ML20209A528
| ML20209A528 | |
| Person / Time | |
|---|---|
| Issue date: | 08/12/2020 |
| From: | Kristine Svinicki NRC/Chairman |
| To: | Barrasso J, Braun M, Pallone F US HR (House of Representatives), US HR, Comm on Energy & Commerce, US SEN (Senate), US SEN, Comm on Environment & Public Works, US SEN, Subcomm on Clean Air & Nuclear Safety |
| Jaclyn Storch | |
| Shared Package | |
| ML20209A529 | List: |
| References | |
| CORR-20-0076 | |
| Download: ML20209A528 (36) | |
Text
STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION For the Reporting Period of April 1, 2020 through June 30, 2020
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 ........................................................ 3 1-3 Full-Time Equivalents (FTE) at the End of Q3 FY 2020 vs. Budgeted FTE ................................. 4 1-4 Budget Authority, FTE Utilization, and Fees ................................................................................. 4 - Status of Specific Items of Interest ................................................................. 6 2-1 Transformation .............................................................................................................................. 6 2-2 Workforce Development and Management .................................................................................. 7 2-3 Accident Tolerant Fuel .................................................................................................................. 7 2-4 Digital Instrumentation and Control ............................................................................................... 9 2-5 Vogtle Electric Generating Plant Units 3 and 4 ........................................................................... 11 2-6 NuScale Small Modular Reactor Design Certification................................................................. 13 2-7 Advanced Nuclear Reactor Technologies ................................................................................... 14 2-8 Oklo Power LLC (Oklo) Combined Operating License Application for the Aurora Compact Fast Reactor ........................................................................................................................................ 16 2-9 Reactor Oversight Process ......................................................................................................... 18 2-10 Backfit .......................................................................................................................................... 18 2-11 Risk-Informed Activities ............................................................................................................... 19 2-12 Coronavirus Disease 2019 Public Health Emergency ................................................................ 21 - Summary of Activities.....................................................................................23 3-1 Reactor Oversight Process Findings........................................................................................... 23 3-2 Licensing Actions ........................................................................................................................ 24 3-3 Licensing Amendment Request Reviews ................................................................................... 25 3-4 Research Activities ...................................................................................................................... 27 3-5 Fees Billed ................................................................................................................................... 31 3-6 Requests for Additional Information ............................................................................................ 33 3-7 Workforce Development and Management ................................................................................ 34 3-8 Inspection Activities ..................................................................................................................... 35 3-9 Backfit .......................................................................................................................................... 35 2
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%
(<100% = Completed Before 70%
60%
Schedule Date) 50%
40%
30%
Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule 1-2 Reactor Oversight Inspection Hours and Percent Complete 180,000 100%
Cumulative Percent of Planned Direct 160,000 90%
Direct Inspection Hours 140,000 80%
70%
120,000 60%
100,000 Inspection Hours Complete 50%
80,000 40%
60,000 30%
40,000 20%
20,000 10%
0 0%
Quarter 1 Quarter 2 Quarter 3 Quarter 4 Calendar Year (CY) 2019 Total Direct ROP Inspection Hours CY 2020 Total Direct ROP Inspection Hours Percent Complete of Total CY 2019 Planned ROP Direct Inspection Hours Percent Complete of Total CY 2020 Planned ROP Direct Inspection Hours 3
1-3 FTE at the End of Q3 FY 2020 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 0 100 200 300 400 500 600 FTE Budgeted FTE On Board FTE 1-4 Budget Authority, FTE Utilization, and Fees NRC FY 2020 Budget Authority - June 30, 2020 (Dollars in Thousands)
Fund Sources FY 2020 Budget 1 Percent Obligated Percent Expended Advanced Reactor $15,844 75% 47%
Commission Funds $11,953 36% 36%
Fee-Based Funds $825,430 69% 55%
General Funds $1,303 52% 23%
International Activities $14,500 58% 45%
Integrated University
$16,000 0% 0%
Program Official Representation $25 25% 19%
Total $885,055 67% 54%
NRC Control Points FY 2020 Budget Percent Obligated Percent Expended Nuclear Reactor Safety $447,940 72% 62%
Nuclear Materials and
$103,191 71% 58%
Waste Safety Decommissioning and
$22,891 73% 62%
Low-Level Waste Corporate Support $295,033 63% 42%
Integrated University
$16,000 0% 0%
Program Total $885,055 67% 54%
1 FY 2020 budget includes the enacted and carryover budget.
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FTE Utilization, Hiring, and Attrition Total Year to Date Projected End of Year Quarter 3 Quarter 3 YTD YTD (YTD) FTE Utilization FTE Total Utilization Hiring Attrition Hiring Attrition 2035.2 2795.2 20 33 61 152 FY 2020 Fees Estimated, Fees Billed, and Fees Collected Through Q3 2
$800,000
$700,000 Amount (Dollars in Thousands)
$600,000
$500,000
$400,000
$300,000
$200,000
$100,000
$0 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep 2020 2020 2020 2020 2020 2020 2020 2020 2020 2020 2020 2020 Total Estimated $195,851 $197,975 $200,031 $381,826 $383,854 $389,390 $575,757 $578,581 $581,030 $640,313 $766,571 $769,024 Total Actual Billed $187,802 $189,956 $192,538 $365,983 $368,664 $371,709 $371,489 $371,320 $371,198 $- $- $-
Total Actual Collected $124,193 $185,896 $190,225 $320,830 $364,708 $367,144 $368,776 $369,346 $369,784 $- $- $-
Total 10 CFR Part 170 Fees Billed (Dollars in Millions)
FY 2018 FY 2019 FY 2020 (Q1 - Q3)
$266.0 $245.3 $109.6 2 In order to temporarily mitigate the financial impacts and economic disruptions caused by the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE) for licensees, the NRC deferred all invoices scheduled to be issued in April, May, and June 2020 until July 22, 2020. See Enclosure 2, Section 2-12, Coronavirus Disease 2019 Public Health Emergency, for more information on NRCs PHE-related actions.
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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 quarter, and projected activities under each item for the next two quarters.
2-1 Transformation The U.S. Nuclear Regulatory Commissions (NRC) transformation initiative currently encompasses a broad set of activities intended to advance the agency towards the vision of being a more modern, risk-informed regulator. There are four focus areas: (1) recruiting, developing, and retaining a strong workforce; (2) improving decisionmaking 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.
During the reporting period, staff conducted an agencywide survey to identify elements of NRC culture that should be addressed to enhance the acceptance of transformation. The results of the survey highlighted behavioral trends of concern that will be addressed in a culture improvement plan. During this reporting period, staff also launched the Innovate NRC 2.0 technology platform to enhance the process by which innovative ideas can be collected, assessed, and implemented. On the day that it was launched, approximately one-third of agency staff accessed the platform and contributed several hundred examples of innovation from their work. Finally, with most staff working remotely during this reporting period, the staff benefited from efforts to adopt modern information technology tools, including those that support remote connectivity, electronic document sharing, and virtual meetings.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected Transformation Activities Completion Date Completion Date Conduct a staff survey to identify elements of the agency culture that should be addressed to 04/03/2020 04/03/2020 enhance the acceptance of transformation.
Implement a new process to recognize staff who contribute innovative ideas for improving the work of 05/31/2020 06/30/2020 3 the agency.
Launch the Innovate NRC 2.0 technology platform and begin agencywide training to facilitate 06/20/2020 06/18/2020 innovation, such as anticipated crowdsourcing.
Projected Activities for the Next Two Reporting Periods (Q4 FY 2020 and Q1 FY 2021)
Projected Projected Transformation Activities Completion Date Begin implementation of updated process to streamline Commission 07/30/2020 paper preparation.
3 The implementation of a new process to recognize staff who contribute innovative ideas was delayed to conduct additional pilot testing and to accommodate work schedule disruptions associated with the COVID-19 PHE.
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Projected Projected Transformation Activities Completion Date Conduct seminar for all agency staff on strategic and managerial aspects 09/01/2020 of risk-informed decisionmaking.
Brief the Commission on staffs transformation activities (public meeting). 09/17/2020 4 Develop the first iteration of the initial nuclear energy sector indicators to pilot in decisionmaking processes, such as workforce planning and the 09/30/2020 agency environmental scan development.
Complete training of senior leaders on behavior and how to effect 09/30/2020 5 cultural change as a part of the transformation initiative.
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. This process projects the amount and type of work anticipated in the next 5 years and identifies the workforce needs in order to perform it. By analyzing the current workforce and comparing it to future needs, skill gaps or surpluses 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.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Workforce Development and Management Projected Completion Date Activities Completion Date Onboard entry-level hires for NRCs new training program, the Nuclear Regulator Apprenticeship Network, and begin 14 weeks of initial training in 06/22/2020 06/22/2020 areas such as regulatory and technical fundamentals.
