ML22280A173
| ML22280A173 | |
| Person / Time | |
|---|---|
| Issue date: | 11/14/2022 |
| From: | Christopher Hanson NRC/Chairman |
| To: | Carper T, Markey E, Pallone F US HR (House of Representatives), US SEN (Senate) |
| Holiday S | |
| Shared Package | |
| ML22280A171 | List: |
| References | |
| CORR-22-0105; SRM-LTR-19-0383-1 | |
| Download: ML22280A173 (44) | |
Text
STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COM MISSION For the Reporting Period of July 11 2022 through September 30 1 2022 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 Process Inspection Hours and Percent Complete.................4 1-3 Full-time Equivalent (FTE) at the End of Quarter (Q) 4 fiscal year (FY) 2022 vs.
Budgeted FTE..................................................................................................... 5 1-4 Budget Authority, FTE Utilization, and Fees....................................................... 5 - Status of Specific Items of lnterest...................................................... 7 2-1 Transformation.................................................................................................... 7 2-2 Workforce Development and Management........................................................ 8 2-3 Accident Tolerant Fuel........................................................................ 9 2-4 Digital Instrumentation and Control................................................................... 10 2-5 Vogtle Electric Generating Plant Units 3 and 4................................................. 12 2-6 NuScale Small Modular Reactor Design Certification....................................... 15 2-7 Advanced Nuclear Reactor Technologies......................................................... 16 2-8 Advanced Reactor Licensing Reviews.............................................................. 19 2-9 Reactor Oversight Process............................................................................... 20 2-10 Backfit............................................................................................................... 21 2-11 Risk-informed Activities.................................................................................... 22 2-12 Coronavirus Disease (COVID-19) Pandemic.................................................... 24 - Summary of Activities......................................................................... 26 3-1 Reactor Oversight Process Findings................................................................ 26 3-2 Licensing Actions.............................................................................................. 27 3-3 Licensing Amendment Request Reviews......................................................... 28 3-4 Research Activities........................................................................................... 30 3-5 Fees Billed........................................................................................................ 38 3-6 Requests for Additional lnformation..................................................................40 3-7 Workforce Development and Management...................................................... 41 3-8 Inspection Activities.......................................................................................... 41 3-9 Backfit............................................................................................................... 42 Enclosure 1 - High Level Summary
Average Timeliness Percentage for Licensing Actions Categorized Under the Nuclear Energy Innovation and Modernization Act
1
41 s... Cl41 0.9 C,2 B 41 0.8
... m _..
41 "0 41 D. 41 'lii 0.7 Ill ai C
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- - II U E.c t-o rn 0.5 41~
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0.2
0.1
-- Operating Reactors Established Schedule
-+ - New Reactors Established Schedule
-e - Fuel Facilities Established Schedule
1 2
1 No licensing actions categorized under the Nuclear Energy Innovation and Modernization Act were completed in Quarter (Q) 2 fiscal year (FY) 2021 for the new reactor business line.
2 There was one activity completed in 03 FY 2022 for the new reactor business line, and it was completed significantly ahead of the established schedule. Because the one activity was completed in 28 percent of the established schedule, this resulted in the Q3 FY 2022 average timeliness percentage for the new reactor business line being 28 percent.
3 1-2 Reactor Oversight Process (ROP) Inspection Hours and Percent Complete
Reactor Oversight Process Inspection Hours and Percent Complete 180000 100% C
160000 90% i 80% Ill a.
- 140000.5
- c 0 70% IL C 120000 0 0:
~ g 100000 60% ts
- a. _g: !l Ill 50% C.!! "O a.
.5 80000 IL 40% m E Cg 0 ;u 0: 60000 30% ii: f!
u... ::,
.~ 40000 C 20% 2i C CD 20000 10% !! CD IL 0 0% CD l Quarter1 Quarter2 Quarter3 Quarter4 :i II
- Calendar Year (CY) 2021 Total Direct ROP Inspection HOUIS E
=CY 2022 Total Direct ROP Inspection Hours u
o Percent Complete of Total CY 2022 Planned Direct ROP Inspection Hours
- Percent Complete of Total CY 2021 Planned Direct ROP Inspection Hours
3
3 "Planned direct ROP inspection hours" refers to the number of hours associated with completion of the U.S. Nuclear Regulatory Commission's (NRC's) "nominal" number of inspection samples established for the baseline inspection program, which is a conservative target. This contrasts with the "minimum" number of hours that would be necessary to complete the set of inspection activities that constitutes completion of the ROP baseline inspection program for the CY.
4 1-3 Full-time E uivalent FTE at the End of Q4 FY 2022 vs. Bud eted 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 Ill Region IV Office of Administration Office of the Chief Financial Officer Office of the Chief Human Capital Officer Office of the Chief Information Officer Office of General Counsel Other 0.0 100.0 200.0 300.0 400.0 500.0 600.0 FTE Budgeted FTE On Board FTE
1-4 Budget Authority, FTE Utilization, and Fees
NRC FY 2022 Bud get Authority Se ptember 30, 2022 ( Dollars in Thousands )
Fund Sources FY 2022 Bud get4 Percent Obliq ated Percent Ex pended Advanced Reactors $23,000 91% 62%
Commission Funds $14,936 37% 37%
Fee-Based Funds $846,923 96% 77%
General Funds 5 $1,295 75% 52%
International Activities $16,635 98% 84%
University Nuclear $29,649 49% 2%
Leadership Pro gram Official Re p resentation $37 71% 34%
Total $932,475 94% 74%
NRC Control Points FY 2022 Bud get Percent Obligated Percent Ex pended Nuclear Reactor Safety $478,520 92% 80%
Nuclear Materials and $109,286 100% 85%
Waste Safe ty Decommissioning and $23,156 93% 82%
Low-Level Waste Cor porate S upp ort $291,863 98% 67%
4 FY 2022 Budget reflects the enactment of the Consolidated Appropriations Act, 2022 and includes the enacted budget and carryover allocated.
5 Consistent with previous reports, this row represents waste incidental to reprocessing activities excluded from the fee-recovery requirement.
5 Fund Sources FY 2022 Bud Qet4 Percent ObliQated Percent Ex pended University Nuclear $29,649 49% 2%
Leadership Pro Qram 6 Total7 $932,475 94% 74%
FTE Utilization, Hiring, and Attrition
Total Year-to-Date Projected End of Year Quarter 4 Quarter 4 YTD YTD
{YTD) FTE Utilization FTE Total Utilization Hiring Attrition Hiring Attrition 2705.3 2705.3 89 47 207 244
FY 2022 Fees Estimated, Fees Billed, and Fees Collected Throu g h Q4
$800,000
...... $700,000
Ill $600,000 "O
C Ill Ill
- > $500,000
.r. 0 I-
.5 $400,000 Ill
.!!! $300,000..
0 e.
c $200,000 :>
0
< E $100,000
$0 01-0ct 02-Nov 03-Dec 04.Jan 05-Feb 06-Mar 07-Apr 08-May 09-.kln 10-.kll 11-Aug 12-Sep 2021 2021 2021 2022 2022 2022 2022 2022 2022 2022 2022 2022
- Total Estimated $178,776 $180,743 $182,642 $348,892 $350,789 $353,153 $525,807 $528,246 $530,543 $578,949 $704,084 $706,494 Total Actual Billed $178,583 $181,024 $183,533 $352,524 $355,144 $358,219 $531,360 $534,478 $537,447 $584,848 $749,857 $748,667 Total Actual Collected $69,500 $177,468 $181,355 $263,372 $351,476 $354,436 $406,470 $528,053 $531,629 $544,683 $584,320 $739,598
Total for Title 10 of the Code of Federal Re gulations ( 10 CFR ) Part 170, "Fees for Facilities, Materials, Im port and Ex port Licenses, and Other Re g ulato ry Services Under the Atomic Energy Act of 1954, As Amended." Fees Billed (Dollars in Millions)
FY 2020 FY 2021 FY 2022 Q1-Q4
$205.7 $183.9 $190.7
6 The FY 2022 Explanatory Statement identified this control point as the "Integrated University Program." Division Z of the Consolidated Appropriations Act, 2021 replaced the Integrated University Program with the University Nuclear Leadership Program.
7 Numbers might not add due to rounding.
6 Enclosure 2 - Status of Specific Items of Interest
Enclosure 2 provides the status of specific items of interest including a summary of the item, the activities planned and accomplished under each item within the reporting period, and projected activities under each item for the next two reporting periods.
2-1 Transformation
The U.S. Nuclear Regulatory Commission (NRC) is becoming a more modern, risk-informed regulator, open to new technologies and ways of implementing our safety and security mission.
The NRC continues to make progress in four focus areas: (1) recruiting, developing, and retaining a strong workforce; (2) improving decision-making through the acceptance of an appropriate level of risk without compromising the NRC's mission; (3) establishing a culture that embraces innovation; and (4) adopting new and existing information technology resources. The agency has completed all but one of our initial agencywide initiatives associated with the four focus areas.
To sustain progress and meet the agency's transformation goals, the NRC will use a variety of tools, including "objectives and key results" that relate to the current four focus areas (i.e., Our People, Be riskSMART, Using Technology, and Innovation). The NRC continues to leverage available technologies, increase opportunities for staff to gain new skills, attract talented new staff, and foster a culture of safety and innovation that accounts for differing viewpoints and risk insights in our decision-making. Planned future activities will focus on incorporating positive transformational changes into the agency's culture and processes.
Activities Planned and Completed for the Reporting Period (Quarter (Q) 4 fiscal year (FY) 2022)
Transformation Activities Projected Completion Date Completion Date
Implement a staff-led effort to recognize NRC employees who make notable and innovative contributions towards attaining agency goals through business improvements, applying risk 07/31/22 08/08/22 8 insights, using data in decision-making, realizing culture, enhancing the work environment, or advancing knowledge management practices.
Projected Activities for the Next Two Reporting Periods (Q1 and 02 FY 2023)
Projected Transformation Activities Projected Completion Date
Update transformation webpages on the NRC's public website to include 12/31/22 9 information regarding sustaining transformational progress.
Launch a follow-on survey of external stakeholder views on NRC 01/31/23 transformation activities.
8 Senior leaders reviewed the staff ideas and selected winners for the Innovation Success of the Year (iSOFTY) 2022 award. Staff winners were announced for the iSOFTY 2022 award on August 8, 2022.
9 The projected completion date was modified from October 31, 2022, to December 31, 2022, to allow additional time for staff to review information related to organizational health activities.
7 Projected Transformation Activities Projected Completion Date
Conduct first-line supervisor and senior leader sessions on "Organizational Health: Sustaining Transformational Progress in a Hybrid 03/31/23 Environment."
Conduct a full reassessment of the agency's cultural norms and 03/31/23 10 behaviors to ensure the agency is sustaining transformational progress.
2-2 Workforce Development and Management
Each fiscal year, the NRC engages in a five-step Strategic Workforce Planning (SWP) process to improve workforce development to meet its near-and long-term work demands. The first step in this process is an Agency Environmental Scan that projects the amount and type of work anticipated in the next five years and identifies the workforce needs in order to perform that work. By analyzing the current workforce and comparing it to future needs, skill gaps can be identified. In the final step of the process, both short-and long-term strategies are developed to enable the agency to recruit, retain, and develop a skilled and diverse workforce with the competencies and agility to address both current and emerging needs and workload fluctuations.
