ML20303A021
| ML20303A021 | |
| Person / Time | |
|---|---|
| Issue date: | 11/12/2020 |
| From: | Kristine Svinicki NRC/Chairman |
| To: | Barrasso J, Braun M, Pallone F US HR, Comm on Energy & Commerce, US SEN, Comm on Environment & Public Works, US SEN, Subcomm on Clean Air & Nuclear Safety |
| Matthew Meyer, OEDO | |
| Shared Package | |
| ML20303A019 | List: |
| References | |
| CORR-20-0105 | |
| Download: ML20303A021 (35) | |
Text
STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION For the Reporting Period of July 1, 2020 through September 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 Q4 Fiscal Year (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.................................................................................................................. 8 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........................................................................................................................................ 17 2-9 Reactor Oversight Process......................................................................................................... 18 2-10 Backfit.......................................................................................................................................... 19 2-11 Risk-Informed Activities............................................................................................................... 20 2-12 Coronavirus Disease 2019 Public Health Emergency................................................................ 22 - Summary of Activities...................................................................................... 24 3-1 Reactor Oversight Process Findings........................................................................................... 24 3-2 Licensing Actions........................................................................................................................ 25 3-3 Licensing Amendment Request Reviews................................................................................... 26 3-4 Research Activities...................................................................................................................... 28 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
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- High Level Summary 1-1 Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act 1-2 Reactor Oversight Inspection Hours and Percent Complete 30%
40%
50%
60%
70%
80%
90%
100%
Average Timeliness Percentage
(<100% = Completed Before Schedule Date)
Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule 0%
10%
20%
30%
40%
50%
60%
70%
80%
90%
100%
0 20,000 40,000 60,000 80,000 100,000 120,000 140,000 160,000 180,000 Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cumulative Percent of Planned Direct Inspection Hours Complete Direct Inspection Hours 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
4 1-3 FTE at the End of Q4 FY 2020 vs. Budgeted FTE 1-4 Budget Authority, FTE Utilization, and Fees NRC FY 2020 Budget Authority - September 30, 2020 (Dollars in Thousands)
Fund Sources FY 2020 Budget1 Percent Obligated Percent Expended Advanced Reactor
$16,015 97%
65%
Commission Funds
$11,908 53%
52%
Fee-Based Funds
$830,150 97%
76%
General Funds
$1,553 71%
43%
International Activities
$14,500 93%
80%
Integrated University Program
$16,000 16%
0%
Official Representation
$25 25%
19%
Total
$890,151 95%
74%
NRC Control Points FY 2020 Budget Percent Obligated Percent Expended Nuclear Reactor Safety
$447,940 97%
84%
Nuclear Materials and Waste Safety
$105,282 98%
81%
Decommissioning and Low-Level Waste
$23,141 92%
83%
Corporate Support
$298,288 96%
60%
Integrated University Program
$16,000 16%
0%
Total
$890,151 95%
74%
1 FY 2020 budget includes the enacted and carryover budget.
0 100 200 300 400 500 600 Other Office of General Counsel Office of the Chief Information Officer Office of the Chief Human Capital Officer Office of the Chief Financial Officer Office of Administration Region IV Region III Region II Region I Office of Nuclear Security and Incident Response Office of Nuclear Regulatory Research Office of Nuclear Material Safety and Safeguards Office of Nuclear Reactor Regulation FTE Budgeted FTE On Board FTE
5 FTE Utilization, Hiring, and Attrition Total Year to Date (YTD) FTE Utilization Projected End of Year FTE Total Utilization Quarter 4 Hiring Quarter 4 Attrition YTD Hiring YTD Attrition 2789.7 2789.7 51 38 112 194 FY 2020 Fees Estimated, Fees Billed, and Fees Collected Through Q42 Total 10 CFR Part 170 Fees Billed (Dollars in Millions)
FY 2018 FY 2019 FY 2020 (Q1 - Q4)
$266.0
$245.3
$205.7 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.
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 $603,433 $723,625 $723,695 Total Actual Collected $124,193 $185,896 $190,225 $320,830 $364,708 $367,144 $368,776 $369,346 $369,784 $397,032 $591,876 $704,941
$0
$100,000
$200,000
$300,000
$400,000
$500,000
$600,000
$700,000
$800,000 Amount (Dollars in Thousands)
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- 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, the NRC staff implemented an improved process for preparing Commission papers that includes formal requirements to ensure early alignment on the papers analytical approaches and key messages. The NRC staff also publicly briefed the Commission on the progress of transformation activities on September 17, 2020. The briefing focused on the Culture Improvement Strategy; the new agencywide innovation platform (Innovate NRC 2.0); the Signposts and Markers dashboard, which uses key indicators to inform strategic decisionmaking; and the use of data analytics to improve the Nuclear Reactor Safety Program.
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Transformation Activities Projected Completion Date Completion Date Begin implementation of improved process to streamline Commission paper preparation.
07/30/2020 08/06/2020 Brief the Commission on staffs transformation activities (public meeting) (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML20253A225).
09/17/2020 09/17/2020 Complete initial training of senior leaders on behavior and how to effect cultural change as a part of the transformation initiative.
09/30/2020 07/30/2020 Develop the first iteration of the Signposts and Markers dashboard to inform decisionmaking processes, such as workforce planning and the agency environmental scan development.
09/30/2020 09/30/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Transformation Activities Projected Completion Date Conduct series of KNOWvember seminars on transformation focus areas and knowledge management activities.
11/30/2020
7 Projected Transformation Activities Projected Completion Date Conduct seminar for all agency staff on strategic and managerial aspects of risk-informed decisionmaking.
12/31/20203 Launch 2021 Objectives and Key Results transformation performance management framework.
01/04/2021 Launch a platform for employees to highlight opportunities and key markers for career progression in disciplines where future staff skills gaps are anticipated.
02/01/2021 Communicate the progress of transformation activities to stakeholders and members of the public at the 2021 Regulatory Information Conference.
03/11/2021 Conduct a survey of NRC staff on organizational culture to assess progress made since the initial survey in March 2020.
03/30/2021 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. The FY 2020 strategies included recruitment and retention activities, as well as cross-training, cross-qualification, and knowledge management activities to build expertise in areas projected to experience skill and proficiency gaps in the future.
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Workforce Development and Management Activities Projected Completion Date Completion Date Onboard 55 summer hire students for virtual internships; 37 students are slated to return next summer.
09/01/2020 09/01/2020 Complete 14 weeks of initial training in regulatory and technical fundamentals for the NRCs Nuclear Regulator Apprenticeship Network.
09/30/2020 09/30/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Workforce Development and Management Activities Projected Completion Date Complete Agency Environmental Scan to support 2021 SWP activities.
12/04/20204 3
Conducting seminars for all agency staff on strategic and managerial aspects of risk-informed decisionmaking was previously scheduled for completion on September 1, 2020, but has been delayed due to limited availability of the main seminar speaker.
4 Completion of the Agency Environmental Scan to support 2021 SWP activities was previously scheduled for completion on September 30, 2020, but has been moved to December 4, 2020, because this activity was merged with an activity that was scheduled to be completed later to streamline the overall process.
8 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 staff is executing the ATF project plan (ADAMS Accession No. ML19301B166). The NRC staff is currently reviewing one ATF fuel vendor topical report on a new type of fuel pellet called ADOPT. The staff is also reviewing another vendor topical report that discusses allowing the use of a limited number of higher burnup lead test assemblies. The NRC staff is also preparing for additional ATF submittals from fuel vendors expected in CY 2021.
