0 N/A N/A Q3 FY 2021 1 0 0 N/A N/A Q4 FY 2021 1 1 1 100% 100%
Q1 FY 2022 0 0 1 100% 100%
61 Consistent with previous reports, this excludes unusually complex and Fukushima-related LARs accepted or initiated prior to July 13, 2019.
62 The established schedule is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
63 One review of an LAR exceeded the established schedule by 180 days, due to the NRC staff identifying an issue that resulted in the licensee submitting a supplement that changed the scope of the request. Given the change in scope, a supplemental Federal Register Notice was published, providing for a new 30-day public comment period and a 60-day opportunity to request a hearing. The staff completed its review in September 2021.
64 One review of an LAR that proposed a first-of-a-kind design exceeded the established schedule by 180 days. The NRC staff identified an issue that resulted in the licensee submitting an update that expanded the licensees proposed submission and extended the staffs review. The staffs evaluation determined a regulatory audit was necessary to gain additional understanding of the design and identified additional information that required docketing by the licensee to support a staff decision on the LAR. With the efficiencies gained through the audit, the staff expects to complete its review in February 2022.
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Fuel Facilities 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 Q2 FY 2021 10 4 8 100% 75% 6564F Q3 FY 2021 10 8 8 100% 83%
Q4 FY 2021 13 7 4 100% 100%
Q1 FY 2022 5 5 13 100% 100%
3-4 Research Activities 66 65F 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.
65 Two licensing actions had delayed issuance at the end of the year, which resulted in both items exceeding the established schedule by 2 percent (5 days).
66 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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Summary of Completed Research Projects 67 66F During the reporting period, RES completed the following activities:
Request to Maintain NRC Capabilities to Perform Anticipated Transient Without SCRAM (ATWS) Confirmatory Reviews (NRR-2015-010)
Maintain NRC confirmatory capabilities to perform safety analysis of Importance to the anticipated transient without SCRAM for extended reactor operating NRC Mission windows to support licensing reviews.
The research program was requested to conduct an experimental study of fuel heat-up processes that were predicted to occur during ATWS scenarios. Licensees have requested amendments to expand their allowable operating domain to new power and flow conditions. Maximum extended load line limit analysis plus or extended flow window operation can exacerbate the consequences of ATWS events compared to plants operating at lower core power-to-flow ratios.
Research Results or Findings Based on the assessment of the experimental results, a new approach to modeling minimum stable film boiling was adopted in the NRCs TRACE thermal hydraulics code. Minimal stable film boiling is a thermal hydraulic phenomenon. The research produced a new experimental validation database, four peer-reviewed technical publications, a publicly available NUREG report detailing the experiments and findings, and several technical reports detailing the experimental setup, results, preliminary analysis of these results and the TRACE assessment.
Duration of the 6 years Project Estimate of Total 2.5 FTE and $2.2 M over the 6-year period Research Resources 67 The research project resources are estimates of staff hours and program support costs based on inspection of project records, including staffing plans and contract spending plans.
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3-5 Fees Billed The tables below provide information on Part 170 fees billed for each fee class. For each fee class, the NRC staff compared the fees billed to the receipts estimated in the annual fee rule. 68 67F FY 2021 Part 170 Part 170 Billed in Total Part 170 - Billed Fee Class Receipts Estimated - Q1 FY 2022 ($M) in FY 2022 ($M)
Annual Fee Rule ($M)
Fuel Facilities $7.4 $2.3 $2.3 Generic $0.5 $0.9 $0.9 Decommissioning Materials Users 69 68F
$1.0 $0.2 $0.2 Operating Power $157.0 $44.5 $44.5 Reactors Research and $3.7 $0.7 $0.7 Test Reactors Spent Fuel Storage / Reactor $12.4 $3.9 $3.9 Decommissioning Transportation $3.6 $1.0 $1.0 Uranium Recovery $0.3 $0.2 $0.2 Significant Ongoing Licensing Actions The following table includes a comparison of the fees billed to projected resources for subsequent license renewal application reviews, Oklos Aurora COL application review, the SHINE Medical Technologies, LLC (SHINE) operating license application review, and the Kairos Hermes construction permit application review.
