ML24302A119
| ML24302A119 | |
| Person / Time | |
|---|---|
| Issue date: | 12/17/2024 |
| From: | Christopher Hanson NRC/Chairman |
| To: | Carper T, Carter B, Duncan J, Fleischmann C, Markey E, Rodgers C US SEN, Comm on Environment & Public Works, US SEN, Subcomm on Clean Air, Climate Change & Nuclear Safety |
| Shared Package | |
| ML24302A113 | List: |
| References | |
| CORR-24-0097, SRM-OGC981013 | |
| Download: ML24302A119 (1) | |
Text
Enclosure SEMIANNUAL STATUS REPORT ON THE LICENSING ACTIVITIES AND REGULATORY DUTIES OF THE U.S. NUCLEAR REGULATORY COMMISSION April 2024-September 2024 Note: The period of performance covered by this report includes activities that occurred from the first day of April 2024 to the last day of September 2024. The transmittal letter to Congress accompanying this report provides additional information to keep Congress fully informed of the current licensing and regulatory activities of the U.S. Nuclear Regulatory Commission.
Protecting People and the Environment
i CONTENTS I.
Reactor Oversight Process.............................................................................................. 1 II.
Implementing Risk-Informed and Performance-Based Regulations................................ 2 III.
Status of Issues Tracked in the Reactor Generic Issues Program.................................. 3 IV.
Licensing Actions and Other Licensing Tasks................................................................. 3 V.
Status of License Renewal Activities............................................................................... 4 VI.
Summary of Reactor Enforcement Actions..................................................................... 7 VII.
Security and Emergency Preparedness and Incident Response Activities................... 11 VIII.
Power Uprates............................................................................................................... 12 IX.
New Reactor Licensing.................................................................................................. 13 X.
ADVANCE Act of 2024................................................................................................. 19 XI.
Planned Rulemaking Activities......................................................................................20 I.
Reactor Oversight Process The Reactor Oversight Process (ROP) is a risk-informed, performance-based oversight program that contains provisions for continuous self-assessment and improvement. The U.S. Nuclear Regulatory Commission (NRC) uses the ROP to assess the performance of operating power reactor licensees and to determine the most effective use of inspection resources. Using inputs from both agency self-assessments and independent evaluations, the NRC adjusts the ROP on an ongoing basis to enhance its effectiveness and efficiency. The NRC staff meets with interested stakeholders periodically to collect feedback on the effectiveness of the process and considers this feedback when making improvements to the ROP.
The agencys most recent performance assessments indicate that all operating power reactor plants continue to operate safely. The NRC staff conducts assessment reviews, communicates changes in licensee performance quarterly, and issues end-of-cycle assessment letters. The NRC issued annual assessment letters to licensees in March 2024. The NRC website reflects the latest power reactor plant performance assessments.
In January 2024, as part of a proposed set of revisions to the agencys enforcement policy, the NRC staff submitted to the Commission a recommendation to revise the qualitative descriptions of white and yellow safety significance in the ROP (SECY-24-0009; Agencywide Document Access and Management System (ADAMS) Accession No. ML22318A121). The NRC staff proposes to revise the description of white safety and security findings from low-to-moderate safety significance to low safety significance and revise yellow safety and security findings from substantial safety significance to moderate safety significance. The NRC staff does not recommend any changes to the descriptions of green or red safety significance. SECY-24-0009 is currently with the Commission for review.
In March 2024, the NRC staff finalized development of a new performance indicator (PI) for emergency response facility and equipment readiness consistent with Commission direction in Staff Requirements Memorandum (SRM)-SECY-23-0010 (ML23244A282). In SRM-SECY-23-0010, the Commission approved the NRC staffs recommendation to eliminate the alert and notification system PI and to develop a new PI for emergency response facility and equipment readiness. The NRC staff successfully piloted the new PI with six sites using data from the second quarter of calendar year (CY) 2024. The pilot will continue with third quarter CY 2024 data. Full implementation of the new PI is planned to be complete in January 2025.
In April 2024, Inspection Manual Chapter (IMC) 2515, Light Water Reactor Inspection Program Operations Phase, was revised to include guidance on when hybrid/virtual meetings (i.e.,
entrances and exits) may be beneficial for effectiveness and efficiency.
In July 2024, the NRC staff completed an evaluation of IMC 0609, Appendix E, Part l, Baseline Security Significance Determination Process for Power Reactors (BSSDP), dated November 8, 2022 (ML22178A222), to determine whether it can be improved or further risk informed. Based on an assessment performed by the NRC staff, and including input from internal and external stakeholders, the NRC staff plans to recommend to the Commission that the current BSSDP be revised and to provide a modified BSSDP as part of that recommendation. The NRC staff will seek additional feedback from external stakeholders as it develops the revised BSSDP.
The NRC staff is also revising Appendix B of IMC 0609, Emergency Preparedness Significance Determination Process (ML15128A462), dated September 22, 2015, as directed by the Commission in SRM-SECY-22-0089, Recommendation for Enhancing the Emergency
Preparedness Significance Determination Process for the Reactor Oversight Process, dated February 9, 2023 (ML23040A378). This revision will further risk inform the significance determination process for inspection findings in the Emergency Preparedness Cornerstone.
See Section X of this report for discussion of ROP assessment in accordance with the ADVANCE Act.
II.
Implementing Risk-Informed and Performance-Based Regulations In 1995, the NRC issued the Probabilistic Risk Assessment (PRA) Policy Statement in the Federal Register (FR) (60 FR 42622; August 16, 1995), which formalized the Commissions commitment to risk-informed regulation through the expanded use of PRA. The use of PRA in regulatory decision-making and licensing activities for U.S. light-water reactors (LWRs) has increased in recent years, and licensees continue to adopt many risk-informed initiatives. PRAs provide licensees with risk insights that allow increased flexibility in plant operations. They also enable both licensees and the NRC to better identify and focus on more safety-significant issues. The NRC staff continues to work with industry to support risk-informed and performance-based initiatives.
Licensees continue to submit applications for adoption of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors. Section 50.69 allows licensees to establish a more risk-informed program for the treatment of structures, systems, and components. Since 2014, licensees have submitted 67 unit amendment applications to adopt 10 CFR 50.69. The NRC staff has reviewed and approved 61 applications and is currently reviewing the remaining six applications. Further, in July 2024, the NRC staff accepted for review Electric Power Research Institute (EPRI) Topical Report 3002025288, Enhanced Risk-Informed Categorization Methodology for Pressure Boundary Components (ML23234A266),
which provides an alternative methodology to adopt 10 CFR 50.69.