Continue SWP agencywide implementation by developing strategies and action plans based on the 06/27/2020 06/26/2020 workforce supply analysis and a prioritized list of workforce gaps and surpluses.
Projected Activities for the Next Two Reporting Periods (Q4 FY 2020 and Q1 FY 2021)
Projected Projected Workforce Development and Management Activities Completion Date Complete Agency Environmental Scan to support 2021 SWP activities. 09/30/2020 2-3 Accident Tolerant Fuel The NRC continues to make significant progress in its preparation for licensing reviews of Accident Tolerant Fuel (ATF) designs for use in U.S. commercial power reactors. The NRC 4 The Commission briefing on the staffs transformation activities was previously scheduled for May 18, 2020, but was postponed due to the COVID-19 PHE.
5 The training of senior leaders was previously scheduled for completion on June 30, 2020 but would be rescheduled.
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staff is currently executing the ATF project plan (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19301B166) and is preparing for imminent ATF submittals from fuel vendors in fall 2020. The NRC is currently reviewing an ATF-related request to allow the transportation of fuel rods with chromium-coated cladding and fuel rods enriched to up to 7 percent. Additionally, the NRC recently approved a license amendment to allow an enrichment facility to enrich fuel to 5.5 percent.
The NRC staff demonstrated the ability to perform confirmatory calculations for ATF applications in June 2020 with the use of the NRCs fuel rod thermal-mechanical Fuel Analysis under Steady-state and Transients (FAST) code. NRC staff used FAST during an audit to complete confirmatory calculations of an ATF design (ADAMS Accession No. ML20098G965). These calculations demonstrated the codes readiness for analysis of coated cladding and doped fuel ATF technologies. The FAST code is also currently being updated to include data transmitted to the NRC by a fuel vendor for their coated cladding design. This will ensure that FAST is ready for confirmatory calculations that may be needed for future licensing reviews.
Additionally, the NRC, along with the Department of Energy (DOE), Electric Power Research Institute, fuel vendors, and international counterparts, is preparing to initiate the Framework for Irradiation Experiments (FIDES) with the support of the Nuclear Energy Agency. This international cooperative research framework will allow for multiple, joint experimental programs for nuclear fuel and reactor materials, including issues related to ATF and higher burnup.
Participation in this cooperative framework offers access to experimental data at a reduced cost, when compared to individual undertakings. The initial agreement term for the FIDES Framework is from 2021 to 2023, and it is expected to support 4-6 joint experimental programs at irradiation facilities worldwide, including one at the Idaho National Laboratory.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected ATF Activities Completion Date Completion Date Complete a revision to a certificate of compliance from GE Hitachi Nuclear Energy to allow transport 04/30/2020 04/23/2020 of irradiated BWR ATF fuel including FeCrAl cladding (ADAMS Package No. ML20108F553).
Complete safety evaluation regarding URENCO Louisiana Energy Services license amendment 05/21/2020 05/19/2020 request (LAR) to allow enrichment up to 5.5 percent (ADAMS Accession No. ML20119A043).
Conduct a pre-application meeting for a new uranium hexafluoride transportation package with 06/10/2020 06/10/2020 between 10 and 20 percent enrichment (ADAMS Accession No. ML20171A774).
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Projected Activities for the Next Two Reporting Periods (Q4 FY 2020 and Q1 FY 2021)
Projected Projected ATF Activities Completion Date Update of the public ATF Web page. 6 This is being enhanced to provide significantly more information to all stakeholders in a more user-friendly 07/31/2020 format with infographics and embedded links.
Conduct high burnup fuel public workshop. This workshop will relay initial NRC expectations to the nuclear industry for licensing submittals 08/31/2020 for high burnup fuels, including clarification on the expected content and estimated timelines for submission.
Complete review of ATF-related request to allow the transportation of fuel rods with chromium-coated cladding, doped pellets, and fuel rods 08/31/2020 enriched to up to 7 percent.
Hold phenomena identification and ranking exercise for severe accidents. This exercise will provide information on the performance of various ATF concepts, high burnup fuel, and fuel with enrichment above 09/31/2020 5% in severe reactor accidents to support refinement of regulatory guidance.
2-4 Digital Instrumentation and Control The NRC staff continues to complete digital instrumentation and control (DI&C) infrastructure improvements to address (1) Protection against Common Cause Failure; (2) Considering Dl&C under 10 CFR 50.59, Changes, Tests, and Experiments; (3) Commercial Grade Dedication of Digital Equipment; and (4) Assessment for Modernization of the Dl&C Regulatory Infrastructure. 7 With the issuance of Regulatory Guide (RG) 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, the NRC staff has completed its infrastructure improvements in this area. Given the extensive changes to this regulatory guide made after the public comment period, the staff is conducting an additional comment period from July 7, 2020, to August 6, 2020; will perform additional inspector training; and will observe industry workshops to ensure consistent application. The staff will no longer report on this item in future quarterly reports.
The NRC staff provided feedback to Nuclear Energy Institute (NEI) on draft 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 19, 2019, and additional feedback following an April 1, 2020, public meeting. On July 9, 2020, the staff held a public meeting to discuss possible ways to address this feedback. NEI intends to revise NEI 17-06, have an additional public interaction on the revised document, and submit NEI 17-06 by the end of calendar year (CY) 2020 for NRC endorsement.
The NRC staff is now preparing for anticipated digital modernization LARs, including pre-application activities with potential applicants. The staff continues to have monthly meetings 6 https://www.nrc.gov/reactors/atf.html.
7 The staff completed its assessment in December 2019 (ADAMS Accession No. ML19351D975) and developed a proposed end state of the full set of DI&C RGs (ADAMS Accession No. ML20100J219). The staff is currently developing schedules and milestones for near-term RG updates that it will manage through its routine RG update process and will no longer report on this item.
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with DOE regarding its support for a LAR that Exelon Generation Company, LLC (Exelon) plans to submit in June 2021, for an extensive upgrade at the Limerick Generating Station. The staff held its first preapplication meeting with Exelon on June 12, 2020. The NRC will incorporate appropriate milestones for these activities into future quarterly reports.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected DI&C Activities Completion Completion Date Date MP2A: Endorse NEI 96-07, Appendix D, Supplemental Guidance for Application of 10 CFR 50.59 to Digital Modifications, through an update to RG 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments.
- Hold a public meeting to discuss feedback 04/27/2020 04/27/2020 (ADAMS Accession No. ML20135H231).
- Hold a public meeting to discuss resolution of public comments (ADAMS Accession No. 06/29/2020 06/29/20 8 ML20196L751).
- The Advisory Committee on Reactor 05/20/2020 and Safeguards (ACRS) review of RG 1.187 06/30/2020 06/03/2020 9 (ADAMS Accession No. ML20174A563).
- Final publication of RG 1.187 (ADAMS 07/31/2020 06/30/2020 Accession No. ML20125A730).
MP3: Endorse NEI 17-06, Guidance on Using IEC 61508 SIL Certification To Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, through issuance of an RG.
- Hold a public meeting to discuss NRC comments on pre-endorsement draft NEI 17-04/01/2020 04/01/2020 06 Revision B (ADAMS Accession No. ML20083F149).
Projected Activities for the Next Two Reporting Periods (Q4 FY 2020 and Q1 FY 2021)
Projected Projected DI&C Activities Completion Date MP1D: Update BTP 7-19, Guidance for Evaluation of Diversity and Defense-In-Depth in Digital Computer Based Instrumentation and Control Systems.
- Second ACRS Subcommittee Meeting. 09/08/2020
- Hold a public meeting to discuss resolution of feedback. 12/21/2020
- ACRS Full Committee Meeting. 11/30/2020
MP3: Endorse NEI 17-06, Guidance on Using IEC 61508 SIL Certification To Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, through issuance of an RG.
8 The NRC staff held an additional public meeting just prior to the issuance of updated RG 1.187 to discuss the resolution of stakeholder feedback.
9 An ACRS Subcommittee meeting was held on May 20, 2020, and an ACRS Full Committee meeting was held on June 3, 2020.
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Projected Projected DI&C Activities Completion Date
- Hold a public meeting for NEI to discuss resolution of staff 07/09/2020 comments (ADAMS Accession No. ML20183A258).
- NEI to submit NEI 17-06 for NRC review. 12/31/2020 2-5 Vogtle Electric Generating Plant Units 3 and 4 The NRC issued two combined licenses to Southern Nuclear Operating Company and its financial partners on February 10, 2012, for two AP1000 units to be built and operated at the Vogtle site near Augusta, GA. The NRCs Vogtle Readiness Group (VRG) provides assessment, coordination, and management direction for NRC activities. On June 16, 2020, the NRC staff provided an information paper to the Commission describing planned changes to the baseline inspection program for the AP1000 reactor design (ADAMS Accession No. ML20058F491). The planned changes consider the unique aspects of the AP1000 design and its use of passive safety systems.
