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Final Presentation Slides for August 26, 2021 Advanced Reactor Stakeholder Public Meeting
	ML21237A463
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Issue date:	08/25/2021
From:	O'Banion M; NRC/NRR/DANU/UARP
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Advanced Reactor Stakeholder Public Meeting August 26, 2021 Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 442 887 144#

Page 1 of 140

Time Agenda Speaker 10:00 - 10:10 am Opening Remarks NRC 10:10 - 10:30 am Part 71 - Transportation Requirements for Micro-Reactors NRC/NMSS 10:30 - 10:45 am Material Control and Accounting of Special Nuclear Material of Moderate NRC/NMSS Strategic Significance (Category II Material): Upcoming Guidance, NUREG-2159, Draft for Public Comment 10:45 am - 12:00 pm Results of U.S. Nuclear Industry Council's 2021 Advanced Nuclear Survey USNIC 12:00 - 1:00 pm Break All 1:00 - 2:00 pm Role and Use of Probabilistic Risk Assessment (PRA) in Support of Advanced NRC/NRR and NEI Reactor Licensing 2:00 - 2:15 pm Status of Non-Light Water Reactor PRA Acceptability Regulatory Guide NRC/NRR 2:15 - 2:45 pm Draft White Paper on Inservice Inspection/Inservice Testing Guidance NRC/NRR and INL 2:45 - 3:15 p.m. Update on Advanced Reactor Exports Working Group Report NRC/OIP 3:15 - 3:30 pm Future Meeting Planning and Concluding Remarks NRC/All Page 2 of 140

Advanced Reactor Integrated Schedule of Activities https://www.nrc.gov/reactors/new-reactors/advanced/details#advSumISRA Page 3 of 140

Transportable Micro-reactors and the Future August 26, 2021 Bernie White, Sr. Project Manager Division of Fuel Management Office of Nuclear Safety and Safeguards Page 4 of 140

Key Messages

Preapplication meetings are vital

Stable regulatory framework for radioactive material transportation

Effective communication is a two-way street Page 5 of 140

Consideration of Various Transport Configurations

Use of various licenses to transport

- Unfueled reactor from fabrication facility

- Fueled reactor from fabrication facility

- Fueled reactor after low power testing operations

- Reactor between operating sites

- Used reactor back to refurbishment facility Page 6 of 140

Package Approval Regulatory Structure

Standard Package approval clearly established

- Specified tests for normal conditions of transport and hypothetical accident conditions

- Post-test criteria

Alternative environmental and test conditions in 10 CFR 71.41(c)

Special package authorization in 10 CFR 71.41(d)

Exemptions pursuant to 10 CFR 71.12 Page 7 of 140

Role of Transportation in Micro-Reactor Development

Will the transportation regulations be factored into the design of the transportable micro-reactor?

Are the transportation regulations in 10 CFR Part 71 a challenge for transportable micro-reactor development or package approval? If so, why?

Page 8 of 140

We welcome preapplication meetings to discuss micro-reactor package approval for transportation Bernard.White@nrc.gov 301-415-6577 Page 9 of 140

Advanced Reactor Stakeholder Meeting Guidance for Material Control and Accounting:

NUREG-2159 Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance Draft for Public Comment James Rubenstone, Chief Material Control and Accounting Branch Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission August 26, 2021 Page 10 of 140

Material Control and Accounting MC&A is a program to control and account for certain types of nuclear material used at a licensed facility, including source and special nuclear material, to deter and detect loss, theft, diversion, misuse, or unauthorized production or enrichment of nuclear material

Material Control - Control access and monitoring status

Material Accounting - Maintain knowledge of location and quantities Page 11 of 140

MC&A Requirements General reporting and recordkeeping requirements apply to each person licensed by NRC who possesses, transfers, or receives 1 gram or more of special nuclear material

Reactors, Medical Isotope Production (Part 50)

Fuel Cycle Facilities, Greater-Than-Critical-Mass Facilities (Part 70)

Independent Spent Fuel Storage Installations (Part 72)

Agreement State Licensees (Part 150)

Special reporting requirements

Licensees possessing certain source material (Part 40)

Licensees subject to IAEA safeguards (Part 75) 10 CFR Part 74, Material Control and Accounting of Special Nuclear Material Page 12 of 140

Graded Approach for MC&A Specific material control & accounting requirements for licensees who:

Possess and use SNM of low strategic significance (Category III)

Possess and use SNM of moderate strategic significance (Category II)

Possess and use formula quantities of strategic SNM (Category I)

Possess uranium source material and equipment capable of producing enriched uranium 10 CFR Part 74, Subparts C, D, and E Page 13 of 140

NUREG-2159, Draft for Comment

Guidance for implementation of requirements in 10 CFR Part 74, Subpart D

Similar to existing guidance for 10 CFR Part 74, Subpart C (NUREG-1065) and Subpart E (NUREG-1280)

Federal Register Notice will announce draft for public comment (week of August 30, tentative)

Provide comments on Regulations.gov

60-day comment period Page 14 of 140

Questions?

NRC encourages pre-application engagement on MC&A and other topics

For MC&A, contact:

Tom.Pham@nrc.gov James.Rubenstone@nrc.gov https://www.nrc.gov/materials/fuel-cycle-fac/nuclear-mat-ctrl-acctng.html Page 15 of 140

Results of U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey For Public Release at U.S. Nuclear Regulatory Commission (NRC)

Advanced Reactor Stakeholder Meeting 26 August 2021 Cyril W. Draffin, Jr.

Senior Fellow, Advanced Nuclear U.S. Nuclear Industry Council Jeffrey S. Merrifield Chairman, Advanced Nuclear Working Group U.S. Nuclear Industry Council Peter Hastings Vice Chairman, Advanced Nuclear Working Group U.S. Nuclear Industry Council Page 16 of 140

Advanced Nuclear Developers Completing 2021 USNIC Advanced Nuclear Anonymous Survey Advanced Reactor Developers: USNIC members (17) Advanced Reactor Developers: Non USNIC members (7)

Advanced Reactor Concepts (Part 53 only)

BWXT Columbia Basin Consulting Group Centrus Flibe Energy Framatome Inc. Holtec GE Hitachi Nuclear Energy Hybrid Power Technologies General Atomics MIT (HTGR)

Kairos Power, Inc Southern Company (molten chloride reactor)

Lightbridge Thorcon MUONS Inc. Note: This is comprehensive survey with large sample size of US developers:

NuScale Power

All answers include 100% (1 company, Oklo) in NRC licensing review, 100%

Oklo Inc. (2 companies, X-Energy & TerraPower) with DOE ARDP Demo awards, 60%

TerraPower (3 of 5 companies) with DOE risk reduction awards, and over 80% (5 of 6 Terrestrial Energy companies) of microreactor developers Ultra Safe Nuclear Corporation

For Part 53 questions, survey includes 100% of DOE ARDP Demo, Risk URENCO (U-Battery) Reduction, and ARC-20 awardees (all 10 organizations). Also, USNIC Westinghouse Electric Company member and non-USNIC member organizations representing 75% (21 of X-energy the 28) non-Light Water Reactor (LWR) designs responded to survey, as well as LWR Small Modular Reactors companies (e.g. NuScale).

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Source: U.S. Nuclear Regulatory Commission, 2021 Page 18 of 140

USNIC 2021 SURVEY TOPICS Policy Issues (Q1-Q3)

Part 53 (Q4-Q9)

Reactor Type, Licensing (Q10-Q12)

US/Canada (Q13-Q15)

EPZ, Operators, Refueling (Q16-Q20)

NRC Fees, EIS (Q21-Q23)

Capitol Hill/States (Q23-Q27)

International/Commerce (Q29-Q32)

DOE Programs (Q28; Q33-39)

HALEU (Q40)

Issues (Q42, Q41)

Page 19 of 140 3 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q1: Of the Policy Issues listed below, please rank their individual importance:

1 Fuel Qualification [Note: #3 in 2020 survey]

2 Probabilistic Risk Assessment, Resolve if Graded Approach Allowed or Required to Follow NEI-1804 [#4 in 2020] Note: Most important 3 Fuel Cycle Facilities, Higher Enrichments, Transportation [#2 in 2020] 6 policy issues in bold 4 Appropriate Source Term, Dose Calculations, and Siting [#1 in 2020]

5 Materials Qualification [#12 in 2020]

6 Operator Staffing for Small or Multi-Modular Facilities [#10 in 2020]

7 Licensing Basis Event Selection 8 Offsite Emergency Planning (EP) Requirements 9 Endorsement of Codes, Standards & Methods 10 Security and Safeguards Requirements 11 Insurance and Liability [#14 in 2020]

12 NRC Planned Rulemaking Modernizing Environmental Reviews 13 Functional Containment Performance Criteria [#5 in 2020]

14 Industrial Facilities Using Nuclear-Generated Process Heat 15 Manufacturing License Requirements [#11 in 2020]

16 NRC & Canadian CNSC Coordination 17 Generic EIS 18 Remote/autonomous Inspections and Monitoring of Operations 19 Operator Training Requirements Blue for Policy Issues listed as more important than 2020 survey; Green with lower importance than prior 2020 survey Page 20 of 140 4 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q1: Of the Policy Issues listed below, please rank their individual importance - Details:

High Low Weighted importance Important Importance Not sure Average 1 Fuel Qualification 64.7% 17.7% 17.7% 0.0% 2.47 Note: Most important 2 Probabilistic Risk Assessment, Resolve if Graded Approach Allowed or Required to 6 policy issues in bold Follow NEI-1804 53.3% 33.3% 13.3% 0.0% 2.4 3 Fuel Cycle Facilities, Higher Enrichments, Transportation 58.8% 17.7% 23.5% 0.0% 2.35 4