Projected Fees Billed Docket Project Name Resources to Date
($M) 70 69F ($M) 71 70F Point Beach Units 1 and 2 Point Beach Units 1 and 2 $5.0 72 $2.3 Subsequent License Renewal 05000266/05000301 71F Application Safety Review 68 The FY 2021 Final Fee Rule estimated collections are being used until the FY 2022 Proposed Fee Rule is published. The FY 2021 Final Fee Rule was published on June 16, 2021 (86 FR 32146).
69 Materials UsersBilled as flat fee applications and included in the estimates and billed.
70 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.
71 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 October, November, and December, would be invoiced to the licensee/applicant in January. Therefore, the total billed amounts listed in Table 3-5 reflects costs for NRC work performed through September 2021.
72 When the formal acceptance letter for the Point Beach subsequent license renewal application was sent to the licensee on January 15, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21006A417), the NRC estimated that it would take approximately $6.4M to complete the application review.
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Projected Fees Billed Docket Project Name Resources to Date
($M) 7069F ($M) 71 70F Point Beach Units 1 and 2 Point Beach Units 1 and 2 Subsequent License Renewal $1.4 $1.0 05000266/05000301 Application Environmental Review North Anna Units 1 and 2 North Anna Units 1 and 2 $5.0 73 $2.9 Subsequent License Renewal 05000338/05000339 72F Application Safety Review North Anna Units 1 and 2 North Anna Units 1 and 2 Subsequent License Renewal $1.4 $1.2 05000338/05000339 Application Environmental Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 05000269/05000270/ Subsequent License Renewal $5.0 74 73F $1.4 05000287 Application Safety Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 Subsequent License Renewal $1.4 $0.2 05000269/05000270/
Application Environmental 05000287 Review SHINE Medical Isotope SHINE Medical Production Facility Operating Technologies, LLC License Application Review $6.2 75 74F
$4.9 05000608 Safety and Environmental Reviews Oklo Aurora COL Application Oklo Aurora 05200049 - Safety and Environmental $0.7 77 76F $0.5 Reviews 76 75F St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 Subsequent License
$5.0 78 $0.3 05000335/05000389 Renewal Application 77F Safety Review St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 Subsequent License $1.4 $0.1 05000335/05000389 Renewal Application 73 When the formal acceptance letter for the North Anna subsequent license renewal application was sent to the licensee on October 13, 2020 (ADAMS Accession No. ML20258A284), the NRC estimated that it would take approximately $6.4M to complete the application review.
74 When the formal acceptance letter for the Oconee subsequent license renewal application was sent to the licensee on July 22, 2021 (ADAMS Accession No. ML21194A245), the NRC estimated that it would take approximately
$6.4M to complete the application review.
75 The projected resource estimate was provided to SHINE by letter dated April 30, 2020 (ADAMS Accession No. ML20114E315).
76 In prior reporting periods the fees billed for the Oklo COL Application were attributed to the safety review. These fees encompass both the safety and environmental reviews, as now reflected in the table text.
77 On January 6, 2022, the NRC staff notified Oklo of its decision to deny the Aurora COL application, without prejudice, (ADAMS Accession No. ML21357A034). Because the staff denied this COL application, this project will no longer be included in this report as an ongoing licensing action.
78 When the formal acceptance letter for the St. Lucie subsequent license renewal application was sent to the licensee on September 24, 2021 (ADAMS Accession No. ML21246A091), the NRC estimated that it would take approximately $6.4M to complete the application review.