During this reporting period, the NRC shifted to remote operations in response to the COVID-19 PHE. Construction inspection and licensing activities continued with only minor interruptions due to the successful application of technology for telework and remote access to licensee information. NRC inspectors have now been cleared to return to the Vogtle site in limited numbers to support important on-site inspections.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Vogtle Electric Generating Plant Units 3 and 4 Projected Completion Date Activities Completion Date Issue amendments for LARs19-010 (ADAMS Accession No. ML20059N763),19-014 (ADAMS Accession No. ML20050J685),19-019 (ADAMS 06/30/2020 05/12/2020 Accession No. ML20054B790), and 19-020 (ADAMS Accession No. ML20057E069).
Issue information paper to the Commission with planned changes to the baseline inspection 06/30/2020 06/16/2020 program for AP1000 reactors (ADAMS Accession No. ML20058F491).
Hold a public meeting on the role and activities of 09/30/2020 06/18/2020 the VRG (ADAMS Accession No. ML20167A006).
Projected Activities for the Next Two Reporting Periods (Q4 FY 2020 and Q1 FY 2021)
Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Develop a supplement to the AP1000 Transition Plan that details the current NRC plan for the transition of Vogtle Unit 3 from the construction 08/31/2020 reactor oversight program to the operating reactor oversight program.
Issue amendments for LARs20-001 20-002, and 20-2003 (provided the 09/30/2020 requisite findings are made).
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Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Issue memorandum to inform the Commission of the status of Vogtle Unit 3 construction. This memo will provide updates on inspections, tests, analyses, and acceptance criteria (ITAAC) completion, inspection 09/30/2020 activities (including construction and operational programs), licensing activities, and any current challenges.
NRC Inspections and ITAAC 10 Reviews for the Reporting Period (Q3 FY 2020)
Number of ITAAC Remaining Inspections Completed 11 ITAAC Inspected 12 Requiring Inspection 84 47 255 ITAAC Reviews Completed for the Reporting Period Q3 FY 2020 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 ID No. Received Date Approval Date Vogtle 4 3.3.00.06a 04/27/2020 04/29/2020 Vogtle 3 2.1.03.02a 04/24/2020 04/28/2020 Vogtle 4 2.2.03.08b.02 04/27/2020 04/28/2020 Vogtle 4 2.2.03.08c.iv.04 04/27/2020 04/28/2020 Vogtle 3 2.2.03.08c.i.02 03/16/2020 04/22/2020 Vogtle 3 E.3.9.05.01.04 04/17/2020 04/21/2020 Vogtle 3 3.3.00.06a 04/02/2020 04/09/2020 Vogtle 3 2.1.02.12a.ix 03/27/2020 04/01/2020 Vogtle 3 2.1.02.08d.iv 03/27/2020 04/01/2020 Vogtle 4 2.1.02.08d.iv 03/27/2020 04/01/2020 Vogtle 4 2.1.02.12a.ix 03/27/2020 04/01/2020 Vogtle 3 2.2.03.08c.i.03 05/11/2020 05/27/2020 Vogtle 3 2.2.03.09a.i 05/11/2020 05/27/2020 Vogtle 4 3.3.00.02g 05/15/2020 05/26/2020 Vogtle 3 2.5.05.03b 05/20/2020 05/26/2020 Vogtle Units 3 and 4 LAR Reviews Completed for the Reporting Period Q3 FY 2020 Number of LAR Reviews Forecast to be Number of LAR Reviews that were Completed in the Reporting Period Completed in the Reporting Period 4 4 10 The ITAAC closure information is available in the Vogtle Units 3 and 4 ITAAC Status Reports at https://www.nrc.gov/reactors/new-reactors/oversight/itaac.html.
11 This column indicates only the inspections that were completed for the reporting period. The forecast of when inspections are planned for a specific month can vary due to the fluidity of the construction schedule and what may be available for inspection as a result.
12 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.
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2-6 NuScale Small Modular Reactor (SMR) Design Certification On March 15, 2017, the NRC accepted the NuScale Power, LLC application for an SMR design certification review. The NRC staffs technical review is proceeding in six phases under an established public schedule of milestones. The review is currently in Phase 5 (ACRS Review of Advanced Safety Evaluation Report (SER) with No Open Items) and proceeding concurrently with Phase 6 (Final SER with No Open Items). In February 2020, NuScale informed the NRC that NuScale had identified an issue with the emergency core cooling system (ECCS) actuating later than expected and resulting in higher containment water level accumulation than previously determined. Consequently, NuScale implemented design changes affecting the ECCS actuation timing and addressed concerns related to containment water level accumulation and boron dilution in the downcomer. The proposed design changes required NuScale to revise parts of its Final Safety Analysis Report (FSAR) and associated technical and topical reports, which required further NRC review. NuScale submitted the final design changes and supporting information to the NRC on May 20, 2020 (ADAMS Accession No. ML20141L787).
On May 1, 2020, the NRC issued a letter to NuScale (ADAMS Accession No. ML20112F455) updating the status and schedule for the NuScale review. The staff completed its review and presented the findings related to the proposed design changes to the ACRS in July 2020. As a result, Phase 5 is anticipated to be completed by July 31, 2020, rather than by June 23, 2020.
The staff is currently on track for issuing the final safety evaluation and meeting the Phase 6 milestone by September 8, 2020. As of June 30, 2020, the staff had issued a total of 1,333 requests for additional information (RAIs), and the applicant has responded to all of them.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected NuScale SMR Design Certification Activities Completion Date Completion Date Complete audit of final FSAR changes to Chapter 6, 04/03/2020 06/26/2020 13 7, and 15 (ADAMS Accession No. ML20059N687).
ACRS Full Committee Meeting on NuScales Boron Dilution, Return to Criticality, Probabilistic Risk 04/08/2020 04/08/2020 Assessment (PRA), and Hydrogen and Oxygen Monitoring (ADAMS Accession No. ML20070R332).
ACRS Full Committee Meeting on NuScales Boron Dilution and Technical Specifications (presentation 06/04/2020 06/04/2020 by NuScale) (ADAMS Accession No. ML20136A245).
Projected Activities for the Next Two Reporting Periods (Q4 FY 2020 and Q1 FY 2021)
Projected Projected NuScale SMR Design Certification Activities Completion Date ACRS Full Committee Meeting on NuScales Boron Redistribution and Technical Specifications (presentation by NRC staff) (ADAMS Accession 07/08/2020 No. ML20170A337).
13 Completion of the audit was previously scheduled for April 3, 2020. The audit completion was extended to June 26, 2020, to allow NuScale to revise parts of its FSAR and associated technical and topical reports and for the NRC staff to review the information.
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Projected Projected NuScale SMR Design Certification Activities Completion Date ACRS Full Committee Meeting on NuScales boron redistribution, NuScales design certification final letter, and lessons learned (ADAMS 07/25/2020 Accession No. ML20170A348).
Complete Phase 5 of the safety review (ACRS Review of Advanced SER 07/31/2020 with No Open Items).
Complete Phase 6 of the safety review (Final SER with No Open Items). 09/08/2020 2-7 Advanced Nuclear Reactor Technologies The NRC is making significant progress in preparation for reviewing non-light-water-reactor (non-LWR) designs, consistent with the staffs vision and strategy (ADAMS Accession No. ML16356A670). The NRC staff is currently executing the implementation action plans to achieve non-LWR safety review readiness. 14 During this reporting period, all of the planned activities were completed on or ahead of schedule. The NRC staff issued a proposed rule to include new alternative emergency preparedness (EP) requirements for SMRs and other new technologies, and a rulemaking plan to develop a risk-informed, technology-inclusive regulatory framework for advanced reactors. The public comment period is open until September 25, 2020. The NRC also provided options and a recommendation to the Commission in a voting paper on possible changes to guidance documents to address population-related siting considerations for advanced reactors. Finally, the NRC issued RG 1.233, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology To Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light- Water Reactors, to provide guidance on the licensing basis and content of applications for non-LWRs designs.
The NRCs public Website lists the open and resolved technical and policy issues related to SMRs and non-LWRs and is updated periodically to show the status of the issues (https://www.nrc.gov/reactors/new-reactors/smr.html#techPolicyIssues). 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 Website (https://www.nrc.gov/reactors/new-reactors/advanced.html#stakeholder).
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date Complete draft safety evaluation for Tristructural Isotropic (TRISO) topical report to support ACRS 04/30/2020 04/07/2020 meeting (ADAMS Package No. ML20085J410).
Issue draft technology-inclusive, risk-informed, and performance-based design review guide for DI&C 04/30/2020 04/08/2020 for advanced reactors (ADAMS Accession No. ML20045D302).
14 The NRCs public Website lists the implementation action plans and is updated periodically to show the status of these activities (https://www.nrc.gov/reactors/new-reactors/advanced.html#advSumISRA).
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Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date Issue rulemaking plan for technology-inclusive regulatory framework for optional use by applicants 04/30/2020 04/13/2020 for new commercial advanced reactor licenses (ADAMS Accession No. ML19340A056).