14-17 responses for Appropriate Source Term, Dose Calculations, and Siting 50.0% 28.6% 21.4% 0.0% 2.29 5

each policy issue, most Materials Qualification 43.8% 31.3% 25.0% 0.0% 2.19 issues had 16 6 Operator Staffing for Small or Multi-Modular Facilities 33.3% 46.7% 20.0% 0.0% 2.13 responses 7 Licensing Basis Event Selection 26.7% 60.0% 6.7% 6.7% 2.07 8 Offsite Emergency Planning (EP) Requirements 26.7% 53.3% 20.0% 0.0% 2.07 9 Endorsement of Codes, Standards & Methods 26.7% 53.3% 20.0% 0.0% 2.07 10 Security and Safeguards Requirements 29.4% 47.1% 23.5% 0.0% 2.06 11 Insurance and Liability 23.5% 52.9% 23.5% 0.0% 2 12 NRC Planned Rulemaking Modernizing Environmental Reviews 33.3% 26.7% 33.3% 6.7% 1.87 13 Functional Containment Performance Criteria 20.0% 46.7% 26.7% 6.7% 1.8 14 Industrial Facilities Using Nuclear-Generated Process Heat 26.7% 20.0% 53.3% 0.0% 1.73 15 Manufacturing License Requirements 13.3% 53.3% 26.7% 6.7% 1.73 16 NRC & Canadian CNSC Coordination 23.5% 35.3% 29.4% 11.8% 1.71 17 Generic EIS 20.0% 33.3% 40.0% 6.7% 1.67 18 Remote/autonomous Inspections and Monitoring of Operations 20.0% 26.7% 46.7% 6.7% 1.6 19 Operator Training Requirements 6.7% 40.0% 53.3% 0.0% 1.53 Blue for Policy Issues listed as more important than 2020 survey; Green with lower importance than prior 2020 survey Page 21 of 140 5 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q2: For policy issues listed in question 1, which issues most need regulatory guidance?

(multiple answers allowed) 1 Fuel Qualification (1) (11 responses) 65%

2 Fuel Cycle Facilities, Higher Enrichments, Transportation (3) (8 responses) 47% Note: Most important 6 policy 3 Probabilistic Risk Assessment (2) (7 responses) 41% issues from Question 1 in bold 3 Operator Staffing for Small or Multi-Modular Facilities (6) (7 responses) 41%

5 Offsite Emergency Planning (EP) Requirements (6 responses) 35%

5 Endorsement of Codes, Standards & Methods (6 responses) 35%

7 Security and Safeguards Requirements 29%

7 Remote/autonomous inspections and monitoring of operations 29%

7 Generic EIS 29%

10 Licensing Basis Event Selection 24%

10 Materials Qualification (5) 24%

10 Industrial Facilities Using Nuclear-Generated Process Heat 24%

13 Appropriate Source Term, Dose Calculations, and Siting (4) 18%

13 Insurance and Liability 18%

15 NRC planned rulemaking modernizing environmental reviews 12%

15 Manufacturing License 12%

17 Functional Containment Performance Criteria 6%

17 NRC & Canadian CNSC coordination 6%

17 Operator Training Requirements (1 response) 6%

6l Page 22 of 140

Q3: Are there any additional NRC policy issues that need to be addressed to allow your technology to move forward that are not included on the lists above?

HALEU transportation regulations; Packaging and shipping requirements

Current requirements for siting outlined in Part 100 are overly prescriptive; Revisiting siting in a more performance-based manner is a higher priority policy issue

Environmental reviews certainly need to be revisited from a regulatory perspective-- The NRC's environmental review is overly burdensome, especially for microreactors, where there is little to no (and often positive) environmental impacts associated with placement of an advanced reactor; The requirements associated with licensing actions designated as needing an EIS versus an EA or even being included in the list of categorical exclusions should be revisited considering certain technologies being proposed

From 1970 to 1978, the number of regulatory guidance documents and positions expanded from 4 to 304-- During this same time period, nuclear growth reduced dramatically. While guidance can be useful, it should be developed thoughtfully to ensure it does not prohibit growth. In particular, industry should not rush to create guidance in advance of an operating non-LWR fleet, rather allow for guidance that complements lessons learned from early operations to inform guidance

Harmonization between selected international standards and domestic requirements

Non-applicabilities remain key policy issue that has not yet been resolved-- The NRC maintains a plain read interpretation of the regulations which is counter to NEIMA and creates unnecessary hurdles to the deployment of non-LWRs

Demonstration of acceptable methods for meeting Quantitative Health Objectives

Siting and population distance requirements

QA standards

Part 53 7 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey Page 23 of 140

USNIC 2021 SURVEY TOPICS - Part 53 Policy Issues (Q1-Q3) For Part 53 questions, very comprehensive USNIC survey with large Part 53 (Q4-Q9) sample size of US developers, including:

Reactor Type, Licensing (Q10-Q12)

100% (all 10 organizations) of DOE US/Canada (Q13-Q15) ARDP Demo (2), Risk Reduction (5),

EPZ, Operators, Refueling (Q16-Q20) and ARC-20 (3) awardees.

NRC Fees, EIS (Q21-Q23)

75% (21 of the 28) non-Light Water Capitol Hill/States (Q23-Q27) Reactor (LWR) designs (slide 2) being developed (by USNIC member and International/Commerce (Q29-Q32) non-USNIC member organizations DOE Programs (Q28; Q33-39) responding to survey)

HALEU (Q40)

Issues (Q42, Q41)

Page 24 of 140 8 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q4: How important is Part 53 likely to be to your company in the next 15 years?

USNIC & non USNIC members

of companies High Importance if Written Appropriately 30% 7 Important if Written Appropriately 30% 7 Low Importance 9% 2 Not sure, depends on the language in final rulemaking 26% 6 (e.g. whether current NRC language is modified)

Not sure, depends on our companys design and 4% 1 licensing approach Page 25 of 140 9 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey May not add to 100% due to rounding 23

Q4: How important is Part 53 likely to be to your company in the next 15 years? - Comments

Critically important that Part 53 provide for meaningful reductions in review time and cost, and allows for progressive reduction in licensing risk for a project.

We can work with Part 50/52 and RG 1.232. Part 53 will be beneficial in long term. The key is it must focus on safety and not piles of documents to be reviewed by the NRC. A few safety and performance targets must be established. The regulator must allow the operator/licensee to show compliance.

Part 53 is more important to a reactor vendor. We are a fuel designer/fabricator.

Part 53 needs to support, but not require, specific implementation techniques such as LMP.

Restrictive/prescriptive requirements around today's tools is to be avoided.

Will be influenced by the future applicants desired licensing approach and not the designer/company licensing approach - Part 53 has to demonstrate a benefit to pursuing that approach versus either Parts 50 or 52

Need to see if final language justifies using it and also if it is timely with our deployment plans.

As a HALEU supplier, ability of reactor developers to get their designs to market will define the HALEU market Page 26 of 140 10 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q5: How important is a usable Part 53 (that is flexible enough and without undue regulatory burden) to U.S.

Advanced Reactor Industry?

USNIC & non USNIC members Essential for longer-term deployment of commercial Advanced Nuclear Reactors in the US (i.e. industry may not survive without appropriate Part 53) 44% 10 Important for deployment of commercial Advanced Nuclear Reactors in the U.S.

30% 91% 7 Desirable for deployment of commercial Advanced 17% 4 Nuclear Reactors in the U.S.

Not critical as we can work within existing regulatory 9% 2 framework (Part 50 and 52)

Not that important 0% 0 Page 27 of 140 11 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey 23

Q6: Assuming Part 53 is useful, when do you expect to need Part 53 to be completed to support your application?

USNIC & non USNIC members 2024-2025 26% 6 2026-2027 17% 4 2028-2030 17% 4 After 2030 17% 4 N/A, not expecting to 22% 5 use Part 53 Page 28 of 140 12 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey 23

Q7: How satisfied are you with the usefulness of Part 53 based on current (ML21148A062) language and explanations provided by NRC USNIC & non USNIC members Excellent, one of the best draft regulations 0% 0 Very satisfied, comprehensive and useful 0% 0 Somewhat satisfied, needs improvement in a few locations 41% 9 Somewhat dissatisfied, substantial changes are 8 36%

necessary Very dissatisfied, not useful with only limited 5% 59% 1 improvement of current Part 50 and 52 Not helpful at all so far 18% 4 Page 29 of 140 13 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey 22 organizations

Q8: Comment on Part 53 issues - Potential Delay USNIC & non USNIC members We would accept a delay in the development of Part 53 to 71% 15 ensure it meets the needs of the industry and the regulator We prefer development of Part 53 on its current schedule 29% 6 21 Comments:

More important for Part 53 to be useful and less burdensome than timely.

Timeliness should not be the key measuring stick

Absolutely vital that we give the regulator and industry enough time to coordinate to create a useful regulation

Not currently intending to license in the US Continued on next page Page 30 of 140 14 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q8: Comment on Part 53 issues - Potential Delay (continued)

USNIC & non USNIC members Comments (continued):

Complexity and cost associated with the NRC have resulted in decision by our management to de-prioritize interactions with the regulator. For that reason, detailed knowledge of Part 53 - its nuances and potential

- is limited in our company. By default, preference is given to Part 50 due to its more-tested nature, and due to costs and difficulties in recent attempts to use Part 52.

Our preference would be for Part 53 to be complete on its current schedule and to meet the needs of the industry/regulator; however, we would accept a minor delay to ensure proper formulation of the rule

We feel an allowance for delay will not result in a better product, just a longer time schedule.

We plan on using a traditional 10CFR50 PSAR/FSAR approach using justifications for modifying changes to the existing requirements where requirements are not germane to non-light water reactors. We view the proposed 10CFR53 as more or less useless.

Page 31 of 140 15 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q8: Comment on Part 53 issues - PRA USNIC & non USNIC members We plan on using significant PRA input (similar to LMP) 35% 6 We plan on using medium PRA input (similar to existing 24% 4 regulatory framework)

We plan on using minor PRA input (similar to maximum 29% 5 credible accident approach)

We plan on taking another licensing methodology approach 12% 2 Note: (a) Only 35% plan on using significant PRA input; 65% plan to use medium/minor/no PRA input.