Licensees also continue to submit applications to adopt the Risk-Informed Technical Specifications (RITS) Initiative 4b. This initiative allows licensees to temporarily extend certain technical specification completion times up to 30 days, based on plant configuration and a real-time risk calculation. To date, licensees have submitted 65 unit amendment applications to adopt RITS Initiative 4b. The NRC staff has reviewed and approved 62 unit amendment applications and is currently reviewing the remaining three applications.
The Very Low Safety Significance Issue Resolution (VLSSIR) process, implemented in January 2020, is a framework to review, assess, and disposition issues of very low safety significance that are not clearly within a plants licensing basis. The process is used regularly and resulted in the timely closure of seven potential issues in May and June of 2024.
In parallel with the VLSSIR initiative, the NRC developed the Risk-Informed Process for Evaluations (RIPE) to resolve very low safety-significant issues commensurate with their risk significance using existing regulations under 10 CFR Section 50.12, Specific exemptions, or 10 CFR Section 50.90, Application for amendment of license, construction permit, or early site permit, and risk information. In July 2024, the NRC staff approved an exemption for Shearon Harris Nuclear Power Plant (ML24170A731) and a Palo Verde Generating Station license amendment (ML24159A470) using RIPE. In August 2024, the NRC staff approved a Joseph M.
Farley Nuclear Plant, Units 1 and 2, risk-informed license amendment (ML24242A133) previously submitted under RIPE in an expedited manner.
In October 2023, the NRC staff issued Regulatory Guide (RG) 1.183, Revision 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (ML23082A305). Revision 2, which includes updates related to higher burnup and increased enrichment fuel applications, is in progress and is anticipated to be issued in early 2025. During this reporting period, NRC staff held public meetings on May 1 and June 12, 2024, to support revision of the RG.
The NRC staff also took steps to review licensing requests for risk-informing the categorization of certain Class 2 and 3 components. On June 12, 2024, the NRC staff authorized licensees in the NextEra fleet to use Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems,Section XI, Division 1 (ML24149A286), in lieu of certain requirements in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI. The code case provides a risk-informed categorization and treatment for certain ASME Class 2 and 3 systems. Previously, on May 30, 2024, the NRC staff approved the use of Code Case N-752 for the Entergy Fleet (ML24060A219).
The NRC staff has increased the use of risk insights in the review of new and advanced reactor applications. Specifically, in preparation for the submittal of the NuScale Standard Design Approval Application (SDAA), the NRC staff collected preliminary risk insights in support of a graded review of the NuScale US460 standard design. The NRC staff continues to use risk insights to inform its ongoing technical reviews of the SDAA and to resolve complex technical issues identified during the review. The NRC staff also leveraged risk insights in its review of the Kairos Power Hermes 2 construction permit application. The Hermes 2 facility contains many structures, systems, and components identical to those in the Hermes 1 facility. The NRC staff review of Hermes 2 focused on the design differences between Hermes 1 and Hermes 2. As a result, the NRC staff was able to incorporate by reference portions of the Hermes 1 safety evaluation (SE) into the Hermes 2 SE.
III.
Status of Issues Tracked in the Reactor Generic Issues Program There were no generic issues during this reporting period. Additional detail of the NRC staffs evaluation may be found on the Generic Issues Dashboard: https://www.nrc.gov/about-nrc/regulatory/gen-issues/dashboard.html.
IV.
Licensing Actions and Other Licensing Tasks Currently there are three Congressional Budget Justification PIs for operating power reactor licensing actions: (1) timely completion of the final SE by the generic milestone date, (2) the percentage of reviews completed within resource estimates, and (3) the average percentage of time allotted used in the established schedule. These PIs are applicable to all requested activities of the Commission that involve a final SE as defined by the Nuclear Energy Innovation and Modernization Act (NEIMA) in the Operating Reactor Business Line.
Table 1 shows the actual fiscal year (FY) 2021 through FY 2024 results and the FY 2024 goals for the above-mentioned PIs.
Table 1 Results and FY 2024 Goals for the NRCs Congressional Budget Justification Performance Indicators Output Measure FY 2021 Actual FY 2022 Actual FY 2023 Actual FY 2024 Current FY 2024 Goal Age of Inventory of Licensing Actions 100%
2 year Discontinued1 Discontinued Discontinued Discontinued Age of Inventory of Other Licensing Tasks 97%
2 year Discontinued Discontinued Discontinued Discontinued Timely Completion of Final SEs 100%
Complete d by the generic milestone schedule 99%
Completed by the generic milestone schedule2 99%
Completed by the generic milestone schedule3 99%
Completed by the generic milestone schedule4 100%
Completed by the generic milestone schedule Average Percentage of Time Allotted Used in the Established Schedule Not Applicable 81.75%
98%
92.12%
115% or 75%
Percentage of Reviews Completed Within Resource Estimates Not Applicable 97.3%
94%
92.40%
>80%
V.
Status of License Renewal Activities During this reporting period, the NRC staff issued two initial renewed licenses (Comanche Peak Units 1 and 2) and two subsequent renewed licenses (North Anna Units 1 and 2); completed the acceptance review of one license renewal application (LRA) (Clinton) and one subsequent license renewal application (SLRA) (Dresden); and issued the draft supplemental environmental impact statement (SEIS) for one LRA (Perry), final SEIS for one LRA (Comanche Peak Units 1 and 2), and final environmental impact statement (EIS) for one SLRA (North Anna Units 1 and 2). Eight additional applications are under review.
1 In FY 2022, the indicators related to the age of the inventory of licensing actions and the age of the inventory of other licensing tasks were discontinued.
2 In FY 2022, one final SE was not issued within the NRCs established generic milestone schedule due to a delay in the applicants response to NRCs request for additional information.
3 In FY 2023, two final SEs were not issued within the NRCs established generic milestone schedule. The first required additional time to bring closure to all safety aspects of the review, which included a supplement to the operating license application for a phased approach to startup operations. The second required additional time to address technical issues identified during an operational event at the plant.
4 One review exceeded the generic milestone schedule; the delay was due to the licensees action and beyond the staffs control. All appropriate notifications for the delay (i.e., Commission/Congress) of the SE were completed on-time.