Develop proposed policy on population-related siting considerations for advanced reactors and issue SECY-20-0045, Population Related Siting 05/30/2020 05/08/2020 Considerations for Advanced Reactors for Commission consideration (ADAMS Package No.
Publish EP for SMRs and other new technologies proposed rule in the Federal Register (ADAMS 05/30/2020 05/12/2020 Accession No. ML20041C665).
Complete scoping process for development of a Generic Environmental Impact Statement for the 06/30/2020 06/30/2020 construction and operation of advanced nuclear reactors.
Develop report on technical and licensing considerations for micro-reactors by Sandia 08/31/2020 04/01/2020 National Laboratory (SNL) (ADAMS Accession No. ML20156A101).
Develop report on remote and autonomous operations of advanced reactors by SNL (ADAMS 09/30/2020 06/30/2020 Accession No. ML20175A117).
Develop guidance for the assessment of tritium and strategies for its detection and control in molten salt reactors (MSRs) and fluoride salt-cooled high 09/30/2020 05/31/2020 temperature reactors prepared by Argonne National Laboratory (ANL) (ADAMS Accession No. ML20157A155).
Issue Final RG 1.233, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology To Inform the Licensing Basis and 09/30/2020 06/09/2020 Content of Applications for Licenses, Certifications, and Approvals for Non-Light- Water Reactors (ADAMS Accession No. ML20091L698).
Projected Activities for the Next Two Quarters (Q4 FY 2020 and Q1 FY 2021)
Projected Projected Advanced Nuclear Reactor Technologies Activities Completion Date Issue SECY paper on micro-reactors. The SECY paper will discuss 08/30/2020 15 potential licensing and policy issues specific to micro-reactors.
Issue final safety evaluation for TRISO topical report. 08/30/2020 15 Issuance delayed from the original projected date of July 30, 2020, due to higher priority activities.
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Projected Projected Advanced Nuclear Reactor Technologies Activities Completion Date Issue report on non-LWR source terms guidance in "Risk-Informed, Performance-Based, Technology-Inclusive Regulatory Infrastructure:
Technology-Inclusive Determination of Mechanistic Source Terms for 09/30/2020 Offsite Dose-Related Assessments for Advanced Nuclear Reactor Facilities" prepared by Idaho National Laboratory.
Develop guidance on fuel qualification criteria for MSRs by Oak Ridge 09/30/2020 National Laboratory (ORNL).
Issue four technical input reports for NRCs review of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III 09/30/2020 Division 5 by Pacific Northwest National Laboratory (PNNL), ORNL, ANL, and NUMARK Associates, Inc..
Issue final technology-inclusive, risk-informed, and performance-based design review guide for instrumentation and controls systems for 09/30/2020 advanced reactors.
Issue white paper with proposed fuel qualification methodology to provide guidance for non-LWR developers on qualification of fuel under 12/31/2020 the Nuclear Energy Innovation and Modernization Act (NEIMA).
Issue Final Interim Staff Guidance, Environmental Considerations 12/31/2020 Associated with Micro-reactors.
Issue report on Environmental Impacts of Non-LWR Fuel Cycle and 12/31/2020 Transportation-NRC prepared by PNNL.
Issue Code Assessment Report, Volume 4, on Dose Assessment. 12/31/2020 Issue Material Control and Accounting guidance for Category II facilities 12/31/2020 (NUREG-2159).
2-8 Oklo Power LLC (Oklo) Combined License Application for the Aurora Compact Fast Reactor The NRC began pre-application discussions with Oklo in November 2016 on an advanced reactor design that uses liquid metal for heat transport. The proposed Aurora design would use heat pipes to transport heat from the reactor core to a power conversion system, where it would then be used to generate electricity. On March 11, 2020, Oklo submitted a custom combined license (COL) application 16 for the Aurora reactor to the NRC (ADAMS Accession No. ML20075A000). The NRC staff has completed a review and determined that the application is acceptable for docketing and is proceeding with the safety and environmental reviews. As part of the acceptance review, the staff conducted a virtual audit on May 27, 2020 (ADAMS Accession No. ML20079L202). The purpose of the audit was to examine the supporting information for the application to ensure sufficient information was presented to support the custom COL application and that the information provides the level of detail necessary for the staff to conduct an efficient and risk-informed review. On June 5, 2020, the NRC issued a letter to Oklo (ADAMS Accession No. ML20149K616) indicating that the staff plans to complete the review in a two-step process. In Step 1, the NRC staff plans to engage Oklo in public meetings, conduct regulatory audits, and issue requests for additional information to efficiently align on four key safety and design aspects of the proposed licensing basis. After gaining alignment on 16 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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the key aspects in Step 1, NRC staff will have defined the scope of the full detailed technical review and will develop a schedule to efficiently perform the review in Step 2. Successful completion of Step 2 will involve the staff making its reasonable assurance findings regarding the custom COL application for the Aurora design, successful completion of the ACRS review, issuance of the staffs Final SER, and holding the mandatory hearing.
The NRC holds periodic public meetings to discuss the review of the custom Aurora Powerhouse. 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).
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected Oklo COL Review Activities Completion Date Completion Date Issue audit plan for acceptance review audit 04/01/2020 04/01/2020 (ADAMS Accession No. ML20079L202).
Complete audit of application supporting 05/22/2020 05/27/2020 information.
Determination on acceptability for docketing of the Oklo COL application for the Aurora reactor 06/05/2020 06/05/2020 (ADAMS Accession No. ML20149K616).
Projected Activities for the Next Two Quarters (Q4 FY 2020 and Q1 FY 2021) 17 Projected Projected Oklo COL Review Activities Completion Date Hold initial public meeting to discuss the methodology used in the 08/04/2020 analysis and evaluation of the maximum credible accident.
Hold initial public meeting to discuss the process to be used for classifying structures, systems, and components (SSCs) in the Aurora 08/05/2020 design and the treatment for each classification of SSCs.
Hold initial public meeting to discuss scope and application of the Quality 08/31/2020 Assurance Program.
Complete an audit on the methodology used in the analysis and 10/06/2020 evaluation of the maximum credible accident.
Hold second public meeting to discuss the methodology used in the 10/31/2020 analysis and evaluation of the maximum credible accident.
Hold second public meeting to discuss the process to be used for classifying SSCs in the Aurora design and the treatment for each 10/31/2020 classification of SSCs.
Complete an audit on the scope and application of the Quality Assurance 10/31/2020 program.
Complete initial outreach to local stakeholders regarding the 10/31/2020 environmental impacts.
Complete Step 1 alignment with Oklo on key technical issues. 11/05/2020 Issue letter documenting the applicable regulations. 11/05/2020 17 The public meeting dates are subject to change. The NRCs public Website is updated periodically to show the status of the meetings (https://www.nrc.gov/reactors/new-reactors/col/aurora-oklo/public-meetings.html).
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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 staff developed recommendations to make enhancements to the ROP in SECY-19-0067, Recommendations for Enhancing the Reactor Oversight Process, (ADAMS Accession No. ML19070A050) which are being considered by the Commission. The staff 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 annual ROP self-assessment program.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected Reactor Oversight Process Activities Completion Date Completion Date Define the problem statement and revise the charter for a comprehensive review of problem identification 04/30/2020 05/15/2020 18 and resolution inspection program (ADAMS Accession No. ML19212A017).
Issue revision to Inspection Manual Chapter 0307, Reactor Oversight Process Self-Assessment 04/30/2020 05/29/2020 Program (ADAMS Accession No. ML19274B865).
Projected Activities for the Next Two Quarters (Q4 FY 2020 and Q1 FY 2021)
Projected Projected Reactor Oversight Process Activities Completion Date Complete comprehensive review of problem identification and resolution 09/30/2020 program and issue report.
Complete effectiveness review of the cross-cutting issues process and 10/31/2020 19 issue report.
Issue revision to Inspection Procedure 95001, Supplemental Inspection 10/31/2020 Response to Action Matrix Column 2 Inputs.
2-10 Backfit The NRCs backfitting rules are codified in 10 CFR 50.109, 70.76, 72.62, and 76.76. The backfitting provisions require, in the absence of an applicable exception, an analysis showing that the backfit would result in a substantial increase in the overall protection of the public health and safety or the common defense and security and that the increased protection warrants the direct and indirect costs of implementation. There are similar requirements, referred to as issue finality, that apply when there are new or amended requirements for licenses, permits, and design approvals and certifications issued under 10 CFR Part 52. The Commission clarified its backfitting and issue finality policy as well as its policy on forward fits, which are requirements imposed as a condition of agency approval of a licensee request, in NRC 18 The NRC staff reviewed the existing charter and determined it was adequate to continue performing a review of the problem identification and resolution inspection program.