(b) Parenthetical similarities present an example- a developer using LMP may use PRA consistent with 17 existing regulatory framework in terms of what goes into the application.

(c) Future discussion will be required as NRC presents Graded PRA approach, recognizing only a minimal PRA may be appropriate at the Construction Phase.

Page 32 of 140 16 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q8: Comment on Part 53 issues - QHO USNIC & non USNIC members Yes, Include quantitative health objectives 36% 5 No, do not include quantitative health objectives 64% 9 14 Comments:

Include quantitative health objectives only if guidance is available to demonstrate how to meet and is only an initial licensing requirement

Subpart H is of interest to our company to expand the available options for phased/progressive licensing of designs and projects

What we plan to do in near-term implementation should not be driver for content of the rule if it is going to make it prescriptive for all technologies Page 33 of 140 17 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q8: Comment on Part 53 issues - Other Comments Comments: USNIC & non USNIC members

Part 53, and NRC more broadly, should be capable of the eventual licensing and regulation of thousands of reactors (Large and small reactors, electricity and non-electricity, mobile and stationary, terrestrial and marine).

Must get rid of ALARA and should push for reasonable response to accidents. Should have quantitative health objectives and liability tied to measured exposures in the event of a release. Our experience base is too small to support proper use of PRA; expect this is true for most novel reactor designs. So PRA in a few areas but mostly we expect to use a demonstration reactor.

Emergency Preparedness section is under revision but still references 50.47. This is critical issue for Advanced Reactor developers. The planning zones should be based on risk analysis for the maximum credible event. Licensee's must be responsible to provide local authorities with information and facilities to coordinate their responses and public information, however, licensee's cannot compel local officials to perform their duties. NRC licensing should require that a licensee provides all necessary training, event information, and facilities for coordination and public information, but not be held responsible for performance of public agencies it cannot control.

Page 34 of 140 18 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey Continued on next page

Q8: Comment on Part 53 issues - Other Comments (continued)

Comments (continued): USNIC & non USNIC members

NRC staff single mindedly focus on using the underlying Congressional Act driving 10CFR53 development as a springboard for inserting new requirements, staff guidance, and staff desires into a major change in the Code of Federal Regulations. Such silo vision is utterly unhelpful for moving advanced reactors forward because much simpler, least cost and most effective solutions are ignored.

We applaud the efforts of DOE and NRC to modernize and expand the licensing process and design requirements to address development of non-LWR and smaller scale power reactors.

NRC seems to be losing sight that Congress wished them to take advantage of the increased safety of the advanced reactors by reducing burden, not increasing the requirements for safety. Demonstrating adequate protection of public health and safety (dose) should be the primary goal. The design and the analysis of the plant will dictate the systems needed to ensure that dose limit is not exceeded. PRA can be used to inform the design as determined by the applicant, but should not be mandated for the design of the plant. A full PRA for operation may be expected or desired unless the risk of operating the plant is extremely low (microreactors).

Long term must recognize that opponents use cost and safety fear as primary tool to eliminate nuclear from the natural dominance it should have in electricity generation. Must get rid of ALARA. Must have defined, sane compensation for exposures. For additional Part 53 developer comments, contact POC at end of this document Page 35 of 140 19 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q9: Do you plan to use Licensing Modernization Project methodology in your licensing application?

USNIC & non USNIC members Yes 21% 5 33%

Yes, with modifications 12.5% 3 Not decided yet 54% 13 e.g. use Performance-based No deterministic approach, such as 12.5% 3 MCA approach 24 Page 36 of 140 20 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q10: What Part do you plan to use (or have used) when you file your first licensing application?

USNIC & non USNIC members

Part 50 provides more flexibility than Part 52.

Part 50 42% 10

Currently plan to use Part 50, however, we will consider using Part 53 if available and does not require definitive design before a construction permit application.

Current plans to use Part 50 for our demonstration reactor Part 52 17% 4 unless Part 53 is available in time.

May not be possible to use Part 53 if application filed before Part 53 4% 1 final Part 53 is released

Note: Other includes companies planning to use 50/52 (have not decided) or not to file in U.S.

Other 37% 9

Planning for Standard Design Approval application under Part 52; however construction licensing process 24 has not yet been determined and is the purview of the future licensee on how to proceed.

Page 37 of 140 21 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Fuel supply only-- likely Part 50 with Part 52 possibility

USNIC 2021 SURVEY TOPICS - Multiple Policy Issues (Q1-Q3)

Part 53 (Q4-Q9)

Reactor Type, Licensing (Q10-Q12)

US/Canada (Q13-Q15)

EPZ, Operators, Refueling (Q16-Q20)

NRC Fees, EIS (Q21-Q23)

Capitol Hill/States (Q23-Q27)

International/Commerce (Q29-Q32)

DOE Programs (Q28; Q33-39)

HALEU (Q40)

Page 38 of 140 Issues (Q42, Q41) 22 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q11: When do you plan to file your first licensing application?

USNIC members Includes HALEU license US filing (perhaps Centrus), US reactor 4 filing (probably Oklo), and non-US filing (in Canada/UK) 3 5 Comments:

Will be filing in Canada and the UK only

We need solid commitment for at least 6 units 2 of our plant.

HALEU production Demo

HALEU License Amendment request approved 2

0 16 Page 39 of 140 23 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q12: What reactor size, number of modules, and technology type? (multiple responses allowed)

USNIC & non USNIC members 9

10 7

Other technology 15 High Temp Gas Fast Reactor with Brayton Cycle HTGRs from 20 MWe to 625 MWe per module 4 Heat pipe reactor 1 Heat pipes Hybrid that uses nuclear and fossil fuel.

4 Fast spectrum reactor utilizing lead-bismuth eutectic primary coolant 8 Reactor operated under Class 104c license HALEU production 5 Fuel only 3 Deconversion, expansion of enrichment segment e.g. Heat pipes, other HTGR 12 Page 40 of 140 24 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q13: Does your company intend to pursue licensing in both the United States and Canada?

11 companies; lower than ~75% in 2020 5 companies; higher than ~12% US-only in 2020 1 company; lower than in 2020 Other countries/regions: UK, eastern Europe, the Middle East, Southeast Asia and Africa Page 41 of 140 25 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q14: Does your company support the effort of the U.S. NRC and the Canadian CNSC to align their regulatory review processes?

4 companies; lower than ~45% in 2020 9 companies 3 companies; higher than in 2020 1 company Page 42 of 140 26 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q15: Are there actions that the NRC/CNSC and/or Industry can undertake to resolve these regulatory review issues, or alternatively, are there other areas where the NRC and CNSC could collaborate?

Comity/parity to avoid having to undergo duplicative licensing proceedings

Cross border transportation of HALEU

Harmonized standards e.g. ASME and NQA-1

Increased reciprocity

CNSC could clarify its process for an approved NRC license.

If technology proposed for deployment is identical, approach where approvals can be streamlined with requisite modifications to meet specific regulatory criteria in each country Page 43 of 140 27 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q16: What is the appropriate Emergency Planning Zone for your technology?

Note: 100% of developers (13 companies) when EPZ relevant 3 companies; including fuel only and within site boundary Page 44 of 140 28 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q17: Does your plant design require control room operators to operate the plant?

13 companies 3 companies (perhaps for microreactors); slightly lower than 23% in 2020 Page 45 of 140 29 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q18: If you answered no to question 17 (i.e. plant design does not require control room operators to operate the plant), please explain why not?

Being designed for autonomous operation; Plant will be autonomous once start-up has been completed after refueling with remote monitoring; Only remote operation intended to be available is reactor trip

Our smallest reactor can operate autonomously, but we are not pursuing that until a real demand materializes

Facility is designed to operate with minimal human interaction and has no safety-related human tasks

"Operate" does not imply safety-related operator actions

Fuel only - depends on plant license, but most probably yes Note: HALEU plant requires 24x7 operators Page 46 of 140 30 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q19: If you answered yes to question 17, how many operators will be required for your commercial advanced reactor design?

Total number of Total number of Will the control Will there be any variance Any substantial change in expected control room modules (when fully room operators in the number of control operators from last year?

operators per shift? built out)? be on site or room operators during located off-site? overnight hours and weekends?

3 4 on-site no no 3 operators per shift Fours module for our on site no no for 4-module plant largest plant Fuel only. Depends Fuel only. Depends on Fuel only. Fuel only. Depends on Fuel only. Depends on plant license.

on plant license. plant license. Depends on plant plant license.

license.

2-3 varies - up to 4 on-site no no TBD Two Units on-site TBD no on site 3 6-12 on-site This is a Licensee choice NRC approved reduction from six licensed (we are a vendor) operators to three for twelve module plant with single control room, and approved elimination of STA position.

TBD however >5 on site TBD no control multiple reactors 1

Page 47 of 140 2 on-site no no

Q20: How often do you intend to refuel?

2 5

0 1 15 companies 2

1 Never, we have a lifetime core 4 Page 48 of 140 32 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q21: What is an appropriate Nuclear Regulatory Commission fee (for the current regulatory framework and desired future regulatory framework)?

The current fee structure is acceptable 4 companies If not the current structure, what fee structures would you recommend for 1) 11 companies licensing review fees, and 2) annual fees? (see next slide)

See comments on next slide Page 49 of 140 33 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q21: What is an appropriate Nuclear Regulatory Commission fee (for the current regulatory framework and desired future regulatory framework)?

