ML21027A442

Status Report on the Licensing Activities and Regulatory Duties of the U.S. NRC - October-December 2020 - Enclosures

ML21027A442
Person / Time
Issue date:	02/16/2021
From:	NRC/Chairman
To:	US Congress, US HR (House of Representatives), US SEN (Senate)
Sara Mroz
Shared Package
ML21027A443	List: ML21027A436 ML21027A442
References
CORR-21-0007
Download: ML21027A442 (37)

Text

STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION For the Reporting Period of October 1, 2020 through December 31, 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 ........................................................ 4 1-3 Full-Time Equivalents (FTE) at the End of Q1 Fiscal Year (FY) 2021 vs. Budgeted FTE ............ 4 1-4 Budget Authority, FTE Utilization, and Fees ................................................................................. 5 - Status of Specific Items of Interest ................................................................. 7 2-1 Transformation .............................................................................................................................. 7 2-2 Workforce Development and Management .................................................................................. 8 2-3 Accident Tolerant Fuel .................................................................................................................. 8 2-4 Digital Instrumentation and Control ............................................................................................. 11 2-5 Vogtle Electric Generating Plant Units 3 and 4 ........................................................................... 13 2-6 NuScale Small Modular Reactor Design Certification................................................................. 15 2-7 Advanced Nuclear Reactor Technologies ................................................................................... 16 2-8 Oklo Power LLC (Oklo) Combined Operating License Application for the Aurora Compact Fast Reactor ........................................................................................................................................ 18 2-9 Reactor Oversight Process (ROP) .............................................................................................. 20 2-10 Backfit .......................................................................................................................................... 20 2-11 Risk-Informed Activities ............................................................................................................... 21 2-12 Coronavirus Disease 2019 .......................................................................................................... 24 - Summary of Activities.....................................................................................27 3-1 Reactor Oversight Process Findings........................................................................................... 27 3-2 Licensing Actions ........................................................................................................................ 28 3-3 Licensing Amendment Request Reviews ................................................................................... 29 3-4 Research Activities ...................................................................................................................... 31 3-5 Fees Billed ................................................................................................................................... 32 3-6 Requests for Additional Information ............................................................................................ 34 3-7 Workforce Development and Management ................................................................................. 35 3-8 Inspection Activities ..................................................................................................................... 36 3-9 Backfit .......................................................................................................................................... 37 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%

Schedule Date) 60%

50%

40%

30%

Operating Reactors Established Schedule New Reactors Established Schedule Fuel Facilities Established Schedule 1

0F 1 New reactor established schedule data for FYOMB 2020 Q3 and Q4 was updated to appropriately account for topical reports submitted by licensees or applicants that were initially submitted prior to an application. Additional information regarding the treatment of topical reports is available at https://www.nrc.gov/about-nrc/generic-schedules.html.

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1-2 Reactor Oversight Inspection Hours and Percent Complete 180000 100%

Cumulative Percent of Planned Direct 160000 90%

Direct Inspection Hours 140000 80%

70%

120000 60%

100000 50%

Inspection Hours Complete 80000 40%

60000 30%

40000 20%

20000 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 2020 Planned ROP Direct Inspection Hours Percent Complete of Total CY 2019 Planned ROP Direct Inspection Hours 1-3 FTE at the End of Q1 FY 2021 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 4

1-4 Budget Authority, FTE Utilization, and Fees NRC FY 2021 Budget Authority December 31, 2020 (Dollars in Thousands)

Fund Sources FY 2021 Budget 2 1F Percent Obligated Percent Expended Advanced Reactors $15,478 18% 14%

Commission Funds $11,836 15% 15%

Fee-Based Funds $785,430 17% 16%

General Funds $1,303 11% 11%

International Activities $14,500 17% 13%

Integrated University $32,352 12% 0%

Program Official Representation $25 0% 0%

Total $860,924 18% 16%

NRC Control Points FY 2021 Budget Percent Obligated Percent Expended Nuclear Reactor Safety $426,653 21% 19%

Nuclear Materials and $98,367 20% 18%

Waste Safety Decommissioning and $21,821 22% 19%

Low-Level Waste Corporate Support $281,731 15% 13%

Integrated University $32,352 12% 0%

Program Total $860,924 18% 16%

FTE Utilization, Hiring, and Attrition Total Year to Date Projected End of Year Quarter 1 Quarter 1 YTD YTD (YTD) FTE Utilization FTE Total Utilization Hiring Attrition Hiring Attrition 638.4 2772.3 23 26 23 26 2 The agency was operating under the Continuing Appropriations Act of 2021 in December 2020; therefore, this table reflects the FY 2020 total annualized rate (i.e., the FY 2020 enacted levels). The next report will reflect the enactment of the Consolidated Appropriations Act, 2021.

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FY 2021 Fees Estimated, Fees Billed, and Fees Collected Through Q1

$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 2021 2021 2021 2021 2021 2021 2021 2021 2021 Total Estimated $184,700 $186,630 $188,440 $358,450 $360,360 $362,740 $536,910 $539,660 $542,230 $589,810 $713,160 $715,590 Total Actual Billed $173,950 $176,310 $178,800 $- $- $- $- $- $- $- $- $-

Total Actual Collected $106,000 $182,800 $187,850 $- $- $- $- $- $- $- $- $-

Total 10 CFR Part 170 Fees Billed (Dollars in Millions)

FY 2019 FY 2020 FY 2021 Q1

$245.3 $205.7 $51.4 6

Enclosure 2 - Status of Specific Items of Interest provides the status of specific items of interest including a summary of the item, the activities planned and accomplished under each item within the reporting period, and projected activities under each item for the next two reporting periods.

2-1 Transformation The U.S. Nuclear Regulatory 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 held seminars for the staff on topics related to the agency transformation as part of the agencys annual KNOWvember knowledge management awareness activities. One seminar featured Professor Malcolm Sparrow of Harvard University, who provided insights on the strategic and managerial aspects of risk-informed decisionmaking.

Other sessions covered topics such as using Wiki platforms in government and industry, the status of the NRCs Innovate NRC 2.0 program, and updates on the agencys transformation efforts related to use of technology.

Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

Projected Transformation Activities Completion Date Completion Date Conduct series of KNOWvember seminars on transformation focus areas and knowledge 11/30/20 11/30/20 management activities.

Conduct seminars for agency staff on strategic and managerial aspects of risk-informed 12/31/20 11/06/20 decisionmaking.

Launch a platform for employees, known as Launch Employee Journey, to highlight opportunities for 02/01/21 12/31/20 career progression in disciplines where future skill gaps are anticipated.

Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Transformation Activities Completion Date Communicate the launch of 2021 Objectives and Key Results (OKR) transformation performance management framework across the agency 01/04/21 with the expectation to develop office-level OKRs that will support transformation.

Launch new training module for the agencys Be riskSMART framework 01/29/21 and include it in the agencys training management system.

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Projected Projected Transformation Activities Completion Date Communicate the progress of transformation activities at the 2021 03/11/21 Regulatory Information Conference.

Conduct a survey of NRC staff on organizational culture to assess 04/30/21 3 progress made since the initial survey in March 2020.