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Projected Fees Billed Docket Project Name Resources to Date
($M) 70 69F ($M) 71 70F Environmental Review Kairos Hermes -
Kairos Hermes 05007513 Construction Permit - Safety $5.5 79 78F $0 and Environmental Reviews 3-6 Requests for Additional Information The table below provides information on requests for additional information (RAIs) associated with licensing actions that are considered requested activities of the Commission for which the NRC staff issues a final safety evaluation, 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 Number Total Inventory of of RAIs Number of Total Number of Type of Facility or Open RAIs as Responded RAIs Issued RAIs Closed in Activity Type of the End of to in in Reporting Reporting Period 80 Reporting Reporting 79F Period Period Period Operating Reactors 175 78 78 95 Non-Power Production and 23 Utilization 615 42 64 Facilities 81 80F Design Certifications for N/A N/A N/A N/A New Reactors 82 81F Early Site Permits N/A N/A N/A N/A for New Reactors 83 82F Combined Licenses 10 0 0 0 for New Reactors Construction 0 0 0 0 Permits for New 79 The projected resource estimated was provide to Kairos Power LLC by letter dated December 15, 2021 (ADAMS Accession No. ML21343A214).
80 RAIs are considered closed once the final safety evaluation, 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.
81 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 10 CFR Part 50, including the ongoing review of the SHINE operating license application.
82 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.
83 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 Number Total Inventory of of RAIs Number of Total Number of Type of Facility or Open RAIs as Responded RAIs Issued RAIs Closed in Activity Type of the End of to in in Reporting Reporting Period 80 Reporting Reporting 79F Period Period Period Reactors or Non-Power Production and Utilization Facilities 84 83F Fuel Facilities 20 11 15 51 Power Reactor 99 24 39 17 Decommissioning Research and Test Reactor 0 0 0 0 Decommissioning Spent Fuel 680 55 20 3 Materials 0 0 0 0 Pre-Application Activities for 9 5 0 0 Advanced Reactors 84 This activity was added to track performance on construction permit applications for new light water reactors, advanced reactors, and non-power production and utilization facilities.
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3-7 Workforce Development and Management FY 2022 Staffing by Office 85 84F End of Year FTE FTE FTE FTE Delta (Q1 FTE Delta (EOY (EOY) 86 FY 2022 Utilization Utilization Utilization Utilization Utilization - Projection -
85F Projection w/
Budget 09/26/21 - 10/24/21 - 11/21/21 - as of FY 2022 FY 2022 Personnel 10/23/21 11/20/21 12/18/21 12/18/21 Budget) Budget)
Actions Totals 2888.4 210.4 209.5 209.3 629.3 -2259.1 2768.6 -119.8 COMM 45.0 2.0 1.8 1.7 5.5 -39.5 32.7 -12.3 OIG 63.0 4.6 4.6 4.6 13.8 -49.2 60.6 -2.4 Totals Other 2780.4 203.8 203.1 203.1 610.0 -2170.4 2675.2 -105.2 Offices OCFO 92.0 6.5 6.7 6.8 20.0 -72.0 91.4 -0.6 OGC 90.7 7.4 7.5 7.5 22.3 -68.4 93.6 2.9 OCA 10.0 0.8 0.8 0.8 2.3 -7.7 9.8 -0.2 OCAA 7.0 0.5 0.5 0.5 1.6 -5.4 6.7 -0.3 OPA 13.0 1.0 1.0 1.0 3.0 -10.0 13.0 0.0 SECY 17.0 1.2 1.2 1.2 3.7 -13.3 17.0 0.0 OIP 34.0 2.5 2.5 2.5 7.6 -26.4 34.8 0.8 ASLBP 23.0 1.6 1.6 1.6 4.7 -18.3 21.3 -1.7 ACRS 23.5 1.8 1.9 1.8 5.4 -18.1 23.4 -0.1 OEDO 26.0 2.0 2.0 2.0 6.1 -19.9 26.8 0.8 NRR 565.6 40.2 40.0 40.1 120.3 -445.3 534.4 -31.2 NMSS 303.4 23.1 22.8 22.6 68.4 -235.0 298.1 -5.3 RES 203.5 15.1 14.7 14.8 44.5 -159.0 196.4 -7.1 NSIR 151.4 11.4 11.1 11.0 33.6 -117.8 145.7 -5.7 R-I 173.2 13.1 12.9 12.9 39.0 -134.2 164.4 -8.8 R-II 208.0 15.0 15.0 15.0 45.0 -163.0 193.4 -14.6 R-III 170.7 12.4 12.7 12.8 37.9 -132.8 164.9 -5.8 R-IV 160.9 13.1 12.9 13.0 38.9 -122.0 166.6 5.7 OE 31.5 2.4 2.4 2.4 7.1 -24.4 29.9 -1.6 OI 35.0 2.8 2.7 2.7 8.2 -26.8 34.3 -0.7 OCIO 169.0 11.3 11.3 11.2 33.8 -135.2 153.8 -15.2 ADM 121.0 8.7 8.9 8.8 26.4 -94.6 118.1 -2.9 SBCR 13.0 1.0 1.0 1.0 3.0 -10.0 13.5 0.5 OCHCO 135.0 8.8 8.9 8.9 26.6 -108.4 121.0 -14.0 CSU 3.0 0.2 0.2 0.2 0.6 -2.4 2.9 -0.1 85 Some numbers might not add due to rounding.