During the reporting period, the agency continued implementing a strategy to recruit approximately 300 new employees during FY 2022, to conduct mission-critical work identified through the SWP process. This recruitment effort, which will continue in subsequent years, will position the agency to fulfill its important safety and security mission well into the future.
Activities Planned and Com p leted for the Re porting Period (04 FY 2022 )
Workforce Development and Management Projected Completion Date Activities Completion Date Discussed FY 2022 SWP High Priority Critical Skill Gaps and associated Strategies and Key Activities, as well as potential improvements to the SWP process, at the Semi-annual Strategic Alignment 09/30/22 08/17/22 Meeting with senior leaders to address the gaps and further integrate SWP with related agency processes.
Onboarded final Summer 2022 intern as well as 25 recent graduates for the Nuclear Regulator Apprenticeship Network (NRAN) cohort. In addition, 75% of the Student Interns who participated in 09/30/22 11 09/30/22 summer internships converted to the Co-Op Program, accepted an offer for a second internship, or received an offer for an entry-level position after g raduation.
10 The projected completion date was modified from December 31, 2022, to March 31, 2023, due to additional time needed for the agency to review and implement Federal Employee Viewpoint Survey 2022 results.
11 In the previous report, the projected completion date to onboard 1 additional Summer 2022 student intern and 25 recent graduates who will form the 2022 NRAN cohort was July 29, 2022. The on boarding of all these employees was completed by September 30, 2022. Additional information is provided regarding Summer Interns continuing service with the NRC.
8 Workforce Development and Management Projected Completion Date Activities Completion Date Continued implementation of the recruitment strategy, onboarding a total of 207 new employees during FY 2022. An additional 78 individuals are 09/30/22 09/30/22 expected to onboard in 01 FY 2023, following com p letion of back Qround investiQations. 12
Pro jected Activities for the Next Two Re porting Periods (01 and Q2 FY 2023 )
Projected Workforce Development and Management Activities Projected Com p letion Date Com plete SWP Step 1, A g enc y Environmental Scan FY 2023 - FY 2028. 12/31/22 Conduct recruitment activities and make selections for the Summer 2023 12/31/22 Internship Pro g ram.
Conduct an evaluation of the SWP process for effectiveness and efficiency improvements as identified in the NRC's Annual Evaluation 03/31/23 Plan for FY 2023. The FY 2023 SWP cycle will initiate following the incorporation of approved recommendations from the evaluation.
Finalize security clearance reviews and prepare for Summer 2023 03/31/23 Student Intern onboardin g.
While the NRC is ready to review and license Accident Tolerant Fuel (ATF}, higher burnup, and increased enrichment submittals under the current regulatory framework, the NRC continues to take steps to make agency processes more efficient and effective. The NRC staff is executing the ATF project plan (Agencywide Documents Access and Management System Accession No. ML21243A298 ), which was revised to include an increased focus on higher burnup and increased enrichment fuels.
During this reporting period, the NRC did not receive any additional ATF fuel vendor topical reports, ATF operating reactor licensing actions, or ATF transportation package applications.
The NRC staff continues to review the eight ATF fuel vendor topical reports and ATF applications that were previously submitted.
The NRC expects to receive additional certificate of compliance amendment applications and license amendment requests (LARs) in CY 2022 from transportation package vendors and fuel fabricators, respectively. The NRC expects that these submittals will request approval for enrichment levels up to 8 weight-percent uranium-235.
12 While the goal to hire approximately 300 new employees in FY 2022 was not met, the NRC will continue its hiring efforts into FY 2023.
9 Activities Planned and Com pleted for the Re porting Period (Q4 FY 2022 )
ATF Activities Projected Completion Date Completion Date
Held the third Higher Burnup workshop
( ML22235A740 ). At this workshop, the NRC staff and representatives from industry discussed the state of development of higher burnup and 09/30/22 08/24/22 increased enrichment technical and regulatory issues. The workshop also provided a public forum for discussions between the NRC, industry, and other stakeholders.
Pro jected Activities for the Next Two Re porting Periods (01 and 02 FY 2023 )
Projected ATF Activities Projected Completion Date
Complete review of the DN30-X transportation package that, if approved, would be used to transport uranium hexafluoride with an 12/30/22 enrichment up to 20 weiqht-precent uranium-235 ( ML21181A001 ).
Participate in the NRC Regulatory Information Conference (RIC) to provide stakeholders an opportunity to learn about the progress of ATF licensing activities and technologies to date and the activities that support efficient licensing of ATF concepts. Through participation at the 03/14/23 RIC, the NRC staff will communicate about ATF readiness activities, planned stakeholder engagements, the NRC's projected licensing timelines, and an y challen ges to A TF de ploy ment timelines.
Hold a Commission meeting to provide an update on the status and 03/31/23 issues associated with the path to licensing ATF conce pts.
2-4 Digital Instrumentation and Control
The NRC staff continues to complete digital instrumentation and control (l&C) infrastructure improvements to address commercial grade dedication of digital equipment and protection against common cause failure (CCF). While some infrastructure improvement activities continue, the staff is transitioning to using the improved infrastructure to support the review of licensees' digital l&C modernization LARs. These activities support the NRC's vision to establish a modern, risk-informed regulatory structure with reduced uncertainty that will enable the expanded safe use of digital technologies.
During the reporting period, the NRC staff issued Regulatory Guide 1.250, "Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants
( ML22153A408 ). RG 1.250 is a new regulatory guide which endorses, with clarifications, Nuclear Energy Institute (NEI) 17-06, "Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications," Revision 1, issued December 2021 ( ML21337A380 ). The NRC staff also continued the development of DG-1374 to consider endorsement of Institute of Electrical and Electronics Engineers Standard 7-4.3.2, "Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations." DG-1374, if finalized, will be issued as Revision 4 to RG 1.152, "Criteria for Use of Computers in Safety Systems of Nuclear Power
10 Plants." In addition, the NRC staff issued SECY-22-0076, "Expansion of Current Policy on Potential Common-Cause Failures in Digital Instrumentation and Control Systems"
( ML22164B003 ), for the Commission's consideration concerning new approaches to address digital l&C CCF to better accommodate risk-informed approaches in the digital l&C policy contained in the Staff Requirements Memorandum (SRM) to SECY-93-087 (ML003708056 ).
Several licensees are planning for digital upgrades. On July 30, 2022 (ML22213A045 ), Florida Power & Light Company (FPL) submitted LARs for Turkey Point Nuclear Plant, Units 3 and 4
{Turkey Point). The LARs, if approved, would permit the use of digital l&C for the reactor protection system, engineered safety features actuation system, and nuclear instrumentation system at Turkey Point. The NRC staff conducted an acceptance review of the Turkey Point LARs. The acceptance review was completed on October 13, 2022 (ML22280A108 ).
In addition, on September 26, 2022 ( ML22269A569 ), Constellation Energy Generation, LLC submitted LARs for Limerick Generating Station, Units 1 and 2 (Limerick) to revise the licensing and design basis to incorporate proposed digital modifications. The LARs also request other changes to plant functions and the reactivity control system. The NRC staff is conducting an acceptance review of the Limerick LARs. The acceptance review is currently scheduled to be completed by the end of November 2022.
Activities Planned and Com pleted for the Re porting Period (Q4 FY 2022 )
Digital l&C Activities Projected Completion Date Completion Date
Review NEI 17-06, "Guidance on Using IEC 61508 SIL Certification to Support the Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Related Applications," and consider endorsement throu g h issuance of an RG.
- Briefed Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on 07/22/22 07/21/22 Dig ital l&C on DG-1402.
- Issued RG 1.250, "Dedication of Commercial-Grade Digital Instrumentation 12/30/22 10/25/22
and Control Items for Use in Nuclear Power Plants." (ML22153A408 )
Consideration of Current CCF Policy in SRM to SECY-93-087
- Submitted SECY paper to the Commission for its consideration (SECY-22-0076) 07/26/22 08/10/22 14
{ ML22164B003 )
Digital Modernization LAR Usi ng the Im proved Digital Re gu latory Infrastructure 15
13 This activity was not identified as a projected activity in the previous report because the ACRS had not yet decided whether a full committee meeting on the RG was necessary.
14 The activity was completed on August 10, 2022, rather than the projected completion date of July 26, 2022, to allow additional time for staff review.
15 Activities reported in this section are related to planned or submitted digital changes for which the licensee is using some portion of the modernized digital regulatory infrastructure.
11 Digital l&C Activities Projected Completion Date Completion Date
- Conducted ninth pre-application meeting with Constellation on the planned digital 08/31/2022 09/08/22 16
l&C LAR for Limerick Generating Station, Units 1 and 2.
- Issued a staff decision on acceptability for review of the NextEra/FPL LAR for digital modernization project at Turkey Point 10/15/22 17 10/13/2022 Units 3 and 4 within 60 days of submission b y licensee.
Pro iected Activities for the Next Two Re porting Periods (01 and Q2 FY 2023 )
Projected Digital l&C Activities Projected Completion Date
DG-137 4 (Revision 4 to RG 1.152, "Criteria for Use of Computers in Safety Systems of Nuclear Power Plants")
- Brief ACRS Subcommittee on Digital l&C to discuss DG-1374. 11/17/22 18 Digital Modernization LAR Using the Improved Digital Regulatory lnfrastructure19
- Issue a staff decision on acceptability for review of the Constellation LAR for digital modernization project at Limerick 11/30/22 20 Units 1 and 2 within 60 days of submission by licensee.
2-5 Vogtle Electric Generating Plant Units 3 and 4
The NRC issued two combined licenses (COLs) to Southern Nuclear Operating Company (SNC) and its financial partners on February 10, 2012, for two AP1000 units to be built and operated at the Vogtle site near Augusta, GA. SNC projects the start of commercial operations for Vogtle Unit 3 in 01 FY 2023. SNC projects Vogtle Unit 4 to begin commercial operations in Q4 FY 2023. The NRC staff adjusted the agency's activities and associated milestone dates to reflect the revised schedule.
On August 3, 2022, the NRC issued Title10 of the Code of Federal Regulations (10 CFR) 52.103(g), "Operation under a combined license," finding for Vogtle Unit 3
( ML20290A282 ). This was the first such finding for a Part 52 licensee. It allows SNC to load fuel and operate Vogtle Unit 3 in accordance with the terms and conditions of the COL. The NRC issued the finding after verifying that all the acceptance criteria in the inspections, tests,
16 The activity was completed on September 8, 2022, rather than the projected completion date of August 31, 2022, because the licensee asked that the meeting be moved from August to September.
17 The projected completion date provided in the previous report was an estimate. The projected completion date was changed from September 30, 2022, to October 15, 2022, after the NRC staff determined that supplemental information was necessary as documented in a letter to the licensee. issued on September 15, 2022 ( ML22255A050 ).
18The projected completion date was modified from October 21, 2022, to November 17, 2022, to accommodate ACRS availability.
