ML22318A303
| ML22318A303 | |
| Person / Time | |
|---|---|
| Site: | Nuclear Energy Institute |
| Issue date: | 11/16/2022 |
| From: | Nuclear Energy Institute |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| Download: ML22318A303 (21) | |
Text
©2022 Nuclear Energy Institute NRC Pre-submittal Meeting November 16, 2022 NEI 22-01, License Termination Process
©2022 Nuclear Energy Institute 2 Culminates extensive body of regulatory guidance and past industry experience into a practical how to Provides user with appropriately selective references to applicable regulations, NUREGs, and other guidance Further consolidates NUREG-1757,Vol. 2 guidance to reflect the specific needs of commercial nuclear power reactors Provides many examples of how license termination tasks have been completed with NRC approval at decommissioned sites Includes suggested planning milestones, timelines, and stakeholder interfaces to promote transparency and efficiency.
Introduction to NEI 22-01, License Termination Process
©2022 Nuclear Energy Institute 3 Name Gerry Van Noordennen (Lead)
Bill Barley Ron Cardarelli Eric Darois Jean Fleming Willie Harris Rich McGrath Bruce Montgomery Sarah Roberts Kris Rowberry Mike Smith Affiliation Energy Solutions (Consultant)
Pacific Gas and Electric (Consultant)
CN Associates RSCS Holtec CN Associates EPRI NEI Energy Solutions Pacific Gas and Electric NEI The NEI 22-01 Team
©2022 Nuclear Energy Institute 4 1.
Introduction to the License Termination Process 2.
Site Characterization 3.
Identification of Remaining Site Dismantlement Activities 4.
Remediation Plans 5.
Final Status Survey Plan 6.
Compliance with Radiological Criteria for License Termination 7.
Update on Site-Specific Decommissioning Costs 8.
Supplement to the Environmental Report 9.
Final Status Survey Reporting NEI 22-01 Contents
©2022 Nuclear Energy Institute 5 A.
Application of Advanced Technologies B.
Example Calcs for Base Case and Operational DCGLs C.
Crosswalk between LTP and NUREG-1700 D.
Suggested Federal and State Regulatory Interface Plan E.
Typical License Termination Milestone Schedule F.
Site Specific Does Modeling Experiences G. Example of Characterization, Remediation and FSS of Groundwater H.
Discrete Radioactive Particles (Future)
NEI 22-01 Appendices
©2022 Nuclear Energy Institute 6 1.1 General Information 1.1.1 Communications among Licensee and Regulators 1.1.2 Standard Format and Content 1.1.3 Acceptance Criteria and Regulatory Review 1.1.4 Crosswalk between LTP and NUREG-1700 1.1.5 History of Partial Site Releases Partial Site Release Requirements Partial Site Release Process 1.1.6 Process for LTP revisions Chapter 1: Introduction to the License Termination Process
©2022 Nuclear Energy Institute 7 2.1 Objectives of Site Characterization 2.2 Types and Numbers of Samples 2.2.1 Types of Concrete Characterization Traditional Core Bores Concrete Dust Collection through small Hollow-Core Drilling (TruePro')
Concrete Laser Ablation and Collection In-situ Gamma Spectroscopy 2.2.2 Numbers of Concrete Measurements/Samples 2.2.3 Surface Soil Samples 2.2.4 Subsurface Soil Samples 2.2.5 Radiological Analysis Strategies Selection of Analysis Suites and Establishing the Initial Radionuclides of Concern (ROC)
Onsite Sample Analysis Offsite Sample Analysis Chapter 2: Site Characterization
©2022 Nuclear Energy Institute 8 2.3 Radiological Data Assessment 2.3.1 Identifying Data Trends and Statistical Observations 2.3.2 Determining Radionuclide Activity Fractions 2.3.3 Determining Insignificant Radionuclides 2.3.4 Final List of Radionuclides of Concern 2.3.5 Surrogate Radionuclides 2.4 Other Use of Site Characterization Data 2.4.1 Initial Survey Area Classification 2.4.2 Understanding the Extent of Contamination Chapter 2: Site Characterization (cont.)
©2022 Nuclear Energy Institute 9 3.1 Introduction 3.2 Radiological Control Procedures 3.3 Structures at License Termination 3.4 Soil and Groundwater Remediation 3.5 Waste Disposal Plans 3.5.1 Disposal at NRC Licensed Facilities 3.5.2 Disposal at Hazardous Waste Landfill Licensed to Receive NRC Exempted Radwaste 3.5.3 NRC Waste Exemption Process 3.5.4 Other Radioactive Waste Considerations 3.6 Schedule Chapter 3: Identification of Remaining Site Dismantlement Activities
©2022 Nuclear Energy Institute 10 4.1 Introduction and Background 4.2 Lessons Learned 4.3 Remediation Levels and ALARA Evaluations 4.3.1 Generic ALARA Screening Levels 4.3.2 Groundwater ALARA Evaluation 4.4 Techniques & Approaches to Remediating Structures, Soils, and Groundwater 4.4.1 Structures 4.4.2 Shallow Remediation Techniques 4.4.3 Agressive Remediation Techniques 4.4.4 Soils 4.4.5 Soil Mixing 4.4.6 Nonstructural Systems 4.5 Ongoing Contamination Control of Remediated Areas & Equipment Chapter 4: Remediation Plans
©2022 Nuclear Energy Institute 11 5.1 Standard Final Site Survey (FSS) Techniques 5.1.1 Data Quality Objectives 5.1.2 Radiological Release Limit Terminology 5.1.3 Other Aspects of FSS Planning Chapter 5: Final Radiation Survey Plan
©2022 Nuclear Energy Institute 12 5.2 Building Surveys 5.2.1 Scanning 5.2.2 Fixed Measurements 5.2.3 Advanced Technologies 5.2.4 Gross Activity DCGLs 5.2.5 Surrogate Ratio DCGLs 5.2.6 Effect of Hard-To-Detect Radionuclides on Scan Surveys for Structure Surfaces 5.2.7 Additional Building Surface FSS Challenges 5.2.8 Building FSS Techniques and Alternate Approaches 5.2.9 Survey of Non-RCA Buildings 5.2.10 Survey Protocol for Non-Structural Systems and Components Chapter 5: Final Radiation Survey Plan (cont.)