19 Completion of the effectiveness review was previously scheduled for October 31, 2019, to be followed by the issuance of the report on December 31, 2019. These completion dates were delayed to provide the opportunity for questions and feedback on the preliminary conclusions from the effectiveness review and potential recommended program adjustments during a public meeting on January 10, 2020.
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Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests. The NRC completed draft NUREG-1409, Backfitting Guidelines, Revision 1, in March 2020 and issued a notice of availability in the Federal Register for public comment (ADAMS Accession No. ML18109A498). This revision would provide additional guidance for the NRC staff on how to implement the Commissions backfitting and forward fitting policy, including how to process contested violations based on the basis of unjustified backfitting. Training was provided to inspection staff on May 28, 2020.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected Backfit Activities Completion Date Completion Date Hold a public meeting or teleconference to discuss the contents of draft NUREG-1409, Revision 1 with 05/29/2020 04/28/2020 stakeholders.
Projected Activities for the Next Two Quarters (Q4 FY 2020 and Q1 FY 2021)
Projected Projected Backfit Activities Completion Date Receive public comments on draft NUREG-1409, Revision 1. 07/31/2020 Evaluate public comments and prepare NUREG-1409, Revision 1 for 09/30/2020 internal agency concurrence.
Provide NUREG-1409, Revision 1 to the Commission for review. 12/31/2020 2-11 Risk-Informed Activities The NRC staff continues to make progress to advance the use of risk insights more broadly to inform decisionmaking. There are numerous activities ranging in scope from agencywide initiatives, such as the Be riskSMART transformation initiative mentioned in section 2-1, to the advanced reactor risk-informed activities listed in section 2-7 of this enclosure, to individual undertakings in program and corporate offices. 20 Specifically, the staff further developed the agencywide Be riskSMART risk-informed decisionmaking framework and continued to illustrate its applicability throughout the agency in the technical, legal, and corporate arenas. As part of the Be riskSMART initiative, the staff is tracking its use of risk-informed decisionmaking.
Activities Planned and Completed for the Reporting Period (Q3 FY 2020)
Projected Risk-Informed Activities Completion Date Completion Date Issue the recommendations on building smarter fuel cycle licensing programs (ADAMS Accession No. 04/30/2020 04/30/2020 ML20099F352).
20 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.
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Projected Risk-Informed Activities Completion Date Completion Date Complete a remote audit of the Pressurized-Water Reactor Owners Groups (PWROGs) effort to collect and analyze operating experience data that will be used to develop equipment reliability estimates for diverse and flexible coping strategies (FLEX) equipment, which was installed as a post- 05/31/2020 05/04/2020 Fukushima safety enhancement. The PWROGs effort, and the NRCs audit, resolves one of the few remaining technical challenges to crediting FLEX in probabilistic risk assessment models (ADAMS Accession No. ML20155K827).
Conduct stakeholder meeting on proposed new Risk-Informed Process for Exemptions (RIPE) initiative. RIPE leverages current regulations and risk initiatives to allow reactor licensees to justify plant-specific exemptions using a streamlined NRC 05/31/2020 05/14/2020 review process. This process can be used to address compliance issues that have minimal safety impact and are of low safety significance (ADAMS Accession No. ML20161A040).
Issue letter on industry use of focused cyber guidance to better risk-inform rule implementation for emergency preparedness digital assets, based 05/31/2020 05/19/2020 on lessons learned from implementation and oversight of the NRCs cyber security requirements (ADAMS Accession No. ML20129J981).
Publish Draft Revision 3 to RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk- 06/30/2020 06/26/2020 Informed Activities for public comment (ADAMS Accession No. ML19308B636).
Issue revised Office of Nuclear Reactor Regulation (NRR) Instruction LIC-206, Integrated Risk- 06/30/2020 06/26/2020 Informed Decision- Making for Licensing Reviews.
Complete initial outreach to each major program office on the Be riskSMART risk-informed decisionmaking framework using examples specific 06/30/2020 06/30/2020 to each major functional area (technical, legal, corporate) including subsequent license renewal, security, fee billing, and inspection.
Projected Activities for the Next Two Quarters Q4 FY 2020 and Q1 FY 2021 Projected Projected Risk-Informed Activities Completion Date Provide a voting paper to the Commission with options for a risk-informed, holistic approach to credit realistic law enforcement response, 08/31/2020 operator action, and use of FLEX equipment.
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Projected Projected Risk-Informed Activities Completion Date Issue a letter on industry use of focused cyber security guidance to better risk-inform rule implementation for balance of plant digital assets, 09/30/2020 based on lessons learned from implementation and oversight of the NRCs cyber security requirements.
Document the Be riskSMART risk-informed decisionmaking framework in 09/30/2020 agency guidance.
Modify risk-informed decisionmaking curriculum to incorporate the 09/30/2020 Be riskSMART framework.
Finalize RIPE initiative and NRC staff guidance on the initiative. 09/30/2020 Brief ACRS on proposed final Draft Revision 3 to RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk 11/05/2020 Assessment Results for Risk- Informed Activities for public comment (ADAMS Accession No. ML19308B636).
Implement the near-term recommendations on building a smarter fuel 11/30/2020 21 cycle licensing program (ADAMS Accession No. ML20184A267).
Implement the recommendations on building a smarter fuel cycle 12/31/2020 inspection program (ADAMS Accession No. ML20183A242).
Implement revisions to the ISFSI inspection guidance. 12/31/2020 Publish Integrated Human Error Analysis System for Event and 12/31/2020 Condition Analysis Human Reliability Analysis Method workshop report.
2-12 Coronavirus Disease 2019 Public Health Emergency On January 31, 2020, the U.S. Department of Health and Human Services declared a PHE for the United States to aid the nations healthcare community in responding to COVID-19. On March 11, 2020, the COVID-19 outbreak was characterized as a pandemic by the World Health Organization. On that same day, the NRC COVID-19 Task Force began developing and implementing precautionary measures in response to the PHE to 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. Throughout the PHE, the NRC continues to protect public health and safety and the environment. The NRC is monitoring the effects of the COVID-19 PHE 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 appropriate steps as needed.
NRC Re-Occupancy of Facilities On June 15, 2020, the NRC moved to Phase 1 of the Re-Occupancy Plan at NRC headquarters, all four regions, and the Technical Training Center (TTC). During Phase 1, building occupancy only moderately increased thereby facilitating NRC efforts to be consistent with CDC, OSHA, and Office of Management and Budget health and safety guidance (e.g.,
social distancing and use of personal protective supplies). On July 12, 2020, the NRC headquarters, Region I, and Region III transitioned to Phase 2 while Region II, Region IV, and the TTC remain in Phase 1 due to consideration of State and local conditions. Enhanced 21 The original projected date of September 30, 2020 for implementing the recommendations on building a smarter fuel cycle licensing program has been updated to reflect the dependence on completing other priority activities associated with the near-term recommendations. Additionally, the activity has been updated to include near-term to clarify that this activity is associated with only the near-term recommendations.
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screening (i.e., temperature checks and access questions) does not apply to facilities in Phase 2 and building occupants are instead requested to self-screen prior to coming to an NRC facility.
Licensing and Oversight Items of Interest The NRC staff has taken a number of steps to identify areas of our regulations that are challenging during the PHE, and the areas where temporary flexibilities, such as exemptions, would not compromise the ability of licensees to maintain the safe and secure operation of NRC-licensed facilities. The NRC staff has communicated the processes available to licensees for requesting these flexibilities in a transparent way through public communications, such as teleconferences and letters. In addition, these processes and the approved flexibilities are posted and updated on the NRC public website (https://www.nrc.gov/about-nrc/covid-19/).
As of June 30, 2020, the NRC has conducted 29 public teleconferences and webinars to address COVID-19 PHE concerns and 179 virtual public meetings on NRC business. The NRC has also developed 29 Web pages devoted to the regulatory activities taken in response to the COVID-19 PHE. Specific pages related to nuclear power plant licensees and nuclear materials licensees have been developed to keep the public informed on how the NRC is adapting its regulatory approach. Between March 31, 2020, and June 20, 2020, the NRC issued 132 licensing actions granting temporary flexibilities to maintain the safe and secure operation of nuclear reactor and nuclear materials licensees. A complete list of licensing actions approved by the NRC in response to the COVID-19 PHE is available on the NRC public Web site at https://www.nrc.gov/about-nrc/covid-19/.
With respect to security, on July 922 and 16 23, 2020, the NRC hosted public meetings with stakeholders, including representatives from NEI, NextEra, Entergy, and the Union of Concerned Scientists, to discuss considerations for resumption of NRC-conducted Force-on-Force (FOF) exercises and the plan for FOF inspection activities during the COVID-19 PHE. During the meeting, the NRC staff discussed considerations for resuming inspections and potential measures that could be implemented to mitigate certain safety concerns related to the PHE, as well as the staffs proposed path forward. The NRC staff also stated that multiple factors would be considered in making decisions regarding the resumption and prioritization of inspection activities, including State, local, and site-specific conditions. The NRC staff has temporarily deferred FOF security inspections, which will resume when conditions permit and is currently finalizing an inspection procedure for limited-scope tactical response drills that would be used until conditions permit the safe resumption of full-scale FOF inspections.