The NRC recently approved three ATF-related requests. The first documents the NRCs review and acceptability of Global Nuclear Fuel - Americas, LLCs assumptions and methodology for performing criticality analyses up to 8 weight percent uranium-235 (ADAMS Accession No. ML20219A463). The second allows the transportation of fuel rods with chromium-coated cladding, doped pellets, and enrichment to up to 7 weight percent uranium-235 (ADAMS Accession No. ML20255A295). The third is for transportation of ATF lead test assembles to Monticello Nuclear Generating Plant (ADAMS Accession No. ML20283A357).
The NRC staff led a workshop on higher burnup fuels in July 2020. The primary purpose of the workshop was to relay the NRC staffs expectations regarding licensing submittals for higher burnup fuels, including clarification on the expected content and estimated timelines for submission.
The NRC held the initial panel discussion for the Severe Accident Phenomena Identification Ranking Table (PIRT) exercise during this reporting period. This PIRT exercise includes a panel of international experts that will address the significant issues affecting core degradation and radiological releases under severe accident conditions for various ATF designs. The scope of the PIRT exercise also includes the impact of higher burnup and higher enrichment fuels.
Once PIRT results are reported, the NRC will have a better understanding of how ATF concepts affect severe accident progression. This information will help improve the agencys severe accident computer code MELCOR.
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
ATF Activities Projected Completion Date Completion Date Update of the public ATF Web page5 to provide more information in a more user-friendly format with infographics and embedded links.
07/31/2020 07/24/2020 Complete review of ATF-related request for a minimum margin of subcriticality to support future processing of enrichments up to 8 percent (ADAMS Accession No. ML20219A463).
10/30/2020 08/13/2020 Conduct higher burnup fuel public workshop. This workshop will relay initial NRC expectations to the nuclear industry for licensing submittals for higher burnup fuels, including clarification on the expected content and estimated timelines for submission.
08/31/2020 07/30/2020 5
https://www.nrc.gov/reactors/atf.html.
9 ATF Activities Projected Completion Date Completion Date Complete review of ATF-related request to allow the transportation of fuel rods with chromium-coated cladding, doped pellets, and fuel rods enriched to up to 7 percent (ADAMS Accession No. ML20255A295).
08/31/2020 09/15/20206 Hold phenomena identification and ranking exercise for severe accidents. This exercise will provide information on the performance of various ATF concepts, higher burnup fuel, and fuel with enrichment above 5 percent in severe reactor accidents to support refinement of regulatory guidance.
09/31/2020 09/11/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected ATF Activities Projected Completion Date Issue iron-chromium-aluminum (FeCrAl) cladding report. This report will identify and discuss degradation and failure modes of FeCrAl cladding concepts, including fuel performance characteristics that may not be addressed within existing regulatory documents.
10/31/2020 Issue Spent Fuel Storage and Transportation of ATF Concepts report.
This report will provide an assessment of available information related to the storage and transportation of spent nuclear fuel involving near-term ATF concepts, specifically Cr-coated zirconium alloy and FeCrAl cladding.
10/31/2020 Complete review of ATF-related request for Framatome to transport ATF lead test assemblies to Monticello Nuclear Generating Plant.
01/08/20217 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 and (2) commercial grade dedication of digital equipment.
Regarding protection against common cause failure, the NRC staff briefed the Advisory Committee on Reactor Safeguards (ACRS) DI&C subcommittee on September 8, 2020, on its update of Branch Technical Position (BTP) 7-19, Guidance for Evaluation of Diversity and Defense-In-Depth in Digital Computer Based Instrumentation and Control Systems. The staff subsequently held a public meeting on September 24, 2020, to discuss comments from the ACRS and other stakeholders. The staff is currently working on finalizing this guidance.
Regarding commercial grade dedication of digital equipment, the NRC staff provided comments to the Nuclear Energy Institute (NEI) on draft NEI 17-06, Guidance on Using IEC 61508 SIL 6
This ATF-related request was previously scheduled for completion on August 31, 2020, but was delayed due to additional time required for internal peer review. The applicant was kept informed of the delay.
7 The staff completed this activity on October 9, 2020 (ADAMS Accession No. ML20283A357), which will be reflected for the next reporting period.
10 Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, on December 19, 2019, and additional comments following public meetings in April, July, and September 2020. NRC staff anticipates receiving NEI 17-06 by the end of CY 2020 for NRC review and potential endorsement.
The NRC staff continues to review and prepare for anticipated digital modernization license amendment requests (LARs). On August 26, 2020, the staff accepted a LAR from Entergy for an upgrade to the core protection calculator at Unit 3 of the Waterford Steam Electric Station (Waterford). The NRC staff anticipates issuing a licensing decision by the end of August 2021.
In a public-private partnership with the Department of Energys (DOEs) Light Water Reactor Sustainability Program, Exelon Generation Corporation, LLC (Exelon) plans to develop and implement an extensive digital modernization of multiple safety systems at the Limerick Generating Station. NRC expects to receive the LAR in CY 2021. The NRC staff held the first preapplication meeting with Exelon on June 12, 2020, and anticipates the next pre-application meeting by the end of CY 2020.
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Digital Instrumentation and Control Activities Projected Completion Date Completion Date 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 09/08/2020 Hold a public meeting with NEI to discuss industry comments (ADAMS Accession No. ML20258A269).
09/24/2020 09/24/2020 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 a regulatory guide (RG).
Hold a public meeting to discuss resolution of NRC staff comments (ADAMS Accession No. ML20183A258).
07/09/2020 07/09/2020 Significant Digital Modernization LAR Milestones Complete acceptance review for Entergy LAR for Waterford Unit 3.8 8/28/2020 8/26/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Digital Instrumentation and Control Activities Projected Completion Date Update BTP 7-19, Guidance for Evaluation of Diversity and Defense-In-Depth in Digital Computer Based Instrumentation and Control Systems.
ACRS Full Committee Meeting.
11/30/2020 8
On July 23, 2020, Entergy submitted a LAR for NRC review to upgrade the core protection calculator at Waterford Unit 3. The LAR is based on updated NRC guidance in Revision 2 of DI&C interim staff guidance (ISG)-06, Licensing Process (ADAMS Accession No. ML18143B633), with a new streamlined Alternate Review Process for early design approval (ISG-06 is a completed DI&C guidance activity previously tracked in this report). The acceptance review decision is a major milestone in the NRC license amendment review process.
11 Projected Digital Instrumentation and Control Activities Projected Completion Date Hold a public meeting to discuss resolution of comments.
12/21/2020 Submit request to the Office of Management and Budget (OMB) for major/non-major rule determination for BTP 7-19 under the Congressional Review Act in preparation for final issuance.
12/31/2020 Issue Revision 8 to BTP 7-19 03/01/20219 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.
Observe audit of a third-party certifying body.
11/30/2020 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 (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. During this reporting period, SNC updated its public milestone for initial fuel loading of Vogtle Electric Generating Plant (Vogtle) Unit 3 from November 23, 2020, to April 30, 2021. The NRCs Vogtle Readiness Group (VRG) increased their meeting frequency to assess NRC activities and schedule, and to identify any regulatory challenges that might affect transition to operations. During the COVID-19 public health emergency (PHE),
construction inspections and licensing activities continue with only minor interruptions due to the successful application of technology for telework and remote access to licensee information.
The NRC continues to perform on-site inspections at Vogtle.