Fee should be scaled to power level and plant safety profile

Without legislative action, annual fees should reflect the level of staff effort as this is a zero sum game and no licensee should be disproportionately burdened by other licensees. Legislation should be pursued to recognize the zero carbon societal benefit of nuclear and to make cost recovery commensurate or favorable when compared to carbon producing technologies

A per-review hour fee basis represents a significant challenge for regulatory reviews of new designs given the uncertainties associated with novel applications and technologies. We support many of the proposals made by NIA such as exclusion of new license fees for activities such as NEPA compliance and pre-application engagement, and consideration of capped or flat application fees. Consider deferred fees

NRC fee structure should be entirely revamped. The current structure disincentives timely and efficient reviews. Current fee structure creates a significant barrier to entry for nuclear reactor companies, especially small businesses. Instead, smaller subset of fees should be assessed for certain applications and allow for broader entry availability. For annual fees shoul d be revisited for whether they are truly necessary. Recent reports suggested alternative fee structures be looked at for applicability, including EPA, FDA, and FAA. These structures recognize the public benefit incurred as a result of the associa ted reviews, and therefore set the expectation that public share in regulatory costs associated with such activities. Under the current structure, microreactor annual fees should be no greater than those applied to research and test reactors

Support a fee structure similar to the ones described as "Alternative 2" or "Alternative 3" (slides 12 and 13) presented by NEI at ARRTF Stakeholder Meeting on April 15, 2021

The NIA recommendation on fee reform is worth pursuing See additional comments on next slide Page 50 of 140 34 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q21: What is an appropriate Nuclear Regulatory Commission fee? - broader issue of cost reduction

Cost reduction is vital through risk-informing the review and reducing review scope to only what is safety-significant

Continually negotiate the scope of various engagements, and ensure all questions are approved by NRC management prior to the vendor spending time on it

Define and enforce scope of ACRS reviews

Reduction in overhead cost (e.g., PMs)

Audit charges were large because of scope creep and continuous timeline extension. Need more focused audits

See NEIs recent NRC letter on reducing Licensing cost, dated 6/9/21, NEI Input on Recent Application Experience for New Reactors, ML21160A246 Page 51 of 140 35 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q22: Should the NRC EIS process include a need for power analysis?

0 Yes, but evaluative process should be 2 streamlined 9

4 Note: similar results in 2020 Page 52 of 140 36 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q22: Should the NRC EIS process include a need for power analysis? - Comments

Need to replace/decarbonize electricity generation is common and well understood by policy makers and regulators

The operator licensee should determine need, not the NRC!

Assume that there is a power need, otherwise a plant would not be proposed.

Many advanced reactors, especially microreactors will benefit from a power analysis performed, however it should not be necessary to support the environmental review.

The defense of purpose and need is the underlying requirement and must be addressed. The NRC staff have not said that they cannot evaluate an application without addressing "need for power";

what they have said is that it has not been worth the effort to develop guidance, absent a demand signal for non-power applications. There are individuals within the staff that don't quite understand this, but in the main, middle and senior management seem to get it.

The need for power or process applications would be one of several topics used to support the Need for the proposed action. It must not be the singular reason for the action. For large scale facilities, the Need for Power was the dominant reason that was used to offset the large potential negative impacts in the cost benefit balancing that is the result of the EIS.

Page 53 of 140 Additional comment on next slide 37 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q22: Should the NRC EIS process include a need for power analysis? - Comments (continued)

The NEI comments on Draft Micro-Reactor Applications COL-ISG-029, Environmental Considerations Associated with Micro-Reactors addressed this matter: two would be project proponents for advanced reactors: governmental authorities and private corporations, both of whom, as a practical matter, are unlikely to change their business plan based on the NRCs alternative analysis. Consider that: (1) if the impetus to increase or generate power reflects a governmental decision (for sites in which energy facilities are regulated by a public utilities commission or co-located on government property), the need for power analysis has already been performed by the government applicant; or (2) if the impetus to provide power, either electric or nonelectric, is a private party decision, the project proponent would have already performed the analysis and will bear the risk of the need for power associated with the project. Further, for many new reactor projects the selected site will be the only site available, for example it may be co-located with an existing generation source, providing heat to an industrial facility, or providing secure power to a Federal facility. Similarly, for non-electric applications such as process heat and desalination, the market would make the decision regarding whether to use nuclear technology and, if so, what type should be use.

While advanced reactor projects commissioned by the Federal government should be still perform the necessary confirmation that the power is needed by a key stakeholder (presumably another government facility), private parties funding the implementation of an advanced reactor at a given site should receive the presumption of having appropriately identified a need for the power.

Page 54 of 140 38 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q23: Are there other special operating characteristics for advanced nuclear that the NRC and the CNSC (if applicable) should consider?

Inherent safety of designs that require no active safety systems to unsure operator and public safety

Treatment of Inherent Design Features in the regulatory framework (i.e., technical basis for reliability of an inherent feature)

Recognition of inherent safety characteristics in licensing process

Consider only credible design basis events (rather than core damage as a required design basis event despite being non-credible, as described in NuScales Lessons Learned Letter, ML21050A431)

Digital circuitry monitoring and requirements for online testing (digital twins)

Appropriate staffing and EPZ size reduction (as discussed elsewhere in the survey)

Fuel only-- Depends on the plant design Page 55 of 140 39 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

USNIC 2021 SURVEY TOPICS - Capitol Hill/States &

International Policy Issues (Q1-Q3)

Part 53 (Q4-Q9)

Reactor Type, Licensing (Q10-Q12)

US/Canada (Q13-Q15)

EPZ, Operators, Refueling (Q16-Q20)

NRC Fees, EIS (Q21-Q23)

Capitol Hill/States (Q23-Q27)

International/Commerce (Q29-Q32)

DOE Programs (Q28; Q33-39)

HALEU (Q40)

Issues (Q42, Q41)

Page 56 of 140 40 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q24: Please rank what Capitol Hill actions could be taken in the next few years that would be most helpful to developing and deploying Advanced Nuclear?

1 Create an Investment tax credit for new nuclear plants 2 Federal clean (non-emitting) energy standards that explicitly include nuclear 3 Carbon tax 4 Modify the current new nuclear Production tax credit (45J) 5 Co-funding of Advanced nuclear projects (beyond current DOE ARDP projects & DOD mobile microreactor project)

Page 57 of 140 41 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q25: If you answered "Other" in question 24, please elaborate

ITCs represent best option to promote deployment of advanced nuclear; Other options would include milestone based funding that uses funding distributions tied to milestone achievements to foster efficient use of government funding

Support funding for development / de-risking the HALEU fuel cycle

Financial backing to build out US technology HALEU supply ahead of commercial market need

Congress needs to push the executive branch to move forward on HALEU fuel supply via a competitive commercial process which takes advantage of existing capabilities, facilities, and licenses in the US

Authorize PPAs that include non-power grid reactors for DOD installations and for the processed heat required manufacturing sector

Tax incentives to consumers of large processed heat requiring should they employ nuclear to meet their needs

Congress should look at ways to incentivize the utilities to employ GEN IV reactor technologies

Fix NRC license review fee and schedule Page 58 of 140 42 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q26: What State actions could be taken in next few years that would be most helpful to developing and deploying Advanced Nuclear?

Investment tax credits (ITCs) or production tax 3 credits State clean (non-emitting ) energy 10 standards that explicitly include nuclear

ITCs/production tax credits AND State clean energy standards including nuclear 4

Elimination of moratoriums and/or paving way by passing or Other modifying legislation to legally allow for deployment of nuclear

Support for development of robust US fuel cycle Page 59 of 140 43 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q27: What States should be focused on first?

Virginia, Wyoming, Idaho, Washington

Virginia (state has nuclear strategic plan)

Ohio, Tennessee, North Carolina

Alaska, Puerto Rico

Maryland, Texas

States with existing nuclear plants in jeopardy of pre-mature closure

Should be all 50 state policy; however, if targeting states begin in de-regulated state markets Actions: Establish a value for non-emitting to level the playing field with otherwise mandated renewable portfolios; Inclusion of nuclear in clean energy standards; Include nuclear as clean true-green power Q28 in DOE section before Q33 Page 60 of 140 44 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q29: If you are seeking to export your design, do you intend to seek support from the Export-Import Bank or U.S. International Development Finance Corporation?

3 Note: lower % seeking funding than in 2020 1

12 Page 61 of 140 45 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q30: If you are seeking to export your design, would debt and/or equity financing from International Development Finance Corporation be helpful for your project?

Note: lower % seeking IDFC financing than in 2020 4

Developing and nations new to nuclear power need such financial support 1

Any financing options will be considered.

11 Page 62 of 140 46 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q31: What level of importance do you believe that the International Development Finance Corporation, World Bank, and other international financial institutions have in assisting on the export of North American advanced reactors?

6 Note: lower % seeking assistance than in 2020

Because financing represents a powerful tool for nuclear project development, ability for the United 7 States reactor vendors and project participants to have access to these tools directly supports competitiveness of US nuclear designs.

Support for regulatory infrastructure and financing of 0 independent regulator.

Provide strategic funding for significant portion of the total plant cost.

3 Page 63 of 140 47 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q32: How useful is the U.S. Department of Commerce's efforts to facilitate reactor exports?

5 7

Comments on next slide Page 64 of 140 48 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q32: How useful is the U.S. Department of Commerce's efforts to facilitate reactor exports? -

additional actions should Commerce be taking

Past opportunities with Department of Commerce have been beneficial in generating prospective market interest

Very useful-- Any time the USG can advocate on behalf of US companies is a good thing

Current actions being taken are useful

Useful to facilitate conversations between countries; they also should host forums for vendor-to-vendor communication to facilitate international supply chain conversations

Commerce is trying but not forceful enough-- need to be in advocacy role, not bystander role

Marginally useful; their efforts appear useful but absent an approach that matches (or balances) the state support from other countries, they come across primarily as a matchmaker.