19Activities reported in this section are related to planned or submitted digital changes for which the licensee is using some portion of the modernized digital regulatory infrastructure.
20 The projected completion date is an estimate and assumes that the licensee will not supplement the LAR during the acceptance review.
12 analyses, and acceptance criteria (ITMC} in the Vogtle Unit 3 COL were met. The NRC describes the basis for this finding in the 10 CFR 52.103(g) basis document ( ML20290A276 ).
Upon the issuance of this finding, the NRC's oversight of Vogtle Unit 3 transitioned from the Construction Reactor Oversight Process to the Reactor Oversight Process (ROP). The NRC placed Vogtle Unit 3 in the Licensee Response Column of the ROP's Action Matrix. In October 2022, SNC completed Vogtle Unit 3 fuel load. NRC will continue to provide oversight for Vogtle Unit 3. For Vogtle Unit 4, the NRC continues to perform ITMC inspections and review ITMC closure notifications.
Activities Planned and Com p leted for the Re porting Period (04 FY 2022 )
Vogtle Electric Generating Plant Units 3 and 4 Projected Completion Date Activities Completion Date Issued a letter regarding Vogtle Unit 3's transition to the operating reactor assessment program 08/31/22 07/29/22 (ML22188A171 ).
Issued a finding in accordance with 10 CFR 52.103(g), which allows the licensee to operate Vogtle Unit 3 in accordance with the terms 08/31/22 08/03/22 and conditions of the license, after the NRC found that all the acceptance criteria in the Vogtle Unit 3 COL were met ( ML20290A282 ).
Completed the SE of a request from SNC to adopt an alternative to the requirements associated with testing of main turbine system valves for Vogtle 10/08/22 09/14/22 Units 3 and 4 (VEGP 3&4-IST-AL T-02)
{ ML22098A144 ).
Pro jected Activities for the Next Two Re porting Periods (01 and Q2 FY 2023 )
Projected Vogtle Electric Generating Plant Units 3 and 4 Projected Activities Completion Date Complete the review of a LAR and exemption request for Vogtle Unit 4 to eliminate and consolidate electrical IT MC based on lessons 01/07/23 learned from Vogtle Unit 3 (LAR 22-003).
A COL allows a licensee to construct a plant and to operate it once construction is complete if certain standards identified in the COL are satisfied. These standards are called ITMC. The majority of IT MC are from the design certification for the particular reactor technology that a plant uses. Throughout the construction process, NRC inspectors will perform inspections based on Ins pection Manual Cha pter 2503, "Construction Inspection Program: Inspections of Inspections, Tests, Analyses and Acceptance Criteria (ITMC) Related Work," and the NRC's Construction Ins pection Pro g ram at the plant site to confirm that the licensee has successfully completed the IT MC.
Additional information on the IT MC process as well as closure for Vogtle Units 3 and 4 is available at https://www.nrc. g ov/reactors/new-reactors/oversi q ht/itaac.html.
13 Number of ITAAC Total Inspections ITAAC ITAAC Unit Remaining Requiring Inspections Inspection Completed 21 lnspected 22 Closed 23 Vogtle 3 0 10 1 9 Vogtle 4 115 13 8 9
ITAAC Reviews Com p leted for the Re porting Period (04 FY 2022 )24
The table below provides ITAAC closure notification reviews completed during the reporting period for Vogtle Units 3 and 4, including the date when the NRC received the ITAAC closure notice and the date when the review was completed.
Unit ITAAC No. Received Date Approval Date 25 Vogtle 3 2.2.01.05.i 06/17/22 06/21/22 Vogtle 3 3.3.00.07c.ii.a 05/19/22 06/21/22 Vogtle 3 3.2.00.01e 06/03/22 06/21/22 Vogtle 3 3.3.00.07ac 06/17/22 06/21/22 Vogtle 3 3.3.00.07bc 06/17/22 06/21/22 Vogtle 3 3.3.00.07c.i.b 06/17/22 06/21/22 Vogtle 3 2.5.02.08b.ii 06/15/22 06/22/22 Vogtle 3 3.3.00.07d.ii.c 06/17/22 06/22/22 Vogtle 4 2.3.10.02a 06/24/22 06/27/22 Vogtle 3 2.6.03.02.i 06/23/22 06/27/22 Vogtle 3 2.5.02.06a.ii 06/23/22 06/29/22 Vogtle 4 2.2.03.09a.ii 07/01/22 07/05/22 Vogtle 4 2.5.02.08b.i 07/05/22 07/06/22 Vogtle 4 2.3.04.11 07/06/22 07/07/22 Vogtle 4 2.1.02.08d.v 07/08/22 07/11/22 Vogtle 3 3.3.00.07d.iv.b 07/15/22 07/19/22 Vogtle 4 3.3.00.02f 07/15/22 07/20/22 Vogtle 4 2.2.01.07.i 07/14/22 07/25/22 Vogtle 3 3.3.00.07bb 07/20/22 07/26/22 Vogtle 3 3.3.00.07c.i.a 07/20/22 07/26/22
21 This column includes all inspections related to Vogtle Units 3 and 4 completed during the reporting period; the column is not limited to ITAAC (e.g., quality assurance inspections).
22 "IT AAC Inspected" refers to the number of IT AAC that were inspected as part of ongoing inspections and does not indicate that all inspections were completed for those ITAAC. Only "targeted ITAAC" - ITAAC selected for inspection by the NRC staff - are included in this count.
23 "ITAAC Inspection Closed" refers to the number of ITAAC for which all associated inspections have been completed during the reporting period.
24 This table accounts for the total number of IT AAC that SNC provided closure notifications for and that the NRC verified. This includes both ITAAC that were selected for inspection by the NRC staff (targeted ITAAC) and ITAAC that were not selected for inspection by the NRC staff (non-targeted ITAAC). This differs from the previous table, where the "ITAAC Inspected" column is the number of targeted ITAAC that were inspected during the designated reporting period.
25 Several ITAAC Closure Notification Reviews completed in June 2022 were inadvertently not included in the last report and are included in this report for completeness.
14 Vogtle 3 3.3.00.07ab 07/20/22 07/26/22 Vogtle 3 3.3.00.07ba 07/21/22 07/26/22 Vogtle 3 3.3.00.07aa 07/21/22 07/26/22 Vogtle 4 3.2.00.02 07/22/22 07/27/22 Vogtle 3 3.3.00.07d.ii.b 07/28/22 07/28/22 Vogtle 4 2.2.01.11 a.i 07/15/22 07/28/22 Vogtle 3 3.3.00.07d.iii.b 07/28/22 07/29/22 Vogtle 3 3.3.00.07d.iii.a 07/29/22 07/29/22 Vogtle 3 3.3.00.07d.ii.a 07/29/22 07/29/22 Vogtle 4 2.3.07.07b.i 07/29/22 08/01/22 Vogtle 4 2.3.07.07b.vii 07/29/22 08/01/22 Vogtle 4 2.6.05.03.i 08/02/22 08/03/22 Vogtle 4 2.2.02.07a.iii 08/05/22 08/08/22 Vogtle 4 2.3.15.03 08/12/22 08/15/22 Vogtle 4 2.5.01.03a 08/12/22 08/15/22 Vogtle 4 2.5.04.01 08/17/22 08/18/22 Vogtle 4 2.3.04.04.i 08/18/22 08/19/22 Vogtle 4 2.2.03.08c.iii 08/18/22 08/19/22 Vogtle 4 2.3.06.12a.i 08/18/22 08/19/22 Vogtle 4 2.5.01.03e 08/18/22 08/19/22 Vogtle 4 2.2.02.05c 08/26/22 08/30/22 Vogtle 4 2.6.09.13c 08/12/22 09/01/22 Vogtle 4 2.3.04.02.i 09/01/22 09/02/22 Vogtle 4 3.3.00.02a.ii.e 09/02/22 09/06/22 Vogtle 4 2.2.03.08c.vi.03 09/07/22 09/09/22 Vogtle 4 2.5.01.04 09/01/22 09/12/22 Vogtle 4 3.3.00.07e 09/02/22 09/22/22 Vogtle 4 E.3.9.05.01.04 09/26/22 09/28/22
Vo q tle Units 3 and 4 LAR Reviews Com pleted (04 FY 2022 )
Number of LAR Reviews Forecast to be Number of LAR Reviews that Were Completed Completed in the Reporting Period in the Reporting Period
0 0
2-6 NuScale Small Modular Reactor (SMR) Design Certification
On March 15, 2017, the NRC accepted the NuScale Power, LLC (NuScale) application for a SMR design certification review. The NRC staff completed the final SE Report on August 28, 2020 ( ML20023A318 }, and issued a standard design approval to NuScale on September 11, 2020 ( ML20247J564 ). The draft final rule was provided to the Commission on July 1, 2022, for its consideration ( ML22004A002 ). On July 29, 2022, the Commission directed the staff to issue a final rule that certifies NuScale's SMR design for use in the United States
( ML22210A158}. The staff expects the final rule will be published in the Federal Register (FR)
15 by November 25, 2022. The design certification's effective date is 30 days after the publication of the final rule in the FR.
Activities Planned and Com p leted for the Re porting Period (04 FY 2022 )
NuScale SMR Design Certification Activities Projected Completion Date Completion Date
Provided the Commission the draft final rule for its N/A26 07/01/22 consideration ( ML22004A002 ).
Pro jected Activities for the Next Two Re porting Periods (Q1 and Q2 FY 2023 )
Projected NuScale SMR Design Certification Activities Projected Completion Date Publish final rule in the FR. 11/25/22
2-7 Advanced Nuclear Reactor Technologies
The NRC continues to make significant progress in preparation for reviewing non-light-water reactor (non-LWR) designs, consistent with the NRC staff's vision and strategy (ML16356A670 )
and implementation action plans to achieve non-LWR safety review readiness. 27 During this reporting period, the NRC staff continued its extensive stakeholder engagement, including holding several public meetings and workshops regarding various advanced reactor topics, development of Framework A (the probabilistic risk assessment (PRA)-led licensing approach) and Framework B (the licensing approach where risk insights are used in a supporting role) of 10 CFR Part 53, "Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors," preliminary proposed rule, and development of guidance for the content of advanced reactor licensing applications.
The NRC staff released the draft proposed rule package for 10 CFR Part 53 ( ML22272A034 ) on September 29, 2022, to support the ACRS Regulatory Rulemaking, Policies and Practices:
Part 53 Subcommittee (formerly the Future Plant Designs Subcommittee) meeting scheduled for October 18-19, 2022, and the ACRS full committee meeting scheduled for the first week of November 2022.
On July 21, 2022, the Commission held a briefing on 10 CFR Part 53 Licensing and Regulation of Advanced Nuclear Reactors consisting of a diverse external panel and an NRC staff panel
( ML22196A025 }. In addition, the NRC staff continued to engage stakeholders on portions of the 10 CFR Part 53 preliminary proposed rule language, including technical, licensing, and administrative requirements during public meetings conducted by the staff on July 28, 2022, and August 18, 2022 ( ML22195A005 and ML22229A507 ). The NRC staff continues to assess and consider diverse stakeholder feedback received throughout the public comment period on the preliminary proposed rule language, which closed on August 31, 2022.