2F Brief the Commission on staffs transformation activities (public meeting). 06/30/21 2-2 Workforce Development and Management The NRC implemented a Strategic Workforce Planning (SWP) process to improve workforce development to meet its near- and long-term work demands. The first step in this process is an Agency Environmental Scan that projects the amount and type of work anticipated in the next 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 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 (Q1 FY 2021)

Workforce Development and Management Projected Completion Date Activities Completion Date Complete Agency Environmental Scan to support 12/04/20 12/10/20 4 2021 SWP activities.

3F Make selections for 63 new 2021 Temporary Summer Student internships in alignment with 12/31/20 12/31/20 short- and long-term identified skill needs.

Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Workforce Development and Management Activities Completion Date Complete SWP process steps for FY 2021. 06/30/21 Complete onboarding activities for Summer Students. 06/30/21 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 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19301B166). The NRC staff is currently reviewing three ATF fuel vendor topical reports. One topical report is on a new type of doped fuel pellet called Westinghouse Advanced Doped Pellet Technology (ADOPTTM) Fuel (ADAMS Accession No. ML20132A014) and another covers increased burnup limits for a fuel cladding material (ADAMS Accession No. ML20003E125). The staff is also reviewing a third vendor topical report that 3 This activity was delayed by one month while awaiting contract funding to administer the survey.

4 The Agency Environmental Scan to support FY 2021 SWP activities was completed on December 10, 2020, which coincided with a discussion among senior leaders on the scan. The Agency Environmental Scan will continue to be refined to account for new information throughout 2021.

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discusses allowing the use of higher burnup lead test assemblies (ADAMS Accession No. ML20350B834). The NRC staff is preparing for several additional ATF submittals from fuel vendors in calendar year (CY) 2021.

During the reporting period, the NRC staff approved one ATF-related request and reviewed three reports on ATF-related topics. The request was for an amendment to the certificate of compliance for a transportation package for lead test assemblies with ATF rods to Monticello Nuclear Generating Plant (ADAMS Accession No. ML20283A357). The first report was prepared by Pacific Northwest National Laboratory (PNNL) for the NRC and concerned storage and transportation of spent nuclear fuel involving near-term ATF concepts, specifically chromium-coated (Cr-coated) zirconium alloy and iron-chromium-aluminum (FeCrAl) cladding (ADAMS Accession No. ML20274A250). The second report, also prepared by PNNL, addressed in-reactor degradation and failure modes of FeCrAl cladding concepts (ADAMS Accession No. ML20272A218). The third report, prepared by Energy Research, Inc., was a literature review examining the implications to severe accident progression and radiological releases for ATF concepts (ADAMS Accession No. ML20287A477). A draft of this third report was used by the expert panel in the Severe Accident Phenomena Identification and Ranking Table (PIRT) exercise that occurred in September 2020. All three reports discuss the current state-of-the art knowledge on these ATF topics and the NRC staff will use them to guide future actions to reduce uncertainty and enhance efficiency in reviews of ATF-related submittals.

As noted in the last quarterly report, the first expert meeting of the Severe Accident PIRT was conducted in September 2020 and a meeting summary is now available at ADAMS Accession No. ML20272A160. Additional meetings were held January 11-15, 2021 and January 25-29, 2021, and more are planned for March 15-19, 2021. The findings of the expert elicitation panels will be documented in a final PIRT report planned for Q3 of FY 2021.

The NRC staff is participating in the Collaborative Research on Advanced Fuel Technologies for Light Water Reactors organized by the Electric Power Research Institute. This effort is focused on addressing technical issues associated with the licensing of ATF concepts involving increased enrichment or higher burnup.

Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

Projected ATF Activities Completion Date Completion Date Issuance of literature review by Energy Research, Inc. on the implications to severe accident progression and radiological releases of accident 10/08/20 10/08/20 tolerant fuel concepts (ADAMS Accession No. ML20287A477). 5 4F Issuance of Spent Fuel Storage and Transportation of ATF Concepts report by PNNL. This report provides an assessment of available information related to the storage and transportation of spent 10/31/20 10/05/20 nuclear fuel involving near-term ATF concepts, specifically Cr-coated zirconium alloy and FeCrAl cladding (ADAMS Accession No. ML20274A250).

5 A draft of this literature review was used by Severe Accident PIRT panel in September 2020.

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Projected ATF Activities Completion Date Completion Date Issuance of FeCrAl cladding report by PNNL. This report identifies and discusses degradation and failure modes of FeCrAl cladding concepts, 10/31/20 09/28/20 including fuel performance characteristics that may not be addressed within existing regulatory documents (ADAMS Accession No. ML20272A218).

Complete review of ATF-related request from Framatome to transport ATF lead test assemblies to 01/08/21 10/09/20 Monticello Nuclear Generating Plant (ADAMS Accession No. ML20283A357).

Hold a pre-application meeting to discuss Framatomes planned request to amend their Certificate of Compliance to allow transport of ATF 12/07/20 12/07/20 with enrichments above 5 weight percent U-235 (ADAMS Accession No. ML20322A452). 6 5F Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected ATF Activities Completion Date Issuance of a report on assessment of existing transportation packages for use with high-assay low-enriched uranium. This report will assess 02/28/21 the potential to use currently licensed transportation packages for the transportation of increased enrichment unirradiated uranium fuel forms.

Issuance of a report on isotopic and fuel lattice parameter trends in increased enrichment and higher burnup pressurized water reactor fuel. 02/28/21 This report will assess the isotopics at increased enrichments and higher burnups and quantify impact on fuel parameters.

Issuance of a report on ATF applied to pressurized and boiling water reactors including reactivity, isotopics, and decay heat. This report will 02/28/21 assess the SCALE code updates necessary to evaluate these parameters for ATF.

Host an NRC Regulatory Information Conference session on ATF. The session will provide the public and other stakeholders with a status 03/09/21 update for ATF activities and an opportunity to ask questions of the NRC staff and industry representatives.

Issue a decision on a proposed license amendment to Calvert Cliffs Nuclear Power Plant to allow the insertion of ATF lead test assemblies in 03/31/21 non-limiting core locations.

Issuance of a severe accident PIRT report that covers the performance of the reactor during severe accidents for the current ATF concepts, higher burnup fuel, and fuel with enrichment above five weight percent.

The report will also document findings from the expert elicitation panels 05/31/21 held in Q1 and Q2 of FY 2021. The report will be used by the NRC to support changes to the regulatory infrastructure for ATF, higher burnup, and fuel with enrichment above five weight percent.

6 This emergent meeting was both requested and held in Q1 of FY 2021 and was not included in the last report.

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2-4 Digital Instrumentation and Control The NRC staff continues to complete digital instrumentation and control infrastructure improvements to address protection against common cause failure and commercial grade dedication of digital equipment.

