ML23250A087
| ML23250A087 | |
| Person / Time | |
|---|---|
| Issue date: | 09/07/2023 |
| From: | Katie Wagner NRC/NRR/DANU/UARP |
| To: | |
| References | |
| Download: ML23250A087 (1) | |
Text
Knowledge, Skills, and Capability Computer Codes and Review Tools Concurrence (Division/Interoffice)
Guidance Federal Register Publication Commission Review Period**
Consensus Codes and Standards Public Comment Period ACRS SC/FC (Scheduled or Planned)
Policy and Key Technical Issues Draft Issuance of Deliverable External Stakeholder Interactions Communication Final Issuance of Deliverable Public Meeting (Scheduled or Planned)
Present Day Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec x
x x
x x
x x
x x
x Reference plant model for Heat Pipe-Cooled Micro Reactor x
Reference plant model for Sodium-Cooled Fast Reactor (update from version 1 to 2)***
Reference plant model for Molten-Salt-Cooled Pebble Bed Reactor (update from version 1 to 2)***
x Reference plant model for Monolith-type Micro-Reactor Reference plant model for Gas-Cooled Pebble Bed Reactor (update from version 1 to 2)***
x Reference plant model for Molten-Salt-Fueled Thermal Reactor (update from version 1 to 2)***
x FAST code assessment for metallic fuel x
FAST code assessment for TRISO fuel x
x Non-LWR MELCOR (Source Term) Demonstration Project x
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 Sodium-Cooled Fast Reactor x
Reference SCALE/MELCOR plant model for Molten Salt Fueled Reactor x
MACCS near-field atmospheric transport and dispersion model assessment x
MACCS near-field atmospheric transport and dispersion model improvement x
MACCS radionuclide screening analysis x
MACCS radionuclide properties on atmospheric transport and dosimetry x
MACCS: Evolution of Radionuclide Properties in the Atmosphere MACCS: Assessment of Capabilities for Assessing Tritium Releases MACCS: Demonstration Project for Advanced Reactors: Heat Pipe Reactor x
x Phase 1 - SIERRA (Atmospheric Code Consolidation)
Phase 2 - SIERRA (Effluent Code Consolidation)
Phase 3 - Habitability Code Consolidation x
Reference SCALE/MELCOR fuel cycle analysis for High-Temperature Gas-Cooled Reactor x
Reference SCALE/MELCOR fuel cycle analysis for Sodium-Cooled Fast Reactor
x Strategy 1
2 Development of Non-LWR Computer Models and Analytical Tools Guidance Code Assessment Report Volume 4 (Licensing and Siting Dose Assessments)
Commission Papers Rulemaking 2022 9/7/23 Code Assessment Report Volume 5 (Fuel Cycle Analysis)
High Temperature Gas-cooled Reactor (HTGR) Technology Molten Salt Reactor (MSR) Technology Code Assessment Reports Volume 1 (Systems Analysis)
Code Assessment Reports Volume 2 (Fuel Perf. Anaylsis)
Code Assessment Reports Volume 3 (Source Term 2023 Complete Identification and Assessment of Available Codes Regulatory Activity NEIMA Development of non-Light Water Reactor (LWR) Training for Advanced Reactors (Adv. Rxs) (NEIMA Section 103(a)(5))
Advanced Reactor Program - Summary of Integrated Schedule and Regulatory Activities*
Legend Strategy 1 Strategy 2 Strategy 3 Strategy 4 Strategy 5 Strategy 6 EDO Concurrence Period Version FAST Reactor Technology Competency Modeling to ensure adequate workforce skillset Research plan and accomplishments in Materials, Chemistry, and Component Integrity for Adv. Rxs.
Knowledge, Skills, and Capability Computer Codes and Review Tools Concurrence (Division/Interoffice)
Guidance Federal Register Publication Commission Review Period**
Consensus Codes and Standards Public Comment Period ACRS SC/FC (Scheduled or Planned)
Policy and Key Technical Issues Draft Issuance of Deliverable External Stakeholder Interactions Communication Final Issuance of Deliverable Public Meeting (Scheduled or Planned)
Present Day Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Strategy Guidance Commission Papers Rulemaking 2022 9/7/23 2023 Complete Regulatory Activity NEIMA Advanced Reactor Program - Summary of Integrated Schedule and Regulatory Activities*
Legend Strategy 1 Strategy 2 Strategy 3 Strategy 4 Strategy 5 Strategy 6 EDO Concurrence Period Version x
x x
x x
x x
x
x
x x
x
x x
x x
x x
x x
x x
x x
x x
x x
x x
x x
x
Develop Regulatory Roadmap for Adv. Rxs (NEIMA Section 103(a)(1))
Disposal Options and Potential Challenges to Waste Packages and Waste Forms in Disposal of Spent (Irradiated)
Potential Challenges with Storage of Spent (Irradiated)
Advanced Reactor Fuel Types Transportation Experience and Potential Challenges with Transportation of Spent (Irradiated) Adv. Rx Fuel Types Develop guidance for Non-power Liquid Fueled Molten Salt Reactors (NEIMA Section 103(a)(3))
Develop Review of Hazards for Molten Salt Reactor Fuel Processing Operations Develop Report on possible Material Control and Accounting Approaches for a Pebble Bed Reactor.