In addition, the NRC staff briefed the ACRS full committee on Part 53 Framework B and Subpart F of Framework A on July 6, 2022. On August 2, 2022, the ACRS issued their fourth
26 In the Q2 FY 2022 report, the projected completion date for this activity was to be determined as the schedule for providing the draft final rule to the Commission was being revised to resolve technical comments.
27 The NRC's public website lists the implementation action plans and is updated periodically to show the status of these activities ( http s://www.nrc. gov/reactors/new-reactors/advanced/details.html#visStra t).
16 interim letter on 10 CFR Part 53 (ML22196A292 ), which included eight conclusions and recommendations. The NRC staff issued a response to the ACRS letter to address the ACRS recommendations ( ML22249A073 ). Details of this and previous ACRS meetings can be found on the NRC's public website ( https://www.nrc. gov/readin g -rm/doc collections/acrs/a qenda/index. htm I).
The NRC staff is scheduled to provide the Commission the Part 53 draft proposed rule package by February 2023 for its consideration. Once the Commission votes, the resulting proposed rule will be issued for public comment. After the staff addresses the public comments, the draft final rule package, including key guidance, will then be submitted to the Commission for consideration by December 2024. The NRC staff's goal is to issue the final rule by July 2025.
Further details about the Part 53 rulemaking schedule can be found on the NRC's public website ( https://www.nrc. gov/reactors/new-reactors/advanced/rulemakin g-and-g uidance/ part-53.htm l).
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 NRC's public website
( https://www.nrc. gov/reactors/new-reactors/advanced/details.html#stakeholder ). The NRC also holds frequent public meetings regarding the Advanced Reactor Content of Application Project (ARCAP). A list of these meetings and related preliminary draft guidance documents to support the meetings can be found on the NRC's public website ( https://www.nrc. gov/reactors/
new-reactors/advanced/details.html#advRxContentA pp Pro j).
Additionally, the NRC staff is preparing, through early interactions with reactor designers, to review specific advanced reactor designs. These pre-application interactions provide predictability in the licensing process through early identification and resolution of technical and policy issues that could affect licensing. Information on the reactor designers that have formally notified the NRC of their intent to engage in regulatory interactions can be found on the NRC's public website ( https://www.nrc. g ov/reactors/new-reactors/advanced/
on g oin g-licensing -activities/p re-a pp lication-activities.html).
This section also discusses the NRC staff's pre-application interactions and review activities before an application is accepted and docketed by the NRC staff. On August 12, 2022, Abilene Christian University (ACU) submitted an application to the NRC for a construction permit for a molten salt research reactor (MSRR) (less than 1 megawatt thermal power) to be located on the ACU campus in Abilene, TX ( ML22227A201 ). On September 27, 2022, the NRC staff notified ACU that it was pausing the acceptance review of the construction permit application to allow the applicant to provide supplemental technical information prior to making an acceptance determination on the application (ML22270A170 ). ACU intends for the purpose of the MSRR to accelerate the development and deployment of molten salt reactor systems through foundational research while also developing a new pipeline to a nuclear-qualified workforce. The MSRR is a single-region, graphite-moderated core, loop-type, thermal-spectrum reactor with a fluoride-based fuel salt flowing through a fuel circuit made from stainless steel. If this application is accepted and docketed, future application review activities will be discussed in section 2-8 of this report.
17 Activities Planned and Com p leted for the Re porting Period (Q4 FY 2022 )
Advanced Nuclear Reactor Technologies Projected Completion Date Activities Completion Date Submitted draft proposed rule providing the alternative physical security requirements for 07/29/22 08/02/22 28 advanced reactors to the Commission for its consideration ( M L21334A003 ).
Issued final SE to X-energy for its topical report on risk-informed performance-based approach 08/01/22 08/04/22 29
( ML22187A271 ).
Released draft proposed rule package for 10 CFR Part 53 to support stakeholder and ACRS 09/30/22 09/29/22 30 interactions in October 2022 (ML22272A034 ).
Pro jected Activities for the Next Two Re porting Periods ( 01 and 02 FY 2023 )
Projected Projected Advanced Nuclear Reactor Technologies Activities Completion Date Release a pre-decisional draft RG on technology-inclusive, risk-informed, and performance-based methodology for seismic design of advanced 10/31/22 reactors and seismically isolated nuclear power plants to support stakeholder en q a qement at a p ublic meetin g.
Issue draft RG (DG-1404) for potential endorsement of industry-led NEI 21-07, "Technology Inclusive Guidance for Non-Light Water Reactors," and 11/30/22 31 nine NRC-led ARCAP interim staff q uidance for public comment.
Complete acceptance review for ACU MSRR construction permit 11/30/22 a pp lication.
Publish the final RG (RG 1.246) for potential endorsement of the ASME Boiler and Pressure Vessel Code Section XI, Division 2, Reliability and 11/30/22 32 Inte g rity Mana gement standard.
Release draft interim staff guidance on material compatibility to support 11/30/22 stakeholder engagement.
Release draft interim staff guidance on facility training programs to support 11/30/22 stakeholder engagement.
Issue final SE to Kairos for its topical report on metallic material 11/30/22 qualification program.
28 The activity was completed on August 2, 2022, rather than the projected completion date of July 29, 2022, to support the development of comprehensive draft guidance and completion of the draft proposed rule package.
29 The activity was completed on August 4, 2022, rather than the projected completion date of August 1, 2022, to allow additional time for staff review.
30 This activity was inadvertently omitted as a projected activity in the previous report.
31 The projected completion date was extended from August 31, 2022, to November 30, 2022, due to prioritization of the development of Part 53 draft preliminary proposed rule text.
32 The projected completion date was extended from September 30, 2022, to November 30, 2022, to coincide with the projected publication of the 2019-2020 ASME Code final rule. The NRC's endorsement of the ASME Boiler and Pressure Vessel Code Section XI, Division 2, is dependent on the endorsement and conditions for the 2019 edition of ASME Boiler and Pressure Vessel Code Section XI, Division 1 via the 2019-2020 ASME Code final rule.
18 Projected Projected Advanced Nuclear Reactor Technologies Activities Completion Date Issue final SE to Kairos for its topical report on graphite materials 11/30/22 qualification.
Publish the final RG (RG 1.87, Revision 2) for potential endorsement of the American Society of Mechanical Engineers (ASME) Boiler and Pressure 12/30/22 Vessel Code Section Ill, Division 5, Hio h Tem perature Reactors.
Issue final SE to Kairos for its topical report on fuel qualification 12/30/22 methodology.
Issue NUREG/CR on Fuel Qualification for Molten Salt Reactors. 12/30/22 Submit SECY paper on options for a fusion regulatory framework to the 12/30/22 Commission for its consideration.
Issue final SE to X-energy for its topical report on transient and safety 01/20/23 analysis methodologies framework.
Submit draft proposed rule providing the 10 CFR Part 53 requirements for 02/23/23 advanced reactors to the Commission for its consideration.
Issue final SE to X-energy for its topical report on pebble fuel qualification 02/24/23 methodology.
Issue draft interim staff guidance on non-LWR PRA standard applicability 02/28/23 33 for initial licensing for public comment.
Issue final SE to X-energy for its topical report on control room staffing 03/25/23 analysis methodology.
2-8 Advanced Reactor Licensing Reviews
Kairos Hermes Construction Permit A pp lication Review
Kairos Power LLC (Kairos) submitted an application for a construction permit for the Kairos Power Fluoride Salt-Cooled, High Temperature Non-Power Reactor (Hermes). Kairos submitted applications documents to the NRC by letters dated September 29, 2021 (submitting the Preliminary Safety Analysis Report) ( ML21272A375 ), and October 31, 2021 (submitting the Environmental Report) (ML21306A131 ).
The NRC staff performed an acceptance review of the Hermes construction permit application and docketed the application on November 29, 2021 ( ML21319A354 ). On December 15, 2021,
the staff issued a letter to Kairos (ML21343A214 ) providing the schedule and resource estimates for the review. The NRC staff is currently conducting a detailed technical review of the safety of the Hermes design, which will lead to a SE report. The NRC staff performed a review of the effects of the Hermes design on the environment and issued a draft environmental impact statement ( ML22259A126 ) for public comment on September 29, 2022 (87 FR 59124 ).
Application documents and information on the review are available on the NRC's public website
( https://www.nrc. g ov/reactors/non-power/hermes-kairos.html ).
33 This activity has been revised from the previous report to clarify the staffs plans. The projected completion date has also been adjusted from the previous report to allow additional time for staff review.
19 Activities Planned and Com p leted for the Re porting Period (04 FY 2022 )
Advanced Reactor Licensing Review Activities Projected Completion Date Com p letion Date Issued the Hermes draft environmental impact 10/28/22 9/29/22 statement for public comment ( ML22259A126 ).
Pro jected Activities for the Next Two Re porting Periods (01 and 02 FY 2023 )
Projected Advanced Reactor Licensing Review Activities Projected Completion Date Complete regulatory audits and evaluate any additional docketed 11/15/22 information necessa for the re aration of the SE re ort.
Release draft SE report for the Hermes construction permit 02/23/23 a lication to su ort en a ement with the ACRS.
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 NRC staff developed recommendations for proposed changes to the ROP in SECY-18-0113, "Recommendations for Modifying the Reactor Oversight Process Engineering Inspections" (ML18144A567 ), and SECY-19-0067, "Recommendations for Enhancing the Reactor Oversight Process" ( ML19070A050 ). The staff requested to withdraw these papers, and on August 5, 2021, the Commission approved the staff's proposed withdrawal (ML21217A284 ). During this reporting period, the staff submitted several SECY papers revisiting the recommendations in these withdrawn papers
( ML22188A221, ML22145A448, and ML22189A201 ); the staff's plan to revisit these recommendations by the end of FY 2022 was discussed with external stakeholders at the January, March, May and July ROP bi-monthly public meetings. 34 The staff also continues to assess and improve the ROP as part of its normal work practices through the NRC's transformation activities, stakeholder correspondence, feedback from ROP public meetings, and the ROP self-assessment program. The staff will seek Commission approval of changes to the ROP, or provide the Commission with notification of changes, in accordance with Management Directive/Directive Handbook 8.13, "Reactor Oversight Process" (ML17347B670 ).
Activities Planned and Com pleted for the Re porting Period (04 FY 2022 )
ROP Activities Projected Completion Date Completion Date
Submitted a paper to the Commission 09/30/22 09/16/22 recommending that the minimum four quarter requirement for Greater-Than-Green findings, coupled with a revision to the treatment of Greater-Than-Green performance indicators, should be eliminated (ML22188A221 ).
34 The ROP bi-monthly public meeting summaries are available at ML22034A766, ML22091A184, ML22159A212,
and ML22221A224.
20 ROP Activities Projected Completion Date Completion Date
Submitted a paper to the Commission with options for the frequency of problem identification and 08/19/22 09/20/22 35 resolution team inspections ( ML22145A448 ).
Submitted a paper to the Commission 08/31/22 09/22/22 36 recommending that a revision should be made to the emergency preparedness significance determination process (SOP ) ( ML22189A201 ).