Regarding protection against common cause failure, the NRC staff briefed the Advisory Committee on Reactor Safeguards (ACRS) full committee on November 4, 2020, on its update of Branch Technical Position (BTP) 7-19, Guidance for Evaluation of Defense-In-Depth and Diversity to Address Common Cause Failure Due to Latent Design Defects in Digital Safety Systems. 7 The ACRS provided a letter recommending issuance of the BTP following 6F incorporation of two recommendations. The NRC staff addressed the recommendations from the ACRS and provided the BTP to the Office of Management and Budget (OMB) on December 16, 2020, for a major/non-major rule determination under the Congressional Review Act (CRA). On December 21, 2020, OMB determined that the BTP was not a major rule under the CRA. The NRC staff published the final BTP on January 29, 2021 (ADAMS Accession No. ML20339A642).

Regarding commercial grade dedication of digital equipment, on November 3 - 6, 2020, the NRC staff observed an accreditation evaluation of Exida (a 3rd party certifying body) by the accrediting body American National Standards Institute National Accreditation Board (ANAB).

This will facilitate the NRC staffs review of the Nuclear Energy Institutes (NEI) 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 (ADAMS Accession No. ML19273A007). NEI is updating NEI 17-06 to better reflect the ANABs accreditation process, add a checklist to the proposed methodology to be used by industry going forward, and to more thoroughly explain the quality assurance activities for the proposed NEI 17-06 methodology.

The NRC staff anticipates receiving NEI 17-06 by the end of February 2021 (a change from NEIs previous goal of submitting by December 31, 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 NRC staff accepted a LAR for review from Entergy for an upgrade to the core protection calculator at Unit 3 of the Waterford Steam Electric Station. The NRC staff anticipates issuing a licensing decision by the end of August 2021. On December 9, 2020, the NRC staff held a public pre-submittal meeting with NextEra Florida Power and Light Company to discuss plans to submit an extensive digital modification LAR at Turkey Point Units 3 and 4 in CY 2021. On December 11, 2020, Exelon Generation Corporation, LLC provided a letter-of-intent to submit a LAR in CY 2022 for an extensive digital modernization of multiple safety systems at the Limerick Generating Station.

7 Revision 7 of the BTP is titled, Guidance for Evaluation of Diversity and Defense-In-Depth in Digital Computer Based Instrumentation and Control Systems. The proposed update (Revision 8) is titled, Guidance for Evaluation of Defense-In-Depth and Diversity to Address Common Cause Failure Due to Latent Design Defects in Digital Safety Systems to better reflect the intent of the updated guidance.

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Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

Projected Digital Instrumentation and Control Activities Completion Date Completion Date Update BTP 7-19, Guidance for Evaluation of Defense-In-Depth and Diversity to Address Common Cause Failure due to Latent Design Defects in Digital Safety Systems.

• ACRS Full Committee Meeting 11/30/20 11/04/20

• Hold a public meeting to discuss resolution 12/21/20 Cancelled of comments. 8 7F

• Submit request to the OMB for major/non-major rule determination for BTP 7-19 under 12/31/20 12/16/20 CRA in preparation for final issuance.

Review NEI 17-06, Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, and consider endorsement through issuance of a regulatory guide (RG).

• Observe audit of a third-party certifying 11/30/20 11/06/20 body.

Significant Digital Modernization LAR Milestones.

• Conduct a pre-application meeting for a major digital modernization project at Turkey 12/09/20 12/09/20 Point Units 3 and 4. 9 8F 8 This activity was cancelled because the additional public comments received on the proposed revision 8 to BTP 7-19 were not substantial enough to warrant a dedicated public meeting.

9 This emergent meeting was both requested and conducted in Q1 FY 2021. Therefore, it was not included in the last report.

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Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Digital Instrumentation and Control Activities Completion Date Update BTP 7-19, Guidance for Evaluation of Defense-In-Depth and Diversity to Address Common Cause Failure due to Latent Design Defects in Digital Safety Systems.

• Issue Revision 8 to BTP 7-19. 01/31/21 Review NEI 17-06, Guidance on Using IEC 61508 SIL Certification to Support the acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications, and consider endorsement through issuance of an RG.

• NEI to submit NEI 17-06 for NRC review. 02/19/21 Significant Digital Modernization LAR Milestones

• Conduct second pre-application meeting for Turkey Point digital 01/13/21 modernization project (ADAMS Accession No. ML20351A205).

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. SNCs public milestone for initial fuel loading of Vogtle Electric Generating Plant (Vogtle) Unit 3 remains April 30, 2021. The NRC staff adjusted the agencys activities and associated milestone dates to reflect the revised initial fuel loading date. In addition, the NRC staff continued licensing and inspection activities to support the NRC staffs evaluation that the acceptance criteria in the combined license are met.

During the COVID-19 public health emergency (PHE), due to the successful application of technology for telework and remote access to licensee information, construction inspections and licensing activities continue with only minor interruptions. The NRC continues to closely monitor COVID-19 cases and perform mission-critical inspections through a combination of remote inspections and targeted onsite inspections based on safety significance and the uniqueness or complexity of the construction activity.

The NRC completed the final two LARs related to the staffs ongoing work toward the 10 CFR 52.103(g) finding (i.e., the finding to confirm whether all inspections, tests, analyses, and acceptance criteria (ITAAC) have been successfully completed) and readiness to transition to operations for Vogtle Unit 3.

Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

Vogtle Electric Generating Plant Units 3 and 4 Projected Completion Date Activities Completion Date Issue amendments for LARs20-004 and 20-005 (ADAMS Accession Nos. ML20247J464 and 12/30/20 12/07/20 ML20314A016, respectively).

Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Conduct public meeting to discuss Vogtle Readiness Group activities. 03/31/21 13

Projected Projected Vogtle Electric Generating Plant Units 3 and 4 Activities Completion Date Issue safety evaluation for request for alternative, Alternative Requirements for American Society of Mechanical Engineers (ASME) 04/13/21 Section XI Examination Coverage of Weldolet Branch Connection Welds (VEGP 3&4-PSI/ISI-ALT-15).

Once the NRC determines that all ITAAC have been met, issue the finding that all acceptance criteria contained in the Vogtle Unit 3 license have been met and that the licensee may operate the facility, in 04/08/21 accordance with 10 CFR 52.103(g) (provided the requisite findings are made).

Provided the requisite findings are made, issue amendment regarding 06/30/21 emergency plan changes.

NRC Inspections and ITAAC Reviews for the Reporting Period (Q1 FY 2021)

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 that a 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.

Number of ITAAC ITAAC Total Inspections ITAAC Unit Remaining Requiring Inspections Completed 10 Inspected 11 Inspection Closed 12 9F 10F 11F Vogtle 3 105 51 32 8 Vogtle 4 131 8 4 0 ITAAC Reviews Completed for the Reporting Period (Q1 FY 2021)

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.

10 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).

11 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.