Commission Direction Related to Subsequent License Renewal (SLR)
On February 24, 2022, the Commission issued three orders (CLI-22-2, CLI-22-3, and CLI-22-4) addressing SLR proceedings for five operating nuclear plants, affecting a total of 11 reactor units. Specifically, the Commission concluded that NUREG-1437, Generic Environmental Impact Statement for License Renewal of Nuclear Plants (LR GEIS), Revision 1, which the agency relied on in part to meet its obligations under the National Environmental Policy Act (NEPA), did not consider SLR, and thus the NRC staffs environmental review of five SLR applications were incomplete. The Commission noted that SLR applicants could wait for the agency to finish efforts to update the LR GEIS to address SLR or perform their own site-specific environmental analyses. The impacted applications include those for the following units:
Turkey Point Units 3 and 4 Oconee Units 1, 2, and 3 Point Beach Units 1 and 2 North Anna Units 1 and 2 Peach Bottom Units 2 and 3 On April 5, 2022, the Commission approved a rulemaking plan proposed by NRC staff that would update the LR GEIS and NRC regulations on environmental reviews for LRs to account for SLR applications (SRM-SECY-22-0024; ML22096A035). The proposed rule was published in the Federal Register on March 3, 2023 (88 FR 13329). On August 6, 2024, the NRC published a final rule (89 FR 64166), with a correction published on August 13, 2024 (89 FR 65755), along with the associated Revision 2 to NUREG-1437, Generic Environmental Impact Statement for License Renewal of Nuclear Plants (LR GEIS) (ML24087A133). The revised LR GEIS specifically supports the updated list of environmental issues and associated environmental impact findings contained in Table B-1 in Appendix B to Subpart A of revised 10 CFR Part 51 for both initial LRs and first SLRs, which allows the NRC staff to fully leverage these generic findings for all applications under review. In August 2024, the licensees for Point Beach, St. Lucie, and Peach Bottom requested that their environmental reviews be resumed.
In March 2024, the NRC staff submitted SECY-24-0026, Achieving Timely Completion of License Renewal Safety and Environmental Reviews (License Renewal Roadmap)
(ML24059A131), which outlines the NRC staff roadmap to ensure the LR program conducts timely and predictable reviews and achieves the goal of 18-month reviews. On April 15, 2024, the NRC staff presented additional information to the Commission in SECY-24-0026A on the efficiency gains being achieved for two ongoing LR projects - the initial LR for Comanche Peak Nuclear Power Plant, Units 1 and 2, and the SLR for Monticello Nuclear Power Plant, Unit 1 (ML24101A364).
On August 8, 2024, the Commission directed the staff, in SRM-COMCTH-24-0003, License Renewal and Subsequent License Renewal Review Expectations, (ML24221A308), to begin completing LR and SLR reviews in no more than 14,000 staff hours and no more than 18 months, assuming a high-quality application submittal and timely responses from the applicant to requests for additional or confirmatory information. The Commission told the staff to implement these new metrics for applications received after the issuance of the SRM. For reviews that have already started, staff should re-evaluate, and to the extent possible, adjust schedules to mee the new metrics.
Applications with Milestones Completed During this Reporting Period North Anna (SLR)
On August 24, 2020, Virginia Electric and Power Company (Dominion) submitted an SLR application for North Anna Power Station, Units 1 and 2 (ML20246G703). On October 13, 2020, the NRC staff issued the formal acceptance letter for the application (ML20258A284). A draft supplemental EIS was issued in August 2021 (ML21228A084). On January 4, 2022, the final SE report was issued (ML21354A174).
On September 29, 2022, Dominion submitted a site-specific environmental report. A notice of intent to prepare a draft EIS supplement and start the 30-day limited scoping period was published on November 15, 2022. The final EIS was issued in July 2024 (ML24206A043). The subsequent renewed licenses were issued on August 28, 2024 (ML24215A220).
Comanche Peak (LR)
On October 3, 2022, Luminant submitted an LR application for Comanche Peak Nuclear Power Plant, Units 1 and 2 (ML22276A082). On November 23, 2022, the NRC staff issued the formal acceptance letter for the application (ML22297A007). The NRC staff issued the SE in March 2024 (ML24068A075) and the final SEIS in April 2024 (ML24078A261). The renewed licenses were issued on July 30, 2024 (ML24136A131).
Perry (LR)
On July 3, 2023, Energy Harbor Nuclear Corp. submitted an LR application for Perry Nuclear Power Plant (ML23184A081). On September 22, 2023, the NRC staff issued the formal acceptance letter for the application (ML23256A359). The draft EIS (ML24241A256) was issued on August 30, 2024.
Clinton (LR)
On February 14, 2024, Constellation Energy Generation, LLC (CEG) submitted an LR application for Clinton Power Station (ML24045A026). On April 11, 2024, the NRC staff issued the formal acceptance letter for the application (ML24089A222).
Dresden (SLR)
On April 17, 2024, CEG submitted an SLR application for Dresden Nuclear Power Station (ML24108A008). On June 14, 2024, the NRC staff issued the formal acceptance letter for the application (ML24128A274).
Turkey Point (Site-specific environmental report for issued SLR license)
Turkey Points subsequent renewed licenses were issued prior to the Commission orders in 2022. One of the orders was specific to Turkey Point (CLI-22-02). Those orders left the subsequent renewed licenses in place but directed NRC staff to (1) change the expiration dates to the dates prior to those licenses being issued (i.e., 60-year expiration instead of 80), and (2) complete the environmental review by conducting a new plant-specific EIS or by waiting for the updated GEIS and then subsequently referencing the GEIS. With the subsequent renewed licenses remaining valid, the findings in the NRC staffs SE also remain valid, as well as any
safety or environmental improvements that the licensee, Florida Power & Light Company (FPL),
may have put in place to comply with the subsequent renewed licenses. By letter dated June 9, 2022 (ML22160A301), FPL submitted an Environmental Report, Supplement 2, related to its 2018 application (ML18037A812) for SLR of Renewed Facility Operating Licenses for the Turkey Point Nuclear Generating Station, Units 3 and 4. The NRC staff issued the final EIS (ML24087A061) on March 29, 2024. On September 17, 2024, the NRC staff modified the licenses to restore the expiration dates to allow 80 years of operation (ML24158A002).
VI.
Summary of Reactor Enforcement Actions The reactor enforcement statistics in the tables below are arranged by region, half FY, FY, and two previous FYs for comparison purposes. These tables provide the non-escalated and escalated reactor enforcement data including traditional enforcement and the ROP. The severity level assigned to a violation (i.e., traditional enforcement) generally reflects the significance of a violation. However, for most violations at power reactors, the significance of inspection findings is assessed using the Significance Determination Process (SDP) under the ROP, which uses risk insights, as appropriate.
