ML21236A029
| ML21236A029 | |
| Person / Time | |
|---|---|
| Issue date: | 08/23/2021 |
| From: | NRC/NRR/DANU |
| To: | |
| O'Banion, Maggie | |
| References | |
| Download: ML21236A029 (3) | |
Text
Advanced Reactor Program - Summary of Integrated Schedule and Regulatory Activities*
Strategy 1 Knowledge, Skills, and C apability Legend Strategy 2 Computer Codes and Review Tools Concurrence (Division/Interoffice) EDO Concurrence Period Strategy 3 Flexible Review Processes Federal Register Publication Commission Review Period**
Strategy 4 Consensus Codes and Standards Public Comment Period ACRS SC/FC (Scheduled or Planned)
Strategy 5 Policy and Key Technical Issues Draft Issuance of Deliverable External Stakeholder Interactions Strategy 6 Communication Final Issuance of Deliverable Public Meeting (Scheduled or Planned)Version Present Day 8/23/21 2020 2021
Regulatory Activity
Development of non-Light W ater Reactor (LW R) Training for Advanced Reactors (Adv. Rxs) (NEIMA Section 103(a)(5))
1 FAST Reactor Technology xx High Temperature Gas-cooled Reactor (HTGR) Technology xx Molten Salt Reactor (MSR) Technology xx Competency Modeling to ensure adequate workforce skillset x Identification and Assessment of Available Codes x Development of Non-LW R Computer Models and Analytical Tools Code Assessment Reports Volume 1 (Systems Analysis) x Reference plant model for Heat Pipe-Cooled Micro Reactor x
Reference plant model for Sodium-Cooled Fast Reactor x
Reference plant model for Fluoride-Salt-Cooled High-Temperature Reactor x Reference plant model for Gas-Cooled Pebble Bed Reactor Reference plant model for Molten Salt Fueled Reactor Code Assessment Reports Volume 2 (Fuel Perf. Anaylsis) x FAST code assessment for metallic fuel x FAST code assessment for TRISO fuel x Code Assessment Reports Volume 3 (Source Term Analysis) x
Non-LWR MELCOR (Source Term) Demonstration Project 2 Reference SCALE/MELCOR plant model for Heat Pipe-Cooled Micro Reactor x Reference SCALE/MELCOR plant model for High-Temperature Gas-Cooled Reactor x Reference SCALE/MELCOR plant model for Molten Salt Cooled Pebble Bed Reactor x Reference SCALE/MELCOR plant model for Molten Salt Fueled Reactor MACCS radionuclide screening analysis MACCS near-field atmospheric transport and dispersion model assessment x MACCS near-field atmospheric transport and dispersion model improvement x Code Assessment Report Volume 4 (Licensing and Siting Dose x Assessments)
Code Assessment Report Volume 5 (Fuel Cycle Analysis) x Research plan and accomplishments in Materials, Chemistry, and x Component Integrity for Adv. Rxs.
Research on risk-informed and performance-based (RIPB) seismic design approaches and adopting seismic isolation technologies Develop Regulatory Roadmap for Adv. Rxs xx (NEIMA Section 103(a)(1))
Develop prototype guidance for Adv. Rxs x Develop non-LW R Design Crtieria for Adv. Rxs x EPRI Topical Report on Tri-structural Isotropic (TRISO) Fuel xx Quality Assurance Program Plan for Sodium-cooled FAST Reactor x Metallic Fuel Data Qualification Develop Fuel Qualification Guidance for Adv. Rxs (NUREG-2246) xx Develop Advanced Reactor Content of Application Project (ARCAP) x 3 Regulatory Guidance Develop Advanced Reactor Technology Inclusive Content of Application x Project (TICAP) Regulatory Guidance Develop non-LW R Design Review Guide (DRG) for Instrumentation and xx Controls reviews Develop Advanced Reactor Inspection and Oversight Framework x Document Develop non-LW R Contruction Permit Guidance
Develop Environmental ISG for Micro Reactors xx
Develop Regulatory Guide for Licensing Modernization Project xx Advanced Reactor Program - Summary of Integrated Schedule and Regulatory Activities*
Strategy 1 Knowledge, Skills, and C apability Legend Strategy 2 Computer Codes and Review Tools Concurrence (Division/Interoffice) EDO Concurrence Period Strategy 3 Flexible Review Processes Federal Register Publication Commission Review Period**
Strategy 4 Consensus Codes and Standards Public Comment Period ACRS SC/FC (Scheduled or Planned)
Strategy 5 Policy and Key Technical Issues Draft Issuance of Deliverable External Stakeholder Interactions Strategy 6 Communication Final Issuance of Deliverable Public Meeting (Scheduled or Planned)Version Present Day 8/23/21 2020 2021
Regulatory Activity
Develop non-LW R Source Term Information xxx (NEIMA Section 103(c)(4)(II)
Develop Molten Salt Reactor fuel qualification guidance Interim MSR fuel qualification guidance x Final MSR fuel qualification guidance Develop guidance for Non-power Liquid Fueled Molten Salt Reactors xxx (NEIMA Section 103(a)(3))
Review of non-LW R Fuel Cycle Assessment of Regulatory Infrastructure.