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

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Unit ITAAC No. Received Date Approval Date Vogtle 3 2.1.02.12a.i 09/28/2020 10/05/2020 Vogtle 3 2.1.03.13 11/25/2020 12/02/2020 Vogtle 3 2.2.01.11a.i 11/24/2020 12/02/2020 Vogtle 3 2.2.02.05c 10/07/2020 10/08/2020 Vogtle 3 2.2.03.12a.iv 10/13/2020 10/20/2020 Vogtle 3 2.3.14.04 11/13/2020 11/18/2020 Vogtle 3 2.4.06.02 10/16/2020 10/20/2020 Vogtle 3 3.2.00.04 12/04/2020 12/08/2020 Vogtle 3 3.3.00.02a.i.a 10/13/2020 10/21/2020 Vogtle 3 3.3.00.02b 10/30/2020 11/05/2020 Vogtle 3 3.3.00.02f 11/06/2020 11/12/2020 Vogtle 3 3.3.00.02h 12/04/2020 12/10/2020 Vogtle 3 3.3.00.13 11/20/2020 12/07/2020 Vogtle 3 E.3.9.05.01.08 10/02/2020 10/06/2020 Vogtle 3 2.2.02.07a.iii 12/11/2020 12/14/2020 Vogtle 3 2.3.06.12a.i 12/10/2020 12/11/2020 Vogtle 3 2.1.02.01 12/18/2020 12/21/2020 Vogtle 3 2.3.02.11a.i 12/17/2020 12/22/2020 Vogtle 3 2.3.04.04.i 12/15/2020 12/16/2020 Vogtle 3 3.3.00.07e 12/14/2020 12/21/2020 Vogtle 4 2.3.03.03a 12/21/2020 12/23/2020 Vogtle Units 3 and 4 License Amendment Request Reviews Completed (Q1 FY 2021)

Number of License Amendment Request Number of License Amendment Request Reviews Forecast to be Completed in Reviews that were Completed in the the Reporting Period Reporting Period 2 2 2-6 NuScale Small Modular Reactor Design Certification On March 15, 2017, the NRC accepted the NuScale Power, LLC (NuScale) application for a small modular reactors (SMR) design certification review. The NRC staff completed its technical review on August 28, 2020.

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 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).

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The NRC staff presented its 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 NRC 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 NRC staff is preparing the draft proposed rule that will propose certifying the design and anticipates publishing the proposed rule for public comment in April 2021. 13 12F Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

NuScale Small Modular Reactor Design Projected Completion Date Certification Activities Completion Date None N/A N/A Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected NuScale Small Modular Reactor Design Certification Projected Activities Completion Date Publish proposed rule for NuScale SMR design certification. 14 13F 04/02/21 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 NRC 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. 15 During this reporting period, the NRC staff 14F completed a number of significant activities, including the issuance of: 1) a paper to the Commission discussing potential licensing and policy issues specific to micro-reactors; 2) Final Interim Staff Guidance, Environmental Considerations Associated with Micro-reactors; and 3) 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. The NRC staff issued preliminary rule language on safety and risk criteria to facilitate discussion of the proposed Part 53 rulemaking during a public meeting held on November 18, 2020. The NRC staff issued additional Part 53 preliminary rule language in December 2020 to support discussion at a January 7, 2021, public meeting.

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/details.html#stakeholder).

13 The original proposed rule publication date of February 8, 2021, has been extended to April 2, 2021.

14 Additional information regarding this rulemaking is available at: https://www.nrc.gov/reading-rm/doc-collections/rulemaking-ruleforum/active/RuleDetails.html?id=40.

15 The NRCs public Web site lists the implementation action plans and is updated periodically to show the status of these activities (https://www.nrc.gov/reactors/new-reactors/advanced/details.html#visStrat).

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Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date Host NRC Standards Forum to facilitate the identification of needed consensus codes and standards and explore collaboration to accelerate 10/13/20 10/13/20 their development with a focus on advanced non-LWR (ADAMS Accession No. ML20337A122).

Issue SECY-20-0093, Policy and Licensing Considerations Related to Micro-Reactors discussing potential licensing and policy issues 10/30/20 10/06/20 specific to micro-reactors (ADAMS Accession No. ML20254A363).

Issuance of technical input reports by NUMARK Associates, Inc. of ASME Boiler and Pressure Vessel Code Section III, Division 5 (ADAMS 10/30/20 12/23/20 Accession Nos. ML20349A001 and ML20358A145).

Issue a memorandum to the Commission providing a schedule with milestones and resource requirements to achieve publication of the final 10 11/02/20 11/02/20 CFR Part 53 rule by October 2024 (ADAMS Accession No. ML20288A251).

Issue Final Interim Staff Guidance (ISG), ISG-029 Environmental Considerations Associated with 12/31/20 11/27/20 Micro-reactors (ADAMS Accession No. ML20252A075). 16 15F Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Advanced Nuclear Reactor Technologies Activities Completion Date Issue annual paper to the Commission on the status of advanced reactor 01/31/21 readiness activities.

Issue draft white paper with NRC staff views on demonstrating the acceptability of probabilistic risk assessments used to support non-LWR 01/31/21 plant licensing.

Issuance of six technical reports regarding operating experience and potential challenges for the transportation, storage, and disposal of 01/31/21 advanced reactor fuel types.

Issuance of technical input report by Argonne National Laboratory for the NRCs review of ASME Boiler and Pressure Vessel Code Section III, 02/28/21 Division 5. 17 16F 16 The Federal Register Notice was published on October 28, 2020, and the guidance became effective on November 27, 2020.

17 Issuance delayed from the previous projected date of October 30, 2020, due to relocation of the principal investigator for the report contracted with Argonne National Laboratory.

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Projected Projected Advanced Nuclear Reactor Technologies Activities Completion Date Issue final technology-inclusive, risk-informed, and performance-based design review guide for instrumentation and controls systems for 03/31/21 advanced reactors. 18 17F Issuance of three technical reports on materials, chemistry, and component integrity addressing molten salt chemistry, salt compatibility 03/31/21 with high temperature materials, high temperature corrosion, and graphite.

Issue Material Control and Accounting guidance for Category II facilities 05/31/21 (NUREG-2159).

Issuance of reports on Siting and Licensing Computer Codes, and 05/31/21 Computer Code Methodology for Nuclear Fuel Cycle Analysis.

Publish draft NUREG for public comment with proposed fuel qualification methodology to provide guidance for non-LWR developers on 06/30/21 qualification of fuel under the Nuclear Energy Innovation and Modernization Act (NEIMA). 19 18F Issue preliminary rule language on 10 CFR Part 53 technical 06/30/21 requirements. 20 19F Publish draft Regulatory Guide for endorsement of the ASME Section III, 06/30/21 Division 5 Standard for public comment.

2-8 Oklo Power LLC 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 21 for the Aurora reactor to the NRC (ADAMS Accession No.

20F 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 informed Oklo (ADAMS Accession No. ML20149K616) that the NRC staff planned 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 NRC staff making its reasonable assurance findings regarding the custom COL application for the Aurora design, conducting its environmental review, and issuing the NRC staffs final SER after the ACRS completes its review.

18 The original projected date of January 31, 2021, has been extended to allow for additional refinement and review.

19 Rather than issue a final white paper, previously projected for completion on December 31, 2020, the NRC staff now plans to incorporate stakeholder feedback into a NUREG to provide more formal regulatory guidance.

20 The NRC staff expects to issue preliminary rule language for some subparts of 10 CFR Part 53 periodically during FY2021 Q2 and Q3.

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.