During this reporting period, the NRC issued two key documents related to Vogtle. On August 14, 2020, the NRC staff issued a memorandum that outlines the plan to provide an effective and efficient transition of Vogtle Units 3 and 4, from the Construction Reactor Oversight Process to the Reactor Oversight Process (ROP) (ADAMS Accession No. ML20191A383). The plan describes inspections and assessments performed before and after the 10 CFR 52.103(g) finding (i.e., the finding that all inspections, tests, analyses, and acceptance criteria (ITAAC) have been successfully completed) and provides details on how each unit transitions to the ROP. In addition, on September 24, 2020, the NRC staff issued a memorandum to the Commission providing updates on ITAAC completion, inspection activities, including construction and operational programs, licensing activities, and any current challenges for Unit 3 (ADAMS Accession No. ML20183A090).
9 Final issuance is contingent on the NRC receiving a major/non-major rule determination from OMB within 60 days.
12 Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Vogtle Electric Generating Plant Units 3 and 4 Activities Projected Completion Date 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 Reactor Oversight Process to the Reactor Oversight Process (ADAMS Accession Nos. ML20191A383 and ML20191A398).
08/31/2020 08/14/2020 Issue amendments for LARs20-001, 20-002, and 20-003 (ADAMS Accession Nos. ML20132A032, ML20196L674, and ML20237F487, respectively).
09/30/2020 09/24/2020 Issue memorandum to inform the Commission of the status of Vogtle Unit 3 construction. This memorandum will provide updates on ITAAC completion, inspection activities (including construction and operational programs), licensing activities, and any current challenges (ADAMS Accession No. ML20183A090).
09/30/2020 09/24/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Projected Completion Date Issue amendments for LARs20-004 and LAR 20-005 (provided the requisite findings are made).
12/30/2020 Conduct public meeting to discuss VRG activities.10 03/31/2021 NRC Inspections and ITAAC Reviews for the Reporting Period (Q4 FY 2020)
A combined license allows a licensee to construct a plant and to operate it once construction is complete if certain standards identified in the combined license are satisfied. These standards are called ITAAC. The majority of ITAAC are from the design certification for the particular reactor technology the plant uses. Throughout the construction process, NRC inspectors will perform inspections based upon Inspection Manual Chapter 2503, Construction Inspection Program: Inspections of Inspections, Tests, Analyses and Acceptance Criteria (ITAAC) Related Work, and the NRC's 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.
10 A public meeting to discuss VRG activities was added to ensure public engagement during the Vogtle 3 and 4 construction.
13 Number of ITAAC Remaining Requiring Inspection Total Inspections Completed11 ITAAC Inspected12 ITAAC Inspections Closed13 244 55 38 11 ITAAC Reviews Completed for the Reporting Period (Q4 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 3 2.1.02.08e 07/06/2020 07/07/2020 Vogtle 4 2.3.05.03a.ii 07/22/2020 07/24/2020 Vogtle 3 2.2.03.08c.ii 07/24/2020 08/04/2020 Vogtle 3 2.2.03.08c.i.04 07/30/2020 07/31/2020 Vogtle 3 2.1.02.08d.i 07/31/2020 08/18/2020 Vogtle 4 2.5.05.03b 07/31/2020 08/05/2020 Vogtle 3 C.3.8.02.01 08/07/2020 08/10/2020 Vogtle 4 C.3.8.02.01 08/07/2020 08/10/2020 Vogtle 3 C.2.6.09.02 08/11/2020 09/10/2020 Vogtle 3 2.3.05.03d.ii 08/19/2020 08/20/2020 Vogtle 3 2.7.06.02.ii 08/27/2020 09/10/2020 Vogtle 3 2.1.02.09b.ii 08/28/2020 09/02/2020 Vogtle 3 3.3.00.02a.i.a 09/15/2020 09/17/2020 Vogtle 3 2.3.05.03c.ii 09/21/2020 09/25/2020 Vogtle Units 3 and 4 LAR Reviews Completed (Q4 FY 2020)
Number of LAR Reviews Forecast to be Completed in the Reporting Period Number of LAR Reviews that were Completed in the Reporting Period 3
3 2-6 NuScale Small Modular Reactor (SMR) Design Certification On March 15, 2017, the NRC accepted the NuScale Power, LLC (NuScale) application for an SMR design certification review. On August 28, 2020, the NRC staffs technical review was completed.
In February 2020, the NRC was informed that NuScale had identified an issue with the emergency core cooling system (ECCS). As a result, 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 and associated technical and topical 11 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).
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.
13 ITAAC Inspection Closed refers to the number of ITAAC for which all associated inspections have been completed during the reporting period.
14 reports, which required further NRC review. NuScale submitted the proposed final design changes and supporting information to the NRC on May 20, 2020 (ADAMS Accession No. ML20141L787).
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 (ACRS Review of Advanced Safety Evaluation Report (SER) with No Open Items) was completed on July 31, 2020. The staff completed the final SER on August 28, 2020, (ADAMS Accession No. ML20023A318) and issued a standard design approval to NuScale on September 11, 2020 (ADAMS Accession No. ML20247J564). The staff is preparing the draft proposed rule that will propose certifying the design and anticipates publishing the proposed rule for public comment in February 2021.
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
NuScale SMR Design Certification Activities Projected Completion Date Completion Date ACRS full committee meeting on NuScales Boron Redistribution and Technical Specifications (presentation by the NRC staff) (ADAMS Accession No. ML20170A337).
07/08/2020 07/08/2020 ACRS full committee meeting on NuScales boron redistribution, NuScales design certification final letter, and lessons learned (ADAMS Accession No. ML20170A348).
07/25/2020 07/22/2020 Complete Phase 5 of the safety review (ACRS Review of Advanced SER with No Open Items).
07/31/202014 07/31/2020 Complete Phase 6 of the safety review (Final SER with No Open Items) (ADAMS Accession No. ML20231A804).
09/08/2020 08/28/2020 Issue standard design approval for the NuScale SMR design certification (ADAMS Accession No. ML20247J564).
09/11/2020 09/11/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected NuScale SMR Design Certification Activities Projected Completion Date Publish proposed rule for NuScale SMR design certification.15 02/08/2021 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 14 Due to NuScale's design change and proposed schedule modification for submitting the revised supporting documentation, the Phase 5 milestone of June 23, 2020, was delayed. This milestone was revised to reflect a Phase 5 milestone of July 31, 2020, upon receipt of NuScale's final design change package; the NRC staff informed NuScale about this update in a letter on May 1, 2020 (ADAMS Accession No. ML20112F455).
15 Additional information regarding this rulemaking is available at the following Web page:
https://www.nrc.gov/reading-rm/doc-collections/rulemaking-ruleforum/active/RuleDetails.html?id=40
15 achieve non-LWR safety review readiness.16 During this reporting period, the NRC staff issued a draft white paper to support public and ACRS interactions on developing a risk-informed, technology-inclusive regulatory framework for advanced reactors (10 CFR Part 53 rulemaking).
The NRC staff also issued the final safety evaluation for a Tristructural Isotropic (TRISO) topical report. The NRC also issued a draft white paper with proposed fuel qualification methodology for non-LWR developers on qualification of fuel as part of its efforts to implement provisions in the Nuclear Energy Innovation and Modernization Act (NEIMA).
On October 6, 2020, the NRC, in coordination with the DOE and the Fusion Industry Association, held a public forum with over 190 participants on developing a regulatory framework for commercial fusion reactors. Chairman Svinicki provided opening remarks and answered questions along with DOEs Under Secretary for Science, Paul Dabbar. The NRC staff will coordinate future meetings with DOE, the Fusion Industry Association, and other stakeholders to support developing options for Commission consideration on a framework for regulating commercial fusion facilities.