Brief descriptions of the escalated reactor enforcement actions associated with traditional enforcement and the ROP (as well as any other significant actions) taken during the applicable fiscal halfyear follow the tables.
Table 2 Non-escalated Reactor Enforcement Actions*
NON-ESCALATED REACTOR ENFORCEMENT ACTIONS Region I Region II Region III Region IV TOTAL Cited Severity Level IV or Green 1st Half FY 24 1
0 0
3 4
2nd Half FY 24 0
0 0
0 0
FY 24 YTD Total 1
0 0
3 4
FY 23 Total 1
4 0
6 11 FY 22 Total 0
8 0
2 10 Non-cited Severity Level IV or Green 1st Half FY 24 52 62 53 53 220 2nd Half FY 24 43 67 47 76 233 FY 24 Total 95 129 100 129 453 FY 23 Total 79 115 99 118 411 FY 22 Total 80 81 69 108 338 TOTAL Cited and Non-cited Severity Level IV or Green 1st Half FY 24 53 62 53 56 224 2nd Half FY 24 43 67 47 76 233 FY 24 Total 96 129 100 132 457 FY 23 Total 80 119 99 124 422 FY 22 Total 80 89 69 110 348
- The non-escalated enforcement data reflect the cited and non-cited violations either categorized at Severity Level IV (the lowest level) or associated with green findings during the indicated time periods. The numbers of cited violations are based on Enforcement Action Tracking System data that may be subject to minor changes following verification. These data do not include green findings that do not have associated violations.
Table 3 Escalated Reactor Enforcement Actions Associated with Traditional Enforcement*
ESCALATED REACTOR ENFORCEMENT ACTIONS ASSOCIATED WITH TRADITIONAL ENFORCEMENT Region I Region II Region III Region IV TOTAL Severity Level I 1st Half FY 24 0
0 0
0 0
2nd Half FY 24 0
0 0
0 0
FY 24 Total 0
0 0
0 0
FY 23Total 0
0 0
0 0
FY 22Total 0
0 0
0 0
Severity Level II 1st Half FY 24 0
0 0
0 0
2nd Half FY 24 0
0 0
0 0
FY 24 Total 0
0 0
0 0
FY 23 Total 0
0 0
0 0
FY 22 Total 0
0 0
0 0
Severity Level III 1st Half FY 24 0
0 0
0 0
2nd Half FY 24 2
2 0
1 5
FY 24 Total 2
2 0
1 5
FY 23 Total 0
2 0
0 2
FY 22 Total 0
1 0
1 2
TOTAL Violations Cited at Severity Level I, II, or III 1st Half FY 24 0
0 0
0 0
2nd Half FY 24 2
2 0
1 5
FY 24 Total 2
2 0
1 5
FY 23 Total 0
2 0
0 2
FY 22 Total 0
1 0
1 2
- The escalated enforcement data reflect the severity level I, II, or III violations or problems cited during the indicated time periods.
Table 4 Escalated Reactor Enforcement Actions Associated with the Reactor Oversight Process*
ESCALATED REACTOR ENFORCEMENT ACTIONS ASSOCIATED WITH THE REACTOR OVERSIGHT PROCESS Region I Region II Region III Region IV TOTAL Violations Related to Red Findings 1st Half FY 24 0
0 0
0 0
2nd Half FY 24 0
0 0
0 0
FY 24 Total 0
0 0
0 0
FY 23Total 0
0 0
0 0
FY 22Total 0
0 0
0 0
Violations Related to Yellow Findings 1st Half FY 24 0
0 0
0 0
2nd Half FY 24 0
0 0
0 0
FY 24 Total 0
0 0
0 0
FY 23 Total 0
0 0
0 0
FY 22 Total 0
0 0
0 0
Violations Related to White Findings 1st Half FY 24 1
2 0
1 4
2nd Half FY 24 0
1 0
0 1
FY 24 Total 1
3 0
1 5
FY 23 Total 2
3 1
4 10 FY 22 Total 0
2 1
1 4
TOTAL*
Related to
- Red, Yellow, or White Findings 1st Half FY 24 1
3 0
1 5
2nd Half FY 24 0
1 0
0 1
FY 24 Total 1
4 0
1 6
FY 23 Total 2
6 1
4 13 FY 22 Total 0
2 1
1 4
- The escalated enforcement data reflect the violations or problems cited during the indicated time periods that were associated with either red, yellow, or white findings. This data does not include red, yellow, or white findings that do not have associated violations. The total will include escalated security violations (i.e., greater-than-green) but are designated official use only -
security related information (OUO-SRI) and not disclosed to the public.
Reactor Escalated Enforcement Actions and Other Significant Actions Catawba Nuclear Station On September 5, 2024, the NRC issued a notice of violation associated with a white finding under the ROP to Duke Energy Carolinas, LLC at Catawba Nuclear Station. The white finding, an issue of low-to-moderate safety significance, involved the licensees failure to maintain the functionality of the emergency ventilation system, which resulted in the inoperability of the 2A emergency diesel generator contrary to 10 CFR Part 50, Appendix B, Criterion III, Design Control, and technical specifications.
VII.
Security and Emergency Preparedness and Incident Response Activities The NRC continues to maintain an appropriate regulatory infrastructure that provides reasonable assurance of adequate protection of public health and safety, promotes the common defense and security while implementing risk-informed strategies, and improves the realism of NRC licensing and oversight activities. The NRCs security, emergency preparedness (EP), and incident response programs contribute to these goals.
Physical Security On August 9, 2024, the proposed rule, Alternative Physical Security Requirements for Advanced Reactors, (89 FR 65226) was published for public comment with a closing date of October 23, 2024, along with the associated draft guidance, Draft Guide (DG) 5072, Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors (ML20041E037) and DG-5071, Revision 2 to RG 5.81, Target Set Identification and Development for Nuclear Power Reactors (non-public). The final rule is due to the Commission in September 2025. In September 2024, the NRC staff submitted to the Commission the proposed rule on Risk-Informed, Technology Inclusive Regulatory Framework for Advanced Reactors (known as Part 53) (ML24095A158) before it was published for public comment. In these proposed rules, both voluntary and graded approaches are included to address a comprehensive range of security areas such as physical and cybersecurity, fitness for duty, and access authorization. The graded approaches may offer applicants increased flexibility in the design of their physical security programs, as well as to implement certain security alternatives commensurate with the risk profiles of their facilities.