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On November 17, 2020, the NRC staff issued a letter to Oklo (ADAMS Accession No. ML20308A677) extending the Step 1 review in the areas of maximum credible accident methodology, safety classification of structures, systems, and components, and scope of the quality assurance program. In the letter, the NRC stated that Oklos RAI responses, audit documents, and audit discussions enhanced the staffs understanding of Oklos novel approach to the Aurora safety case, but did not provide sufficient information to define the scope of the full Step 2 technical review. The NRC staff completed its review of one of the key aspects of the licensing basis, the applicability of regulations, and issued a separate letter documenting Step 1 closure on this topic on November 17, 2020 (ADAMS Accession No. ML20300A593). The NRC staff continue to work with Oklo on a plan to proceed with remaining review items. Previously reported projected activities have been deferred to dates to be determined, pending a plan from and engagement with the applicant on the path forward.

The NRC holds periodic public meetings to discuss the review of the COL application for the Oklo Aurora design. A list of the meetings can be found on the NRCs public Web site (https://www.nrc.gov/reactors/new-reactors/col/aurora-oklo/public-meetings.html).

Activities Planned and Completed for the Reporting Period (Q1 FY 2021)

Oklo Combined Operating License Review Projected Completion Date Activities Completion Date Complete initial outreach to local stakeholders (e.g.,

Governors office, Congressional staff, Tribes) 10/31/20 10/29/20 regarding the environmental review.

Complete audit related to applicability of regulations 10/31/20 11/17/20 (ADAMS Accession No. ML20332A178).

Issue letter to document the NRCs review and closure of the applicability of regulations to the Oklo 11/05/20 11/17/20 Aurora (ADAMS Accession No. ML20300A593).

Issue letter documenting the status of all Step 1 11/05/20 11/17/20 issues. (ADAMS Accession No. ML20308A677).

Hold second public meeting to discuss the methodology used in the analysis and evaluation of 10/31/20 Canceled 2221F the maximum credible accident.

Hold second public meeting to discuss the process to be used for classifying structures, systems, and 10/31/20 Canceled 23 components (SSCs) in the Aurora design and the 22F treatment for each classification of SSCs.

The completion date has been Complete Step 1 and document the NRC staffs deferred until understanding of alignment with Oklo on Key 11/05/20 more information technical issues. is available to complete the staffs review 22 While this activity was projected for FY 2021 Q1 in the FY 2020 Q4 report, the NRC staff now plans to address this issue through the RAI process and audits.

23 While this activity was projected for FY 2021 Q1 in the FY 2020 Q4 report, the NRC staff now plans to address this issue through the RAI process and audits.

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Projected Activities for the Next Two Quarters (Q2 and Q3 FY 2021)

As described, previously projected activities have been deferred.

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 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 (Q1 FY 2021)

Projected Reactor Oversight Process Activities Completion Date Completion Date Issue revision to Inspection Procedure 95001, Supplemental Inspection Response to Action 10/31/20 10/21/20 Matrix Column 2 Inputs (ADAMS Accession No. ML19179A011).

Complete comprehensive review of problem identification and resolution program and issue 11/27/20 11/12/20 report (ADAMS Accession No ML20247J590).

Complete Annual Regional ROP Implementation Audit (Region IV) and issue audit report (ADAMS 11/30/20 11/24/20 Accession No. ML20290A887).

Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Reactor Oversight Process Activities Completion Date Conduct effectiveness review of the Very Low Safety Significance Issue 03/31/21 Resolution process and issue a report.

Conduct effectiveness review of Action Matrix Change for White Findings 03/31/21 and issue a report.

Complete CY 2020 ROP Self-Assessment and issue paper to the 03/31/21 Commission.

2-10 Backfit The NRCs backfitting rules are codified in 10 CFR 50.109, 70.76, 72.62, and 76.76. The backfitting rules define backfitting as the modification of or addition to systems, structures, components, or design of a facility; or the design approval or manufacturing license for a facility; or the procedures or organization required to design, construct or operate a facility; any of which may result from a new or amended provision in the Commissions regulations or the imposition of a regulatory staff position interpreting the Commissions regulations that is either new or different from a previously applicable staff position. 24 The rules require, in the absence of an 23F applicable exception, an analysis showing that the backfit would result in a substantial increase 24 10 CFR 50.109(a)(1). Substantially similar definitions are provided in § 70.76, Backfitting, § 72.62, Backfitting, and § 76.76, Backfitting for non-reactor facilities.

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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 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 (Q1 FY 2021)

Projected Backfit Activities Completion Date Completion Date Evaluate public comments and prepare NUREG-1409, Revision 1 for internal agency 11/30/20 12/14/20 25 24F concurrence.

Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Backfit Activities Completion Date Provide NUREG-1409, Revision 1 to the Commission. 03/31/21 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. 26 The NRC staff is implementing the 25F 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.

25 The NRC staff completed this item 2 weeks after the projected date due to the complexity of comment resolution.

26 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 (Q1 FY 2021)

Projected Risk-Informed Activities Completion Completion Date Date Issue the technical evaluation report for Exubrion Therapeutics proposed procedure for the release of dogs 10/29/20 10/30/20 following treatment with a tin-117m colloid (ADAMS Accession Number ML20269A274).

Finalize Risk-Informed Process for Evaluations (RIPE) initiative and associated NRC staff guidance. RIPE leverages current regulations and risk initiatives to allow reactor licensees to 10/30/20 01/07/21 justify plant-specific licensing basis changes using a streamlined NRC review process (ADAMS Accession No. ML21006A324). 27 26F Brief ACRS on proposed final draft Revision 3 to RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk 11/05/20 11/05/20 Assessment Results for Risk- Informed Activities for public comment (ADAMS Accession No. ML20324A742).

Provide a seminar for NRC management and staff by Professor 11/06/20 11/06/20 Malcolm Sparrow related to risk and regulatory strategies.

Conduct a table-top exercise with NEI on implementing an alternative and flexible licensing strategy for shielding 11/06/20 11/06/20 analysis provided in spent fuel storage system applications.

Develop a risk tool to enhance the staffs safety focus during reviews of spent fuel storage system applications 12/17/20 12/17/20 and conduct a workshop for external stakeholders to demonstrate how the tool will be applied.

27 This initiative was originally titled Risk-Informed Process for Exemptions. The title was updated to Risk-Informed Process for Evaluations to reflect the initiatives broader applicability to multiple types of licensing basis change requests (e.g., exemptions, license amendments).

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Projected Risk-Informed Activities Completion Completion Date Date Issue draft Revision 2 of RG 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, for public 12/18/20 11/16/20 comment (available at 85 Fed. Reg. 73088 and ADAMS Accession No. ML20231A856).

Publish Integrated Human Error Analysis System for Event and 12/31/20 12/21/20 Condition Analysis Human Reliability Analysis Method workshop report.

Implement revisions to the independent spent fuel storage installation 12/31/20 12/31/20 inspection guidance.

Issue Revision 3 of RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk 03/31/21 12/29/20 Assessment Results for Risk- Informed Activities (ADAMS Accession No. ML20238B871).