Uncertain

Once designs mature, greater involvement of AR developers at general conference

For a reactor that provides decentralized energy, Commerce efforts can be made to promote the solution to remote application such as small communities and remote mining

Virtually useless so far-- "Team USA" is a travel and dining club; designate a lead agency and individual, assign them as the capture lead, then give them the appropriate incentives and tools to close a transaction for the strategic benefit of the United States Page 65 of 140 49 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

USNIC 2021 SURVEY TOPICS - DOE & HALEU Policy Issues (Q1-Q3)

Part 53 (Q4-Q9)

Reactor Type, Licensing (Q10-Q12)

US/Canada (Q13-Q15)

EPZ, Operators, Refueling (Q16-Q20)

NRC Fees, EIS (Q21-Q23)

Capitol Hill/States (Q23-Q27)

International/Commerce (Q29-Q32)

DOE Programs (Q28; Q33-39)

HALEU (Q40)

Issues (Q42, Q41)

Page 66 of 140 50 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q28: Do you plan to seek funding from DOE Loan Guarantee Program?

Evaluating DOE LPO and planning to talk with prospective customers about 6 Note: lower % seeking funding than 45% in 2020 DOE LPO as a financing option

Perhaps, depending on terms and conditions

Not in the short term-- possibly for factory build-out

Operator owners of our reactor design will need loan 9 guarantee

Loan guarantee program provides a valuable tool for project financing

Not needed Page 67 of 140 51 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q33: Was your company a recipient of the DOE GAIN (Gateway for Accelerated Innovation in Nuclear) program?

7 Note: similar to 2020 10 Page 68 of 140 52 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q34: What are your views regarding the DOE GAIN program? (multiple answers allowed)

Note: higher % seeking improvement than in 2020 Page 69 of 140 53 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q34: What are your views regarding the DOE GAIN program? (additional comments)

Program biased to DOE Laboratory research interests vs applications that are more fundamental to bringing new reactors to market.

Biased toward projects with the DOE labs; more science focused rather than paths to deployment of stronger designs.

GAIN approach should be broader and more fully funded.

Needs to also be able to fund industry directly. Cost share required from industry is burdensome.

GAIN provides legitimacy for work at national labs. The industry needs to do the work. National labs need to do basic R&D.

Increase number of applications and vouchers per organizationsuggest 3 active vouchers and 3 applications at a time.

The GAIN program is very good for jump-starting a program and getting access to the National Lab complex. Our company has benefited greatly from the program. It could have better funding, and/or allow for more than 2 awards. The implementation (especially contracting) across the various labs is not consistent, and could benefit from some intermural lessons learned.

Page 70 of 140

Q35: Do you plan on using the DOE Office of Nuclear Energy Funding Opportunity (FOA) Awards?

Note: higher % have received award than in 2020

DOE's contracting approach must be modernized More

Entirely depends on the program function. Additional funding awards should consider 100% vouchers to be applied comments to labs even for partnerships-- current cost share awards do not allow for that. Additionally, DOE should consider on next slide milestone-based approaches (e.g., NASA COTS program), similar to the SpaceX funding awards where payouts were contingent upon achieving milestones.

Our company has tried many times to receive an award, but every time DOE finds an excuse to not fund our company. We will continue to engage DOE.

Page 71 of 140 55 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q36: For people interested in FOA program, please provide your perspectives on the program (e.g., well managed, too complicated, insufficient $, insufficient awards)

Opportunities have been value-added, and administrative requirements commensurate with the value-added

Good. Well managed, spectrum of awards from deploy to R&D concept is good

FOA funded projects have rarely led to commercial success

Difficult to understand the selection process/criteria for the iFOA

Overly burdensome administrative and labor intensive process

Current FOAs are not well managed. Cost shares are ok, but could benefit from milestone-based approach (e.g., NASA COTS). Current payment structures cause unnecessary inflation in pricing, which is hugely detrimental to nuclear industry

Insufficient # of awards

Insufficient awards; awards not necessarily on merits of technology for timely deployment and do not recognize applications that provide path to near term deployment, vs. funding what amount to essentially "legacy" projects

Way too complicated and expensive to administer-- Refer to NIA's "SpaceX for Nuclear" report

Find a way to sustain the ARDP and ARC awards, but also provide ability to be directly funded via other RD&D funding opportunities

If partial awards are granted in lieu of full awards, that creates additional friction in executing awards and adds administrative burden and uncertainty on fulfilling non-funded part; suggest more opportunity for discussion/negotiation/resubmittal if partial award is planned on being awarded

Recommend more clarity on full program funding opportunity versus initial funding and more clear instructions related to submittal of costs; decrease timeline from award announcement to contract Page 72 of 140 56 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q37: Interest in using a milestone based program, that was authorized by the energy act, for current/future demonstration projects at DOE 7

5 0

5 Page 73 of 140 57 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q38: What new DOE Office of Nuclear Energy initiatives are needed?

Higher-confidence approach to HALEU supply

Continued support for access to HALEU and spent fuel disposition and fuel/spent fuel transportation

Defined program to build out commercial HALEU supply and deconversion to oxide

HALEU fuel supply and back end used fuel management strategy; HALEU is progressing but back end infrastructure could become a deployment barrier

DOE should have more communication and coordination with the NRC in support of US initiatives

New materials development FOA-type with industry leadership

Pick and stick with projects that actually show promise of near term demonstration and deployment

Fund companies that have real track record in the nuclear industry

Creating a funding opportunity for risk reduction awardees to proceed through demonstration

TVA-like program to actually authorize, procure and build a government owned plant -- the SpaceX model

New apolitical programs to drive clean energy research (including nuclear) without having to switch gears after changes in administration with a clear and targeted focus and goals (e.g. NIH)

Contracting reform. Real milestone-based program, not one that actually increases the reporting/administrative burden Page 74 of 140 58 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q39: Any additional perspectives on how US or foreign governments are doing to support nuclear (that we can convey to them so they can consider improving their performance)?

Significant support from UK government under its 10 point plan is supporting advanced technologies in the UK

US needs to solve the political issues associated with used fuel; Recycling should be pursued, but near-term with surface storage

Inclusion of nuclear in clean energy policy and support for efficiencies in the siting and regulation of nuclear projects

US doing terrible job in the support for the operating fleet and advanced reactors.

Foreign governments on the other hand seem to be gaining even more traction in supporting their domestic programs, as well as exports of nuclear technologies.

Work harder with industry to clear regulatory hurdles

Russia and China are eating our lunch; we need a durable policy (i.e., that will survive Administration changes) on how we will compete Page 75 of 140 59 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q40: If your design uses High-Assay Low-Enriched Uranium (HALEU) fuel, please provide answers for each question How much do you need in next Where do you plan to get it? How do you plan to ship it?

10 years?

20 MT First Tenex, then US sources Tenex to ship Insufficient design detail to confirm Parent body Appropriate containers It depends on how many reactors we Commercial market place if demand is there. Will design and license commercial HALEU sell. Max 200 Tons Can also produce it ourselves if the market shipping casks demands it Lab quantities in the short term, but US Strategic Reserve, weapons down-blending, Likely in metallic form. Depends on core reload quantities ultimately. or other commercial channels as available. regulations.

~180+ MTHM steady state by 2035 24MT Russia (until US capability is established) TBD 200-500 MT DOE, domestically if available, internationally if Existing canister designs support transport necessary TBD (1) DOE or (2) foreign suppliers if DOE cannot Existing transport packages meet our needs DOE 33,000 kg DOE, Y12, Centrus, TENEX Develop containers complying to 10CFR71 equivalent or IAEA Safety Standard SSR-6 Page 76 of 140 TBD US downblend or enrichment capability TBD 60 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q40: If your design uses High-Assay Low-Enriched Uranium (HALEU) fuel, please provide answers for each question (continued)

Where will you need it shipped to? How much are you budgeting How do you plan to pay for it?

for the cost of HALEU?

US location Private info private investment plus demo match UK Insufficient detail to confirm Confidential Fuel factory to reactor site if enrichment Ultimately $500/Ib FOAK plant should be free from DOE; facility is not near the fuel plant Then commercial market place rules Undetermined at this point-- A TBD USG grant for development quantities fabrication facility. Commercial contracts for production quantities.

TBD $100-$125mm TBD Private funding and customers TBD Private or where allowed, DOE programs To TRISO manufacturers in US and then $8,000/kg U DOE funding or from operations to Assembly facility in US or Canada TBD TBD TBD Page 77 of 140 61 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q40: If your design uses High-Assay Low-Enriched Uranium (HALEU) fuel, please provide answers for each question (continued)

Is a U.S. Government HALEU fuel bank What non HALEU fuel do you plan to use, important? and how much to you need in the next 10 years?

Yes None N/A Not enough for commercial use; Good None for FOAK of a few plants Yes-- It provides stability of prices and Not applicable to our design surety of supply Yes, if it serves as motivation to support Not applicable US capability Maybe, depends upon structure Yes None Yes None Yes None Yes None Page 78 of 140 62 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

USNIC 2021 SURVEY TOPICS - Issues Policy Issues (Q1-Q3)

Part 53 (Q4-Q9)

Reactor Type, Licensing (Q10-Q12)

US/Canada (Q13-Q15)

EPZ, Operators, Refueling (Q16-Q20)

NRC Fees, EIS (Q21-Q23)

Capitol Hill/States (Q23-Q27)

International/Commerce (Q29-Q32)

DOE Programs (Q28; Q33-39)

HALEU (Q40)

Issues (Q42, Q41, Concluding Insights)

Page 79 of 140 63 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q42: Additional comments (not provided in response to other questions)

Revisit role of ACRS-- ACRS scope is broad and allows them to interject on nearly any licensing action. Role should be revised to be more constructive, rather than simply performing a redundant independent review already performed by the NRC staff

Reliable (DOE) funding over long time periods

Sufficient NRC review resources

Certain statutory requirements in the AEA provide limitations in the area of security requirements (e.g., force-on force exercises, fingerprint collection, federal background checks) that may not be appropriate or necessary given the current environment or proposed operational programs for advanced reactors.

Page 80 of 140 64 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Q41: What issues keep you up at night?