The NRC staff is assessing options for physical and cybersecurity, fitness for duty, and access authorization in the licensing of nth-of-a-kind micro-reactors (i.e., micro-reactors of a standard common design that has been previously approved by the NRC). On September 27, 2024, the NRC staff published a draft white paper, Nth-of-a-Kind Micro-Reactor Licensing and Deployment Considerations (ML24270A206). The NRC staff has also engaged in readiness assessment, pre-application, and other public meetings to support various licensing actions, including a public meeting on May 14, 2024, regarding nth-of-a-kind micro-reactors, and a Palisades Restart Panel meeting on September 10, 2024.
During the reporting period, the NRC staff continued to implement its normal security inspection activities, and the NRCs security oversight program continued to inspect for any vulnerabilities or deficiencies in site protective strategies and programs and take prompt action, as necessary.
In addition, kinetic assessment methods, such as force-on-force (FOF) inspections, provided performance-based insights regarding licensee readiness to defend their sites. On June 24, 2024, the NRC issued the Report to Congress on the Security Inspection Program for
Operating Commercial Power Reactors and Category I Fuel Cycle Facilities: Results and Updates (ML24086A417). This report details results of the NRCs security inspection activities for CY 2023.
Cybersecurity Under 10 CFR 73.54, Protection of digital computer and communication systems and networks, the NRC requires nuclear power plant licensees and new license applicants to provide reasonable assurance that digital computer and communication systems and networks are adequately protected against cyberattacks. These licensees must implement a cybersecurity program to ensure that safety, security, and EP functions are protected from cyberattacks. In conjunction with this, the NRC has developed an oversight program for power reactor cybersecurity that includes an inspection program, inspector training, and a process for evaluating the significance of inspection findings.
In January 2024, the NRC staff began its second biennial inspection cycle of licensees cybersecurity programs as part of the ROP using Inspection Procedure 71130.10, Cybersecurity (ML21271A106). Between April 2024 and September 2024, the NRC staff completed 14 cybersecurity inspections.
On May 7 and June 5, 2024, the NRC staff held public meetings to discuss potential changes to cybersecurity guidance and the biennial inspection cycle based on lessons learned and insights gained from the first biennial inspection cycle. The NRC staff intends to apply the lessons learned in future efforts to improve cybersecurity inspection efficiency.
VIII.
Power Uprates Since the 1970s, licensees have applied for and implemented power uprates to increase the output of their plants. The NRC staff has reviewed and approved 172 power uprates to date.
Existing plants have gained approximately 24,089 megawatts thermal or 8,030 megawatts in electric generating capacity (the equivalent of about 8 large nuclear power plant units) through power uprates. At this time, the NRC has no power uprate applications under review; however, the NRC staff continues to engage with licensees through pre-application meetings. During this reporting period, the NRC staff met with Public Service Enterprise Group to discuss their plans for a potential measurement uncertainty recapture power uprate in late 2025 and a stretch power uprate in mid2027 (ML24239A840).
The NRC staff also held two public meetings related to the agencys efforts to improve power uprate reviews. On June 26, 2024, the NRC staff held a public meeting between the NRC and the Nuclear Energy Institute (NEI) to discuss NRC staff and industry preparations for upcoming power uprate licensing applications (ML24178A037 and ML24172A147). The discussion in the meeting identified several potential areas for continued industry engagement including plant-specific licensing using the recently approved EPRI Technical Report 3002018337, Use of Data Validation and Reconciliation Methods for Measurement Uncertainty Recapture, risk insights, bundled and linked amendments, and guidance updates. On September 5, 2024, the NRC staff held a public meeting with NEI to discuss potential improvements in NRC guidance for power uprate reviews (ML24249A115). Topics focused on potentially updating NRC guidance to provide regulatory certainty for combined or linked license amendments related to power uprates. NEI also discussed allowing license amendment requests (LARs) to reference unapproved topical reports (at the draft SE stage), expanding the use of license conditions, environmental qualifications, and implementing higher burnup/increased enrichment for power
uprates. The NRC staff plans on continued external engagement on these topics.
Lastly, in September 2024, the NRC staff issued its preliminary recommendations on ways to improve the power uprate application and review process (ML24239A394). Another memorandum, which will describe the NRC staffs final recommendation and its schedule for completion of those recommendations, will be issued following the planned external stakeholder engagements.
IX.
New Reactor Licensing The NRCs new reactor program is (1) focusing on licensing and construction oversight activities for large LWRs, small modular LWRs, and non-LWRs, and (2) continuing to develop the specific regulatory framework and infrastructure for advanced reactors (non-LWRs).
NuScale Power, LLC, Small Modular Reactor Standard Design Approval Application On December 31, 2022, NuScale submitted an SDAA for its US460 small modular reactor design under 10 CFR Part 52, Subpart E, Standard Design Approvals (ML22339A066). The proposed 77 megawatt electric (MWe) nuclear power module US460 design is capable of producing more power than the certified 50 MWe NuScale design and features additional design changes. On July 31, 2023, the NRC informed NuScale that its SDAA, as supplemented by information to address technical sufficiency issues identified by NRC staff, was acceptable for docketing (ML23198A163). The NRC provided a four-phase, 24-month review schedule and committed to provide resource estimates within 60 days of the issuance of the letter. The NRC staff completed its evaluation of the resource needs and communicated these to NuScale by letter dated September 22, 2023 (ML23254A192). The review of the SDAA is progressing on schedule. As of September 2024, the NRC staff has substantially completed developing the SE with open items for all 19 SDAA chapters and the 4 associated topical reports.
Vogtle Units 3 and 4 Construction of Vogtle Units 3 and 4 is complete, and all inspection activities for both units are being conducted under the ROP. During this reporting period, Vogtle Units 3 and 4 were in the Licensee Response Column of the ROP action matrix. Vogtle Unit 3 began commercial operations on July 31, 2023, and Unit 4 entered commercial operations on April 29, 2024.
Vendor Inspections The NRC staff uses the Vendor Inspection Program to confirm that reactor applicants and licensees are fulfilling their regulatory obligations to oversee the supply chain. The NRC staff conducts inspections to verify the implementation of vendor quality assurance (QA) programs to ensure the quality of materials, equipment, and services supplied to the commercial nuclear industry. These inspections ensure that vendors maintain an effective system for reporting defects under 10 CFR Part 21, Reporting of defects and noncompliance, and verify the use of commercial-grade dedication programs for safety-related materials, equipment, and services.