Regulatory Activities Taken in Response to the COVID-19 PHE Number of COVID-19 Average Number of Licensee Type Requests Approved During the Days to Approve Reporting Period COVID-19 Requests 24 Power Reactor 67 12 Non-Power Reactor 6 14 22 The July 9, 2020, public meeting summary, NRC presentation, and meeting decision summary are available at ADAMS Accession Nos. ML20197A033, ML20188A177, and ML20196L994, respectively.
23 The July 16, 2020, public meeting summary, NRC presentation, and meeting decision summary are available at ADAMS Accession Nos. ML20175A681, ML20167A109, and ML20169A688, respectively.
24 The average is calculated based on the date received and date completed, which may include review time of supplemental information submitted after the date received.
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Number of COVID-19 Average Number of Licensee Type Requests Approved During the Days to Approve Reporting Period COVID-19 Requests 24 Other (e.g., topical reports) 3 20 Decommissioning of Nuclear 6 12 Facilities and Uranium Recovery Storage and Transportation of 5 25 Spent Nuclear Fuel Fuel Cycle Facilities 8 29 Medical, Industrial and Academic Uses of Nuclear Materials and 27 15 Agreement States Enclosure 3 - Summary of Activities 3-1 Reactor Oversight Process Findings The table below provides the CY ROP findings for the year-to-date (YTD) and 3-year rolling metrics Location Number of Findings CY 2017 CY 2018 CY 2019 CY 2020 (YTD)
Nationally Total 560 478 440 83 25 Green 126 107 95 13 White 2 1 0 0 Yellow 0 0 0 0 Red 0 0 0 0 Region I Greater Than Green 0 0 0 0 Security Total 128 108 95 13 No. of Units 25 25 24 22 26 Operating During CY Green 119 113 110 23 White 3 0 1 1 Yellow 0 0 0 0 Red 0 0 0 0 Region II Greater Than Green 2 0 0 1 Security Total 124 113 111 25 No. of Units 33 33 33 33 Operating During CY Green 133 110 96 14 Region III White 4 2 1 0 Yellow 0 0 0 0 25 The inspection reports for the second quarter of CY 2020 will continue to be finalized through August 15, 2020.
The report for the next reporting period will be updated to include any additional findings from the second quarter of CY 2020.
26 The reduction of two units for CY 2020 reflects the permanent shutdown of Pilgrim Nuclear Station on May 31, 2019, and Three Mile Island, Unit 1, on September 20, 2019. Additionally, Indian Point Nuclear Generating Unit 2 permanently ceased operations on April 30, 2020, but will remain counted in this table until the conclusion of CY 2020 as it transitions to decommissioning.
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Location Number of Findings CY 2017 CY 2018 CY 2019 CY 2020 (YTD)
Red 0 0 0 0 Greater Than Green 0 0 0 0 Security Total 137 112 97 14 No. of Units 23 23 23 23 Operating During CY Green 167 145 137 31 White 2 0 0 0 Yellow 0 0 0 0 Red 0 0 0 0 Region IV Greater Than Green 2 0 0 0 Security Total 171 145 137 31 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 NRC staff issues a final safety evaluation.
These totals do not include LARs, as they are addressed separately in section 3-3. The total inventory of licensing actions is the number open at the end of the quarter.
Operating Reactors Percentage of Percentage Licensing Licensing Licensing of Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule 28 Schedule 27 Q4 FY 2019 160 72 120 100% 96%
Q1 FY 2020 170 40 37 100% 89%
Q2 FY 2020 173 96 82 100% 94%
Q3 FY 2020 29 205 183 158 100% 91%
27 Excludes unusually complex and Fukushima-related licensing actions accepted or initiated prior to July 13, 2019 (consistent with previous monthly reports).
28 The established scheduled is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
29 Inventory has been updated to include operating Non-Power Production and Utilization Facility licensing actions beginning with Q3 FY2020 (Inventory - 8 Actions, Initiated Actions - 6, and Completed Actions - 6).
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New Reactors Percentage of Percentage Licensing Licensing Licensing of Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule Schedule Q4 FY 2019 7 0 2 100% 100%
Q1 FY 2020 5 2 0 N/A N/A Q2 FY 2020 3 0 1 100% 100%
Q3 FY 2020 8 5 0 N/A N/A Fuel Facilities 30 Percentage of Percentage Licensing Licensing Licensing of Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule Schedule Q4 FY 2019 4 3 0 N/A N/A Q1 FY 2020 6 3 1 100% 100%
Q2 FY 2020 6 4 4 100% 100%
Q3 FY 2020 4 3 5 100% 100%
3-3 Licensing Amendment Request Reviews The tables below provide the status of LARs organized by licensing program. Consistent with Section 102(c) of NEIMA, the LARs referenced in this section include requested activities of the Commission for which the NRC staff 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).
30 Corrections were made to previous quarters due to quality checking older records and formats, to present the most accurate data to date.
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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 31 Schedule 32 Q4 FY 2019 400 129 123 100% 86%
Q1 FY 2020 400 97 122 100% 92%
Q2 FY2020 367 84 115 100% 91%
Q3 FY 2020 33 371 92 69 100% 94%
New Reactors Percentage of LARs LAR Percentage of LAR Reviews Submitted Reviews LAR Reviews Completed Reporting Total During Completed Completed Prior to the Period Inventory the During the Prior to the Generic Reporting Reporting Established Milestone Period Period Schedule Schedule Q4 FY 2019 14 8 2 100% 100%
Q1 FY 2020 12 4 6 100% 100%
Q2 FY 2020 6 2 8 100% 100%
Q3 FY 2020 5 3 4 100% 100%
Fuel Facilities 34 Percentage of LARs LAR Percentage of LAR Reviews Submitted Reviews LAR Reviews Completed Reporting Total During Completed Completed Prior to the Period Inventory the During the Prior to the Generic Reporting Reporting Established Milestone Period Period Schedule Schedule Q4 FY 2019 6 1 3 100% 100%
Q1 FY 2020 35 12 10 4 100% 100%
Q2 FY 2020 11 5 6 100% 100%
Q3 FY 2020 12 14 13 100% 93%
31 Excludes unusually complex and Fukushima-related LARs accepted or initiated prior to July 13, 2019 (consistent with previous monthly reports).
32 The established scheduled is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
33 Inventory has been updated to include operating Non-Power Production and Utilization Facility LARs beginning with Q3 FY2020 (Inventory - 11 LARs, Submitted - 6 and Completed - 4).
34 Corrections were made to previous quarters due quality checking older records and formats, to present the most accurate data to date.
35 Corrected numbers reflect LARs that were received during the reporting period but entered in the tracking system after the previous report was issued.
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Unusually Complex LARs 36 The staff has identified certain LARs (accepted for review prior to July 13, 2019), as unusually complex. Consistent with the previous reports, these unusually complex submittals are not included in the internal performance measures as they do not lend themselves to realistic schedule forecasting. Rather, they are given escalated management attention to ensure progress is made toward resolving outstanding issues and completing the reviews in a timely manner.
Exclusive Age Unusually Complex LAR Description Justification (Months)
North Anna Units 1 and 2 -Revision of the Small Break Involves multiple plant Loss of Coolant Accident (SBLOCA) Analytical specific SBLOCA 22 Methodologies. methodologies.
Involves multiple plant Surry Units 1 and 2 -Revision of Analytical specific SBLOCA 22 Methodologies for SBLOCA.
methodologies.
Unique, first of a kind Shearon Harris - Request to modify departure from review based on a nucleate boiling ratio safety limit to support transition to 12 37 correlation with a fuel a new fuel design.
of a different design.
3-4 Research Activities 38 Summary of New Research Projects 39 During the reporting period, the Office of Nuclear Regulatory Research initiated research on or substantially revised the following projects:
Future-Focused Research Projects This project will assist the NRC in identifying emerging opportunities to Importance to improve external awareness, support closure of technical gaps ahead of the NRC regulatory needs, foster research and development university funding Mission opportunities, and build new capabilities to attract top talent to support NRCs safety and security mission.
Five projects to be undertaken this year include the following: 1) identify and develop strategies to address regulatory challenges in a future with digital twin technologies, 2) use advanced licensing concepts and PRA Planned models to identify candidates for risk-informed applications, 3) enable staff Activities: use of advanced simulation-based dynamic PRA methods, 4) educate staff on advanced causality analysis for integration into NRC's risk analysis approach, and 5) identify agency Artificial Intelligence/Big Data needs and available tools and develop a path forward.
Requesting All NRC Business Lines Business Line 36 There were no unusually complex LARs for New Reactors or Fuel Facilities within the reporting period.