Pro jected Activities for the Next Two Re porting Periods (Q1 and Q2 FY 2023 )
Projected ROP Activities Projected Completion Date
Complete a ROP program area evaluation on the SOP timeliness. 11/30/22 37
Complete an effectiveness review of the incorporation of safety culture 12/15/22 38 oversight into the ROP.
Submit a paper to the Commission recommending whether the Alert and 12/30/22 Notification System Performance Indicator should be eliminated.
2-10 Backfit
The NRC's backfitting rules are codified in 10 CFR 50.109, "Backfitting," 70. 76, "Backfitting,"
72.62, "Backfitting," and 76. 76, "Backfitting." The backfitting rules define backfitting "as the modification of or addition to systems, structures, components, or design of a facility; or the design approval or manufacturing license for a facility; or the procedures or organization required to design, construct or operate a facility; any of which may result from a new or amended provision in the Commission's regulations or the imposition of a regulatory staff position interpreting the Commission's regulations that is either new or different from a previously applicable staff position.... "39 The rules require, in the absence of an applicable exception, an analysis showing that the backfit would result in a substantial increase in the overall protection of the public health and safety or the common defense and security and that the increased protection warrants the direct and indirect costs of implementation. There are similar requirements, referred to as "issue finality," that apply when there are new or amended requirements for licenses, permits, and design approvals and certifications issued under 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants."
The Commission changed its backfitting and issue finality policy as well as its policy on "forward fits," which it defined as requirements or staff interpretations of requirements imposed as a
35 The activity was completed on September 20, 2022, rather than the projected completion date of August 19, 2022, to allow additional time for staff review.
36 The activity was completed on September 22, 2022, rather than the projected completion date of August 31, 2022, to allow additional time for staff review.
37 The projected completion date was extended from September 30, 2022, to November 30, 2022, due to prioritization of the ROP enhancement papers.
38 The projected completion date was extended from September 30, 2022, to December 15, 2022, due to prioritization of the ROP enhancement papers.
39 1 O 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.
21 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"
{ ML180938087 ). The NRC completed draft NUREG-1409, "Backfitting Guidelines," Revision 1, in March 2020 and issued a notice of availability in the FR for public comment { ML18109A498 ).
This revision would provide additional guidance for the NRC staff on how to implement the Commission's backfitting and issue finality regulations and policies and forward fitting policy, including how to process violations that are contested based on claims of unjustified backfitting.
The NRC received approximately 250 individual comments from members of the public, licensees, and industry representatives. The NRC staff evaluated the comments, updated the draft NUREG, and provided the Commission with the staff's proposed NUREG-1409, Revision 1 (Final Report) ( ML21006A431 ). This revised document is currently before the Commission for its consideration.
Activities Planned and Com pleted for the Re porting Period (04 FY 2022 )
Backfit Activities Projected Completion Date Completion Date
None.
Pro jected Activities for the Next Two Re porting Periods (01 and Q2 FY 2023 )
Projected Backfit Activities Projected Completion Date
Issue the Fitness-for-Duty Drug Testing Requirements 12/29/22 40 Final Rule, which will constitute backfitting.
2-11 Risk-informed Activities
The NRC staff continues to make progress to advance the use of risk insights more broadly to inform decision-making. There are numerous activities ranging in scope from agencywide initiatives, such as the "Be riskSMART" initiative, which is part of the transformation efforts discussed in section 2-1, to the advanced reactor risk-informed activities listed in section 2-7, to individual undertakings in program and corporate offices.41 The NRC staff continues to implement and track the use of the agencywide Be riskSMART risk-informed decision-making framework to inform a broad range of decisions spanning technical, legal, and corporate arenas.
For example, the NRC staff continues to review and approve applications to adopt advanced risk management programs such as 10 CFR 50.69, "Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors," and Risk-Informed Technical Specifications Initiative 4b, 42 that provide for operational flexibilities that enhance safety by ensuring that power reactor licensees and the NRC prioritize the most risk significant issues. In addition, the staff has successfully completed its reviews and approved the
40 The Commission approved an extension request from October 31, 2022, to December 29, 2022, to allow for procedural reviews.
41 The NRC maintains a listing of risk-informed activities that is updated annually at http s://www.nrc. g ov/
about-nrc/re g ulato ry /risk-informed/rpp.html.
42 A description of these and other operating reactors risk-informed initiatives is available at htto s://www.nrc. gov/about-nrc/re g ulato ry /risk-informed/rpp/reactor-safe ty -o peratinq.html. To date, the NRC has approved 28 and 19 applications enabling licensees to adopt 10 CFR 50.69 and Risk-Informed Technical Specifications Initiative 4b, respectively.
22 applications submitted by all operating reactor licensees to adopt a risk-informed surveillance frequency control program, Risk-Informed Technical Specifications Initiative 5b.
Activities Planned and Com pleted for the Re porting Period (Q4 FY 2022 )
Risk-Informed Activities Projected Completion Date Completion Date
Completed LIC-504 assessment of the risk significance of high energy arcing faults (HEAF).
Issued report concluding that there is no significant increase in total HEAF risk warranting the need for any additional regulatory requirements. In addition, 07/22/22 07/22/22 evaluated various communication options that would enable the staff to share its insights with external stakeholders for licensee consideration to implement effective steps to further reduce and/or mitigate HEAF risks ( ML22200A272 ).
Developed an Assessments and Observations report on early lessons learned during acceptance reviews from the pilot program for the Risk Tool to 09/30/22 08/03/22 risk-inform technical reviews for spent nuclear fuel dry storage.
Completed Be riskSMART evaluation of Inspection Procedure (IP) 71152, "Problem Identification and Resolution," team inspection periodicity and 08/19/22 09/20/2243 submitted a paper to the Commission
( ML22145A448 ).
Submitted a paper to the Commission recommending whether to revise the Emergency Preparedness Significance Determination Process 08/31/22 44 09/22/22 Failure to Comply assessment methodology to risk-inform areas susceptible to Greater-Than-Green inspection findings ( ML22189A201 ).
43 The activity was completed on September 20, 2022, rather than the projected completion date of August 19, 2022, to allow additional time for staff review.
44 The previous report erroneously included September 30, 2022, as the projected completion date for this activity.
23 Proiected Activities for the Next Two Re o ortina Periods (Q1 and Q2 FY 2023 )
Projected Risk-Informed Activities Projected Com p letion Date Complete the revision of four materials IPs associated with Inspection Manual Chapter 2800 (specifically, IP 87121, "Industrial Radiography Programs"; IP 87122, "lrradiator Programs"; IP 87125, "Materials Processor/Manufacturer Programs"; and IP 87127, "Radiopharmacy 12/30/22 Programs"). The NRC staff is developing risk modules in each IP, with each module focusing on the risks of the relevant types of radioactive materials and their usa Qe.
Develop a seminar for new staff to provide an overview of the Risk Tool and its use to risk-inform technical reviews for spent nuclear fuel 12/30/22 dry storage.
2-12 Coronavirus Disease (COVID-19) Pandemic
The NRC continues to develop and implement precautionary measures in response to the pandemic to help protect the health and safety of our workforce consistent with guidance provided by the Federal Government, including the Centers for Disease Control and Prevention (CDC), as well as considerations of State and local conditions around NRC facilities. The NRC is monitoring the effects of the COVID-19 pandemic on NRG-licensed activities as well as actions taken in response to State, local, and site-specific conditions. The NRC is poised to take additional steps as warranted without compromising its public health and safety mission.
NRC Occu panc y of Facilities
During this reporting period, the NRC continued to operate in a hybrid work environment at all locations, combining telework and in-office staff presence. The guidance for inspection program implementation remains in effect in accordance with memorandum, "Implementation of Inspection Programs Following Re-Entry from the Public Health Emergency for the Reactor Safety Program" ( ML21295A302 ). The agency continues to closely monitor guidance from the Federal Government's Safer Federal Workforce Taskforce, the CDC, and the Occupational Safety and Health Administration to facilitate a healthy and safe physical workspace.
Licensin g and Oversig ht Items of Interest
The NRC staff took steps to identify areas of our regulations that proved challenging during the pandemic, and the areas where temporary flexibilities, such as exemptions, would not compromise the ability of licensees to maintain the safe and secure operation of NRG-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, webcasts, and letters. In addition, these processes and the approved flexibilities are posted and updated on the NRC public website ( https://www.nrc. gov/about-nrc/covid-19/ ).
The NRC has also developed portions of its website devoted to the regulatory activities taken in response to the COVID-19 pandemic. Specific posts related to nuclear power p lant licensees, nuclear materials licensees, and security and emer g enc y p reparedness are available to keep the public informed on how the NRC adapted its regulatory approach during the pandemic.
Between July 1 and September 30, 2022, the NRC did not receive any requests for COVID related flexibilities from nuclear materials or nuclear reactor licensees. A complete list of
24 licensing requests approved by the NRC in response to the COVID-19 pandemic is available on the NRC public website at https://www.nrc. gov/about-nrc/covid-19/.
Re g ulato ry Activities Taken in Res ponse to the COVID-19 Pandemic Durin g the Re porting Period
Number of COVID-19 Average Number of Licensee Type Requests Approved During Days to Review the Reporting Period COVID-19 Re q uests 45 Power Reactor 0 N/A Non-Power Reactor 0 N/A Other (e. g., to pical reports) 0 N/A Decommissioning of Nuclear 0 N/A Facilities and Uranium Recove ry Storage and Transportation of 0 N/A S o ent Nuclear Fuel Fuel Cy cle Facilities 0 N/A Medical, Industrial and Academic Uses of Nuclear Materials and 0 N/A A greement States
45 This average is calculated based on the dates the request is received and the review is completed; review time may be longer in cases where a supplement to a request is received after the initial submission date.
25 Enclosure 3 - Summary of Activities
3-1 Reactor Oversight Process (ROP) Findings
The table below provides the calendar year (CY) ROP findings for the year-to-date and 3-year rolling metrics.46
Location Number of Findin gs CY 2019 CY 2020 CY 2021 CY2022 Nationall y Total 440 291 278 265 47 95 50 61 60 White 0 0 1 0 Yellow 0 0 0 0 0 0 0 0 Region I Greater-Than-Green 0 0 0 0 Security Total 95 50 62 60 No. of Units 24 22 48 2149 20 50 O peratin Durin g CY 110 77 69 59 White 1 2 0 0 Yellow 0 0 0 0 0 0 0 0 Region II Greater-Than-Green 0 1 0 0 Securi ty Total 111 80 69 59 No. of Units 33 33 33 33 O peratin Durin g CY 96 51 65 51 White 1 0 0 1 Yellow 0 0 0 0 0 0 0 0 Region Ill Greater-Than-Green 0 0 1 1 Securi ty Total 97 51 66 53 No. of Units 23 22s1 22 22 O o eratino Durin g CY
46 For the purposes of this report, the total number of findings per CY is based on the year in which an inspection report was issued instead of the year in which a finding was identified. The latter approach was used to describe the inspection finding trend in SECY-22-0029, "Reactor Oversight Process Self-Assessment for Calendar Year 2021"
( ML22033A288 ), which shows the first year-over-year increase in green inspection findings since CY 2011.