The NRCs public Web site 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 Web site (https://www.nrc.gov/reactors/new-reactors/advanced.html#stakeholder).
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Advanced Nuclear Reactor Technologies Activities Projected Completion Date Completion Date Issue a draft white paper to support public and ACRS interactions on developing a risk-informed, technology-inclusive regulatory framework for advanced reactors (10 CFR Part 53 rulemaking)
(ADAMS Accession No. ML20195A270).
07/31/2020 07/20/2020 Issue final safety evaluation for TRISO topical report (ADAMS Accession No. ML20216A323).
08/30/2020 08/11/2020 Issue Scoping Summary Report for the Advanced Nuclear Reactor Generic Environmental Impact Statement (ADAMS Accession No. ML20260H180).
09/25/2020 09/25/2020 Issuance of report by the Idaho National Laboratory entitled, Risk-Informed, Performance-Based, Technology-Inclusive Regulatory Infrastructure:
Technology-Inclusive Determination of Mechanistic Source Terms for Offsite Dose-Related Assessments for Advanced Nuclear Reactor Facilities (ADAMS Accession No. ML20192A250).
09/30/2020 06/30/2020 Issuance of report by Oak Ridge National Laboratory (ORNL) entitled, MSR Fuel Salt Qualification Methodology (ADAMS Accession No. ML20197A257).
09/30/2020 07/01/2020 16 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.html#advSumISRA).
16 Advanced Nuclear Reactor Technologies Activities Projected Completion Date Completion Date Issuance of two technical input reports by ORNL and Pacific Northwest National Laboratory (PNNL) for the NRCs review of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III Division 5 (ADAMS Accession Nos.
ML20269A125 and ML20269A145).
09/30/2020 09/04/2020 Issue draft white paper with proposed fuel qualification methodology to provide guidance for non-LWR developers on qualification of fuel under NEIMA (ADAMS Accession No. ML20191A259).
12/31/2020 09/15/2020 Issuance of report by PNNL on environmental impacts of non-LWR fuel cycle and transportation (ADAMS Accession Nos. ML20267A157).
12/31/2020 09/30/2020 Issue Code Assessment Report, Volume 4, on Dose Assessment. (ADAMS Accession No. ML20028F255).
12/31/2020 09/04/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Advanced Nuclear Reactor Technologies Activities Projected Completion Date Host NRC Standards Forum to facilitate the identification of needed consensus codes and standards and explore collaboration to accelerate their development with a focus on advanced non-light water reactors.
10/13/2020 Issue a paper to the Commission on micro-reactors. The paper will discuss potential licensing and policy issues specific to micro-reactors.
10/30/202017 Issue two technical input reports by ANL and NUMARK Associates, Inc.
for the NRCs review of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III Division 5.
10/30/202018 Issue a memorandum to the Commission providing a schedule with milestones and resource requirements to achieve publication of the final 10 CFR Part 53 rule by October 2024.
11/02/2020 Issue final white paper with proposed fuel qualification methodology to provide guidance for non-LWR developers on qualification of fuel under NEIMA.
12/31/2020 Issue Final Interim Staff Guidance, Environmental Considerations Associated with Micro-reactors.
12/31/2020 Issue annual paper to the Commission on the status of advanced reactor readiness activities.
01/31/2021 17 Issuance delayed from the previous projected date of August 30, 2020, due to higher priority activities.
18 Two of the four technical input reports projected in the FY 2020 Q3 report were issued in August and September 2020. The remaining two reports are now scheduled for October 30, 2020, to address additional comments.
17 Projected Advanced Nuclear Reactor Technologies Activities Projected Completion Date Issue final technology-inclusive, risk-informed, and performance-based design review guide for instrumentation and controls systems for advanced reactors.
01/31/202119 Issue three technical reports on molten salt chemistry, salt compatibility with high temperature materials, and high temperature corrosion.
03/31/2021 Issue Material Control and Accounting guidance for Category II facilities (NUREG-2159).
05/31/202120 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) application21 for the Aurora reactor to the NRC (ADAMS Accession No. ML20075A000). The NRC staff determined that the application is acceptable for docketing and is proceeding with the safety and environmental reviews. 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 (RAIs) to efficiently align on four key safety and design aspects of the proposed licensing basis. After aligning on the key aspects in Step 1, the 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, conducting its environmental review, and issuing the staffs final SER after the ACRS completes its review.
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 (Q4 FY 2020)
Oklo COL Review Activities Projected Completion Date Completion Date Hold initial public meeting to discuss the methodology used in the analysis and evaluation of the maximum credible accident.
08/04/2020 08/04/2020 19 The schedule for final issuance has been revised to ensure sufficient time for ACRS review and comment. The ACRS subcommittee meeting was held on October 21, 2020, and the ACRS full committee is scheduled for December 3, 2020.
20 Issuance delayed from the original projected date of January 31, 2020, due to higher priority licensing actions.
21 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.
18 Oklo COL Review Activities Projected Completion Date Completion Date Hold initial public meeting to discuss the process to be used for classifying structures, systems, and components (SSCs) in the Aurora design and the treatment for each classification of SSCs.
08/05/2020 08/05/2020 Complete an audit on the maximum credible accident heat transfer in reactor system.
08/29/2020 08/29/2020 Hold initial public meeting to discuss scope and application of the Quality Assurance Program.
08/31/2020 N/A22 Issue RAIs on the Step 1 review topics (ADAMS Accession Nos. ML20265A346, ML20267A529, ML20265A121, ML20265A123 ).
09/23/2020 09/23/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)23 Projected Oklo COL Review Activities Projected Completion Date Complete an audit on the methodology used in the analysis and evaluation of the maximum credible accident.
10/21/202024 Hold second public meeting to discuss the methodology used in the analysis and evaluation of the maximum credible accident.
10/31/2020 Hold second public meeting to discuss the process to be used for classifying SSCs in the Aurora design and the treatment for each classification of SSCs.
10/31/2020 Conduct audits for Step 1 review topics25 related to maximum credible accident, classification of SSCs, and applicability of regulations 10/30/2020 Complete initial outreach to local stakeholders (e.g., Governors office, Congressional staff, Tribes) regarding the environmental impacts.
10/31/2020 Complete Step 1 and document the NRC staffs understanding of alignment with Oklo on key technical issues.
11/05/2020 Issue letter documenting the status of all Step 1 issues.
11/05/2020 Issue Notice of Intent to Prepare an Environmental Impact Statement and initiate project scoping process for the Oklo Aurora design.
12/31/2020 2-9 Reactor Oversight Process The ROP is a risk-informed, performance-based oversight program that contains provisions for continuous self-assessment and improvement. The staff developed recommendations to make changes to the ROP in SECY-19-0067, Recommendations for Enhancing the Reactor Oversight Process, (ADAMS Accession No. ML19070A050) which are being considered by the 22 This activity was projected for FY2020 Q4 in the FY 2020 Q3 report. The staff plans to address this issue instead through the RAI process and subsequent inspection.
23 The public meeting dates are subject to change. The NRCs public Web site is updated periodically to show the status of the meetings (https://www.nrc.gov/reactors/new-reactors/col/aurora-oklo/public-meetings.html).
24 The projected date for this audit was extended to allow the staff additional time to review the applicants audit materials.
25 The FY2020 Q3 report included a planned activity to conduct an audit on the Quality Assurance program. That has been expanded in this report to conduct audits as needed for all Step 1 issues.