Other activities conducted by the NRC staff include ensuring that counterfeit items are removed and prevented from use in safety-related applications, participation in international cooperation efforts, and the development of industry consensus standards. Focus areas for operating reactors include replacement components, commercial-grade dedication, safeguards information protection, software QA, digital instrumentation and control systems upgrades, and fuel fabrication. The NRC staff also includes review of existing commercial nuclear suppliers
who have been contracted in support of design approvals related to new and advanced reactor designs.
During the reporting period, the NRC completed 10 vendor inspections. For FY 2024, the NRC has completed 21 vendor inspections, exceeding the goal of completing at least 20 inspections.
In June 2024, the NRC staff observed one vendor audit performed by Nuclear Procurement Issues Corporation (NUPIC). NUPIC is a licensee-operated organization that performs joint utility audits of nuclear facility suppliers. The NRC staff observes NUPIC-led audits up to three times a year to verify the effectiveness of the audits. The typical NUPIC-led audit scope is to determine the overall acceptability and verify the effective implementation of a vendors QA and 10 CFR Part 21 programs.
On May 8 and June 11, 2024, the NRC staff held two public meetings to discuss with external stakeholders several potential ideas considered by the NRC staff for inclusion of Code Case N-883, Construction of Items Prior to the Establishment of a Section III, Division 1 Owner,Section III, Division 1, into RG 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III. These meetings (ML24164A200 and ML24218A197) provided an opportunity for external stakeholders to share their views, particularly with respect to the nuclear industrys related needs for using Code Case N-883.
On June 5, 2024, the NRC staff published Regulatory Issue Summary (RIS) 2024-02, Required Assessment of U.S. Department of Energy Laboratories by Licensees, Applicants, and Suppliers to Verify the Effective Implementation of Their Quality Assurance Programs (ML23342A179). This RIS clarifies the NRCs regulatory position on the required assessment of U.S. Department of Energy (DOE) national laboratories by licensees, applicants, and vendors to verify the effective implementation of the laboratories QA programs.
On June 13, 2024, the NRC staff successfully hosted its 9th Regulatory Workshop on Vendor Oversight. The audience included approximately 350 attendees from eight different countries including Taiwan, Spain, United Arab Emirates, Canada, Romania, Japan, France, and Mexico.
The purpose of the meeting was to allow the NRC staff to engage in an open dialogue with external stakeholders to discuss any current issues of importance to the nuclear industry.
Topics covered during the meeting included control of items under an Appendix B to 10 CFR Part 50 QA program, safety culture and safety conscious work environment guidelines for vendors, navigating 10 CFR Part 21, and the different roles the ASME, the National Board of Boiler and Pressure Vessel Inspectors, Authorized Inspection Agencies, and the NRC play in supplier oversight. The meeting ended with a question-and-answer session between the meeting attendees and the NRC staff.
In July 2024, the NRC staff hosted visiting regulators from the Polish National Atomic Energy Agency interested in understanding the QA and vendor inspection work performed by the NRC.
The NRC staff prepared a series of training sessions focused on areas of regulatory oversight including 10 CFR Part 21, Appendix B to 10 CFR Part 50, conduct of vendor and QA implementation inspections, commercial-grade dedication, comparison of Appendix B to ISO-9001, Quality Management Systems - Requirements, and training and qualification activities for vendor inspectors and QA staff.
Operator Licensing The NRC staff continues to prepare for operator licensing activities involving advanced reactors as part of developing the proposed rule to establish a new, voluntary framework for commercial nuclear plants (Part 53). Notably, this framework introduces new flexibilities such as provisions for automatic load following, online refueling, customized licensed operator staffing, a modernization of the traditional Shift Technical Advisor position, allowance for facilities to administer their own operator licensing examinations, and the ability for facilities to develop operator license examinations of appropriate scope and format based on their unique design and operational considerations. This framework is also compatible with the human-system considerations that will potentially be associated with the remote or autonomous operation of micro-reactors.
In parallel with Part 53 efforts, the NRC staff is working to make improvements to operator licensing and human factors-related reviews for new facilities that pursue licensing under 10 CFR Parts 50 and 52. This includes the issuance in March 2024 of Advanced Reactor Content of Application Project guidance (ML23277A143) on organization and human-system considerations to support the NRC staffs reviews of non-LWR facility applicants under 10 CFR Part 50 and 52. The NRC staff is using the guidance to facilitate the ongoing Kemmerer Power Station (a non-LWR design) construction permit safety review.
During the reporting period, the NRC staff participated in ongoing information sharing with stakeholders, including collaboration with Idaho National Laboratory on the remote operation of nuclear power plants and Brookhaven National Laboratory on the development of new human factors engineering review-related guidance. In addition, the NRC staff is coordinating with the Canadian Nuclear Safety Commission regarding operator licensing activities for new reactors and with the Nuclear Energy Agency regarding human factors-related considerations in areas such as small modular reactors, artificial intelligence, and remote operations.
Non-Light-Water Reactors The NRC staff continues to make significant progress executing its vision and strategy for advanced reactor readiness and meeting the requirements in Section 103 of NEIMA. Additional information on the status of advanced reactor readiness and activities is available on the NRCs public website at https://www.nrc.gov/reactors/new-reactors/advanced.html.
Non-LWR Infrastructure Activities During the reporting period, the NRC staff continued to hold periodic public meetings on numerous advanced reactor topics and extensive stakeholder engagement on various initiatives related to establishing a technology-inclusive, risk-informed, and performance-based regulatory framework, including hosting public meetings on the advanced reactor construction oversight process (ARCOP), micro-reactor licensing, RG 1.247, Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities (ML21235A008),
development of risk metrics to support implementation of risk-informed programs for advanced reactors, and the alternative physical security requirements for advanced reactors rulemaking.
Other recent activities include:
On April 3, 2024, the NRC staff presented Status Update on Computer Code and Model Development for Non-Light-Water Reactors (ML24121A190) to the Advisory Committee on Reactor Safeguards.
On April 4, 2024, the NRC staff conducted a public workshop on codes and standards for new and advanced reactors (ML24065A472).
On May 22, 2024, the NRC staff conducted a public workshop on the ARCOP (ML24129A079).
On July 11, 2024, the NRC staff conducted a public workshop on the SCALE/MELCOR non-LWR fuel cycle demonstration project for a molten salt reactor (ML24107A937).