Develop Metal Fuel Fabrication Safety and Hazards Final Report Material Compatibility Interim Staff Guidance (DANU-ISG-2023-01)
Develop non-LWR Source Term Information (NEIMA Section 103(c)(4)(II)
Non-LWR PRA Standard Applicability Interim Staff Guidance (DANU-ISG-2023-02)
Methodology and Guidance on the Treatment of Consequence Uncertainty Facility Training Programs Interim Staff Guidance (DRO-ISG-2023-04)
Develop non-LWR Construction Permit Guidance Develop Molten Salt Reactor fuel qualification guidance (NUREG/CR-7299)
Develop Advanced Reactor Technology Inclusive Content of Application Project (TICAP) Regulatory Guidance Technology Inclusive Management of Safety Case (TIMASC)
Guidance Endorsement 3
Storage Experience with Spent (Irradiated) Advanced Reactor Fuel Types Review of non-LWR Fuel Cycle Assessment of Regulatory Infrastructure.
Develop Advanced Reactor Inspection and Oversight Program Framework Interim MSR fuel qualification guidance Final MSR fuel qualification guidance Develop Advanced Reactor Content of Application Project (ARCAP) Regulatory Guidance Develop prototype guidance for Adv. Rxs Research on risk-informed and performance-based (RIPB) seismic design approaches and adopting seismic isolation technologies Potential Challenges with Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types Develop MC&A guidance for Cat II facilities (NUREG-2159)
Review of Operating Experience for Transportation of Fresh (Unirradiated) Advanced Reactor Fuel Types Information Gaps and Potential Information Needs Associated with Transportation of Fresh (Unirradiated) Adv.
Rx Fuel Types Develop non-LWR Design Crtieria for Adv. Rxs Develop Regulatory Guide for Licensing Modernization Project Develop non-LWR Design Review Guide (DRG) for Instrumentation and Controls reviews Develop Fuel Qualification Guidance for Adv. Rxs (NUREG-2246)
Technology Inclusive Risk-Informed Change Evaluation (TIRICE)
Guidance Endorsement
Knowledge, Skills, and Capability Computer Codes and Review Tools Concurrence (Division/Interoffice)
Guidance Federal Register Publication Commission Review Period**
Consensus Codes and Standards Public Comment Period ACRS SC/FC (Scheduled or Planned)
Policy and Key Technical Issues Draft Issuance of Deliverable External Stakeholder Interactions Communication Final Issuance of Deliverable Public Meeting (Scheduled or Planned)
Present Day Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Strategy Guidance Commission Papers Rulemaking 2022 9/7/23 2023 Complete Regulatory Activity NEIMA Advanced Reactor Program - Summary of Integrated Schedule and Regulatory Activities*
Legend Strategy 1 Strategy 2 Strategy 3 Strategy 4 Strategy 5 Strategy 6 EDO Concurrence Period Version
x x
x x
x x
x x
x x
x x
x x
x x
x x
x x
x x
x
x
x x
x x
x 5
Public Meetings ACRS Interactions Develop draft Generic Environmental Impact Statement for Advanced Reactors. Final GEIS.*(Has been voted to rulemaking by Comm.)
Part 53 Plan - Risk-Informed, Technology Inclusive Regulatory Framework for Advanced Reactors (NEIMA Section 103(a)(4))
- Dates reflected above are best estimates. Actual dates will be updated as additional information becomes available.
Draft Regulatory Guides for risk-informed and performance-based (RIPB) seismic design approaches and adopting seismic isolation technologies Develop contractor report on technology-inclusive human factors engineering reviews Develop supplemental human factors engineering review guidance associated with eight technical areas where we have identified knowledge gaps For additional technical and policy issues related to Adv. Rxs, please visit:
https://www.nrc.gov/reactors/new-reactors/smr.html#techPolicyIssues
- The timeframe for the Commissions review is for planning purposes only, and does not reflect an expected date for Commission decision.
6 Rulemaking Develop Regulatory Guide endorsing ASME Section XI Division 2 Reliability and Integrity Management (RIM)
Develop annual SECY paper regarding status of non-LWR activities NRC DOE Workshops Develop SECY Paper regarding Population-Related Siting Considerations for Advanced Reactors 4
Alloy 617 Code Cases (N-872 and N-898)
Develop SECY paper related to Functional Containment (SECY-18-0096)
RG 1.87 Rev 2 for endorsement of the ASME Section III, Division 5, "High Temperature Reactors" and technical basis NUREG-Physical Security for Advanced Reactors Emergency Preparedness Requirements for Small Modular Reactors and Other New Technologies.(NEIMA Section 103(a)(2))
Revise Regulatory Guide (RG) 4.7 to implement SRM to SECY-20-0045 Develop Regulatory Guide for endorsement of the non-LWR Probabilistic Risk Assessment Standard Develop SECY paper related to EP for Small Modular Reactors and Other New Technologies (SECY-18-0103)
Annual Fees for Non-Light Water Reactors and Microreactors Develop SECY paper related to Consequence Based Security (SECY-18-0076)
SECY-20-0093 Policy and Licensing Considerations related to Micro Reactors Report regarding review of the insurance and liability for advanced reactors (Price-Anderson Act)