19 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 (Q4 FY 2020)
Reactor Oversight Process Activities Projected Completion Date Completion Date Complete effectiveness review of the cross-cutting issues process and issue report (ADAMS Accession No. ML20239A806).
10/31/2020 09/21/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Reactor Oversight Process Activities Projected Completion Date Issue revision to Inspection Procedure 95001, Supplemental Inspection Response to Action Matrix Column 2 Inputs.
10/31/2020 Complete comprehensive review of problem identification and resolution program and issue report.
11/27/202026 Complete Annual Regional ROP Implementation Audit (Region IV) and issue audit report.
11/30/2020 Conduct effectiveness review of the Very Low Safety Significance Issue Resolution process and issue a report.
03/31/2021 Conduct effectiveness review of Action Matrix Change for White Findings and issue a report.
03/31/2021 Complete CY 2020 ROP Self-Assessment and issue paper to the Commission.
03/31/2021 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.27 The rules require, in the absence of an applicable exception, an analysis showing that the backfit would result in a substantial increase in the overall protection of the public health and safety or the common defense and security and that the increased protection warrants the direct and indirect costs of implementation. There are similar requirements, referred to as issue finality, that apply when there are new or amended requirements for licenses, permits, and design approvals and certifications issued under 10 CFR Part 52. The Commission clarified its backfitting and issue finality policy as well as its policy on forward fits, which are requirements or staff interpretations of requirements imposed as a condition of agency approval of a licensee request that result in the modification of or 26 Completion of the comprehensive review was previously scheduled for September 30, 2020. The completion date was delayed to seek additional internal review and feedback on the preliminary conclusions.
27 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.
20 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. 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 violations that are contested based on unjustified backfitting.
Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Backfit Activities Projected Completion Date Completion Date Receive public comments on draft NUREG-1409, Revision 1.
07/31/2020 07/31/2020 Projected Activities for the Next Two Reporting Periods (Q1 and Q2 FY 2021)
Projected Backfit Activities Projected Completion Date Evaluate public comments and prepare NUREG-1409, Revision 1 for internal agency concurrence.
11/30/202028 Provide NUREG-1409, Revision 1 to the Commission for review.
03/31/202129 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 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.30 The NRC staff has started implementing the agencywide Be riskSMART risk-informed decisionmaking framework to inform a broad range of decisions spanning technical, legal, and corporate arenas. As part of the Be riskSMART initiative, the staff is tracking its use of risk-informed decisionmaking.
28 The previous projected completion date for this activity was September 30, 2020. Additional time is needed to address the over 200 individual public comments received on the draft NUREG. The NRC expects that resolution of those comments will result in substantially improved and clarified final NUREG-1409 guidance.
29 The previous projected date for this activity was December 31, 2020, and has been extended for the reasons discussed in the prior footnote.
30 The NRC maintains a listing of risk-informed activities that is updated annually at https://www.nrc.gov/about-nrc/regulatory/risk-informed/rpp.html.
21 Activities Planned and Completed for the Reporting Period (Q4 FY 2020)
Risk-Informed Activities Projected Completion Date Completion Date Issue a letter on industry use of focused cyber security guidance to better risk-inform rule implementation for important-to-safety and safety-related digital assets, based on lessons learned from implementation and oversight of the NRCs cyber security requirements (ADAMS Accession No. ML20223A256).
08/30/2020 08/28/2020 Provide a Commission paper with options for a risk-informed, holistic approach to credit realistic law enforcement response, operator action, and use of Flexible Coping Strategies (FLEX)31 equipment.32 08/31/2020 07/30/2020 Coordinate and participate in a FLEX Summit with NEI and Electric Power Research Institute covering topics such as FLEX operating experience and the use of FLEX beyond the original purpose, such as crediting of FLEX equipment for NRC licensing and oversight and modeling in probabilistic risk assessments.
09/10/2020 09/10/2020 Issue a letter on industry use of focused cyber security guidance to better risk-inform rule implementation for balance of plant digital assets, based on lessons learned from implementation and oversight of the NRCs cyber security requirements (ADAMS Accession No. ML20209A442).
09/30/2020 08/14/2020 Document the Be riskSMART risk-informed decisionmaking framework in agency guidance.
09/30/2020 09/30/2020 Modify risk-informed decisionmaking curriculum to incorporate the Be riskSMART framework.
09/30/2020 09/30/2020 Complete decision-making on all seismic probabilistic risk assessments submitted in response to the 10 CFR 50.54(f) letter (ADAMS Accession No. ML12053A340) as part of the agencys post-Fukushima actions.
09/30/2020 09/24/2020 Publish Draft Revision 1 to NUREG/CR-7002, Criteria for Development of Evacuation Time Estimate Studies for public comment (ADAMS Accession No. ML20233A7002).
01/04/2021 08/27/2020 31 FLEX is the nuclear industrys term for the strategies that were implemented in response to NRC Order EA 049 (ADAMS Accession No. ML12054A735), which was issued following the earthquake and tsunami at the Fukushima Dai-ichi nuclear power plant in March 2011, to establish requirements for mitigation strategies for beyond-design-basis external events.
32 This paper is not publicly available.
22 Projected Activities for the Next Two Reporting Periods Q1 and Q2 FY 2021 Projected Risk-Informed Activities Projected Completion Date Finalize Risk-Informed Process for Exemptions (RIPE) initiative and associated NRC staff guidance. RIPE leverages current regulations and risk initiatives to allow reactor licensees to justify plant-specific exemptions using a streamlined NRC review process (ADAMS Accession No. ML20161A040).
10/30/202033 Brief ACRS on proposed final Draft Revision 3 to RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities for public comment (ADAMS Accession No. ML19308B636).
11/05/2020 Provide training to NRC management and staff by Professor Malcolm Sparrow related to risk and regulatory strategies.
11/06/2020 Publish draft regulatory basis for rulemaking to align licensing processes and apply lessons learned from new reactor Licensing for public comment (ADAMS Accession No. ML19161A169).
12/16/2020 Implement the near-term recommendations on building a smarter fuel cycle licensing program (ADAMS Accession No. ML20184A267).
11/30/2020 Issue draft Revision 2 of RG 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, for public comment (ADAMS Accession No. ML20231A856).
12/18/2020 Implement the recommendations on building a smarter fuel cycle inspection program (ADAMS Accession No. ML20183A242).
12/31/2020 Implement revisions to the independent spent fuel storage installation inspection guidance.
12/31/2020 Publish Integrated Human Error Analysis System for Event and Condition Analysis Human Reliability Analysis Method workshop report.
12/31/2020 Complete review of LAR to revise the emergency plans for SNC fleet to ch emergency response organization staffing composition and extend staff au 03/23/2021 Issue Revision 3 of RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities (ADAMS Accession No. ML20238B871).
03/31/2021 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 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. 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.
33 The original projected date for the RIPE initiative and guidance has been extended to allow for additional refinement and review.
23 On September 15, 2020, the NRC staff briefed the Commission on the NRCs response to the COVID-19 PHE, including licensing and oversight activities, the use of technology, public engagement, and strategies to overcome ongoing and emergent challenges (ADAMS Accession No. ML20253A200). This public meeting is part of the NRCs ongoing efforts to ensure transparency during the COVID-19 PHE.
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, Occupational Safety and Health Administration, and OMB health and safety guidance (e.g., social distancing and use of personal protective supplies). On July 12, 2020, 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 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. No changes to the NRCs re-occupancy status occurred during this reporting period.
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 Web site (https://www.nrc.gov/about-nrc/covid-19/).
