ML23130A097

From kanterella
Jump to navigation Jump to search
M230516: Slides/Supporting Presentation Material - Staff - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors
ML23130A097
Person / Time
Issue date: 05/16/2023
From:
NRC/OCM
To:
Shared Package
ML23067A030 List:
References
M230516, 10 CFR Part 53, NRC-2019-0062, RIN 3150-AK31
Download: ML23130A097 (26)
v • d • e


Text

Scott Morris Deputy Executive Director for Reactor and Preparedness Programs 2

Andrea Veil, Delivering on the Requirements of the Nuclear Energy Innovation and Modernization Act Mohamed Shams, Overview of Draft Proposed Rule Development and Addressing Stakeholder Comments Nanette Valliere, Draft Proposed Rule Structure and Key Topics Martin Stutzke, Development of Innovative Risk Assessment Methodology for Part 53 Tara Inverso, Leveraging Innovation in the Rulemaking Process 3

Andrea Veil Director, Office of Nuclear Reactor Regulation 4

o On target to complete the rulemaking in advance of the NEIMA schedule o Risk-informed, performance-based, and technology-inclusive o Achieves an equivalent level of safety to existing regulations 5

Rulemakings on emergency preparedness, Leveraging innovative approaches under physical security, and environmental impacts 01 08 10 CFR Parts 50 and 52 Trial use guidance on PRA acceptability Addressing applicant use of Licensing for non-light-water reactors 02 07 Modernization Project concepts ASME Code Sections on High Temperature Incorporating licensing efficiencies Reactors & Reliability and Integrity Management 03 06 in guidance Guidance on fuel qualification 04 05 Making improvements in NRC processes for advanced reactors 6

Stakeholder Draft proposed rule Continuing Engagement input Considered feedback Engagement Expected, planned for, and and evolved the to continue during actively sought draft proposed rule public comment period 7

Mohamed Shams Director, Division of Advanced Reactors and Non-Power Production and Utilization Facilities, Office of Nuclear Reactor Regulation 8

o Reflects internal collaboration and stakeholder feedback o Incorporates technology-inclusive, performance-based approaches o Embodies Commission policy decisions 9

Framework A Framework B o Responsive to stakeholder Subpart A - General Provisions feedback Technology-inclusive PRA-led approach traditional framework o Flexible licensing alternatives Technology-inclusive o Technology-inclusive traditional framework approaches AERI 10

Balances level of detail Enables flexibility Embraces adaptability For effective and consistent implementation Performance-based approaches and Optimal combination of programs, design with prescriptive methods in guidance broadening code and standard accessibility features, and human actions to demonstrate safety 11

Nanette Valliere Senior Project Manager, Division of Advanced Reactors and Non-Power Production and Utilization Facilities, Office of Nuclear Reactor Regulation 12

Enclosure 4 to SECY-23-0021 Discusses these topics and Outlines possible implications provides the rationale for the of adopting alternative NRC staffs recommendations approaches for each topic 13

Tied to Existing Regulatory Framework ALARA in Part 53 Beyond-design-basis events (BDBEs)

Generally consistent with current NRC requirements Inclusion in licensing bases Allows flexibility to combine design dates back decades attributes & programmatic elements Regulatory justification for rules Includes a technology-inclusive played role in labeling performance goal BDBEs affected plant designs Is supported by performance-based guidance 14

Part 53 Innovations Facility Safety Program Generally Licensed Reactor Operators

  • Allows licensees to continue to
  • Addresses whether reactor operators leverage PRA insights during operation have a role in maintaining and fulfilling safety functions
  • Assesses potential changes to plant hazards and considers risk reduction
  • Incorporates greater operational measures, when appropriate flexibility 15

Martin Stutzke Senior Technical Advisor for Probabilistic Risk Assessment, Division of Advanced Reactors and Non-Power Production and Utilization Facilities, Office of Nuclear Reactor Regulation 16

Defense-in-Depth Provisions

§ 53.250, § 53.450 Overall Framework A Design Ensuring a Comparable (crosswalks, 2. Change is consistent Requirements with defense-in-depth Level of Safety existing standards) philosophy. § 53.210, § 53.440

1. Change meets current regulations unless it is
3. Maintain sufficient specifically related to safety margins.

a requested exemption. Integrated Decision Making

4. Proposed changes in
5. Use performance-risk are small and are measurement consistent with the strategies to monitor Framework A is consistent with Performance changes.

Commissions Safety Goal Policy Statement. Risk Metrics the principles of risk-informed Monitoring § 53.220, § 53.450 integrated decision making Subparts F, I RG 1.174 (QHOs or described in RG 1.174 Risk-Informed surrogates)

Integrated Decision Making 17 17

o Defines an acceptable level of radiological risk, i.e.,

how safe is safe enough o Provides one element of the safety criteria o Implements Commission policies o Consistent with guidance for performance-based regulation in NUREG/BR-0303 o Consistent with SRM-SECY-98-144 concerning risk-informed and performance-based regulation o Applies to all reactor technologies 18

o Provides alternative to PRA o Achieves underlying purposes of Commission policies o May be used by plants with small fission product inventories and straightforward designs o AERI entry conditions are not safety or siting criteria 19

Tara Inverso Director, Division of Security Operations, Office of Nuclear Security and Incident Response 20

o Frequent meetings with NRC Steering and Advisory Committees o Close coordination with ACRS on key topics of interest o Developed core team of SMEs across the agency Result: Shorter overall rulemaking schedule 21

Pre-Rule Phase Enhanced Part 53 Approach Steps Less frequent release 20+ iterations of draft rule of rule language (if language released any)

Less frequent 24 public meetings held engagement with 16 ACRS meetings conducted stakeholders and ACRS 126 letters received Result: Demonstrated the flexibility and scalability of NRCs rulemaking process to achieve positive outcomes.

22

Addressing challenges:

Aligning on rulemaking scope Engaging on key issues Developing supporting guidance o Reviewing the proposed rule within a 60-day public comment period 23

o Conduct a multiday public meeting during the proposed rule public comment period o Provide a formal response to public comments o Engage with ACRS 24

Scott Morris Deputy Executive Director for Reactor and Preparedness Programs 25

  • ACRS - Advisory Committee on Reactor
  • NUREG - U.S. NRC technical report Safeguards designation
  • AERI - Alternative Evaluation for Risk
  • NUREG/BR - NUREG brochure Insights
  • ALARA - As Low As is Reasonably
  • RG - Regulatory Guide Achievable
  • SMEs - Subject Matter Experts
  • ASME - American Society of
  • SRM - Staff requirements Mechanical Engineers memorandum
  • BDBEs - Beyond-Design-Basis Events
  • QHOs - Quantitative Health Objectives
  • CFR - Code of Federal Regulations
Retrieved from "https://kanterella.com/w/index.php?title=ML23130A097&oldid=3537335"