Develop Report on possible Material Control and Accounting x Approaches for a Pebble Bed Reactor.
Develop Metal Fuel Fabrication Safety and Hazards Final Report x Develop Review of Hazards for Molten Salt Reactor Fuel Processing x Operations 3 Review of Operating Experience for Transportation of Fresh x (Unirradiated) Advanced Reactor Fuel Types Potential Challenges with Transportation of Fresh (Unirradiated) x Advanced Reactor Fuel Types Storage Experience with Spent (Irradiated) Advanced Reactor Fuel x Types Potential Challenges with Storage of Spent (Irradiated) Advanced x Reactor Fuel Types Transportation Experience and Potential Challenges with x Transportation of Spent (Irradiated) Adv. Rx Fuel Types Disposal Options and Potential Challenges to Waste Packages and x Waste Forms in Disposal of Spent (Irradiated) Advanced Reactor Information Gaps and Potential Information Needs Associated with x `
Transportation of Fresh (Unirradiated) Adv. Rx Fuel Types Develop MC&A guidance for Ca t II facilities (NUREG-2159)
Develop contractor report on technology-inclusive human factors x engineering reviews Develop Regulatory Guide for endorsement of the non-LW R Probabilistic x Risk Assessment Standard Dev elop Regulatory Guide for endorsement of the ASME Section III, x 4 Division 5 Standard Alloy 617 Code Cases (N-872 and N-898)
Develop Draft Guide endorsing ASME Section XI Division 2 Reliability and Integrity Management (RIM)
Develop SECY paper related to Consequence Based Security (SECY x 0076)
Develop SECY paper related to EP for Small Modular Reactors and xx Other New Technologies (SECY-18-0103)
Develop SECY paper related to Functional Containment xx (SECY-18-0096) 5 SECY-20-0093 Policy and Licensing Considerations related to Micro xx Reactors Report regarding review of the insurance and liability for advanced x reactors (Price-Anderson Act)
Annual Fees for Non-Light W ater Reactors and Microreactors
Develop SECY Paper regarding Population-Related Siting x Considerations for Advanced Reactors Develop annual SECY paper regarding status of non-LW R activities x 6 NRC DOE W orkshops x
Part 53 Plan - Risk-Informed, Technology Inclusive Regulatory xx Framework for Advanced Reactors (NEIMA Section 103(a)(4))
Public Meetings
ACRS Interactions
Physical Security for Advanced Reactors x Develop draft Generic Environmental Impact Statement for Advanced Reactors. Final GEIS.*(Has been voted to rulemaking by Comm.)
Advanced Reactor Program - Summary of Integrated Schedule and Regulatory Activities*
Strategy 1 Knowledge, Skills, and C apability Legend Strategy 2 Computer Codes and Review Tools Concurrence (Division/Interoffice) EDO Concurrence Period Strategy 3 Flexible Review Processes Federal Register Publication Commission Review Period**
Strategy 4 Consensus Codes and Standards Public Comment Period ACRS SC/FC (Scheduled or Planned)
Strategy 5 Policy and Key Technical Issues Draft Issuance of Deliverable External Stakeholder Interactions Strategy 6 Communication Final Issuance of Deliverable Public Meeting (Scheduled or Planned)Version Present Day 8/23/21 2020 2021
Regulatory Activity
Emergency Preparedness Requirements for Small Modular Reactors and xx Other New Technologies.(NEIMA Section 103(a)(2))
Provide report to Congress regarding licensing processes for Advanced xx Reactors (NEIMA Section 103(b))
Provide report to Congress regarding the use of risk-informed and performance based techniques for Adv. Rx. Licensing (NEIMA Section xx 103(c))
Provide report to Congress on preparing the licensing process for RTRs within existing Regulatory Framework xx (NEIMA Section 103(d))
Provide report to Congress on completing the rulemaking to establish a "technology-inclusive regulatory framework" xx (NEIMA Section 103(e))
- Dates reflected above are best estimates. Actual dates will be updated as additional information becomes available.
- The timeframe for the Commissions review is for planning purposes only, and does not reflect an expected date for Commission decision.
For additional technical and policy issues related to Adv. Rxs, please visit: https://www.nrc.gov/reactors/new-reactors/smr.html#techPolicyIssues