From April through September 2020, the agency noticed 431 public meetings in the Washington, DC area and in States with NRC-licensed or proposed facilities to address a range of NRC issues. Due to health and safety concerns related to COVID-19, 417 of these meetings were held virtually or via teleconference. The NRC has also developed portions of its Web site devoted to the regulatory activities taken in response to the COVID-19 PHE. 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. Between July 1, 2020, and September 30, 2020, the NRC issued 61 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/.
On October 15, 2020, the NRC hosted a public meeting with stakeholders, including representatives from NEI, NextEra, Entergy, and the public, to discuss and solicit feedback on potential future licensing and regulatory issues to address the COVID-19 PHE going forward (ADAMS Accession ML20269A175). The NRC staff emphasized that each request submitted by industry will be considered on a case-and situation-specific basis, and the staff will consider applicable exemption standards to ensure that adequate safety and security are preserved.
24 Regulatory Activities Taken in Response to the COVID-19 PHE During the Reporting Period Licensee Type Number of COVID-19 Requests Approved During the Reporting Period Average Number of Days to Approve COVID-19 Requests34 Power Reactor 51 36 Non-Power Reactor 2
15 Other (e.g., topical reports) 0 N/A Decommissioning of Nuclear Facilities and Uranium Recovery 0
N/A Storage and Transportation of Spent Nuclear Fuel 0
N/A Fuel Cycle Facilities 0
N/A Medical, Industrial and Academic Uses of Nuclear Materials and Agreement States 8
24
- Summary of Activities 3-1 Reactor Oversight Process Findings The table below provides the CY ROP findings for the YTD and 3-year rolling metrics.
Location Number of Findings CY 2017 CY 2018 CY 2019 CY 2020 (YTD)
Nationally Total 560 478 440 149 Region I Green 126 107 95 29 White 2
1 0
0 Yellow 0
0 0
0 Red 0
0 0
0 Greater Than Green Security 0
0 0
0 Total 128 108 95 29 No. of Units Operating During CY 25 25 24 2235 Region II Green 119 113 110 37 White 3
0 1
1 Yellow 0
0 0
0 Red 0
0 0
0 Greater Than Green Security 2
0 0
1 Total 124 113 111 39 No. of Units Operating During CY 33 33 33 33 34 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.
35 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.
25 Location Number of Findings CY 2017 CY 2018 CY 2019 CY 2020 (YTD)
Region III Green 133 110 96 22 White 4
2 1
0 Yellow 0
0 0
0 Red 0
0 0
0 Greater Than Green Security 0
0 0
0 Total 137 112 97 22 No. of Units Operating During CY 23 23 23 23 Region IV Green 167 145 137 61 White 2
0 0
0 Yellow 0
0 0
0 Red 0
0 0
0 Greater Than Green Security 2
0 0
0 Total 171 145 137 61 No. of Units Operating During CY 18 18 18 18 3-2 Licensing Actions The tables below provide the status of licensing actions organized by licensing program.
Consistent with Section 102(c) of 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 Reactors36 Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period Percentage of Licensing Actions Completed Prior to the Generic Milestone Schedule37 Percentage of Licensing Actions Completed Prior to the Established Schedule38 Q1 FY 2020 159 40 44 100%
77%
Q2 FY 2020 173 96 82 100%
94%
Q3 FY 2020 191 213 203 100%
93%
Q4 FY 2020 238 233 186 100%
98%
36 The table is updated to include results obtained after the prior reporting periods using a new data analytics tool that compiles real-time results. The tool replaces a manual process and was developed as part of an agencywide effort to provide improved tracking and data.
37 Consistent with previous reports, this excludes unusually complex and Fukushima-related licensing actions accepted or initiated prior to July 13, 2019.
38 The established scheduled is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
26 New Reactors Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period Percentage of Licensing Actions Completed Prior to the Generic Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule 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 Q4 FY 2020 3
1 6
100%
100%
Fuel Facilities Reporting Period Total Inventory Licensing Actions Initiated During the Reporting Period Licensing Actions Completed During the Reporting Period Percentage of Licensing Actions Completed Prior to the Generic Milestone Schedule Percentage of Licensing Actions Completed Prior to the Established Schedule Q1 FY 2020 6
3 1
100%
100%
Q2 FY 2020 6
4 4
100%
100%
Q3 FY 2020 4
3 5
100%
100%
Q4 FY 2020 3
1 2
100%
100%
3-3 Licensing Amendment Request Reviews The tables below provide the status of LARs organized by licensing program. Consistent with Section 102(c) of NEIMA, the LARs referenced in this section include requested activities of the Commission for which the NRC staff issues a final 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).
27 Operating Reactors39 Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the Generic Milestone Schedule40 Percentage of LAR Reviews Completed Prior to the Established Schedule41 Q1 FY 2020 394 97 122 100%
92%
Q2 FY2020 343 84 138 100%
92%
Q3 FY 2020 382 125 95 100%
96%
Q4 FY 2020 362 125 145 100%
91%
New Reactors Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the Generic Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule Q1 FY 2020 12 4
6 100%
100%
Q2 FY 2020 6
2 8
100%
100%
Q3 FY 2020 5
3 4
100%
100%
Q4 FY 2020 3
1 3
100%
100%
Fuel Facilities42 Reporting Period Total Inventory LARs Submitted During the Reporting Period LAR Reviews Completed During the Reporting Period Percentage of LAR Reviews Completed Prior to the Generic Milestone Schedule Percentage of LAR Reviews Completed Prior to the Established Schedule Q1 FY 2020 12 10 4
100%
100%
Q2 FY 2020 11 5
6 100%
100%
Q3 FY 2020 12 14 13 100%
93%
Q4 FY 2020 14 7
5 100%
80%
39 The table is updated to include results obtained after the prior reporting periods using a new data analytics tool that compiles real-time results. The tool replaces a manual process and was developed as part of an agencywide effort to provide improved tracking and data analytics.
40 Consistent with previous reports, this excludes unusually complex and Fukushima-related LARs accepted or initiated prior to July 13, 2019.
41 The established scheduled is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
42 Corrections were made to previous quarters due quality checking older records and formats, to present the most accurate data to date.
28 Unusually Complex LARs43 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.
Unusually Complex LAR Description Exclusive Justification Age (Months)
North Anna Units 1 and 2 -Revision of the Small Break Loss of Coolant Accident (SBLOCA) Analytical Methodologies.
Involves multiple plant specific SBLOCA methodologies.
25 Surry Units 1 and 2 -Revision of Analytical Methodologies for SBLOCA.
Involves multiple plant specific SBLOCA methodologies.
25 Seabrook Unit 1 - Exemption to support resolution of GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Exemption requested relies on completion of the significant review of a unique, plant-specific methodology to resolve issues from GL 2004-
- 02.
2544 Point Beach Units 1 and 2 - Exemption to support resolution of GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Exemption requested relies on completion of the significant review of a unique, plant-specific methodology to resolve issues from GL 2004-
- 02.
2345 Shearon Harris - Request to modify departure from nucleate boiling ratio safety limit to support transition to a new fuel design.
Unique, first of a kind review based on a correlation with a fuel of a different design.
1546 3-4 Research Activities47 Summary of New Research Projects48 During the reporting period, the Office of Nuclear Regulatory Research initiated research on or substantially revised the following projects:
43 There were no unusually complex LARs for New Reactors or Fuel Facilities within the reporting period.
44 The Seabrook LAR was determined to be unusually complex during the technical review.
45 The Point Beach LAR was determined to be unusually complex during the technical review.
46 The Shearon Harris LAR was determined to be unusually complex during the technical review.
47 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).