47 The inspection reports for the third quarter of CY 2022 will continue to be finalized through November 15, 2022.
The report for the next reporting period will be updated to include any additional findings from the third quarter of CY2022.
48 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.
49 The reduction of one unit for CY 2021 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 2 on April 30, 2020.
50 The reduction of one unit for CY 2022 reflects the permanent shutdown of Indian Point Nuclear Generating Unit 3 on April 30, 2021.
5 1 The reduction of one unit for CY 2020 reflects the permanent shutdown of Duane Arnold on August 10, 2020.
26 Location CY 2019 CY 2020 CY 2021 CY 2022 137 110 81 92 White 0 0 0 1 Yellow 0 0 0 0 0 0 0 0 Region IV Greater-Than-Green 0 0 0 0 Securi t Total 137 110 81 93 No. of Units 18 18 18 18 0 CY
3-2 Licensing Actions
The tables below provide the status of licensing actions organized by licensing program.
Consistent with Section 102(c) of the Nuclear Energy Innovation and Modernization Act (NEIMA), the licensing actions referenced in this section include "requested activities of the Commission" for which the U.S. Nuclear Regulatory Commission (NRC) staff issues a final safety evaluation (SE). These totals do not include license amendment requests (LARs ), as they are addressed separately in section 3-3. "Total Inventory" refers to the total number of licensing actions that are open and accepted by the NRC at the end of the quarter. "Licensing Actions Initiated During the Reporting Period" are the number of licensing actions (regardless of acceptance) that are received by the NRC during the reporting period.
O perating Reactors
Percentage Percentage of Licensing Licensing of Licensing Licensing Actions Actions Actions Reporting Total Initiated Completed Completed Actions Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule 52 Schedule Quarter (Q) 1 fiscal 132 33 107 100% 94%
year (FY) 2022 Q2 FY 2022 144 103 93 100% 95%
Q3 FY 2022 136 41 43 100% 100%
04 FY2022 124 28 32 100% 81%53
52 The "established schedule" is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
53 This percentage is due to a smaller number of actions in the quarter and the disproportionate weight of a Dominion Fleet request involving six actions that required verification of referenced topical reports.
27 New Reactors
Percentage Percentage Licensing Licensing of Licensing of Licensing Actions Actions Actions Reporting Total Initiated Completed Completed Actions Completed Period Inventory During the During the Prior to the Prior to the Reporting Reporting Generic Established Period Period Milestone Schedule Schedule 01 FY2022 2 3 3 100% 100%
02 FY2022 1 0 154 N/A N/A 03 FY2022 155 1 1 100% 100%
04 FY2022 1 1 1 100% 100%
Fuel Facilities
Licensing Licensing Percentage of Percentage of Actions Actions Licensing Licensing Reporting Total Initiated Completed Actions Actions Completed Prior Completed Period Inventory During the During the to the Generic Prior to the Reporting Reporting Milestone Established Period Period Schedule Schedule 01 FY 2022 2 11 13 100% 92%56 02 FY2022 6 8 4 100% 75%57 Q3 FY2022 6 6 6 100% 100%
Q4 FY2022 8 8 6 100% 60%58
3-3 Licensing Amendment Request Reviews
The tables below provide the status of LARs organized by licensing program. Consistent with Section 102( c) of NEIMA, the LARs referenced in this section include "requested activities of the Commission" for which the NRC staff issues a final SE. The total inventory is the number of open LARs at the end of the quarter. LARs are included in the total inventory after they have been accepted by the NRC (the acceptance review period is generally 30 days after the application is submitted).
54 During the reporting period, the NRC staff denied, without prejudice, the Oklo Aurora combined license application and terminated all review activities.
55 The total inventory was erroneously reported as 2 instead of 1 in the previous report.
56 One licensing action was complex due to security issues, which resulted in it exceeding the established schedule by 17 days.
57 One licensing action exceeded the established schedule by 82 days due to additional time needed for the licensee to obtain signed financial documents from a third party.
58 Two fuel cycle licensing actions exceeded the established schedule by approximately one month due to a need to prioritize other work.
28 Operating Reactors
LARs LAR Percentage of Percentage of Reporting Total During the Completed Completed Prior Completed Submitted Reviews LAR Reviews LAR Reviews Period Inventory During the to the Generic Prior Reporting Reporting Milestone Established to the Period Period Schedule Schedule 59 Q1 FY 2022 317 105 81 99% 95%60 Q2 FY 2022 304 72 94 100% 99%
03 FY2022 289 78 93 100% 91%
04 FY2022 269 65 84 100% 93%
New Reactors
LARs LAR Percentage of Percentage of Reporting Total During the Completed Completed Prior Completed Submitted Reviews LAR Reviews LARReviews Period Inventory During the to the Generic Prior Reporting Reporting Milestone Established to the Period Period Schedule Schedule 01 FY 2022 0 0 1 100% 100%
02 FY 2022 0 0 0 N/A N/A 03 FY 2022 0 0 0 N/A N/A 04 FY2022 1 1 0 N/A N/A
Fuel Facilities
LARs LAR Percentage of Percentage of Reporting Total During the Completed Completed Prior Completed Submitted Reviews LAR Reviews LAR Reviews Period Inventory During the to the Generic Prior Reporting Reporting Milestone Established to the Period Period Schedule Schedule 01 FY 2022 5 5 13 100% 100%
02 FY2022 11 12 7 100% 100%
03 FY 2022 10 4 5 100% 60%61 04 FY2022 7 1 4 100% 75%62
59 The "established schedule" is the schedule communicated to the licensee and made publicly available at the completion of the acceptance review.
60 One review of an LAR that proposed a first-of-a-kind design exceeded the established schedule by 180 days. The NRC staff identified an issue that resulted in the licensee submitting an update that expanded the licensee's proposed submission and extended the staffs review. The staff issued the SE on February 28, 2022.
61 Reviews for two LARs exceeded the established schedule, one by 5 days and the other by 7 days, due to a need to prioritize other work.
62 One review of an LAR exceeded the established schedule by 26 days due to a need to prioritize other work.
29 3-4 Research Activities63
Summa ry of New Research Pro jects
During the reporting period, the Office of Nuclear Regulatory Research (RES) initiated research on or substantially revised the following projects:
Support in the Development and Enhancement of NRC Risk Analysis Tools
( NRR-2022-001 )
This research program update supports NRC capabilities and maintenance of risk tools used in the NRC's ROP and supports advancements in the use of risk insights in oversight and licensing activities. These research activities will enhance the NRC's capabilities in applying risk assessment to risk-informed regulatory programs, including the Significance Determination Process (SDP), the Accident Sequence Precursor program, and the Incident Investigation Program, and in evaluating Notices of Enforcement Discretion. The work performed under Importance to this research project is a critical element of the ROP as it provides the the NRC independent method to model risk for operating reactors and address Mission performance deficiencies and assess operating events. In addition, updated Standardized Plant Analysis Risk (SPAR) models will be used in ongoing or emerging risk assessment activities; SPAR model development and enhancements for new reactors is intended to support the implementation of the ROP as the reactors transition from design approval or certification into construction and operation or from construction to operation through the issuance of an operating license.
The closure and results from the prior program plan are provided in the Summary of Completed Research Projects below (Office of Nuclear Reactor Re g ulation ( NRR )-2015-009 ).
Maintainin g and u 12dating SPAR models: RES maintains and updates SPAR models. SPAR models will be modified, documented, tested, and reviewed in accordance with the appropriate guidance. Currently, six to eight SPAR models are updated per year. The goal is to slowly progress toward 12 SPAR model updates per year. The goal of 12 SPAR model updates per year is to increase SPAR model readiness, which in turn increases SDP efficiency by having the best available information. This task is a continuation of the previous program plan and is intended to Planned meet the goal of 12 SPAR model updates per year by incorporating plant Activities modifications, operating experience, state-of-the-art methods, and applicable internal and external hazards to reflect the current as-built, as operated plants.
Develo 12 ing and enhancin g SPAR models for new reactors: This task applies to development of and future enhancements to SPAR models for new reactors, while the first task above applies to SPAR models for operating reactors. This is a new task that will develop SPAR models for new reactors to su pp ort implementation of the ROP as the reactors
63 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.
30 transition from design approval or certification into construction and operation or from the construction to operation through issuance of an operating license.
Maintainin g and enhancin g SAPHIRE 64 : RES will update SAPHIRE biannually or more frequently based on software compatibility, security patches, or user input. RES will communicate updates to all active users and make the software available through the developer website. This task is a continuation of the previous program plan intended to maintain the SAPHIRE program by fixing software bugs and enhancing it to include the latest capabilities and probabilistic risk assessment (PRA) methods.
Develo p ing risk assessment g uidance: The objectives of this task are to develop guidance for the application of new or enhanced risk tools and methods and clarify or expand existing guidance based on lessons learned from field use. This task is a continuation of the previous program plan and will update existing guidance and will concentrate in the development of new guidance in risk assessment to provide consistent performance of risk assessment, model development, and knowledge management.
Level 3 PRA Pro ject knowled ge mana gement and transfer: RES will support knowledge management activities, including the transfer of knowledge on methods, models, and data used for the Level 3 PRA project. RES will leverage the Level 3 PRA model and risk insights to apply to new risk applications and research projects. This may take the form of guidance, model, and software enhancements and will be communicated through standing calls with regional staff, seminars, and counterpart meetings. This is a new task that supports knowledge management and transfer gained through the implementation of this project by incorporating the state-of-practice approaches from this project into existino risk tools, such as the SPAR models and SPAR-DASH.
Requesting Business Operating Reactors Line Estimated FY 2027 Com p letion Estimate of Total 52.9 Full-Time Equivalent (FTE) and $12.9M over a 5-year period Research Resources
64 A Risk and Reliability Assessment Tool
31 Support for Component Reliability and Integrity Assessment for Advanced Reactors (NRR-2022-009 )
The research activities will provide necessary information and tools to Importance to support NRC reviews related to advanced reactor technologies. The the NRC research activities will assist the NRC in understanding the risk and Mission reliability considerations for component performance and monitoring and will provide NRC reviewers with necessary methods and tools to support reg ulato ry review of non-li g ht-water reactor designs.
Activities include evaluating the use of Reliability Integrity Management for life cycle management of passive components, developing guidance Planned for evaluating the adequacy of applicants' approaches for setting Activities reliability targets, assessing the potential for stress relaxation cracking, and developing tools and technical basis to support integrity assessment of graphite.
Requesting New Reactors Business Line Estimated FY 2025 Com p letion Estimate of Total Research 3.6 FTE and $1.3M over a 3-year period Resources
Radiation Protection Computer Code Analysis and Maintenance Program (RAMP)
Support for Decommissioning Computer Codes (Office of Nuclear Material Safety and Safe g uards (NMSS)-2022-008 )
Importance to The purpose of this work is to provide technical support, maintenance, the NRC training, and code distribution of the decommissioning and the uranium Mission recove ry com puter codes via the RAMP.
The planned activities are to provide hosting and technical support for the Planned various RAMP web pages to support the decommissioning computer Activities codes and to provide maintenance, technical support, error fixing, and traininQ su pport for five decommissionin Q com puter codes.