Projected Activities for the Next Two Reporting Periods (Q2 and Q3 FY 2021)

Projected Projected Risk-Informed Activities Completion Date Publish draft regulatory basis for rulemaking to align licensing processes and apply lessons learned from new reactor licensing for 02/26/21 2827F public comment (ADAMS Accession No. ML19161A169).

Issue implementation guidance associated with the RIPE initiative 01/31/21 (ADAMS Accession Nos. ML20261H475 and ML21006A324). 29 28F Conduct a public meeting to discuss rollout of the RIPE initiative and 01/31/21 options to broaden the applicability of RIPE to additional NRC licensees.

Complete review of LAR to revise the emergency plans for SNC fleet to change emergency response organization staffing composition and 03/23/21 extend staff augmentation times. These LARs are significant in that they result from the risk-informed aspects of the 2019 revision of NUREG-0654, the definitive emergency preparedness evaluation guidance.

Implement the near-term recommendations on building a smarter fuel 03/26/21 cycle licensing program (ADAMS Accession No. ML20184A267). 30 29F Publish Revision 1 to NUREG/CR-7002, Criteria for Development of 03/30/21 Evacuation Time Estimate Studies.

28 The projected completion date has been extended from December 16, 2020, to February 26, 2021, to provide additional time for staff to finalize the document.

29 The implementation guidance was issued earlier than projected (January 7, 2021), and will be reflected as a completed activity in the next report.

30 The projected completion date has been extended from December 31, 2020, to March 26, 2021, to provide additional time for the staff to finalize the document.

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Issue final safety evaluation report for the first topical report related to Holtec spent fuel storage systems related to a generic and risk-informed approach on heat load zone configurations. This approach, if approved 04/30/21 and adopted for a given Holtec design, will reduce the number of future license amendments.

Brief ACRS on draft Revision 2 of RG 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear 06/30/21 Power Plants, for public comment (ADAMS Accession No. ML20231A856).

Implement the recommendations on building a smarter fuel cycle 06/30/21 31 inspection program (ADAMS Accession No. ML20183A242).

30F Identify potential need for changes in guidance to the definition of term gross-rupture which could result in operational and licensing efficiencies 06/30/21 for spent fuel storage systems through engagement with external stakeholders.

2-12 Coronavirus Disease 2019 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 around NRC facilities. 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.

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 was 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). On July 12, 2020, NRC headquarters, Region I, and Region III transitioned to Phase 2 while Region II, Region IV, and the TTC remained in Phase 1 due to consideration of State and local conditions. On November 19, 2020, NRC Region III transitioned from Phase 2 back to Phase 1 of the NRC Re-Occupancy Plan. On December 18, 2020, NRC Region I transitioned from Phase 2 back to Phase 1 of the NRC Re-Occupancy Plan. These shifts from low to moderate mitigation considered both worsening COVID-19 conditions in Illinois and Pennsylvania, respectively, and 31 This activity was originally projected to be completed by November 30, 2020, and most of the inspection procedures identified for revision were completed by December 31, 2020. However, seven procedures (not needed to complete inspection in Q1 of CY 2021) remain in the final stages of review. The staff also plans to implement two longer-term recommendations from the smarter fuel cycle inspection report in the third quarter of FY 2021: 1) performing an in-depth assessment of the scope of resident inspector guidance and 2) incorporating into the inspection program the results of the Operating Experience Program and the Fuel Cycle Inspection Assessment Program.

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the re-imposition of increased State and local mitigation measures. Enhanced screening (i.e.,

temperature checks and access questions) applies to NRC facilities in Phase 1. The agency continues to closely monitor State and local conditions as well as guidance from the CDC, Occupational Safety and Health Administration, and OMB in consideration of re-occupancy decisions to help protect the health and safety of the workforce.

Licensing and Oversight Items of Interest The NRC staff has taken 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 continues to communicate the processes available to licensees for requesting these flexibilities in a transparent way through public communications, such as teleconferences, webcasts, and letters. In addition, these processes and the approved flexibilities are posted and updated on the NRC public Web site (https://www.nrc.gov/about-nrc/covid-19/).

During the reporting period, the agency noticed 181 public meetings in the Washington, D.C.

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, these meetings were held virtually via webcast or by 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 during the pandemic. Between October 1, 2020, and December 31, 2020, the NRC issued 105 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 November 10, 2020 (ADAMS Accession No. ML20261H515), the NRC issued a letter to provide guidance on the continued use of expedited processes beyond December 31, 2020, for COVID-19 related requests in seven topical areas. Enclosures to the letter addressed informational needs for each of the seven topical areas to facilitate the continued licensees use of the NRC's expedited review process, such as providing justifications for the exemptions requested due to COVID-19 PHE challenges and information related to the potential cumulative effects of these exemptions.

Regulatory Activities Taken in Response to the COVID-19 PHE During the Reporting Period Number of COVID-19 Average Number of Licensee Type Requests Approved During the Days to Review Reporting Period COVID-19 Requests 32 31F Power Reactor 96 34 Non-Power Reactor 1 45 Other (e.g., topical reports) 0 N/A 32 This average is calculated based on the date the request is received and the review is completed; review time may be longer in cases where a supplement to a request is received after the initial submission date.

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Decommissioning of Nuclear 0 Facilities and Uranium Recovery N/A Storage and Transportation of 0 Spent Nuclear Fuel N/A Fuel Cycle Facilities 2 18 Medical, Industrial and Academic Uses of Nuclear Materials and 6 32 Agreement States 26

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.

CY 2020 Location Number of Findings CY 2017 CY 2018 CY 2019 (YTD)

Nationally Total 560 478 440 254 33 32F Green 126 107 95 43 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 43 No. of Units 25 25 24 21 34 Operating During CY 33F Green 119 113 110 69 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 71 No. of Units 33 33 33 33 Operating During CY Green 133 110 96 37 White 4 2 1 0 Yellow 0 0 0 0 Region III Red 0 0 0 0 Greater Than Green 0 0 0 1 Security 33 The inspection reports for the fourth quarter of CY 2020 will continue to be finalized through February 15, 2021.

The report for the next reporting period will be updated to include any additional findings from the fourth quarter of CY 2020.

34 The reduction of three units for CY 2020 reflects the permanent shutdown of Pilgrim Nuclear Station on May 31, 2019, Three Mile Island, Unit 1, on September 20, 2019, and Indian Point Nuclear Generating Unit 2 on April 30, 2020.

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CY 2020 Location Number of Findings CY 2017 CY 2018 CY 2019 (YTD)

Total 137 112 97 38 No. of Units 23 23 23 22 35 Operating During CY 34F Green 167 145 137 102 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 171 145 137 102 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 Percentage Licensing Licensing of Licensing of Licensing Reporting Total Actions Actions Actions Actions Period Inventory Initiated Completed Completed Completed During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule 37 36F Schedule 3635F Q2 FY 2020 173 96 82 100% 94%

Q3 FY 2020 191 213 203 100% 93%

Q4 FY 2020 238 233 186 100% 98%

Q1 FY 2021 224 226 237 100% 92%

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

36 Consistent with previous reports, this excludes unusually complex and Fukushima-related licensing actions accepted or initiated prior to July 13, 2019.