48 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.
29 Regulatory Research Supporting Licensing of Near-Term Accident Tolerant Fuel Importance to the NRC Mission The NRC staff is preparing to review license applications for near-term ATF concepts proposed by nuclear fuel vendors. These licensing activities may include the development of new regulatory guidance documents, topical report reviews, and confirmatory calculations. To efficiently support these activities, the staff is enhancing its capability to analyze the performance of these fuels for fresh fuel transportation, spent fuel dry storage and transportation, and support the agencys ATF Project Plan through external engagements.
Planned Activities:
The scope of work from FY 2020 through FY 2023 includes activities in support of the safety review of transportation packages for fresh/spent ATF and the dry storage of spent ATF. This work addresses fresh/spent ATF with uranium-235 (U-235) enrichments less than 5 percent by weight and includes commissioning the formation of a phenomenon identification and ranking table on spent fuel storage and transportation of Cr-coated Zircaloy and FeCrAl claddings.
Requesting Business Line Spent Fuel Storage and Transportation Estimated Completion FY 2023 Estimate of Total Research Resources
$0.6M for program support and 0.6 FTE Regulatory Research Supporting Licensing of Increased Enrichment and Higher Burnup LWR Fuels Importance to the NRC Mission The NRC staff is preparing to review license applications for the Phase 1
(~67 GWd/mtU rod average) and Phase 2 (~75 GWd/mtU rod average) higher burnup activities, along with increased enrichments (greater than 5 percent by weight in U-235), being pursued by nuclear fuel vendors and industry. These licensing activities support the development of new regulatory guidance documents, topical report reviews, and confirmatory calculations. To efficiently support these activities, the staff is enhancing its ability to analyze the performance of these fuels for fresh fuel transportation, spent fuel storage and transportation, and to support the agencys Accident Tolerant Fuel Project Plan through external engagements.
Planned Activities:
The scope of these research includes activities in support of the safety review of transportation packages for fresh/spent fuel and the dry storage of fuel. This work ensures that the staff and the NRCs confirmatory codes are ready for application reviews on fresh fuels with increased U-235 enrichments and spent fuel storage and transportation with increased U-235 enrichments and higher burnups through technical reports, assessment reports, confirmatory calculations, and expert elicitation on the technical basis of higher burnup and increased enrichment.
Requesting Business Line Spent Fuel Storage and Transportation Estimated Completion FY 2023
30 Regulatory Research Supporting Licensing of Increased Enrichment and Higher Burnup LWR Fuels Estimate of Total Research Resources
$4.5M for program support and 1.3 FTE Technical Assistance for Research on Innovative Methods and Technologies to Enhance Seismic Safety for Design and Construction of Commercial Reactors Importance to the NRC Mission This project supports the licensing review of advanced non-LWRs by addressing seismic safety within the Licensing Modernization Project (LMP) framework, and by identifying and evaluating technical criteria for regulatory guidance for the design and review of seismic isolation technologies included in licensing applications for commercial nuclear power plants.
Planned Activities:
Development of a technology-inclusive, risk-informed and performance-based pathway for advanced non-LWR to address seismic safety within the LMP framework. The scope of this research includes (1) evaluating feasibility and adequacy of potential technical criteria through demonstration studies, (2) performing communication and outreach activities to help reach consensus with pertinent stakeholders on a viable and practical technology-inclusive, risk-informed, and performed-based approach forward for advanced non-LWR seismic safety (3) developing associated implementation guidance, and (4) identifying potential regulatory improvements for future rulemaking activities. Other activities include identifying and evaluating technical criteria for regulatory guidance for the design and review of seismic isolation technologies included in licensing application for commercial nuclear power plants.
Requesting Business Line New Reactors Estimated Completion FY 2023 Estimate of Total Research Resources
$0.9M for program support Summary of Completed Research Projects49 During the reporting period, Office of Nuclear Regulatory Research completed the following projects:
Development of the Technical Basis for the Evaluation of Neutron Absorber Materials in Spent Fuel Pools Importance to the NRC Mission Provided technical information and data to support regulatory decisions related to the use and monitoring of aluminum-based neutron absorber materials in spent fuel pools.
49 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.
31 Development of the Technical Basis for the Evaluation of Neutron Absorber Materials in Spent Fuel Pools Research Results or Findings This research showed that aluminum-based neutron absorber materials qualification programs addressed the relevant degradation mechanisms and that the current monitoring program guidance is adequate for the intended service life of neutron absorber panels.
Three reports were published under the project: Assessment of Aluminum-Based Neutron Absorber Materials Qualification Testing and Surveillance Monitoring Programs (ADAMS Accession No. ML19353A030); Addressing Uncertainties in SuperBADGER Measurements at the Zion Nuclear Power Plant Spent Fuel Pool on December 5-8, 2014, Revision 1 (ADAMS Accession No. ML19318F214); and Characterization and Analysis of Boral from the Zion Nuclear Power Plant Spent Fuel Pool (ADAMS Accession No. ML19155A215).
Duration of the Project 6 years Estimate of Total Research Resources
$1.1M for program support and 4.5 FTE 3-5 Fees Billed The tables below provide information on Part 170 fees billed for each fee class. For each fee class, the staff compared the fees billed to the receipts estimated in the annual fee rule.50 Fee Class FY 2019 Part 170 Receipts Final -
Annual Fee Rule ($M)
Part 170 Billed in FY 2020 Q4 ($M)
Total Part 170 - Billed in FY 2020 ($M)
Fuel Facilities
$6.8
$2.9
$6.4 Generic Decommissioning
$3.6
$1.8
$3.7 Materials Users51
$1.0
$0.3
$1.0 Operating Power Reactors
$186.7
$81.8
$177.1 Research and Test Reactors
$3.0
$1.9
$3.2 Spent Fuel Storage / Reactor Decommissioning
$15.9
$6.2
$11.7 Transportation
$2.8
$1.0
$2.3 Uranium Recovery
$0.4
$0.1
$0.4 Significant Ongoing Licensing Actions The following table includes a comparison of the fees billed to projected resources for the NuScale SMR design certification review, subsequent license renewal application reviews, Oklos Aurora COL application, and the SHINE Medical Technologies, LLC (SHINE) operating 50 In order to mitigate the financial impacts and economic disruptions to licensees caused by the COVID-19 PHE, the NRC deferred all invoices scheduled to be issued in April, May, and June 2020 until July 22, 2020.
51 Materials UsersBilled as flat fee applications and included in the estimates and billed.
32 license application review. The subsequent renewed licenses for Turkey Point Units 3 and 4 and Peach Bottom Units 2 and 3 were issued on December 4, 2019, and March 5, 2020, respectively.
Docket Project Name Projected Resources ($M)52 Fees Billed to Date
($M)53 NuScale Power Reactor 05200048 NuScale SMR Design Certification Application Review
$66.054
$56.2 NuScale Power Reactor 99902043 NuScale SMR Topical Report Reviews (Only those that directly support the design certification review)
$8.3 Peach Bottom Units 2 and 3 05000277/05000278 Peach Bottom Units 2 and 3 Subsequent License Renewal Application Safety Review
$4.3
$4.3 Peach Bottom Units 2 and 3 05000277/05000278 Peach Bottom Units 2 and 3 Subsequent License Renewal Application Environmental Review
$1.5
$1.6 Surry Units 1 and 2 05000280/05000281 Surry Units 1 and 2 Subsequent License Renewal Application Safety Review
$4.9
$4.6 Surry Units 1 and 2 05000280/05000281 Surry Units 1 and 2 Subsequent License Renewal Application Environmental Review
$1.4
$1.955 SHINE Medical Technologies, LLC 05000608 SHINE Medical Isotope Production Facility Operating License Application Review Safety and Environmental Reviews
$6.256
$2.7 52 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.