86 Based on FTE utilization as of December 18, 2021.
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3-8 Inspection Activities The table below shows the average number of hours of direct inspection per plant in CY 2021.
Average Reactor Oversight Process 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 1,685 Hours 1,624 Hours 2,397 Hours 87 3,450 Hours 88 Column 4 86F 87F The table below shows the staff hours expended for inspection-related effort at operating power reactor sites by CY.
Items Description CY 2020 (Hours) CY 2021 (Hours)
- i. Baseline Inspection 219,178 227,375 ii. Plant-Specific Inspection 7,521 4,773 iii. Generic Safety Issue Inspections 911 2,426 iv. Performance Assessment 1,880 3,486 89 88F
- v. Other Activities 86,074 91,971 vi. Total Staff Effort 315,563 330,030 vii. Total Staff Effort Per Operating Site 5,536 9089F 5,893 91 90F 87 As of December 31, 2021, Callaway Plant (one-unit Pressured Water Reactor (PWR)) was in Column 2 of the ROP Action Matrix (ROP Action Matrix). Surry Power Station Unit 2 (two-unit PWR) was in Column 2 in Q1 CY 2021 and returned to Column 1 on April 1, 2021 (ADAMS Accession No. ML20365A007). Clinton Power Station (one-unit Boiling Water Reactor (BWR)) was in Column 2 in Q1 and Q2 CY 2021 and returned to Column 1 on July 1, 2021 (ADAMS Accession No. ML21197A022). Turkey Point Nuclear Generating Unit 3 (two-unit PWR) was in Column 2 in Q1, Q2, and Q3 CY 2021 and returned to Column 1 on October 1, 2021 (ADAMS Accession No. ML21307A137). James A. Fitzpatrick (one-unit BWR) was in Column 2 in Q1, Q2, and Q3 CY 2021 and returned to Column 1 on October 1, 2021 (ADAMS Accession No. ML21308A407).
88 On March 3, 2021, Grand Gulf Nuclear Station (one-unit BWR) entered Column 3 of the ROP Action Matrix in Q4 CY 2020 (ADAMS Accession No. ML21055A008) and returned to Column 1 on November 18, 2021 (ADAMS Accession No. ML21306A311).
89 The increase in Performance Assessment hours is due to a change in tabulation of hours. The CY 2020 hours did not include hours assigned to ROP cycles other than 2020, while the CY 2021 hours includes ROP Cycle 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br /> charged in 2021. Applying the same methodology to the CY 2020 hours would increase the number to 3,569 from 1,880.
90 Total staff effort is divided by 57 sites for CY 2020, due to Three Mile Island Unit 1 permanently ceasing operations on September 20, 2019.
91 Total staff effort is divided by 56 sites for CY 2021, due to Duane Arnold Unit 1 permanently ceasing operations in August 2020. Because Duane Arnold Unit 1 operated for the majority of CY 2020, it was included as an operating site in CY 2020.
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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.
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