(multiple answers allowed)

Rank Issue Score # of companies 2020 1 Availability of High Assay Low-Enriched Uranium 65% 11 #1 2 Ability to sell initial 10-20 commercial units (beyond initial demo unit) 53% 9 #2 3tie Current NRC reactor licensing process (other than Part 53) 47% 8 #7 3tie Sufficient government funding for the development of advanced reactor technologies 47% 8 #3 3tie Availability of financing for domestic deployment 47% 8 #4 6tie Administration change (in 4-8 years) to one that is not supportive of nuclear 29% 5 #5 6tie Availability of financing for international deployment 29% 5 #6 6tie Sufficient domestic manufacturing resources to produce your design 29% 5 9 Potential requirements for safeguards and security 24% 4 10 Part 53 (based on NRC current language) 18% 3 Other Clear waste disposition policy, sufficient federal resources, etc. - ---

Page 81 of 140 65 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey 17

Concluding High Level Insights (1 of 2)

Action needed to provide multi-decade U.S availability of High Assay Low-Enriched Uranium (HALEU) for advanced reactor deployment

Selling, financing, and deploying 10-20 commercial units (after initial demos) is important for industrys health (and to prove advanced nuclear can substantially contribute to worlds clean energy goals)

Fuel qualification, fuel cycle (facilities, higher enrichment, transportation), PRA &

operator staffing (for small & multi-modular facilities) need regulatory guidance

Although over 90% think Part 53 is important/desirable for industry (rest would use Part 50 or 52 or take different approach), majority of developers are dissatisfied or very dissatisfied with usefulness of current Part 53 Page 82 of 140 66 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

Concluding High Level Insights (2 of 2)

Only 35% of companies currently plan on using significant PRA input

2/3 of companies plan on licensing in Canada and U.S., so harmonization and reciprocity is desirable

When EPZ is applicable, all developers think appropriate EPZ is the site boundary

Almost 20% of advanced reactor designs do not require control room operators

U.S. government programs are important for international sales to compete against foreign national government sponsored competitors

Ongoing U.S. government funding and incentives for advanced nuclear are important, as well as states & U.S. government including nuclear in their clean energy standards Page 83 of 140 67 l U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey

U.S. Nuclear Industry Council 2021 Advanced Nuclear Survey For questions contact Cyril W. Draffin, Jr. Jerey S. Merri"eld Senior Fellow, Advanced Nuclear, Chairman, US Nuclear Industry Council U.S. Nuclear Industry Council Advanced Reactors Working Group Cyril.Draffin@usnic.org Je.Merri"eld@pillsburylaw.com Page 84 of 140

Advanced Reactor Stakeholder Public Meeting Break Meeting will resume at 1pm EST Microsoft Teams Meeting Bridgeline: 301-576-2978 Conference ID: 442 887 144#

Page 85 of 140

Role and Use of PRA in Support of Advanced Reactor Licensing Nathan Sanfilippo, Special Assistant Marty Stutzke, Senior Level Advisor for PRA Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation August 26, 2021 Page 86 of 140

Overview of the Graded PRA Initiative How It Started A Change in Direction How Its Going Next Steps Page 87 of 140

How It Started

In the spring of 2021, a working group was formed to develop viable options to grade the PRA to conform to the preliminary Part 53 language that had been issued.

The staff originally envisioned a three-phase process:

Phase 1 Develop a graded PRA approach Phase 2 Craft guidance Phase 3 Explore alternatives to PRA Page 88 of 140

Working Definitions as of the Advanced Reactor Stakeholders Meeting Held 5/27/2021 Note: These definitions are quoted from our presentation in the May 27th Advanced Reactor Stakeholder Meeting Slide Package (please see Slide 47 of ML21146A347).

Graded PRA approach

A process that uses bounding, conservative, and/or qualitative assessments to establish a PRAs scope, level of detail, degre e of plant representation, and/or level of peer review commensurate with the licensing stage (which dictates the level of detail and fin ality of the information used to develop the PRA) and how the PRA will be used in risk-informed decision-making.

Graded PRA

A PRA of appropriate degree of scope, level of detail, plant representation, and technical adequacy to support a specific advanced reactor licensing application.

Note: Graded should not imply that a design is not yet complete -acceptance of a graded PRA could only be considered if a design is well understood and conservatively modeled.

Dose/consequence-based criterion

A potential entry condition to enable a graded PRA that uses bounding, conservative, and/or qualitative assessments of the do ses or consequences arising from potential unplanned release scenarios, without consideration of the release scenario likelihood. Th is approach is being considered as a specific criterion for developing a graded PRA to adequately demonstrate that an applicant meets the intent of the Commissions Severe Accident Policy in an efficient and effective manner.

Page 89 of 140

A Change in Direction

Based on feedback during the Advanced Reactor Stakeholders public meeting held 5/27/2021, the staff learned that industry concerns were largely directed Leading Supporting at grading how PRA was used in the Role Role licensing process, rather than grading the technical content of the PRA itself.

There was general recognition from industry that the NLWR PRA standard How will the PRA be used in already offers opportunities to grade the the licensing process?

content of the PRA.

Page 90 of 140

How Its Going

Since that time, the staff has further explored the scope of the PRA and how it is used in licensing.

Significant effort has been invested in thoroughly understanding:

- The uses and role of the PRA in the licensing process,

- Whether those uses and role could be adequately addressed with other tools/techniques/bounding assessments, and

- How that information fits into the overall approach to licensing under Part 50, Part 52, and preliminary Part 53.

Page 91 of 140

operating experience accrues Operations Commercial Operations PRA Evolution Operations PRA Level of Detail and Plant Representation walkdowns and procedures Fuel Load Operating site License (OL) selected Combined License (COL)

Use OL or custom CP based on site COL to develop a selected subsequent DC. custom SDA, ML or DC COL Standard Design Manufacturing Design Approval (SDA) License (ML) Certification (DC)

Construction The scope of all PRAs considers:

Part 50 May reference Part 53 site Permit (CP) a. All radiological sources suitability review (SSR) site selected Part 52 b. All plant operating states May reference Part 52 or Part 53 Part 53 early site permit (ESP) c. All internal and external hazards Page 92 of 140

The Staff Is Considering Three Approaches to Safety Analyses The Dose-Based Deterministic Approach

Use of bounding analyses (e.g., MHA) and alternatives to PRA to a craft a deterministic safety analysis for reactors that meet an extremely low dose/consequence-based criterion.

The Traditional PRA Approach

Use of a PRA to support/confirm a more deterministic safety analysis (e.g., current Part 52 approach, use of IAEA Specific Safety Requirements SSR-2/1 approach, etc.).

The Enhanced PRA Approach

Use of a PRA in a leading role in the safety analysis (e.g., the LMP approach and preliminary Part 53 as currently envisioned).

Page 93 of 140

Uses of the PRA in the Licensing Process Traditional PRA Approach (supporting/confirmatory role)

Enhanced PRA Approach

Demonstrate that quantitative health (leading role) objectives (QHOs) are met

All uses in traditional PRA Dose-Based

Search for severe accident vulnerabilities approach Deterministic Approach

Support severe accident mitigation AND

Bounding or conservative analysis design alternatives (SAMDA) analysis

Licensing basis event (LBE) to demonstrate that QHOs are met

Other uses per Standard Review Plan selection

Qualitative methods to search for (SRP) 19.0, such as:

System, structure, and severe accident vulnerabilities o Design reliability assurance program component (SSC)

No risk-informed applications (D-RAP) classification

Maintenance/upgrade o Inspections, tests, analyses, and

Defense-in-depth (DID) requirement acceptance criteria (ITAACs) evaluation o Combined License (COL) Action Items

Facility Safety Program (FSP)

Voluntary risk-informed applications

Other uses from Part 53

Periodic PRA maintenance/upgrade Page 94 of 140

Potential Alternatives to PRA for Conducting a Systematic and Comprehensive Vulnerability Search

Master logic diagram (MLD)

Event sequence diagram (ESD)

Integrated safety assessment (ISA)

Process hazard analysis (PHA)

Checklist

Use a combination

What-if analysis of methods

Checklist/what-if analysis

Guidance needs to

Hazard and operability analysis (HazOp) be developed

Failure modes and effects analysis (FMEA)

Failure modes, effects, and criticality analysis (FMECA)

Layers of protection analysis (LOPA)

Etc., etc.

Page 95 of 140

Potential Entry Conditions for the Dose-Based Deterministic Approach Dose/consequence considerations Reactor thermal power Design incorporates one or more of the attributes identified in the Commissions Advanced Reactor Policy Statement (73 FR 60612; October 14, 2008)

Page 96 of 140

Next Steps Continue investigating entry conditions for the Dose-Based Deterministic Approach Seek guidance from Establish RES project to identify additional Agency expertise and evaluate qualitative methods for systematic and comprehensive vulnerability search Identify and resolve policy issues:

Advanced Reactor Policy Statement

PRA Policy Statement Coordinate with rulemaking activities:

Safety Goal Policy Statement

Part 53 (NRC-2019-0062; RIN 3150-AK31)

Severe Accident Policy Statement

Part 52 Lesson Learned (NRC-2009-0196;

Authority under Nuclear Energy and RIN 3150-AI66)

Innovation Modernization Act (NEIMA)

Page 97 of 140

Part 53 Rulemaking:

Role of the PRA Marc Nichol Senior Director, New Reactors August 26, 2021

Unified Industry Position on Part 53 Letter Industry perspectives relevant to Role of PRA Usefulness

All licensing approaches are viable

Less burdensome over the lifecycle of activities

Guidance will be important to explain how to meet the regulation Risk-Informed

NRC PRA policy statement: use of PRA to the extent it is practical

Primary expectation is that decisions are informed by the use of a PRA

In some cases alternatives to a PRA may provide equivalent benefits

Part 53 should allow a variety of roles and uses of the PRA

Allow for both leading and confirmatory/supporting roles

Flexibility on the Role of PRA Role of the PRA has been one of industrys greatest concerns

