Text

NEI-22-01 License Termination Process Pre-Submittal Meeting November 16, 2022 (Presentation)
	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)
	v • d • e

NEI 22-01, License Termination Process NRC Pre-submittal Meeting November 16, 2022

Introduction to NEI 22-01, License Termination Process 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.

The NEI 22-01 Team Name Affiliation Gerry Van Noordennen (Lead) Energy Solutions (Consultant)

Bill Barley Pacific Gas and Electric (Consultant)

Ron Cardarelli CN Associates Eric Darois RSCS Jean Fleming Holtec Willie Harris CN Associates Rich McGrath EPRI Bruce Montgomery NEI Sarah Roberts Energy Solutions Kris Rowberry Pacific Gas and Electric Mike Smith NEI

NEI 22-01 Contents

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 Appendices 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)

Chapter 1: Introduction to the License Termination Process 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 2: Site Characterization 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 (cont.)

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 3: Identification of Remaining Site Dismantlement Activities 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 4: Remediation Plans 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 5: Final Radiation Survey Plan 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 (cont.)

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.)

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 6: Compliance with Radiological Criteria for License Termination 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 (cont.)

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 7: Update on Site-Specific Decommissioning Costs 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 8: Supplement to the Environmental Report 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 9: Final Status Survey Reporting 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

NEI 22-01 Appendices 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 Schedule Action Date

Complete Draft Rev. 0,

November 15 distribute for industry review

Pre-submittal Meeting

November 16

Submit to NRC for review

December 15, 2022

Submit fee waiver request

December 15, 2022

Respond to NRC RAIs, as

2023 needed

NRC approval (desired outcome)

TBD

Closing Thoughts 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

ML22318A303

Text

Navigation menu

Search