On August 9, 2024, the NRC staff published the proposed rule on Alternative Physical Security Requirements for Advanced Reactors (ML21334A003) (89 FR 65226).
On September 6, 2024, the NRC staff submitted to the Commission the proposed rule on Risk-Informed, Technology Inclusive Regulatory Framework for Advanced Reactors (known as Part 53) after addressing SRM comments (ML24095A158).
On September 27, 2024, the NRC staff published a White Paper discussing strategies for nth-of-a-kind licensing of micro-reactors (ML24270A206).
Non-LWR Licensing Activities The NRC staff continues to implement flexible and staged non-LWR regulatory review processes and pre-application engagement. The NRC staff completed its review of the construction permit application submitted in October 2021 for the Kairos Hermes 1 test reactor in Oak Ridge, TN, which is intended to support the development of Kaiross fluoride salt-cooled, high-temperature reactor technology (ML21272A375 and ML21306A131).
On July 14, 2023, Kairos submitted a second construction permit application for a two-unit test reactor facility (Hermes 2) that would be located on the same site as the Hermes 1 test reactor (ML23195A121). The Hermes 2 test reactors would use the same fluoride salt cooled, high-temperature reactor technology as the Hermes 1 reactor but would incorporate some additional features, such as intermediate salt loops and a shared turbine generator system. The NRC staff accepted the Hermes 2 construction permit application for review on September 11, 2023 (ML23233A167). On July 19, 2024, the NRC staff issued the SE for the Hermes 2 construction permit application (ML24200A114). On August 30, 2024, the NRC staff issued the final Environmental Assessment (EA) and Finding of No Significant Impact (FONSI) for the Construction Permits and Environmental Review Exemptions for the Kairos Hermes 2 test reactors (ML24240A034). The notice of mandatory hearing for Hermes 2 was issued on September 12, 2024 (89 FR 74303). Application documents and information regarding the review are available on the NRCs public website at https://www.nrc.gov/reactors/non-power/new-facility-licensing/hermes2-kairos.html.
On September 16, 2024, the NRC issued a construction permit and associated SE to Abilene Christian University (ACU) for its non-power molten salt research reactor (MSRR) to be located
on its campus in Abilene, Texas. The construction permit application was submitted in August 2022 (ML22227A201) and the NRC staff issued the EA and FONSI on March 14, 2024 (89 FR 18678). On December 21, 2023, the NRC staff notified ACU that additional information would be needed for the NRC staff to complete its review of the MSRR application (ML23348A196). ACU provided the additional information needed on March 28, 2024 (ML24094A332), and April 30, 2024 (ML24121A272). On June 12, 2024, the NRC staff notified ACU (ML24162A093) of its revised review schedule and plan to issue the final SE and the construction permit by September 30, 2024.
On March 28, 2024, TerraPower, LLC (TerraPower), on behalf of US SFR Owner, LLC, a wholly owned subsidiary of TerraPower, submitted a construction permit application for Kemmerer Power Station Unit 1 (Kemmerer Unit 1) (ML24088A059). Kemmerer Unit 1 would be sited in Lincoln County, WY, and would be used to demonstrate the Natrium sodium fast reactor technology under DOEs Advanced Reactor Demonstration Program. The NRC staff accepted the TerraPower application on May 21, 2024 (ML24135A109). On June 12, 2024, the NRC staff issued a letter to TerraPower outlining the estimated schedule and resources needed to complete the safety and environmental reviews for the construction permit application (ML24162A063). On June 12, 2024, the NRC also published in the Federal Register a Notice of Intent to conduct scoping and prepare an EIS (89 FR 49917). The public scoping meeting was held in Kemmerer, WY, on July 16, 2024. Application documents and information regarding the review are available on the NRCs public website at https://www.nrc.gov/reactors/new-reactors/advanced/who-were-working-with/applicant-projects/terrapower.html.
The NRC staff is reviewing pre-application reports and meeting regularly with vendors on potential future applications, including: X-energy on its pebble-bed, high-temperature gas-cooled reactor; Kairos Power on its TRISO particle fuel, fluoride-cooled high-temperature commercial power reactor; Terrestrial Energy on its molten salt coolant, molten salt fuel reactor; Westinghouse Electric Company on its high-temperature heat pipe micro-reactor; General Atomics on its high-temperature gas-cooled reactor; the University of Illinois, Urbana-Champaign on its power-generating TRISO fuel research reactor; and Oklo Inc. on its liquid-metal-cooled fast reactor.
With respect to advanced reactor fuel fabrication, in September 2022, the NRC staff received the completed application to construct and operate a TRISO fuel fabrication facility from TRISO-X, which is a subsidiary of X-energy, LLC (ML22101A200 and ML22266A269). The application was docketed for formal review on November 4, 2022 (ML22320A110). TRISO-X submitted the Electrical and Instrumentation and Control portion of the application on February 29, 2024 (ML24060A239). TRISO-X also notified the NRC staff of its plans to update the license application and environmental report to account for a modified facility design to be submitted in December 2024 (ML24020A010). The NRC staff and TRISO-X staff are actively working to resolve approximately 140 requests for additional information, which will be resolved in a future update of the license application and environmental report.
In October 2021, Global Nuclear Fuel-Americas (GNF-A) expressed intent (ML21292A180) to submit an LAR to permit high-assay low-enriched uranium (HALEU) fuel fabrication. In March 2023, GNF-A received approval of an exemption (ML23039A151) to submit the license amendment application supporting the development of Natrium fuel in two parts: the supplemental environmental report followed by the safety and safeguards portion. The exemption allowed GNF-A one year from the submittal of the supplemental environmental report to submit the safety and safeguards portion. GNF-A submitted the supplemental environmental report on March 6, 2023 (ML23065A072). On July 11, 2023, GNF-A informed the NRC of
concerns with the near-term availability of HALEU and asked for a 24-month delay in the review of the supplemental environmental report (until early 2025). GNF-A also indicated that the safety and safeguards portion would be delayed to the third quarter of 2025. With the exemption set to expire on March 6, 2024, GNF-A verbally informed the NRC of its intent to withdraw the supplemental environmental report on March 6, 2024, and followed up by letter documenting the withdrawal request on March 8, 2024 (ML24068A130). In a pre-application meeting held on June 13, 2024, GNF-A informed the NRC of plans to submit a complete application in the second quarter of 2026 (ML24156A203).