Requesting Decommissioning and Low-Level Waste Business Line Estimated FY 2025 Com p letion Estimate of Total 1.2 FTE and $195K over a 3-year period Research Resources
32 Recommendations for NRC Regulatory Guidance Updates (Fuel and Irradiation Parameters) for High-Assay Low-Enriched Uranium and High Burnup Light Water Reactor S p ent Fuels (NMSS-2022-005 )
The purpose of this work is to provide recommendations on updates to NRC regulatory guidance documents related to spent fuel dry storage Importance to systems and facilities and for transportation packages for spent fuel and the NRC parameters for the radioactive material, regarding any needed changes to fuel and irradiation Mission burnup light treatment of higher initial enrichment and higher water reactor spent fuels. These updates are essential for NMSS staff to be able to review and license higher enrichment and higher burnup spent fuel applications for transportation and dry storage systems.
The planned activities are to provide an in-depth review of the current Planned NRC regulatory guidance documents related to spent fuel storage and Activities transportation and provide recommendations for the treatment of increased enrichment and higher burnup spent fuels, specifically for performing shielding and criticality analyses.
Requesting Spent Fuel Storage and Transportation Business Line Estimated FY 2023 Com p.letion Estimate of Total 0.3 FTE and $450K over a 2-year period Research Resources
Recommendations for Using Sensitivity/Uncertainty Analyses in Validation of Computational Methods for Criticality Safety of High-Assay Low-Enriched Uranium S y stems (NMSS-2022-006 )
A portion of the criticality safety review process, for fissile material systems, is understanding the computer code and the associated nuclear data ability of predicting criticality. Sensitivity/uncertainty analyses may assist in demonstrating that current critical experiments can be extended Importance to to higher enrichment fissile material systems utilized in fuel cycle facilities, the NRC transportation packages, and storage systems. Sensitivity/uncertainty a wider applicability of criticality Mission methods may be used to identify experiments, resulting in a higher fidelity validation methods. These
methods may benefit other technologies by identifying additional critical experiments that can be used in validating new fuel designs like accident tolerant fuel and advanced non-light-water-reactor fuels.
The planned activities will review current methods and best practices for Planned validating criticality codes and provide new recommendations when using Activities sensitivity/uncertainty methods for the validation of criticality safety calculations and software for high-assay low-enriched uranium applications.
Requesting New Reactors & Spent Fuel Storage and Transportation Business Line Estimated FY 2023 Com p letion
33 Estimate of Total Research 0.3 FTE and $400K over a 2-year period Resources
Supporting Burnup Credit (BUC) Analyses for Accident Tolerant, Increased Enriched and Hig her Burnu p Fuels ( NMSS-2022-007 )
This work will support the NRC with criticality safety analyses for fissile materials systems used under Title 10 of the Code of Federal Regulations (CFR) Part 71, "Packaging and Transportation of Radioactive Material,"
Importance to and 10 CFR Part 72, "Licensing Requirements for the Independent the NRC Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Mission Reactor-Related Greater Than Class C Waste." Specifically, this work will support evaluations related to the licensing and certification of spent fuel systems that rely on BUC in the criticality safety analysis for increased enrichment and higher burnup fuel applications.
The planned activities are being initiated to respond to industry initiatives to operate with increased uranium-235 initial enrichments and higher burnups beyond existing practice (e.g., up 8 weight-percent initial enrichment and 75 GWd/MTU assembly average burn up) for BUC Planned applications. BUC is taking credit for the reduced reactivity of spent Activities nuclear fuel in criticality analyses. One important component of BUC is the validation of the criticality code used for these predictions. Work will consist of updating technical documents related to the validation of minor actinides and fission products in BUC criticality safety analyses of commercial spent nuclear fuel storage and transportation systems for increased enrichment and higher burnup applications.
Requesting Spent Fuel Storage and Transportation Business Line Estimated FY 2023 Completion Estimate of Total Research 0.4 FTE and $490K over a 2-year period Resources
Severe Accident Analysis and Licensing Support for Small Modular Reactors (SM Rs)
(NRR-2022-015 )
The purpose of this work is to update or create MELCOR models for the
Importance to NuScale US460 standard design approval application, General Electric Hitachi BWRX-300, and Holtec SMR-160 using information submitted by the NRC the respective SMR applicants and to perform confirmatory analysis using Mission these models to support the review of severe accident analysis and risk insights from PRAs.
For each SMR design, planned research will include updating or creating Planned the MELCOR model based on design information submitted by the Activities applicant and performing calculations to confirm phenomenological processes impacting severe accident progression.
Requesting New Reactors Business Line
34 Estimated FY 2025 Com p letion Estimate of Total Research 3.3 FTE and $775K over a 4-year period Resources
Re g ulato ry Guidance Develo p ment Su pp ort for Veterinarian Release (NMSS-2022-001 )
The NRC authorizes the release of animals to owners following veterinary Importance to procedures involving byproduct material when the exposure to members the NRC of the public from the animal is expected to be below the public dose limits Mission in 10 CFR Part 20, "Standards for Protection Against Radiation. " Industry and NRC staff reviewers have requested that guidance be updated to reflect the current state-of-knowled g e.
RES staff will provide support to NMSS by updating the PIMAL (modeling tool for dosimetry calculations for radiation workers) code to include Planned canine, cat, and horse phantoms; developing a technical basis document Activities to support regulatory guidance development; and developing a Regulatory Guide to provide licensees with acceptable methodologies for development of animal release criteria.
Requesting Nuclear Materials Users Business Line Estimated FY 2027 Com p letion Estimate of Total Research 2.6 FTE and $620K over a 6-year period Resources
Summa ry of Com pleted Research Pro jects65
During the reporting period, the following research projects were completed:
Support in the Development and Enhancement of NRC Risk Analysis Tools (NRR-2015-009 )
The primary objective of this activity was to provide and maintain standard tools, methods, and guidance for risk analysis of inspection findings and reactor incidents for the SOP, the Accident Sequence Precursor Program, and Incident Investigation Program, while recognizing differences in purpose among programs. By using these Importance to standard tools, methods, and guidance, NRC analysts from various the NRC Headquarters and regional offices will achieve more consistent results Mission when performing risk assessments of licensee performance issues and operational events.
The research program plan for these capabilities has been updated and reported in the Summary of New Research Projects section under NRR-2022-001.
65 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.
35 RES accomplished updates to routine SPAR models, documentation, shutdown model, and data. In addition, model modifications were made to Research assess SDP findings, some models were converted to an all-hazard Results or model, and the external hazards were enhanced in all models. RES also Findings accomplished new software revisions, which corrected errors, made improvements, added new features, and began development of a web-based version of SAPHIRE.
Duration of 7 years the Pro ject Estimate of Total 38.5 FTE and $16.9M over the 7-year period Research Resources
Confirmato ry Testina of Carbon Fiber Reinforced Pol y mer (CFRP ) (NRR-2019-001 )
This research effort acquired confirmatory testing data related to CFRP to Importance to address uncertainties and provided the technical bases to support staff the NRC reviews of licensees' relief requests and American Society of Mechanical Mission Engineers Code actions related to the use of CFRP for repair of piping systems.
Supporting operations and repair of CFRP piping in the fleet, RES issued Research several reports including: (1) a report documenting the results of CFRP Results or mechanical testing; (2) a report documenting the results of CFRP material Findings adjustment factors testing; and (3) a white paper on non-destructive examination of CFRP composites. An additional task was also completed to evaluate the risk due to the potential failure of the CFRP repairs.
Duration of the 3 years Pro ject Estimate of Total Research 1.5 FTE and $600K over the 3-year period Resources
BWRX-300 Containment Evaluation Method Licensing Topical Report Confirmatory Anal y sis (NRR-2021-001 )
The NRC is currently engaged in pre-application activities with General Importance to Electric Hitachi for the BWRX-300 design. General Electric Hitachi the NRC which presents a novel evaluation methodology to analyze the submitted the BWRX-300 Containment Method Licensing Topical Report, Mission design. Confirmatory analyses were needed to assess the BWRX-300 conservatism of certain aspects of the topical report.
RES staff developed and analyzed TRACE thermal hydraulic and MELCOR severe accident models of the primary and containment Research systems of the BWRX-300 design to independently evaluate the novel Results or aspects of the BWRX-300 containment methodology. Several important Findings findings were communicated to NRR staff to inform audit questions and requests for additional information (RAls). RES staff documented their findings in a report. RES staff also presented the staff's analysis to the Advisory Committee on Reactor Safeguards.
36 Duration of the 1.5 years Pro ject Estimate of Total Research 1 FTE over the 1.5-year period Resources
User Need Request NRO-2015-006, "Develop the Technical Bases to Support Revisions to Re g ulato ry Guide 1.208."
This research supported the NRC's external hazards safety assessment Importance to activities in the area of seismic hazards. Given the change in current the NRC monitored evolving scientific understanding of earthquake hazard across the country, this research Mission information and knowledge into technical documents to be used in theories and incorporated newly discovered
updating the relevant regulatory guidance.
As part of these research activities, 10 different technical documents were developed addressing different aspects of seismic hazards, including a Research new guidance document on how to develop site response calculations, a Results or new set of recommendations on how to develop probabilistic seismic Findings hazard assessments, an assessment of newly developed ground motion models, and development of probabilistic strain compatible properties for soil structure interaction anal ys is.
Duration of the 7 years Pro ject Estimate of Total Research 5 FTE and $1.4M over the 7-year period Resources
Modification of the Refence Plant Fluoride Salt-Cooled Reactor to Support the Review of the Hermes Non-p ower Test Reactor Prelimina ry Safe ty Anal y ses (NRR-2022-001 )
This research involved independent analyses using the SCALE Importance to (neutronics) and MELCOR (severe accident) computer codes to develop the NRC insights into Kairos Power LLC's Hermes non-power reactor transient Mission behavior in order to aid in the review of the construction permit application.
The modifications to the reference plant modeling were based on publicly available information in the Hermes construction permit application. Using Research the modified reference plant model, three scenarios were simulated in Results or order to simulate transients, and results were compared with the results in Findings the construction permit application. Sensitivity analyses were performed to gain additional insights into the plant response, supporting the timely review of the application.
Duration of the 1 year Pro ject Estimate of Total Research 0.2 FTE and $BOK Resources
37 3-5 Fees Billed
The tables below provide information on Part 170 fees billed for each fee class. For each fee cass, e sa com pare e ees Ie 0 e receI 0* I th NRC t ff d th f b"II d t th. t f t d s es Ima e m e annua ee ru e.. th If I 66 FY 2022 Part 170 Total Part 170 -
Fee Class Receipts Proposed Part 170 Billed in Q4 Billed in FY 2022
- Annual Fee Rule FY 2022 ($M) ($M)
($M )
Fuel Facilities $7.8 $2.6 $8.8 Generic $0.7 $0.6 $2.9 Decommissionin q Materials Users 67 $0.9 $0.1 $1.0 Operating Power $160.0 $36.3 $156.6 Reactors Research and $5.8 $1.6 $5.0 Test Reactors Spent Fuel Storage I Reactor $10.3 $2.6 $12.3 Decommissionin q Rare Earth $0.1 $0.0 $0.1 Transportation $2.8 $0.9 $3.5 Uranium $0.5 $0.1 $0.6 Recove rv
Sig nificant On g oin g Licensin g Actions
The following table includes a comparison of the fees billed to projected resources for subsequent license renewal application reviews, the SHINE Medical Technologies, LLC (SHINE) operating license application review, and the Kairos Hermes construction permit a pp Ica I0n review. I' f.
