ML20206L363
| ML20206L363 | |
| Person / Time | |
|---|---|
| Issue date: | 07/24/2020 |
| From: | Beverly Smith Office of Nuclear Reactor Regulation |
| To: | |
| Betancourt L, NRR, 415-6146 | |
| Shared Package | |
| ML20206L360 | List: |
| References | |
| Download: ML20206L363 (13) | |
Text
2018 International Congress on Advances in Nuclear Power Plants Modern Risk-Informed Regulatory Framework Brian Smith Deputy Director, Division of Advanced Reactors and Non-Power Production and Utilization Facilities, Office of Nuclear Reactor Regulation
ADVANCED REACTORS STAKEHOLDERS NEIMA NEICA PUBLIC 2
Broad Landscape 3
Broad Landscape of Designs
Advanced Reactor Vision and Strategy 4
4
Strategy 1 Knowledge, Skills and Capability Strategy 2 Computer Codes
& Review Tools Strategy 3 Flexible Review Processes Strategy 5 Policy and Key Technical Issues Strategy 6 Communication Strategy 4 Consensus Codes and Standards ONRL Molten Salt Reactor Training Knowledge Management Competency Modeling Regulatory Roadmap Non-LWR Design Criteria ASME BPVC Section III Division 5 ANS Standards 20.1, 20.2 30.2, 54.1 ASME/ANS Non-LWR PRA Standard Siting near densely populated areas (SECY 0045)
Insurance and Liability Consequence Based Security (SECY-18-0076)
NRC DOE Workshops Periodic Stakeholder Meetings NRC/DOE GAIN, VTR & NEICA MOUs Code assessment for transient and accident analysis WGSAR Licensing Modernization Project (LMP)
Functional Containment (SECY-18-0096)
EP for SMRs and ONTs (SECY-18-0103)
Environmental Review Micro Reactor ISG Fast Reactor Training Micro Reactor Policy issues HTGR Training Code Development/V&V Environmental GEIS SECY-20-0020 Technology Inclusive Content Applications Project (TICAP)
NRC DOE DOD Micro Reactor MOU Memorandum of Cooperation with CNSC New Rulemaking 10 CFR Part 53 Inspection and Oversight 5
Advanced Reactor Readiness 5
NRC//DOE MOU on Adv Rx Demo Program Code assessment for fuel analysis Code assessment for accident dose analysis Code assessment for radiation protection analysis Code assessment for fuel cycle analysis
Facilitating Innovation with an Integrated Safety Approach Fuel Performance Functional Containment Siting Emergency Preparedness Environmental Insurance SSC Classification
& Event Selection Holistically Considering Consequences &
Safety Margins 6
6
Developing a Modern Risk-Informed Framework SECY-19-0117 NEI-18-04 RG 1.233 6 LMP Pilots Licensing Modernization Project (LMP) 7 7
Risk-Informing the Content of Applications Application LMP BDBE Safety-Related SSCs Non-Safety-Related SSCs Non-Safety-Related SSCs With Special Treatment Safety Classification Advanced Reactor Design 8
8
Pathway to New Regulatory Framework
- Part 53
- NEIMA required rulemaking to establish a technology-inclusive, risk-informed and performance based regulatory framework
- Rulemaking Plan Issued in April 2020 - SECY-20-0032
- Builds on current activities including the Licensing Modernization Project
- Significant stakeholder engagement planned 9
Modernizing the Environmental Review 10
Integrated Review Approach 11 Executing Strategies for Near-Term Reviews
- OKLO Aurora COL application docketed
- Preapplication reviews underway
- Meetings/White papers/Topical reports
- Timely and effective reviews
- Core review team
- Integrated safety review to reach reasonable assurance of adequate protection finding
- Exemptions where appropriate for non-LWR technologies
- Guidance available
- Advanced Reactor Design Criteria (RG 1.232)
- Licensing Modernization Project (RG 1.233)
- ISG for environmental review
- Key policy issues resolved
- Functional containment
- Risk-informed event selection
- SSC classification
- Defense-in-depth
Pre-Application Engagement is Encouraged
- Regulatory Review Roadmap
- Encourages early engagement with NRC
- Stresses use of Regulatory Engagement Plans
- Interact in meetings or in review of white papers, technical reports, topical reports, etc.
20 12
- Regulatory Issue Summary (RIS) 2017-08
- Request pre-application and application plans
- Robust pre-application engagement program
- May lead to shorter and more predictable review schedules
- NRCs Advanced Reactor Website o https://www.nrc.gov/reactors/new-reactors/advanced.html References 21 13