Regulatory Infrastructure The NRC continues to enhance its regulatory infrastructure to meet its goals of improving the planning, licensing, and oversight of future new reactor applications; making timely and effective policy decisions; and updating regulatory guidance for large LWRs, small modular reactors, and non-LWRs. The previous section discussed infrastructure activities that are largely for non-LWRs. The sections below describe infrastructure activities focused on LWRs conducted during the reporting period.
Environmental Reviews for New Nuclear Reactors The NRC staff initially developed a draft GEIS and proposed rulemaking for the environmental review process for the construction and operation of advanced nuclear reactors as described in SECY-20-0020, Results of Exploratory Process for Developing a Generic Environmental Impact Statement for the Construction and Operation of Advanced Nuclear Reactors (ML20052D029). This GEIS would use a technology-neutral regulatory framework and performance-based assumptions to determine generic environmental impacts for new commercial advanced nuclear reactors. On September 21, 2020, in SRM-SECY-20-0020 (ML20265A112), the Commission directed the NRC staff to initiate rulemaking for the GEIS. The NRC staff provided this draft GEIS and proposed rule to the Commission on November 29, 2021 (ML21222A044), for its consideration. On April 17, 2024, in SRM-SECY-21-0098 (ML24108A200), the Commission directed the NRC staff to proceed with publication of the draft GEIS after modifying it to be applicable to any new nuclear reactor application. The NRC has retitled this rulemaking from Advanced Nuclear Reactor Generic Environmental Impact Statement to Generic Environmental Impact Statement for Licensing of New Nuclear Reactors to reflect the change in the applicability of the GEIS and rule. The rule is expected to be published in November 2024. Additional information about this rulemaking is available at https://www.nrc.gov/reading-rm/doc-collections/rulemaking-ruleforum/active/ruledetails.html?id=1139.
Alignment of Licensing Processes and Lessons Learned from New Reactor Licensing The NRC staff is working on a rulemaking to address the alignment of licensing requirements in 10 CFR Part 50, Domestic licensing of production and utilization facilities, and 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. The Commission directed the NRC staff to pursue rulemaking to incorporate lessons learned from recent new power reactor licensing reviews. This rulemaking would help ensure consistency in new reactor licensing reviews, regardless of whether an applicant chooses to use the Part 50 or Part 52 licensing process. On June 6, 2022, the NRC staff submitted the draft proposed rule (SECY 0052; ML21159A055) to the Commission for its consideration. At the end of this reporting period, SECY-22-0052 was still pending before the Commission.
Standard Review Plan Modernization The NRC staff is working to modernize NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition.6 The Standard Review Plan (SRP) modernization effort aims to provide guidance to the NRC staff to focus licensing reviews on the regulatory requirements and associated acceptance criteria that determine whether there is reasonable assurance of adequate protection. During this reporting period, realignment of the effort was approved to prioritize development of the framework that will be used for risk-informing and modernizing SRP sections through the routine update process.
Environmental Guidance Updates The NRC staff is currently updating NUREG-1555, Standard Review Plans for Environmental Reviews for Nuclear Power Plants: Environmental Standard Review Plan, which was last revised in July 2007.7 The update will reflect changes in reactor technology and NRC policy and regulations and will incorporate streamlined processes based on experience gained through completed environmental reviews. The update will also reflect statutory requirements, applicable Executive Orders, judicial developments, and agency administrative decisions and will consider, as appropriate and in coordination with a potential NRC rulemaking, any new environmental regulations issued by the Council on Environmental Quality.
As discussed in Section V of this report, on August 6, 2024, the final rule, Renewing Nuclear Power Plant Operating Licenses-Environmental Review, LR GEIS, and guidance were published in the Federal Register (89 FR 64166). The NRC's regulatory framework for operating reactor license renewal anticipates that the LR GEIS will be reviewed and updated every 10 years to account for new information and lessons learned.
X.
ADVANCE Act of 2024 This section highlights significant actions taken by the NRC during the reporting period to implement the ADVANCE Act of 2024 (the Act), which was enacted in July 2024.
In July 2024, the NRC Executive Director for Operations established a dedicated Core Team with a lead executive to coordinate the agencywide efforts for implementation of the Act. The agency issued 35 taskings to NRC offices for actions required by the Act or related to its implementation. Project teams, in several cases spanning multiple offices within the agency, were established and are actively working on each of these taskings.
To facilitate stakeholder engagement, the NRC staff hosted two public meetings during the reporting period to provide information on the agencys actions and receive feedback. On September 25, 2024, the NRC staff held a public meeting regarding modernization of nuclear reactor environmental reviews (Section 506 of the Act; meeting summary at ML24277A138) and held a session during the 2024 NRC Standards Forum to engage stakeholders on methods of manufacturing and construction for nuclear energy projects (Section 401 of the Act; slides at ML24267A245). On September 30, 2024, the NRC staff held a public meeting on advanced methods of manufacturing and construction for nuclear energy projects and obtained 6 The SRP for safety reviews is available online at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/index.html.
7 The SRP for environmental reviews is available online at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1555/updates.html.
stakeholder feedback (slides at ML24269A140). The NRC staff has taken additional steps to meet requirements in the Act, such as developing options for the Commission on updating the agencys mission statement (SECY-24-0083; ML24281A190), working on updates to internal processes to reflect changes to the NEIMA reporting requirements for delays associated with requested activities of the Commission, and preparing for future implementation of the reduced hourly rate for advanced nuclear reactor applicants and pre-applicants.
XI.
Planned Rulemaking Activities The attached report lists the status of NRC rulemaking activities as of September 30, 2024, including their priorities and schedules. Of the 68 rulemaking activities, 62 rulemakings are planned activities. The NRC is also reviewing six petitions for rulemaking. The 62 planned rulemaking activities include 14 proposals in response to industry requests, 15 that could reduce or clarify existing requirements, 9 that are required by statute or are needed to conform NRC regulations to other agency requirements or to international treaties or agreements, and 24 that could establish new requirements. The NRC uses a single tracking and reporting system to provide real-time updates on all NRC rulemaking activities. Members of the public can access the NRCs rulemaking activity information at https://www.nrc.gov/about-nrc/regulatory/rulemaking/rules-petitions.html.
At the time of publication, each proposed and final rule includes a statement that addresses actions taken to meet applicable backfitting and issue finality requirements, including which, if any, backfitting and issue finality requirements apply and how the NRC staff evaluated the rule with respect to those requirements.