37 The Shearon Harris LAR was determined to be unusually complex during the technical review.
38 Provides information about projects that were started during the reporting period and exceeded 300 staff hours or $500K of program support for the duration of the project (consistent with previous reports).
39 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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Future-Focused Research Projects Estimated 2023 Completion Estimate of Total Research $0.7M Resources Investigation of modeling requirements for fast-spectrum, metal-fueled, micro-reactor technologies The NRC staff must prepare to review applications in the near-term for Importance to micro-reactor concepts being proposed by advanced reactor vendors.
the NRC These micro-reactor designs utilize several novel features and design Mission approaches that the staff must be knowledgeable of in-order to perform risk-informed, safety-focused reviews.
The staff plans to perform research analyses for the following: 1) investigate the suitability of modeling approaches proposed by advanced Planned reactor vendors and 2) understand the significance of phenomena Activities:
associated with the unique design features associated with micro-reactor technologies.
Requesting Operating Reactors Business Line Estimated 2022 Completion Estimate of Total Research 1.1 FTE and $0.15M Resources Risk-Informed Reviews of DI&C Systems and Components: Integrating Risk Insights into the DI&C Regulatory Framework Importance to This project supports approaches to further risk-inform DI&C reviews to the NRC complement the existing regulatory framework.
Mission The objective is to provide support in developing the technical basis for integrating risk insights into the regulatory framework for DI&C systems and components by (1) assessing the technical feasibility of risk-informed approaches and gaps associated with further integrating risk insights into regulatory reviews for DI&C systems and components; (2) as applicable, Planned piloting a risk-informed categorization process that is compatible with the Activities:
existing regulatory framework, including Title 10 of the Code of Federal Regulations (10 CFR) 50.69, to classify DI&C systems and components with respect to risk insights and safety significance; and (3) developing recommendations to enhance the use of risk insights within the existing risk-informed regulatory framework for DI&C systems.
Requesting Operating Reactors Business Line Estimated 2021 Completion Estimate of Total Research 1 FTE and $0.4M Resources 28
Research and Development of Guidance for Subsurface Characterization and Radiological Surveys and Guidance on Performance Assessment and Modeling of Waste Covers The NRC staff must be prepared to evaluate new Evapotranspiration (ET)
Importance to covers on Uranium Mill Tailings Radiation Control Act waste that are the NRC planned by DOE. The ability to assess near-term decommissioning of Mission sites with soil that is contaminated with radioactive material at subsurface levels is of importance.
Guidance will be developed for staff to evaluate the ability of ET covers to meet regulatory criteria including investigating suitability of models for Planned long-term performance. Guidance will be developed to allow a licensee to Activities: use, and NRC to evaluate, historical, scoping, characterization, and radiological surveys that are appropriate for evaluating dose impacts from subsurface contamination.
Requesting Decommissioning and Low-Level Waste Business Line Estimated 2023 Completion Estimate of Total Research 8.9 FTE and $1.6M Resources Summary of Completed Research Projects 40 During the reporting period, Office of Nuclear Regulatory Research completed the following projects:
Applied Research to Inform Nuclear Plant EP Regulatory Oversight EP supports licensees, States, and other stakeholders in developing Importance to the effective plans to respond to a potential radiological event impacting NRC Mission the public.
The project examined several technical areas of evacuation modeling and the findings incorporated into a NUREG to serve as the technical basis for the revision of NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate [ETE] Studies. The Research Results or results provide the opportunity to update NRC guidance for the Findings standardization of ETEs and recommendations for acceptable methods to licensees. Staff also published NUREG/CR-7269, Enhancing Guidance for Evacuation Time Estimate Studies, (ADAMS Accession No. ML20070158) on March 31, 2020.
Duration of the 3 years Project Estimate of Total 1.5 FTE and $0.7M Research Resources 40 The research project resources are estimates of staff hours and program support costs based on inspection of project records, including staffing plans and contract spending plans.
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Research Assistance on Reactor Pressure Vessel (RPV) Integrity Issues This research enhanced the analysis tools necessary to support staff Importance to the review and maintenance of the technical basis for the trending of NRC Mission vessel embrittlement to preclude component failure.
Four major tasks were completed to enable NRC to better evaluate RPV integrity, including verification and validation and knowledge management for the Fracture Analysis of Vessels: Oak Ridge Research Results or computer code, understanding of the effects of small surface-Findings breaking flaws on RPV integrity, support for the Radiation Embrittlement Archive Project, and support of NRR rulemaking for Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H.
Duration of the 3 years Project Estimate of Total 5.0 FTE and $2.6M Research Resources NuScale Reactor Systems Analysis Research Plan Importance to the Technical input was developed to inform the safety evaluation of the NRC Mission NuScale SMR Design Certification Application.
The results of this research project were provided in three key deliverables that include: 1) confirmatory analyses to assist NRRs Research Results or review of specific design basis and special events, 2) evaluation of Findings topical and technical reports, and 3) presentations to support ACRS meetings.
Duration of the 4 years Project Estimate of Total 15 FTE and $0.6M Research Resources Flaw Evaluation, Repair and Mitigation Techniques for Primary Water Stress Corrosion Cracking The confirmatory research provides guidance for regulatory treatment of the generic aspects of primary water stress corrosion Importance to the cracking (PWSCC) of Ni-based Alloy 600/182 and Alloys NRC Mission 690/52/152, flaw evaluation, probabilistic pipe rupture, and PWSCC mitigation.
This project identified areas of primary water stress corrosion crack growth rate susceptibility of Alloy 690 weld metal (Alloy 52 and 152, and its many variants), measured heat-to-heat variability, the effect of welding parameters, and the effect of cold work; measured crack initiation times for Alloy 600 and Alloy 182 and on Alloys 690/52/152, Research Results or including the effects of applied stress; developed and documented Findings validation approaches for finite element modeling of weld residual stress and ended the related research activity; updated flaw evaluation software, developed a User Guide, and trained regulatory staff in the use of the tool; evaluated the effectiveness of PWSCC mitigation techniques and sunset the related confirmatory research program.
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Flaw Evaluation, Repair and Mitigation Techniques for Primary Water Stress Corrosion Cracking Duration of the 3 years Project Estimate of Total 9.75 FTE and $4.25M Research Resources Evaluating the Reliability of Nondestructive Examinations of Vessels and Piping Importance to the This research evaluated of the effectiveness and reliability of NRC Mission Nondestructive Examinations (NDEs) of vessels and piping.
The project included eight major tasks designed to enable the NRC to better evaluate the effectiveness and reliability of NDEs including qualification requirements. The results provided the technical bases Research Results or for assessments of the American Society of Mechanical Engineers Findings Boiler and Pressure Vessel Code Edition and Addenda and Code Case rulemakings, licensee relief requests, license renewal reviews, and new degradation mitigation techniques.
Duration of the 5 years Project Estimate of Total 12.5 FTE and $7.5M Research Resources 3-5 Fees Billed The tables below provide information on Part 170 fees billed for each fee class. For each fee class, the staff compared the fees billed to the receipts estimated in the annual fee rule. 41 FY 2019 Part 170 Part 170 Billed in Total Part 170 - Billed Fee Class Receipts Final -
FY 2020 Q3 ($M) in FY 2020 ($M)
Annual Fee Rule ($M)
Fuel Facilities $6.8 $0.0 $3.5 Generic
$3.6 $0.0 $1.9 Decommissioning Materials Users 42 $1.0 $0.0 $0.6 Operating Power
$186.7 $0.0 $95.2 Reactors Research and
$3.0 $0.0 $1.3 Test Reactors Spent Fuel Storage / Reactor $15.9 $0.0 $5.5 Decommissioning Transportation $2.8 $0.0 $1.3 Uranium Recovery $0.4 $0.0 $0.2 41 In order to temporarily mitigate the financial impacts and economic disruptions to licensees caused by the COVID-19 PHE, the NRC deferred all invoices scheduled to be issued in April, May, and June 2020 until July 22, 2020.
42 Materials UsersBilled as flat fee applications and included in the estimates and billed.
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Significant Ongoing Licensing Actions The following table includes a comparison of the fees billed to projected resources for the NuScale SMR design certification review, subsequent license renewal application reviews, Oklos Aurora combined license application, and the SHINE Medical Technologies, LLC operating license application review. The subsequent renewed licenses for Turkey Point Units 3 and 4 and Peach Bottom Units 2 and 3 were issued on December 4, 2019, and March 5, 2020, respectively.
Fees Billed Projected Docket Project Name to Date Resources ($M) 43
($M) 44 NuScale Power NuScale SMR Design
$55.0 Reactor 05200048 Certification Application Review NuScale SMR Topical Report
$66.0 45 NuScale Power Reviews (Only those that
$7.9 Reactor 99902043 directly support the design certification review).