Must allow for both leading and confirmatory roles

Range of mix of deterministic and PRA A confirmatory option is important

Not everyone will pursue a leading role

NRC prior approval of confirmatory role as sufficient to meet Policy Statement

Accomplishing Risk-informing Benefits of Risk-informing

=

Integrated approach of PRA Deterministic Risk Risk- complements deterministic Criteria Information Informed

Characterize the overall residual risks of a design

Can help focus on issues of

=

safety significance Risk Deterministic Risk-Information Criteria Informed

Should yield greater operational flexibility after licensing

Spectrum of Risk-informed Approaches Risk-informed Continuum

NEI Paper Technology-Inclusive, Performance-Based and Risk-Informed Approaches for Assessing the Safety Adequacy of the Design for Part 53 Goals:

Advance discussion of how different approaches may fit under Part 53

More clearly illuminate the role of PRA and risk information Approach:

Establish a flexible framework of principles for a sufficient safety case

Build on elements of a TI-RIPB process for assessing safety adequacy

Present four examples across the spectrum of potential approaches

Demonstrate how each example meets the guiding principles

Each example has a different balance between deterministic safety analyses and risk information in what is always a risk-informed process

Key Elements of Part 53 Addressed Limits for protecting the public health and safety Safety functions Licensing basis events Defense-in-depth Design features Functional design criteria Safety categorization Notes

The paper does not imply an endorsement of the NRC preliminary rule text, but acknowledges that these key elements are important to the safety case

Other Part 53 elements are important to the licensing basis, but are not included since they do not have a primary effect on the TI-RIPB process

It is envisioned that the TI-RIPB process in the paper will inform future changes to

Principles for TI-RIPB Process

1. The plant meets the established limits for the adequate protection of the public health and safety.

2. The safety functions, design features and functional design criteria relied upon to meet the safety criteria are established.

3. The selected LBEs adequately cover the range of hazards that a specific design is exposed to.

4. The SSCs are categorized according to their safety significance.

5. The design reflects the application of an appropriate philosophy of defense-in-depth.

6. The special treatment for SSCs, and associated programmatic controls and human actions, provide reasonable assurance that the SSCs will perform the safety functions for which they are relied upon. (Not addressed at this time)

7. The scope and level of detail for the design and analysis of the plant in the licensing basis information adequately describes the safety case. (Not Page 105 of 140addressed at this time)

Example A: NEI 18-04 (Leading Role)

TI-RIPB Principle Approach to Meet Principle in Example A

1. Meet established limits for

PRA frequencies and consequences ensure LBEs are adequate protection within the F-C curve, and QHOs are not challenged

Deterministic safety analyses for DBAs validate safety case made by PRA

2. Establish the safety functions, PRA delineates the relevant safety functions, which define design features and functional safety features, which are used to select functional design design criteria criteria for each type of LBE

3. Selected LBEs adequately cover

PRA is the primary component of an iterative process to the range of hazards select the LBEs in a systematic and comprehensive manner

Deterministic methods are used to support the iterative process to select LBEs based on the PRA

4. SSCs are categorized according PRA is used to categorize SSCs according to the roles they to their safety significance play in satisfying the safety functions

5. Design reflects the application of PRA is used to establish DID through systematic evaluation of an appropriate philosophy of LBEs, with systematic determinations of adequacy, including defense-in-depth the need to account for uncertainties ©2021 Nuclear Energy Institute 9 Page 106 of 140

Example B: NEI 18-04 (Confirmatory Role)

TI-RIPB Principle Approach to Meet Principle in Example B

1. Meet established limits for

Deterministic analyses determine the limits are met adequate protection

PRA confirms F-C curve and the QHOs are not challenged

2. Establish the safety functions,

Deterministic analyses establish safety functions, safety design features and functional features and functional design criteria (e.g., use of ARDC) design criteria

PRA confirms or identifies vulnerabilities to address

3. Selected LBEs adequately cover

Deterministic methods are primary component of iterative the range of hazards and systematic process to select the LBEs

PRA supports deterministic methods in iterative process

4. SSCs are categorized according

Deterministic methods used to categorize SSCs according to their safety significance to the roles they play in the DBA analysis

PRA determines additional SSCs with special treatment

5. Design reflects the application of

Deterministic methods systematically establish DID and an appropriate philosophy of adequacy, including the accounting for uncertainties defense-in-depth

PRA confirms or adjusts DID to establish adequacy

Example C: IAEA TI-RIPB Principle Approach to Meet Principle in Example C

1. Meet established limits for

Deterministic analyses determine the limits are met adequate protection

PRA searches for cliff-edge effects, and can be used to confirm F-C curve and the QHOs are not challenged

2. Establish the safety functions,

Deterministic assessments and requirements establish design features and functional safety functions, principal technical requirements and design criteria design requirements (equivalent to NRC)

PRA at discretion/member state requirements to confirm

3. Selected LBEs adequately cover

Deterministic methods establish LBEs (Normal, AOO, DBA, the range of hazards and BDBE)

PRA informs through perspective on the frequencies

4. SSCs are categorized according

Deterministic assessments are primary means of to their safety significance categorizing SSCs and are informed by PRA insights

5. Design reflects the application of

Deterministic framework of five levels of DID an appropriate philosophy of

PRA results provide further assurance of DID adequacy defense-in-depth

Example D: Bounding Analysis TI-RIPB Principle Approach to Meet Principle in Example B

1. Meet established limits for

Deterministic analyses determine the limits are met adequate protection

Risk information* provides perspective on the margin and demonstrates that the QHOs are not challenged

2. Establish the safety functions,

Deterministic analyses establish safety functions, safety design features and functional features and functional design criteria (e.g., use of ARDC) design criteria

3. Selected LBEs adequately cover

Deterministic methods identify and confirm adequacy of the range of hazards events (one or small set) with bounding consequences

Risk information in limited role confirm events are bounding

4. SSCs are categorized according

Deterministic assessments conservatively categorize SSCs to their safety significance

Risk information at discretion to reduce conservatism and address non-safety SSCs

5. Design reflects the application of

Deterministic methods systematically and conservatively an appropriate philosophy of establish DID and adequacy defense-in-depth

Risk information may be used to inform process

Risk information may be from a simplified PRA, or alternative conservative and simpler systematic ©2021 Nuclear Energy Institute 12 Page 109 of 140 risk assessment approach.

Next Steps NEI White Paper on TIRIPB Approaches for Development of Licensing Bases for Part 53

Send for NRC review early to mid September (expected)

NRC feedback

Confirmation that the safety framework in the paper (i.e., guiding principles) is appropriate for Part 53

Agreement that examples in the paper sufficiently implement the safety framework

Whether more detail about the principles or examples is needed in order to inform Part 53 requirements

Advanced Reactor Stakeholder Meeting Status of Regulatory Guide Endorsing the Advanced Non-LWR PRA Standard U.S. Nuclear Regulatory Commission August 26, 2021 Page 111 of 140

Development of Regulatory Guidance on PRA Acceptability for NLWRs

Consistent with current regulatory principles for LWR PRA acceptability

Supports Licensing Modernization Project implementation

Provide staff position and endorsement in a trial use Regulatory Guide

Stakeholders can use the trial use RG as a basis for preparing near-term initial licensing applications.

No public comment period before issuance. Trial use period is the public comment period for final Reg Guide.

Draft white paper issued January 15, 2021 (ML21015A434). Issues not addressed in RG 1.247 will be included in later documents.

Timing:

Support near-term applicants

Promote long-term regulatory stability 2

Page 112 of 140

Documents to be endorsed

In February 2021, ASME and ANS jointly issued ASME/ANS RA-S-1.4-2021, Probabilistic Risk Assessment Standard for Advanced Non- Light Water Reactor Nuclear Power Plants

In May 2021, NEI submitted NEI 20-09, Rev. 1, Performance of PRA Peer Reviews Using the ASME/ANS Advanced Non-LWR PRA Standard

Initially submitted May 2020.

Public meetings held July, October and December 2020.

3 Page 113 of 140

RG 1.247 - ACCEPTABILITY OF PROBABILISTIC RISK ASSESSMENT RESULTS FOR ADVANCED NON-LIGHT WATER REACTOR RISK-INFORMED ACTIVITIES

Structure is similar to RG 1.200 - An Approach for Determining the Technical Adequacy of PRA Results for Risk-Informed Activities

Draft provided to ACRS to support September 20, 2021, Subcommittee meeting. Will be public prior to September 20.

No formal solicitation of comments for a trial use Reg Guide. Public meeting to be planned for October 2021.

4 Page 114 of 140

Schedule 5

Page 115 of 140

Stakeholders Meeting Advanced Reactor Content of Application Project Risk-Informed Inservice Inspection/

Inservice Testing Programs Interim Staff Guidance Page 116 of 140

Background

The Advanced Reactor Content of Application Project (ARCAP) has been developing guidance to support the review of non-LWRs, modular LWRs and stationary micro-reactors.

The guidance has been developed in the form of draft Interim Staff Guidance (ISG) documents.

One of those draft documents is the ISG on Risk-Informed ISI/IST Programs (ADAMS Accession No. ML21216A051)

The purpose of this ISG is to facilitate the review of advanced reactor applications that use a risk-informed approach to develop or modify the scope of their ISI/IST programs.

Page 117 of 140

Background (cont.)

The guidance in this ISG can be applied to any non-LWR, small modular LWR or stationary micro-reactor applying for a CP, OL, COL, DC or ML under 10 CFR 50 or 52.

The ISG guidance requires the use of risk information from a plant-specific PRA that is in conformance with an NRC endorsed PRA standard.

The ISG guidance will be updated to apply to applications under Part 53, when Part 53 is issued.

Page 118 of 140

Approach

The ISG is divided into two parts:

Part 1 applies to LWRs Part 2 applies to non-LWRs

LWRs have existing requirements for ISI/IST program content and implementation in 10 CFR 50.55a, which are based upon NRC endorsed ASME Code requirements.