©2022 Nuclear Energy Institute 13
5.3 Survey Considerations for Outdoor Areas 5.3.1 Residual Radioactivity in Surface Soils
Advanced Technology
Fixed Measurement Requirements
Background Reference Area Determination 5.3.2 Residual Radioactivity in Subsurface Soil
Connecticut Yankee Subsurface Soil FSS
Zion Subsurface Soil FSS
FSS of Caisson Area at Humboldt Bay 5.3.3 Paved Areas 5.3.4 Groundwater Assessments 5.3.5 Bedrock Assessments 5.3.6 Storm Drains and Other Buried Piping 5.3.7 Final Status Survey and/or Radiological Assessment of Excavations
5.4 Survey Data Assessment Chapter 5: Final Radiation Survey Plan (cont.)
©2022 Nuclear Energy Institute 14 6.1 U.S. NRC Site Release Regulations and Guidance 6.1.1 U.S. Nuclear Regulatory Commission Criteria for Unrestricted Release of a Site 6.1.2 Evolution of Dose Model Scenarios
Resident Farmer Scenario
Building Occupancy Scenario 6.1.3 Revision to NRC Guidance on Dose Modeling 6.1.4 NUREG 1757, Consolidated Decommissioning Guidance 6.1.5 Realistic Dose Modeling Scenarios Industrial Worker Scenario 6.1.6 Site Future Use Decision Case Studies
Connecticut Yankee
Big Rock Point - Modified Resident Farmer Scenario
Rancho Seco - Industrial Use Scenario
Zion Resident Farmer Scenario
LaCrosse Chapter 6: Compliance with Radiological Criteria for License Termination
©2022 Nuclear Energy Institute 15 6.2 Dose Modeling to Determine Site Release Limits 6.2.1 Land Areas
Options for Development of Land Area Site Release Limits
NRC Published Screening Values for Soil
Adjusting NRC Screening Values for Potentially Contaminated Groundwater Chapter 6: Compliance with Radiological Criteria for License Termination (cont.)
©2022 Nuclear Energy Institute 16 7.1 Decommissioning Cost Estimate 7.1.1 Cost Estimate Description and Methodology 7.1.2 Summary of the Site-Specific Decommissioning Cost Estimate 7.1.3 License Termination Costs 7.1.4 Spent Fuel Management Costs 7.1.5 Site Restoration Costs 7.1.6 Contingency 7.2 Decommissioning Funding Plan Chapter 7: Update on Site-Specific Decommissioning Costs
©2022 Nuclear Energy Institute 17 8.1 Introduction 8.2 General Guidance 8.3 Lessons Learned 8.4 Land Use - Offsite Land Use Activities 8.5 Aquatic Ecology - Offsite Effects Beyond the Operational Area 8.6 Terrestrial Ecology 8.7 Threatened and Endangered Species 8.8 Environmental Justice 8.9 Cultural and Historic Activities Beyond the Operational Area Chapter 8: Supplement to the Environmental Report
©2022 Nuclear Energy Institute 18 9.1 Introduction 9.2 Final Status Report Content 9.3 Role of NRC Independent Oversight and Confirmatory Measurements 9.3.1 NRC Oversight 9.3.2 Confirmatory Surveys 9.3.3 Optimizing Regulatory Engagement Chapter 9: Final Status Survey Reporting
©2022 Nuclear Energy Institute 19 A.
Application of Advanced Technologies B.
Example Calcs for Base Case and Operational DCGLs C.
Crosswalk between LTP and NUREG-1700 D.
Suggested Federal and State Regulatory Interface Plan E.
Typical License Termination Milestone Schedule F.
Site Specific Does Modeling Experiences G. Example of Characterization, Remediation and FSS of Groundwater H.
Discrete Radioactive Particles (Future)
NEI 22-01 Appendices
©2022 Nuclear Energy Institute 20 Action Complete Draft Rev. 0, distribute for industry review Pre-submittal Meeting Submit to NRC for review Submit fee waiver request Respond to NRC RAIs, as needed NRC approval (desired outcome)
Date November 15 November 16 December 15, 2022 December 15, 2022 2023 TBD NEI 22-01 Schedule
©2022 Nuclear Energy Institute 21 Success in DECON is a key enabler in demonstrating the sustainability of commercial nuclear energy Progress is being made on front end with the proposed transition rule, emphasis needs to shift to improving efficiencies on the back end License termination remains one of the most technically challenging and time-consuming aspects of DECON, and companies face many uncertainties during planning and execution NRC and industry should continue to focus on those issues most relevant to public health and safety and protection of the environment A strong bias for action is imperative to close gaps in regulatory guidance to better serve the communities with plants undergoing DECON today Closing Thoughts