ML21337A141
| ML21337A141 | |
| Person / Time | |
|---|---|
| Issue date: | 12/03/2021 |
| From: | NRC/OCM |
| To: | |
| Shared Package | |
| ML21301A174 | List: |
| References | |
| M211209 | |
| Download: ML21337A141 (27) | |
Text
Dan Dorman Executive Director for Operations 2
Andrea Veil, Part 53 Vision Mohamed Shams, Transformative Attributes and Licensing Framework Comparison Nanette Valliere, Overview and Stakeholder Feedback Michele Sampson, Performance-Based Security and Emergency Preparedness Provisions Ilka Berrios, Rulemaking Process and Outreach 3
Andrea Veil Director, Office of Nuclear Reactor Regulation 4
o Developing an innovative, predictable, and appropriately flexible framework o Executing our Implementation Action Plans o Providing equivalent level of safety with operational flexibility 5
o Leveraging risk-informed approaches o Taking into consideration stakeholder requests for a more traditional, deterministic option o Developing options on the appropriate treatment of fusion technologies 6
Mohamed Shams Director, Division of Advanced Reactors and Non-Power Production and Utilization Facilities 7
PA R T 5 3 l T R A N S F O R M AT I V E Part 53 builds on a strong foundation of Commission policies and decisions F E AT U R E S o Evolves use of risk o Leverages performance-based requirements o Modernizes licensing basis change process o Includes consequence-oriented scalable requirements o Enables operational flexibility o Optimizes balance between flexibility and predictability Establishes a Transformative Regulatory Framework 8
PA R T 5 3 l M O D E R N Part 53 evolves existing requirements into a modern, risk-informed, performance-based approach 9
Frequency & Consequence-Oriented Requirements Technology Inclusive Explicit Consideration of Defense in Depth QHOs in Rule Expanded Use of Graded Equipment Performance Requirements Part 53 Prescriptive Requirements Optimized for Specific Technology Augmented for Operating Experience Conservative Assumptions & Analyses QHOs Support Deterministic Requirements Parts 50/52 vs Quantitative Health Objectives (QHOs) - Risk of:
Immediate health effects within 1 mile of site < 5E-7/year Latent health effects within 10 miles of site <2E-6/year
PA R T 5 3 l S A F E T Y & S C A L A B I L I T Y Equivalent Safety Both approaches are equally viable PART53 Risk-informed, performance-based requirements scaled based on design features and safety margin PARTS50/52 Deterministic requirements define the design capabilities required to achieve the desired margin 10
Nanette Valliere Senior Project Manager, Division of Advanced Reactors and Non-Power Production and Utilization Facilities 11
Demonstrating safety Leveraging the best of the past and developing new tools for the future Crediting technological advancements Operational flexibilities with increased margins of safety Prioritizing risk-informed and performance-based approaches Accommodating various advanced reactor technologies Part 53 12
Effective Coordination 5 years of effective coordination to support development of this novel regulatory framework.
Relies on existing safety goals, safety performance expectations, and guidance Facilitates staff review efforts Leverages transformative methodology from Licensing Modernization Project Licensing Modernization Project Funded by DOE and developed by the U.S. nuclear industry.
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Added requirements for safe, stable end state and subcritical conditions Offered a licensing pathway that includes prototype testing 08 07 06 05 Will provide a detailed explanation of the integrated intent of the rule Expanded activities under a manufacturing license Provided a traditional, deterministic option Decoupled requirements for normal operation 01 02 03 04 Eliminated the two-tier structure Formulated QA requirements to allow broader set of codes and standards The staff is listening to all stakeholders and has made changes in response to stakeholder feedback.
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Michele Sampson Deputy Director, Division of Physical and Cyber Security Policy, Office of Nuclear Security and Incident Response 15
Providing an equivalent level of safety and security Developing effective guidance to support a performance-based regulatory framework Leveraging the Emergency Preparedness for Small Modular Reactors and Other New Technologies Rulemaking 16
Part 53 Options for Traditional Physical Security Programs or New Performance-based Physical Security Traditional Access Authorization and Fitness for Duty Programs Inherent Design Features for Security Protection of Special Nuclear Material Scaled Access Authorization and Fitness for Duty 17
o Options for traditional cybersecurity regulation or new consequence-based program o Protection of safety and security critical digital assets o Defense in depth 18
Ilka Berrios Branch Chief, Reactor Rulemaking and Project Management Branch, Office of Nuclear Material Safety and Safeguards 19
20 PRELIMINARY PROPOSED RULE LANGUAGE AND PUBLIC MEETINGS
Ongoing Stakeholder Outreach July 2023 Publish Proposed Rule and Draft Key Guidance with a 60-day public comment period July 2025 Publish Final Rule and Key Guidance Draft Proposed Rule to Commission February 2023 December 2024 Draft Final Rule to Commission 21
Broadening engagement:
o Topic specific public and ACRS meetings o Releasing initial and revised preliminary proposed rule language o Further considering stakeholder comments 22
Over 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> spent in 12 public topical meetings Next meeting scheduled for January 6, 2022 Over 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> spent in 13 meetings with ACRS Next meeting scheduled for December 16-17, 2021 Over 173 public comment submittals have been received 23
Addressing challenges:
o Alignment on rulemaking scope o Engagement on key issues o Timing of guidance development Remaining risk:
o 60-day public comment period 24
o Continued frequent engagement with all stakeholders o Revising preliminary rule language, as appropriate, based on stakeholder engagement 25
Dan Dorman Executive Director for Operations 26
ACRS Advisory Committee on Reactor Safeguards CFR Code of Federal Regulations DOE Department of Energy QA Quality assurance QHO Quantitative health objectives NEIMA Nuclear Energy Innovation and Modernization Act NMSS Office of Nuclear Material Safety and Safeguards NRR Office of Nuclear Reactor Regulation NSIR Office of Nuclear Security and Incident Response PRA Probabilistic risk assessment US United States of America 27