LWRs also have existing guidance (RGs 1.175/1.178) that describe one acceptable way to make risk-informed changes to their ISI/IST programs.

10 CFR contains only general requirements (e.g., 50.34(b)(6)(iv))

related to non-LWR ISI/IST programs, although ASME has recently issued Section XI, Division 2, which NRC is reviewing for application to non-LWR ISI programs.

Page 119 of 140

Part 1 - LWRs

LWR ISI requirements are listed in 10 CFR 50.55a and are based upon ASME Section XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components.

Guidance for making risk-informed changes to LWR ISI programs is given in RG 1.178 An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping.

LWR IST requirements are listed in 10 CFR 50.55a and are based upon the ASME Operation and Maintenance of Nuclear Power Plants Code (OM Code), Division 1.

Guidance for making risk-informed changes to LWR IST programs is given in RG 1.175 An Approach for Plant-Specific Risk-Informed Decisionmaking: Inservice Testing.

For LWRs, a risk-informed approach to ISI/IST can be applied to all or Page 120 of 140 only a portion of the program.

Part 1 - LWRs (cont.)

Therefore, a framework for evaluating a risk-informed approach to LWR ISI/IST programs exists and is used in the ISG as the basis for the review guidance.

The review guidance consists of the following major elements:

The baseline for evaluating risk-informed changes to ISI/IST programs are the requirements in 10 CFR 50.55a.

The plant-specific PRA must model the components included in the ISI/IST programs and must be used to assess the change in risk from the 10 CFR 50.55a baseline ISI/IST programs.

The acceptability of any risk-informed changes to the baseline ISI/IST programs is evaluated using the 4 principles in RGs 1.178 and 1,175:

1. Maintaining defense-in-depth

2. Maintaining safety margins

3. Keeping any increase in risk small (using RG 1.174 criteria)

4. Monitoring program effectiveness Page 121 of 140

Part 1 - LWRs (cont.)

Key issues in reviewing LWR risk-informed changes to ISI/IST:

Advanced designs may utilize passive components to perform active safety functions. These components may not fall within the traditional IST program scope.

Therefore, applicants will need to propose (based on risk considerations) which of the passive components need to be included in the programs, what degradation mechanisms apply to the components, what inspection/testing techniques are capable of detecting the degradation, what are the appropriate inspection/testing frequencies and what are the acceptance criteria?

The review will also need to assess whether portions of the risk-informed ISI/IST programs are included in other programs (e.g., maintenance) and, if so, do the other programs adequately cover the risk-informed ISI/IST requirements?

Page 122 of 140

Part 1 - LWRs (cont.)

The review of risk-informed ISI/IST programs for LWRs include the following:

Is the PRA based upon an NRC endorsed PRA standard?

Does the PRA model the plant-specific components in the ISI/IST programs?

Have the programs been expanded to cover any passive components with active safety functions?

Are the inspection/testing techniques that differ from 10 CFR 50.55a requirements sufficient to detect the degradation?

Was the guidance in RG 1.175/178 used to determine the acceptability of changes to inspection/testing techniques and/or frequencies?

Are acceptance criteria defined for the inspection/testing that differs from 10 CFR 50.55a?

Is there a process defined for tracking any degradation and determining what actions, if any, are needed?

Page 123 of 140 What QA applies to the programs?

Part 2 - Non-LWRs

As stated previously, 10 CFR has only general requirements related to non-LWR ISI/IST programs.

For non-LWR ISI, applicants are expected to use the risk information from their plant-specific PRA to identify the piping, reactor coolant boundary, pressure retaining and passive components and their supports to be included in the program, along with other components whose failure could prevent a safety function from being accomplished.

For non-LWR IST, applicants are expected to use the risk information from their plant-specific PRA and associated design reviews to identify the active valves, pumps and dynamic restraint devices and the passive components with active safety functions to be included in the program.

For non-LWRs, the ISG assumes that the ISI/IST programs will be Page 124 of 140 risk-informed (i.e., no partial risk-informed programs).

Part 2 - Non-LWRs (cont.)

For non-LWR ISI, the ISG is based upon the applicant using the requirements in ASME Section XI, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants (which is the subject of draft RG-1383).

Section XI, Division 2, allows the applicant to develop an ISI program specific to the technology of the non-LWR design using expert panels and plant-specific risk information to:

Identify the components to be included in the program, Develop reliability targets for the components in the program, Identify the degradation mechanisms applicable to the materials and operating conditions of the design, Identify inspection techniques (RIM strategies) applicable to the design, Develop inspection frequencies for the components, and Where the acceptance criteria in Appendix VII of Section XI, Div. 2, are not used, develop and justify acceptance criteria for the inspections.

Page 125 of 140

Part 2 - Non-LWRs (cont.)

For non-LWR IST, the ISG allows the applicant to develop an IST program specific to the technology of the non-LWR design. The program must be based on the risk information from the plant-specific PRA. The application needs to describe and justify:

How the components in the program were selected, The specific testing to be performed for each component, The frequency of testing for each component, The reliability and performance targets for each component, and The acceptance criteria for each test.

The ISI/IST programs will also need to describe how trends in reliability and performance degradation are tracked and what actions are to be taken when degradation in performance or reliability is detected.

Page 126 of 140

Part 2 - Non-LWRs (cont.)

Key issues in reviewing non-LWR risk-informed ISI/IST programs:

As with advanced LWR designs, non-LWRs may rely more on passive components to perform active safety functions.

Accordingly, applicants will need to develop and justify IST activities capable of assessing the operational readiness of those components.

Non-LWR designs will likely have limited data applicable to the degradation of material and component reliability and performance at the operating conditions of the design. This issue was addressed when new designs were being considered under 10 CFR 52. Regulatory Issue Summary (RIS) 2012-08 (Rev. 1), Developing Inservice Testing and Inservice Inspection Programs Under 10 CFR Part 52, July 17, 2013, provides useful information on how to address this issue.

Reliability targets and inspection/testing frequencies will need to be derived from the PRA.

Page 127 of 140

Part 2 - Non-LWRs (cont.)

The review of risk-informed ISI/IST programs for non-LWRs include the following:

Is the PRA based upon an NRC endorsed PRA standard?

Does the PRA model the plant specific components in the ISI/IST programs?

Are the degradation mechanisms of concern identified?

Are the proposed inspection/testing techniques capable of detecting the degradation of concern?

Are there acceptance criteria identified for each inspection/test?

Was risk information used to identify the components included in the program and their inspection/testing frequencies?

Is there a process for tracking trends in degradation and determining what actions, if any, are needed?

What QA applies to the programs?

Page 128 of 140

NRC Preparations for Advanced Reactor Exports Follow-Up Lauren Mayros International Policy Analyst Export Controls and Nonproliferation Branch Office of International Programs Periodic Advanced Reactor Stakeholders Meeting August 26, 2021 Page 129 of 140

AREWG Purpose and

Background

Forward looking in the spirit of innovation and transformation.

Keep pace with fast moving developments in the field of advanced reactors.

Ensure that the NRC is prepared to license the export of these technologies in an independent, predictable and efficient way.

Page 130 of 140

AREWG Mandate

Evaluate NRCs readiness to complete exports (10 CFR 110) of advanced reactors to other countries consistent with NRCs Principles of Good Regulation (independence, openness, efficiency, clarity, and reliability).

Assess if current level of review for advanced reactors is still appropriate.

Conduct outreach to prospective vendors of advanced reactors on NRCs export licensing process.

Develop a communication plan for future outreach.

Page 131 of 140

OIP

OGC

NMSS

NSIR Participants

NRR

RES

Department of Energy/National Nuclear Security Administration

Argonne National Laboratory Page 132 of 140

Design Types Studied

1) high temperature gas-cooled reactors

2) sodium fast reactors

3) fluoride salt-cooled high temperature reactors

4) molten salt reactors, including liquid fluoride salt and liquid chloride salt-cooled reactors

5) small heat pipe reactors.

Page 133 of 140

Conclusions and Recommendations

1. 10 CFR Part 110 is generally ready to license the materials and components associated with the 5 types of advanced reactor types studied.

2. Identified one advanced reactor system that is not clearly captured under Part 110 for export - the use of salt as a coolant.

3. Recommended several clarifying changes to Part 110 to remove any ambiguity that advanced reactors are covered under Part 110, i.e. fuel cladding other than Zirc. Tubes and salt.

4. Recommended working with the USG interagency to coordinate the recommended changes to Part 110 with the technical agenda of the NSG and conduct industry outreach on its conclusions.

5. Did not recommend changing the level of review for applications involving material and/or components for advanced reactors, i.e.

Commission level review.

Page 134 of 140

Example of One Proposed Clarification

Current Entry in 10 CFR Part 110, Appendix(6):

Zirconium tubes, i.e., zirconium metal and alloys in the form of tubes or assemblies of tubes especially designed or prepared for use as fuel cladding in a nuclear reactor.

Proposed Clarification: Cladding, i.e. any material especially designed or prepared for use as nuclear fuel cladding Page 135 of 140

AREWG Public Report Public Website

https://www.nrc.gov/about-nrc/ip/us-nrc-prep-export-advanced-reactors.html

https://www.nrc.gov/about-nrc/ip/export-import.html ADAMS

https://adamswebsearch2.nrc.gov/webSearch2/main.j sp?AccessionNumber=ML21194A213 Hyperlink

The Advanced Reactor Export Working Group Public Report Page 136 of 140

Next Steps We want to hear from you!!

Would you prefer rulemaking or a reg guide to clarify the provisions for advanced reactor exports under Part 110?

Page 137 of 140

To contact the NRC Office of International Programs 301-287-9056 Lauren Mayros 301-287-9088 Lauren.Mayros@nrc.gov Page 138 of 140

Thank You!

Any questions?

Page 139 of 140

Future Meeting Planning

The next periodic stakeholder meeting is scheduled for September 29, 2021.

If you have suggested topics, please reach out to Margaret.O'Banion@nrc.gov Page 140 of 140

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