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

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New Reactors Percentage Percentage Licensing Licensing of Licensing of Licensing Reporting Total Actions Actions Actions Actions Period Inventory Initiated Completed Completed Completed During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule Schedule Q2 FY 2020 3 0 1 100% 100%

Q3 FY 2020 8 5 0 N/A N/A Q4 FY 2020 3 1 6 100% 100%

Q1 FY 2021 2 1 2 100% 100%

Fuel Facilities Percentage of Percentage of Licensing Licensing Licensing Licensing Actions Actions Actions Actions Reporting Total Initiated Completed Completed Prior Completed Period Inventory During the During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule Q2 FY 2020 6 4 4 100% 100%

Q3 FY 2020 4 3 5 100% 100%

Q4 FY 2020 3 1 2 100% 100%

Q1 FY 2021 2 1 2 100% 0% 38 37F 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).

38 One licensing action was complex; the other was completed approximately 25 days after the established schedule. Both licensing actions were completed within the generic milestone schedule.

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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 39 38F Schedule 40 39F Q2 FY 2020 343 84 138 100% 92%

Q3 FY 2020 382 125 95 100% 96%

Q4 FY 2020 362 125 145 100% 91%

Q1 FY 2021 354 84 94 100% 92%

New Reactors LAR Percentage of Percentage of LARs Reviews LAR Reviews LAR Reviews Submitted Reporting Total Completed Completed Prior Completed During the Period Inventory During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule Q2 FY 2020 6 2 8 100% 100%

Q3 FY 2020 5 3 4 100% 100%

Q4 FY 2020 3 1 3 100% 100%

Q1 FY 2021 1 0 2 100% 100%

Fuel Facilities LAR Percentage of Percentage of LARs Reviews LAR Reviews LAR Reviews Submitted Reporting Total Completed Completed Prior Completed During the Period Inventory During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule Q2 FY 2020 11 5 6 100% 100%

Q3 FY 2020 12 14 13 100% 93%

Q4 FY 2020 14 7 5 100% 80%

Q1 FY 2021 14 6 6 100% 100%

39 Consistent with previous reports, this excludes unusually complex and Fukushima-related LARs accepted or initiated prior to July 13, 2019.

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

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Unusually Complex LARs 41 40F 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.

Age Unusually Complex LAR Description Exclusive Justification (Months)

Point Beach Units 1 and 2 - Exemption to support Exemption requested resolution of GL 2004-02, Potential Impact of Debris relies on completion of the Blockage on Emergency Recirculation During Design significant review of a 26 42 Basis Accidents at Pressurized-Water Reactors. unique, plant-specific 41F methodology to resolve issues from GL 2004-02.

3-4 Research Activities 43 42F Summary of New Research Projects During the reporting period, the Office of Nuclear Regulatory Research did not initiate research on or substantially revise any projects.

Summary of Completed Research Projects 44 43F During the reporting period, Office of Nuclear Regulatory Research completed the following activities:

Technical Support for Nuclear Reactor Regulation National Fire Protection Association (NFPA) 805 Transition Program and other Ongoing Fire Protection Activities The tasks and milestones for this research project provided support Importance to the for the implementation of, and licensee transitions to, the risk-NRC Mission informed, performance-based protection NFPA 805 rule and other ongoing fire protection activities.

The NRC staff made significant contributions supporting the licensing reviews including how to appropriately reflect uncertainties Research Results or and advance realism in fire protection modeling. Research work led Findings to the development or revision of multiple reference documents, including, but not limited to:

• NUREG-1824, Verification and Validation of Selected Fire Models for Nuclear Plant Application; 41 There were no unusually complex license amendment requests for new reactors or fuel facilities within the reporting period.

42 The Point Beach LAR was determined to be unusually complex during the technical review.

43 This section provides information about projects that were started or completed during the reporting period that exceeded 300 staff hours or $500K of program support for the total duration of the project.

44 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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Technical Support for Nuclear Reactor Regulation National Fire Protection Association (NFPA) 805 Transition Program and other Ongoing Fire Protection Activities

• NUREG-1921, EPRI/NRC-RES Fire Human Reliability Analysis Guidelines and its supplements;

• NUREG-1934, Nuclear Power Plant Fire Modeling Analysis Guidelines;

• NUREG-2180, Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities;

• NUREG/CR-7010, Cable Heat Release, Ignition, and Spread in Tray Installations During Fire; and

• NUREG/CR-7100, Direct Current Electrical Shorting in Response to Exposure Fire.

Duration of the 12 years Project Estimate of Total 27 FTE and $9M Research Resources 3-5 Fees Billed The tables below provide information on Part 170 fees billed for each fee class. For each fee class, the NRC staff compared the fees billed to the receipts estimated in the annual fee rule. 45 44F FY 2020 Part 170 Part 170 Billed in Total Part 170 - Billed Fee Class Receipts Final - FY 2021 Q1 ($M) in FY 2021 ($M)

Annual Fee Rule ($M)

Fuel Facilities $6.8 $1.9 $1.9 Generic $3.6 $0.9 $0.9 Decommissioning Materials Users 46 45F

$1.0 $0.1 $0.1 Operating Power $186.7 $44.4 $44.4 Reactors Research and $3.0 $0.7 $0.7 Test Reactors Spent Fuel Storage / Reactor $15.9 $3.2 $3.2 Decommissioning Transportation $2.8 $0.2 $0.2 Uranium Recovery $0.4 $0.0 $0.0 45 The FY 2020 Final Fee Rule estimated collections are being used until the FY 2021 Proposed Fee Rule is in the final stages of publication.

46 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 COL application, and the SHINE Medical Technologies, LLC (SHINE) operating license application review.

Projected Fees Billed Docket Project Name Resources to Date

($M) 47 46F ($M) 48 47F NuScale Power NuScale SMR Design $57.8 Reactor 05200048 Certification Application Review NuScale SMR Topical Report

$66.0 49 NuScale Power Reviews (Only those that $8.3 48F Reactor 99902043 directly support the design certification review)

North Anna Units 1 and 2 North Anna Units 1 and $5.0 50 $0.2 Subsequent License Renewal 2 05000338/05000339 49F Application Safety Review North Anna Units 1 and 2 North Anna Units 1 and Subsequent License Renewal $1.4 $0.1 2 05000338/05000339 Application Environmental Review Surry Units 1 and 2 Surry Units 1 and 2 05000280/05000281 Subsequent License Renewal Application Safety Review $4.9 $4.6 Surry Units 1 and 2 Surry Units 1 and 2 Subsequent License Renewal

$1.4 $1.9 51 05000280/05000281 Application Environmental 50F Review SHINE Medical Isotope $3.2 Production Facility 47 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.

48 The NRC bills its licensees/applicants in the first month of the quarter following the timeframe in which the work was performed. For example, NRC work performed in October, November, and December, would be invoiced to the licensee/applicant in January. Therefore, the total billed amounts listed in Table 3-5 reflects costs for NRC work performed through September 2020.