Projected Fees Billed Docket Project Name Resources to Date
($M )68 ($M )sg
Point Beach Units 1 and 2 Point Beach Units 1 and 2 05000266/05000301 Subsequent License Renewal $5.070 $3.5 A pp lication - Safe ty Review Point Beach Units 1 and 2 Point Beach Units 1 and 2 Subsequent License Renewal $1.4 $1.4 05000266/05000301 Application - Environmental Review
66 The FY 2022 Final Fee Rule was published in the Federal Register (FR) on June 22, 2022 87 FR 37197.
67 Materials Users-Billed as flat fee applications and included in the estimates and billed.
68 Projected resources are calculated based on the FTE estimates provided to applicants in the acceptance letters.
Dollar amounts are obtained by multiplying the hours estimate by the professional hourly rate.
69 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 2022.
70 When the formal acceptance letter for the Point Beach subsequent license renewal application was sent to the licensee on January 15, 2021 ML21006A417, the NRC estimated that it would take approximately $6.4M to complete the application review.
38 Projected Fees Billed Docket Project Name Resources to Date
( $M )68 ($M )69 North Anna Units 1 and 2 North Anna Units 1 and 2 05000338/05000339 Subsequent License Renewal $5.071 $3.0 A pp lication - Safe ty Review North Anna Units 1 and 2 North Anna Units 1 and 2 Subsequent License Renewal $1.4 $1.5 05000338/05000339 Application - Environmental Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 05000269/05000270/ Subsequent License Renewal $5.072 $3.3 05000287 A pp lication - Safe ty Review Oconee Units 1, 2, and 3 Oconee Units 1, 2, and 3 05000269/05000270/ Subsequent License Renewal $1.4 $0.7 05000287 Application - Environmental Review SHINE Medical Isotope SHINE Medical Production Facility Operating Technologies, LLC License Application Review $6.573 $6.974 05000608 - Safety and Environmental Reviews St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 Subsequent License $5.075 $2.8 05000335/05000389 Renewal Application -
Safety Review St. Lucie Units 1 and 2 St. Lucie Units 1 and 2 Subsequent License $1.4 $0.4 05000335/05000389 Renewal Application -
Environmental Review Kairos Hermes -
Kairos Hermes 05007513 Construction Permit-Safety $5.576 $2.4 and Environmental Reviews
71 When the formal acceptance letter for the North Anna subsequent license renewal application was sent to the licensee on October 13, 2020 ( ML20258A284 ), the NRC estimated that it would take approximately $6.4M to complete the application review.
72 When the formal acceptance letter for the Oconee subsequent license renewal application was sent to the licensee on July 22, 2021 (ML21194A245 ), the NRC estimated that it would take approximately $6.4M to complete the application review.
73 The update to the projected resource estimate for this application review was provided to SHINE by letter dated February 17, 2022 (ML22047A179 ).
74 Increases in the scope of the review related to the phased construction approach, unexpected design modifications, and novel technical and licensing challenges for this first-of-a-kind facility resulted in increased resource expenditures relative to the estimate.
75 When the formal acceptance letter for the St. Lucie subsequent license renewal application was sent to the licensee on September 24, 2021 ( ML21246A091 ), the NRC estimated that it would take approximately $6.4M to complete the application review.
76 The projected resource estimate was provided to Kairos Power LLC by letter dated December 15, 2021
( ML21343A214 ).
39 3-6 Requests for Additional Information (RAls}
The table below provides information on RAls associated with licensing actions that are considered "requested activities of the Commission" for which the NRC staff issues a final SE, consistent with Section 102(c) of NEIMA. While Section 102(c) of NEIMA only applies to licensing actions accepted after July 13, 2019, the RAI data also include licensing actions accepted prior to July 13, 2019, to provide a complete inventory.
Total Total Inventory of Total Number Total Number Number of Type of Facility or Activity Open RAls of RAls of RAls RAls Type as of the Issued in Responded to Closed in End of Reporting in Reporting Reporting Reporting Period Period Period 77 Period O perating Reactors 333 44 118 117 Non-Power Production and 458 3 0 8 Utilization Facilities78 Design Certifications for N/A N/A N/A N/A New Reactors 79 Early Site Permits for New N/A N/A N/A N/A Reactors 80 Combined Licenses for 0 0 0 0 New Reactors Construction Permits for New Reactors or Non- 0 4s1 4 4 Power Production and Utilization Facilities Fuel Facilities 42 13 11 7 Power Reactor 70 17 17 0 Decommissionin g Research and Test Reactor 12 12s2 12 0 Decommissionin o Spent Fuel 769 18 18 1 Materials 0 0 0 0 Pre-Application Activities for 5 0 0 0 Advanced Reactors
77 RAls are considered closed once the final SE, environmental assessment, or environmental impact statement is finalized except for RAls associated with new reactor application reviews. Due to the phased approach taken over several years for new reactor application reviews, RAls are closed throughout the review process once the staff has determined that no additional information is needed to resolve the issue.
78 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, "Domestic Licensing of Production and Utilization Facilities," including the ongoing review of the SHINE operating license application.
79 No design certification applications are currently under review by the NRC; therefore, there will be no RAI data to report until an application is submitted and accepted by the NRC for review.
80 No early site permit applications are currently under review by the NRC; therefore, there will be no RAI data to report until an application is submitted and accepted by the NRC for review.
81 These RAls are associated with the Kairos Hermes construction permit application.
82 These RAls are associated with the Aerotest Radiography and Research Reactor Decommissioning Plan
( ML22151A252 ).
40 3-7 Workforce Development and Management FY 2022 Staffing b y Office83
FTE FTE FTE FTE Delta (Q4 End of Year Delta (EOY FY2022 Utilization Utilization Utilization Utilization FTE Budget 06/19/22 - 07/31/22 - 08/28/22 - as of Utilization - (EOY)84 Utilization -
07/30/22 08/27/22 09/24/22 09/24/22 FY 2022 Actual FY 2022 Budget) Utilization Budget)
Totals 2889.9 316.6 209.0 214.1 2705.3 -184.6 2705.3 -184.6 COMM 42.0 2.5 1.7 1.8 22.9 OIG 63.5 7.0 4.4 4.2 59.0 -19.1 22.9 -19.1 -4.5 59.0 -4.5
Totals Other 2784.4 307.1 202.9 208.1 2623.4 -161.0 2623.4 -161.0 Offices OCFO 92.0 10.5 6.8 6.8 88.6 -3.4 88.6 -3.4 OGC 90.7 10.9 7.0 7.3 93.9 OCA 10.0 1.2 0.7 0.7 10.0 0.0 10.0 0.0 3.2 93.9 3.2 OCAA 7.0 0.5 0.4 0.4 5.7 -1.3 5.7 -1.3 SECY 17.0 2.0 1.3 1.4 16.5 OPA 13.0 1.5 1.0 1.0 13.0 -0.5 16.5 -0.5 0.0 13.0 0.0 OIP 34.0 3.9 2.5 2.4 32.8 -1.2 32.8 -1.2 ASLBP 23.0 2.3 1.4 1.4 19.5 -3.5 19.5 -3.5 OEDO 26.0 2.9 2.1 2.1 26.2 ACRS 23.5 2.8 1.6 1.8 23.2 -0.3 23.2 -0.3 0.2 26.2 0.2 NRR 565.6 59.1 37.9 40.2 511.1 -54.5 511.1 -54.5 NMSS 302.2 34.0 22.5 23.5 291.3 -10.9 291.3 -10.9 RES 202.7 22.8 14.9 14.8 190.7 -12.0 190.7 -12.0 NSIR 159.3 17.1 11.1 11.2 143.9 -15.4 143.9 -15.4 R-1 171.2 19.0 12.9 13.5 165.2 -6.0 165.2 -6.0 R-11 208.0 23.9 16.2 16.6 200.7 -7.3 200.7 -7.3 R-111 170.7 20.1 13.5 13.8 168.6 -2.1 168.6 -2.1 R-IV 160.9 19.4 12.7 13.5 167.1 OE 31.5 3.3 2.2 2.2 29.2 -2.3 29.2 -2.3 6.2 167.1 6.2 01 35.0 3.6 2.4 2.4 32.3 -2.7 32.3 -2.7 OCIO 169.0 18.4 12.2 12.2 150.1 -18.9 150.1 -18.9 ADM 119.1 13.6 9.4 9.2 116.1 -3.0 116.1 -3.0 SBCR 13.0 1.5 1.0 1.0 13.0 0.0 13.0 0.0 OCHCO 137.0 12.8 9.1 8.8 113.0 -24.0 113.0 -24.0 CSU 3.0 0.1 0.1 0.1 1.7 -1.3 1.7 -1.3
3-8 Inspection Activities
The table below shows the average number of hours of direct inspection per plant in CY 2022.
83 Some numbers might not add due to rounding.
84 Based on FTE utilization as of September 24, 2022.
41 Avera ge ROP Direct Ins pection Hours
Nationwide Per Column 1 of Column 2 of Column 3 of Column 4 of Plant (unit) ROPAction ROPAction ROPAction ROPAction Matrix Matrix Matrix Matrix
1107 Hours 1107 Hours 1986 Hours 85 No Plants in No Plants in Column 3 Column 4
The table below shows the staff hours expended for inspection-related effort at operating power reactor sites by CY
Items Descrip tion CY 2021 (Hours ) CY 2022 (Hours )
- i. Baseline Ins pection 230,383 162,659 ii. Plant-S pecific Ins pection 4,854 6,416 iii. Generic Safe ty Issue Ins pections 2,426 83 iv. Performance Assessment 3,530 2,914 V. Other Activities 93,068 73,504 vi. Total Staff Effort 334,261 245,575 vii. Total Staff Effort Per Ope rating Site 5,96986 4,465 87
3-9 Backfit
Facility -S pecific Backfits
No facility-specific backfits were issued during the reporting period.
Generic Backfits
No generic backfits were issued during the reporting period.
Backfit A ppeals Filed b y Licensees and A pp licants
There were no backfit appeals submitted to the NRC during the reporting period.
85 Callaway Plant was in Column 2 of the ROP Action Matrix (ROP Action Matrix) in Q1 FY 2022, and moved to Column 1 on May 6, 2022 ( ML22123A227 ). Davis-Besse Nuclear Power Station, Unit 1 was in Column 2 in Q1 and Q2 FY 2022 ( ML22055B117 ).
86 Total staff effort is divided by 56 sites for CY 2021, due to Duane Arnold Unit 1 permanently ceasing operations in August 2020.
87 Total staff effort is divided by 55 sites for CY 2022, due to Indian Point Unit 3 permanently ceasing operations in April 2021.
42