53 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 July, August, and September, would be invoiced to the licensee/applicant in October. Therefore, the total billed amounts listed in Table 3-5 reflects costs for NRC work performed through June 2020.
54 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.
55 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 $7.6M.
56 The projected resource estimate was provided to SHINE by letter dated April 30, 2020 (ADAMS Accession No. ML20114E315).
33 Docket Project Name Projected Resources ($M)52 Fees Billed to Date
($M)53 Oklo Aurora 05200049 Oklo Aurora COL Application -
Safety Review
$0.557
$0.058 Oklo Aurora 05200049 Oklo Aurora COL Application -
Environmental Review
$0.2
$0.0 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.
Type of Facility or Activity Type Total Inventory of Open RAIs as of the End of Reporting Period Total Number of RAIs Issued in Reporting Period Total Number of RAIs Responded to in Reporting Period Total Number of RAIs Closed in Reporting Period59 Operating Reactors 518 310 226 163 Non-Power Production and Utilization Facilities60 450 10 31 10 Design Certifications for New Reactors 0
0 0
0 Early Site Permits for New Reactors61 N/A N/A N/A N/A Combined Licenses for New Reactors 10 10 0
0 Fuel Facilities 148 136 20 13 Power Reactor Decommissioning 38 16 10 5
Research and Test Reactor Decommissioning 6
0 6
0 57 When the Oklo COL application 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 the identified Step 1 safety and environmental aspects of the review.
58 Fees billed to date for the Oklo Aurora Combined License Application safety and environmental review are smaller than the number of significant figures reported.
59 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.
60 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.
61 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.
34 Type of Facility or Activity Type Total Inventory of Open RAIs as of the End of Reporting Period Total Number of RAIs Issued in Reporting Period Total Number of RAIs Responded to in Reporting Period Total Number of RAIs Closed in Reporting Period59 Spent Fuel 746 46 58 11 Materials 6
0 0
0 Pre-Application Activities for Advanced Reactors 27 0
0 14 3-7 Workforce Development and Management FY 2020 Staffing by Office62 FY 2020 Budget FTE Utilization 06/21/20 -
08/01/20 FTE Utilization 08/02/20 -
08/29/20 FTE Utilization 08/30/20 -
09/26/20 FTE Utilization as of 09/26/20 Delta (Q4 FTE Utilization -
FY 2020 Budget)
End of Year (EOY)63 Projection w/
Personnel Actions Delta (EOY Projection -
FY 2020 Budget)
Totals 2979.0 326.2 215.2 213.0 2789.7
-189.3 2789.7
-189.3 COMM 45.0 4.0 2.7 2.7 30.3
-14.7 30.3
-14.7 OIG 63.0 6.7 4.4 4.2 55.2
-7.8 55.2
-7.8 Totals Other Offices 2871.0 315.5 208.0 206.1 2704.2
-166.8 2704.2
-166.8 OCFO 96.0 10.7 7.0 6.9 90.7
-5.3 90.7
-5.3 OGC 96.0 10.5 7.0 6.9 91.6
-4.4 91.6
-4.4 OCA 11.0 1.2 0.8 0.8 10.4
-0.6 10.4
-0.6 OCAA 8.0 0.8 0.5 0.5 6.4
-1.6 6.4
-1.6 OPA 15.0 1.5 1.0 1.0 13.5
-1.5 13.5
-1.5 SECY 18.0 2.0 1.3 1.3 16.0
-2.0 16.0
-2.0 OIP 35.0 3.8 2.5 2.5 32.9
-2.1 32.9
-2.1 ASLBP 24.0 2.5 1.6 1.6 22.0
-2.0 22.0
-2.0 ACRS 24.0 3.2 1.9 2.2 27.2 3.2 27.2 3.2 OEDO 23.0 2.4 1.6 1.6 20.7
-2.3 20.7
-2.3 NRR 601.3 63.9 41.9 40.9 560.7
-41.6 560.7
-41.6 NMSS 296.2 36.0 23.9 23.5 308.7 12.5 308.7 12.5 RES 205.4 22.4 14.7 14.5 188.1
-16.3 188.1
-16.3 NSIR 158.5 18.9 12.2 12.2 159.6 1.1 159.6 1.1 R-I 182.3 19.5 12.8 12.8 168.4
-13.9 168.4
-13.9 R-II 235.7 24.6 16.5 16.2 216.6
-19.1 216.6
-19.1 R-III 178.9 19.8 13.0 12.9 171.3
-7.6 171.3
-7.6 R-IV 166.1 18.9 12.5 12.8 161.1
-5.0 161.1
-5.0 OE 30.6 3.4 2.3 2.3 29.9
-0.7 29.9
-0.7 OI 38.0 4.5 3.0 3.0 39.7 1.7 39.7 1.7 OCIO 171.0 17.7 11.7 11.7 151.9
-19.1 151.9
-19.1 ADM 131.0 13.5 8.9 8.9 115.0
-16.0 115.0
-16.0 SBCR 13.0 1.4 0.9 0.9 10.9
-2.1 10.9
-2.1 OCHCO 112.0 12.4 8.4 8.2 88.7
-23.3 88.7
-23.3 62 Some numbers might not add due to rounding.
63 Based on FTE utilization as of September 26, 2020.
35 FY 2020 Budget FTE Utilization 06/21/20 -
08/01/20 FTE Utilization 08/02/20 -
08/29/20 FTE Utilization 08/30/20 -
09/26/20 FTE Utilization as of 09/26/20 Delta (Q4 FTE Utilization -
FY 2020 Budget)
End of Year (EOY)63 Projection w/
Personnel Actions Delta (EOY Projection -
FY 2020 Budget)
CSU 1.0 0.2 0.2 0.2 2.2 1.2 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 Nationwide Per Plant Column 1 of ROP Action Matrix Column 2 of ROP Action Matrix Column 3 of ROP Action Matrix Column 4 of ROP Action Matrix 1,190 Hours 1,210 Hours 892 Hours64 No Plants in Column 3 No Plants in Column 4 The table below shows the staff hours expended for inspection-related effort at operating power reactor sites by CY.
Items Description CY 2019 (Hours)65 CY 2020 (YTD) (Hours)66
- i.
Baseline Inspection 235,718 165,431 ii.
Plant Specific Inspection 9,096 5,458 iii.
Generic Safety Issue Inspections 3,200 573 iv.
Performance Assessment 1,532 1,660
- v.
Other Activities 98,614 67,883 vi.
Total Staff Effort 348,160 241,005 vii.
Total Staff Effort Per Operating Site 6,003 4,228 3-9 Backfit Facility-Specific Backfits There were no facility-specific backfits issued during the reporting period.
Generic Backfits There were no generic backfits issued during the reporting period.
64 Browns Ferry Nuclear Plant (three-unit boiling water reactor site), Vogtle Electric Generating Plant (two-unit pressurized water reactor site), and Surry Power Station Unit 2 (two-unit pressurized water reactor site) were in Column 2 of the ROP Action Matrix year-to-date in CY 2020.
65 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.
66 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.
36 Backfit Appeals Filed by Licensees and Applicants There were no backfit appeals submitted to the NRC during the reporting period.