49 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 expected to bill through the end of the technical review in September 2020 ($7.9M). The NRC staff completed its technical review of the NuScale DC and supporting topical reports by the scheduled due date and did so within the projected resources for the remainder of the review. Costs associated with pre-application activities are not included.

50 When the formal acceptance letter for the North Anna subsequent license renewal application was sent to the licensee on October 13, 2020 (ADAMS Accession No. ML20258A284), the NRC estimated that it would take approximately $6.4M to complete the application review.

51 When the Surry subsequent license renewal application was accepted for review on December 3, 2018 (ADAMS Accession No. ML18320A236), the NRC estimated it would take approximately $6.3M to complete the application review.

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Projected Fees Billed Docket Project Name Resources to Date

($M) 4746F ($M) 48 47F SHINE Medical Operating License $6.2 52 51F Technologies, LLC Application Review 05000608 Safety and Environmental Reviews Oklo Aurora Oklo Aurora COL 05200049 Application - $0.5 53 52F $0.2 Safety Review Oklo Aurora 05200049 Oklo Aurora COL Application - Environmental $0.2 $0.1 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 54 53F Operating Reactors 359 112 158 64 Non-Power Production and 519 69 48 0 Utilization Facilities 55 54F Design Certifications N/A N/A N/A N/A for New Reactors 56 55F 52 The projected resource estimate was provided to SHINE by letter dated April 30, 2020 (ADAMS Accession No. ML20114E315).

53 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 contains the projected resources to complete the identified Step 1 safety and environmental aspects of the review (ADAMS Accession No. ML20308A677).

54 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.

55 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.

56 There are no design certification 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 54 53F Early Site Permits N/A N/A N/A N/A for New Reactors 57 56F Combined Licenses 10 0 10 0 for New Reactors Fuel Facilities 183 61 97 26 Power Reactor 59 24 33 3 Decommissioning Research and Test Reactor 6 0 6 0 Decommissioning Spent Fuel 871 157 182 32 Materials 0 0 0 6 Pre-Application Activities for 27 0 0 0 Advanced Reactors 3-7 Workforce Development and Management FY 2021 Staffing by Office 58 57F Delta (Q1 End of Year Delta (EOY FTE FTE FTE FTE FTE (EOY) 59 FY 2021 Utilization Utilization Utilization Utilization Utilization - Projection w/ Projection -

58F Budget 09/27/20 - 10/25/20 - 11/22/20 - as of FY 2021 FY 2021 Personnel 10/24/20 11/21/20 12/19/20 12/19/20 Budget)

Budget) Actions Totals 2879.1 212.9 212.6 212.8 638.4 -2240.7 2772.3 -106.8 COMM 45.0 2.7 2.7 2.7 8.2 -36.8 38.4 -6.6 OIG 63.0 4.2 4.4 4.3 12.9 -50.1 57.8 -5.2 Totals Other 2771.1 205.9 205.5 205.7 617.3 -2153.8 2676.1 -95.0 Offices OCFO 93.0 6.9 7.0 7.0 21.0 -72.0 91.0 -2.0 OGC 93.0 7.0 6.9 6.9 20.8 -73.2 90.5 -3.5 OCA 10.0 0.8 0.8 0.8 2.4 -7.6 10.9 0.9 OCAA 7.0 0.5 0.5 0.5 1.6 -5.4 6.7 -0.3 OPA 13.0 1.0 1.0 1.0 3.0 -10.0 12.3 -0.7 57 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.

58 Some numbers might not add due to rounding.

59 Based on FTE utilization as of December 19, 2020.

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Delta (Q1 End of Year Delta (EOY FTE FTE FTE FTE FTE (EOY) 59 FY 2021 Utilization Utilization Utilization Utilization Utilization - Projection w/ Projection -

58F Budget 09/27/20 - 10/25/20 - 11/22/20 - as of FY 2021 FY 2021 Personnel 10/24/20 11/21/20 12/19/20 12/19/20 Budget)

Budget) Actions SECY 17.0 1.4 1.4 1.4 4.2 -12.8 18.0 1.0 OIP 34.0 2.5 2.5 2.5 7.4 -26.6 33.1 -0.9 ASLBP 23.0 1.6 1.6 1.6 4.9 -18.1 20.6 -2.4 ACRS 24.0 2.0 2.0 2.0 5.9 -18.1 26.3 2.3 OEDO 23.0 1.6 1.8 1.8 5.2 -17.8 22.9 -0.1 NRR 552.4 41.0 41.3 41.5 123.8 -428.6 537.7 -14.7 NMSS 293.5 23.2 23.0 23.0 69.2 -224.3 296.5 3.0 RES 197.0 14.5 14.5 14.6 43.6 -153.4 191.7 -5.3 NSIR 152.0 12.0 11.9 11.9 35.8 -116.2 151.3 -0.7 R-I 180.2 12.8 12.9 13.1 38.8 -141.4 170.3 -9.9 R-II 223.3 16.3 16.3 16.2 48.8 -174.5 207.5 -15.8 R-III 174.4 12.7 12.6 12.6 37.9 -136.5 164.5 -9.9 R-IV 164.0 12.6 12.4 12.3 37.4 -126.6 158.4 -5.6 OE 30.3 2.3 2.3 2.2 6.8 -23.5 28.6 -1.7 OI 35.0 3.0 3.0 3.1 9.1 -25.9 38.9 3.9 OCIO 167.0 11.7 11.6 11.4 34.6 -132.4 151.4 -15.6 ADM 123.0 9.0 8.9 8.8 26.7 -96.3 116.7 -6.3 SBCR 13.0 0.9 0.8 0.8 2.6 -10.4 11.1 -1.9 OCHC O 127.0 8.4 8.4 8.5 25.3 -101.7 117.3 -9.7 CSU 1.0 0.2 0.2 0.2 0.5 -0.5 2.0 1.0 3-8 Inspection Activities The table below shows the average number of hours of direct inspection per plant in CY 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 No Plants in No Plants in 1579 Hours 1582 Hours 1548 Hours 60 Column 3 Column 4 59F 60 Browns Ferry Nuclear Plant (three-unit boiling water reactor (BWR) site), Vogtle Electric Generating Plant (two-unit pressurized water reactor (PWR) site), Clinton Power Station (1-unit BWR), Grand Gulf Nuclear Station (1-unit BWR) and Surry Power Station Unit 2 (two-unit PWR reactor site) were in Column 2 of the ROP Action Matrix YTD in CY 2020.

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The table below shows the staff hours expended for inspection-related effort at operating power reactor sites by calendar year.

Items Description CY 2019 (Hours) CY 2020 (YTD) (Hours)

i. Baseline Inspection 235,718 213,035 ii. Plant-Specific Inspection 9,096 8,585 iii. Generic Safety Issue Inspections 3,200 915 iv. Performance Assessment 1,532 1,836

v. Other Activities 98,614 87,797 vi. Total Staff Effort 348,160 312,168 vii. Total Staff Effort Per Operating Site 6,003 61 60F 5,477 62 61F 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.

Backfit Appeals Filed by Licensees and Applicants There were no backfit appeals submitted to the NRC during the reporting period.

61 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.

62 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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