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Title page 1

Contents 7

ABSTRACT 5

EXECUTIVE SUMMARY 15

ABBREVIATIONS AND ACRONYMS 21

1. INTRODUCTION 28

1.1. Purpose and Need for this GEIS 29

1.2. NEPA Process 29

1.2.1. Public Scoping 29

1.2.2. Issuance of the Draft Generic Environmental Impact Statement for Licensing New Nuclear Reactors and Proposed Rule 30

1.2.3. Public Comments on the Draft NR GEIS and Proposed Rule 30

1.2.4. Changes Between the Draft and Final GEIS 31

1.2.4.1. Limited Work Authorizations 31

1.2.4.2. Executive Order 14154 and Rescinding of Council on Environmental Quality (CEQ) NEPA Regulations 31

1.2.4.3. Withdrawal of Environmental Justice 31

1.2.4.4. Severe Accidents and Mitigation 31

1.2.4.5. Tribal/Historic Resources Consultation 32

1.2.4.6. Climate Change Impacts on Environmental Resources 32

1.3. Analytical Approach Used in this GEIS 32

1.3.1. Methodology 32

1.3.2. Primary Documents Used to Develop this GEIS 37

1.3.3. Issue Categories 38

1.3.3.1. Category 1 Issues - Generic Analysis 38

1.3.3.2. Category 2 Issues - Project-Specific Analysis 38

1.3.3.3. Uncertain Issues 42

1.4. Implementation of the Rule (10 CFR Part 51) 47

1.4.1. General Requirements 48

1.4.2. Applicant's Environmental Report 48

1.4.3. The NRC's SEIS 49

1.4.4. Public Scoping and Public Comments 49

1.4.5. The NRC's Draft SEIS 49

1.4.6. The NRC's Final SEIS 49

1.4.7. Consultations 49

2. DESCRIPTION OF PROPOSED ACTION AND ALTERNATIVES 51

2.1. Proposed Action and Alternatives to the GEIS 51

2.1.1. Proposed Action: Issue Technology-Neutral GEIS Based on Performance-Based Assumptions 51

2.1.2. No-Action Alternative: No GEIS - Project-Specific National Environmental Policy Act Review Only 52

2.1.3. Other Alternatives Considered but Not Analyzed in Detail 52

2.1.3.1. Limiting the GEIS to Reactors Less than 30 MWt 52

2.1.3.2. GEIS for Advanced Nuclear Reactors Only 52

2.1.3.3. GEIS Analyzing All Potential Environmental Impacts 53

3. AFFECTED ENVIRONMENT AND ENVIRONMENTAL CONSEQUENCES 54

3.1. Land Use 55

3.1.1. Baseline Conditions and PPE/SPE Values and Assumptions 55

3.1.2. Land Use Impacts 57

3.1.2.1. Environmental Consequences of Construction 58

3.1.2.2. Environmental Consequences of Operation 62

3.2. Visual Resources 64

3.2.1. Baseline Conditions and PPE/SPE Values and Assumptions 64

3.2.2. Visual Resources Impacts 64

3.2.2.1. Environmental Consequences of Construction 65

3.2.2.2. Environmental Consequences of Operation 67

3.3. Meteorology and Air Quality 68

3.3.1. Baseline Conditions and PPE/SPE Values and Assumptions 68

3.3.2. Air Quality Impacts 73

3.3.2.1. Environmental Consequences of Construction 74

3.3.2.2. Environmental Consequences of Operation 76

3.4. Water Resources 80

3.4.1. Baseline Conditions and PPE/SPE Values and Assumptions 80

3.4.1.1. Surface Water Resources 82

3.4.1.2. Groundwater Resources 84

3.4.2. Water Resources Impacts 87

3.4.2.1. Environmental Consequences of Construction 88

3.4.2.2. Environmental Consequences of Operation 96

3.5. Terrestrial Ecology 113

3.5.1. Baseline Conditions and PPE/SPE Values and Assumptions 113

3.5.2. Terrestrial Ecology Impacts 115

3.5.2.1. Environmental Consequences of Construction 115

3.5.2.2. Environmental Consequences of Operation 126

3.6. Aquatic Ecology 137

3.6.1. Baseline Conditions and PPE/SPE Values and Assumptions 137

3.6.2. Aquatic Ecology Impacts 139

3.6.2.1. Environmental Consequences of Construction 139

3.6.2.2. Environmental Consequences of Operation 145

3.7. Historic and Cultural Resources 153

3.7.1. Baseline Conditions 153