Peach Bottom Units 2 Peach Bottom Units 2 and 3 and 3 Subsequent License Renewal $4.3 $4.1 05000277/05000278 ApplicationSafety Review Peach Bottom Units 2 and 3 Peach Bottom Units 2 Subsequent License Renewal and 3 $1.5 $1.5 ApplicationEnvironmental 05000277/05000278 Review Surry Units 1 and 2 Surry Units 1 and 2 Subsequent License Renewal $4.9 $4.6 05000280/05000281 Application Safety Review Surry Units 1 and 2 Surry Units 1 and 2 Subsequent License Renewal
$1.4 $1.6 46 05000280/05000281 Application Environmental Review 43 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 $275/hour.
44 In order to temporarily mitigate the financial impacts and economic disruptions caused by the COVID-19 PHE, the NRC deferred all Q3 FY 2020 invoices (ADAMS Accession No. ML20112F428). Although the subsequent renewed licenses for Peach Bottom Units 2 and 3 were issued, fees billed are retained because Q3 FY 2020 invoices were deferred.
45 When the NuScale design certification application was submitted, the NRC staff did not provide projected resources to applicants. This number was calculated for this report using fees billed to date (for the NuScale design certification application and supporting topical reports - $58.1M) plus a projection of the fees that the NRC staff expects to bill through the end of the technical review in September 2020 ($7.9M). This estimate is based on critical assumptions such as high quality and timely submittals by NuScale for the remainder of the review.
Costs associated with pre-application activities are not included.
46 When the Surry subsequent license renewal application was accepted for review on December 3, 2018, the NRC estimate was $6.3M. At that time, the NRC had not yet completed the review of the first subsequent license renewal application to provide a basis for comparison. The staff provided a revised estimated cost of $7.6M.
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Fees Billed Projected Docket Project Name to Date Resources ($M) 43
($M) 44 SHINE Medical Isotope SHINE Medical Production Facility Operating Technologies, LLC License Application Review $6.2 47 $1.7 05000608 Safety and Environmental Reviews Oklo Aurora Oklo Aurora Combined License
$0.5 48 $0.0 05200049 Application - Safety Review Oklo Aurora Oklo Aurora Combined License 05200049 Application - Environmental $0.2 $0.0 Review 3-6 Requests for Additional Information The table below provides information on RAIs associated with licensing actions that are considered requested activities of the Commission for which the NRC staff issues a final 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 Inventory Total Number Total Number Total Number of Open RAIs as of RAIs of RAIs of RAIs Type of Facility or of the End of Issued in Responded to Closed in Activity Type Reporting Reporting in Reporting Reporting Period Period Period Period 49 Operating Reactors 359 194 227 162 Non-Power Production and 450 75 54 20 Utilization Facilities 50 Design Certifications 0 0 0 4 for New Reactors Early Site Permits N/A N/A N/A N/A for New Reactors 51 Combined Licenses 0 0 0 0 for New Reactors Fuel Facilities 25 18 42 28 47 The projected resource estimate was provided to SHINE by letter dated April 30, 2020 (ADAMS Accession No. ML20114E315).
48 When the Oklo COL was accepted, the NRC indicated that the staff plans to complete the review in a two-step process. This table only contains the projected resources to complete Step 1 of the review.
49 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 no additional information is needed to resolve the issue.
50 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 Medical Technologies, LLC operating license application.
51 There are no early site permit applications 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 Inventory Total Number Total Number Total Number of Open RAIs as of RAIs of RAIs of RAIs Type of Facility or of the End of Issued in Responded to Closed in Activity Type Reporting Reporting in Reporting Reporting Period Period Period Period 49 Power Reactor 27 16 16 0 Decommissioning Research and Test Reactor 6 0 0 0 Decommissioning Spent Fuel 711 79 221 1 Materials 6 6 0 0 Pre-Application Activities for 41 0 0 0 Advanced Reactors 3-7 Workforce Development and Management FY 2020 Staffing by Office 52 End of Year FTE FTE FTE FTE Delta (Q3 FTE Delta (EOY (EOY) 53 FY 2020 Utilization Utilization Utilization Utilization Utilization - Projection -
Projection w/
Budget 03/15/20 - 04/26/20 - 05/24/20 - as of FY 2020 FY 2020 Personnel 04/25/20 05/23/20 06/20/20 06/20/20 Budget) Budget)
Actions Totals 54 2979.0 211.4 210.9 215.4 2035.2 -943.8 2795.2 -183.8 COMM 45.0 2.2 2.2 2.3 20.8 -24.2 30.2 - 14.8 OIG 63.0 3.9 4.0 4.3 39.9 -23.1 55.6 -7.4 Totals Other 2871.0 205.3 204.7 208.8 1974.4 -896.6 2709.4 -161.6 Offices OCFO 96.0 6.9 6.8 7.0 66.1 -29.9 90.9 -5.1 OGC 96.0 7.0 7.0 7.1 67.2 -28.8 91.8 -4.2 OCA 11.0 0.8 0.8 0.8 7.7 -3.3 10.4 -0.6 OCAA 8.0 0.4 0.4 0.5 4.5 -3.5 6.3 -1.7 OPA 15.0 1.0 1.0 1.0 10.0 -5.0 13.5 -1.5 SECY 18.0 1.2 1.2 1.3 11.5 -6.6 16.1 -1.9 OIP 35.0 2.6 2.5 2.5 24.2 -10.8 33.4 -1.6 ASLBP 24.0 1.7 1.7 1.7 16.3 -7.7 21.9 -2.1 ACRS 24.0 2.1 2.1 2.1 19.9 -4.1 27.2 3.2 OEDO 23.0 1.6 1.6 1.6 15.2 -7.8 20.8 -2.2 NRR 601.3 42.4 42.4 43.2 413.9 -188.4 563.6 -38.7 NMSS 296.2 23.7 23.6 24.2 225.3 -70.9 309.2 13.0 RES 205.4 14.1 14.1 15.0 136.5 -67.9 188.9 -15.5 NSIR 158.5 12.3 12.2 12.3 116.4 -42.1 159.0 0.5 R-I 182.3 12.7 12.6 12.8 123.3 -59.0 169.0 -13.3 R-II 235.7 16.6 16.5 16.4 159.3 -76.4 216.7 -19.0 R-III 178.9 12.9 12.9 13.4 125.7 -53.2 171.8 -7.1 52 Some numbers might not add due to rounding.
53 Based on FTE utilization as of June 20, 2020.
54 Totals include Office of the Inspector General.
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End of Year FTE FTE FTE FTE Delta (Q3 FTE Delta (EOY (EOY) 53 FY 2020 Utilization Utilization Utilization Utilization Utilization - Projection -
Projection w/
Budget 03/15/20 - 04/26/20 - 05/24/20 - as of FY 2020 FY 2020 Personnel 04/25/20 05/23/20 06/20/20 06/20/20 Budget) Budget)
Actions R-IV 166.1 12.4 12.3 12.4 116.9 -49.2 160.8 -5.3 OE 30.6 2.3 2.3 2.3 21.9 -8.7 30.0 -0.6 OI 38.0 3.0 3.0 3.0 29.2 -8.8 39.6 1.6 OCIO 171.0 11.6 11.5 11.7 110.8 -60.2 152.1 -18.9 ADM 131.0 8.8 8.9 9.0 83.7 -47.3 114.5 -16.5 SBCR 13.0 0.8 0.8 0.8 7.7 -5.3 11.0 -2.0 OCHCO 112.0 6.1 6.1 6.5 59.8 -52.2 88.6 -23.4 CSU 1.0 0.2 0.2 0.2 1.6 0.6 2.2 1.2 3-8 Inspection Activities The table below shows the average number of hours of direct inspection per plant in FY 2020.
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 Matrix Matrix Matrix Matrix 730 Hours 739 Hours 577 Hours 55 No Plants in No Plants in Column 3 Column 4 The table below shows the staff hours expended for inspection-related effort at operating power reactor sites by CY.
Items Description CY 2019 (Hours) CY 2020 (YTD) (Hours)
- i. Baseline Inspection 235,718 99,612 ii. Plant Specific Inspection 9,096 3,588 iii. Generic Safety Issue Inspections 3,200 522 iv. Performance Assessment 1,532 880
- v. Other Activities 98,614 44,191 vi. Total Staff Effort 348,160 148,793 vii. Total Staff Effort Per Operating Site 6,003 56 2,610 57 3-9 Backfit Facility-Specific Backfits There were no facility-specific backfits issued during the reporting period.
55 Browns Ferry Nuclear Plant (three-unit boiling water reactor site) and Vogtle Electric Generating Plant (two-unit pressurized water reactor site) were in Column 2 of the ROP Action Matrix year-to-date in CY 2020.
56 Total staff effort is divided by 58 sites for CY 2019, due to Pilgrim Nuclear Station permanently ceasing operations on May 31, 2019. Because Three Mile Island, Unit 1, operated for the majority of CY 2019, it was included as an operating site.
57 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.
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Generic Backfits There were no generic backfits 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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