3.7.1.1. National Historic Preservation Act and NEPA 154

3.7.2. Historic and Cultural Resources Impacts 155

3.7.2.1. Environmental Consequences of Construction 156

3.7.2.2. Environmental Consequences of Operation 157

3.8. Environmental Hazards 158

3.8.1. Radiological Environment 158

3.8.1.1. Baseline Conditions and PPE/SPE Values and Assumptions 158

3.8.1.2. Radiological Environment Impacts 163

3.8.2. Nonradiological Environment 172

3.8.2.1. Baseline Conditions and PPE/SPE Values and Assumptions 172

3.8.2.2. Nonradiological Environment Impacts 174

3.9. Noise 179

3.9.1. Baseline Conditions and PPE/SPE Values and Assumptions 179

3.9.2. Noise Impacts 180

3.9.2.1. Environmental Consequences of Construction 180

3.9.2.2. Environmental Consequences of Operation 180

3.10. Waste Management 181

3.10.1. Radiological Waste Management 181

3.10.1.1. Baseline Conditions and PPE/SPE Values and Assumptions 181

3.10.1.2. Radiological Waste Impacts 184

3.10.2. Nonradiological Waste Management 186

3.10.2.1. Baseline Conditions and PPE/SPE Values 186

3.10.2.2. Nonradiological Waste Impacts 187

3.11. Postulated Accidents 190

3.11.1. Baseline Conditions and PPE/SPE Values and Assumptions 190

3.11.1.1. Design Basis Accidents Involving Radiological Releases 190

3.11.1.2. Accidents Involving Releases of Hazardous Chemicals 191

3.11.1.3. Severe Accidents 192

3.11.1.4. Acts of Terrorism 195

3.11.2. Postulated Accidents Impacts 196

3.11.2.1. Design Basis Accidents Involving Radiological Releases 197

3.11.2.2. Accidents Involving Releases of Hazardous Chemicals 198

3.11.2.3. Severe Accidents 198

3.11.2.4. Acts of Terrorism 199

3.12. Socioeconomics 199

3.12.1. Baseline Conditions and PPE/SPE Values and Assumptions 199

3.12.2. Socioeconomic Impacts 200

3.12.2.1. Socioeconomic Consequences of Construction 201

3.12.2.2. Socioeconomic Consequences of Operations 204

3.13. (Withdrawn) 207

3.14. Fuel Cycle 207

3.14.1. Baseline Conditions and PPE/SPE Values and Assumptions 207

3.14.1.1. Uranium Fuel Cycle Environmental Data 207

3.14.1.2. Other Fissile Fuel Cycles 209

3.14.1.3. DOE High-Assay Low-Enriched Uranium Availability Program 210

3.14.1.4. Nuclear Fuel Cycle Regulatory Requirements for New Reactors 210

3.14.1.5. Changes in the Nuclear Fuel Cycle since WASH-1248 211

3.14.1.6. PPE Assumptions 212

3.14.2. Fuel Cycle Impacts 213

3.14.2.1. Uranium Recovery 214

3.14.2.2. Uranium Conversion 215

3.14.2.3. Enrichment 216

3.14.2.4. Fuel Fabrication 217

3.14.2.5. Reprocessing 224

3.14.2.6. Storage and Disposal of Radiological Wastes 226

3.14.3. Staff Conclusions about the Environmental Impacts of a New Reactor Fuel Cycle 232

3.15. Transportation of Fuel and Waste 232

3.15.1. Baseline Conditions and PPE/SPE Values and Assumptions 232

3.15.1.1. Table S-4 on the Transportation of Fuel and Waste 233

3.15.1.2. Additional NRC Studies of the Risk from the Transportation of SNF 233

3.15.1.3. Additional NRC Information Sources 235

3.15.1.4. U.S. Department of Energy Transportation Risk Assessments 235

3.15.1.5. Issues for the Transportation of Non-LWR Fuel and Wastes 236

3.15.1.6. Development of the Transportation Plant Parameter Envelope 236

3.15.1.7. Transportation of Unirradiated New Reactor Fuel 238

3.15.1.8. Transportation of Radioactive Waste from New Reactors 244

3.15.1.9. Transportation of SNF from New Reactors 249

3.15.2. Transportation Impacts 255

3.15.2.1. Transportation of Unirradiated New Reactor Fuel 256

3.15.2.2. Transportation of Radioactive Waste from New Reactors 257

3.15.2.3. Transportation of Irradiated Fuel from New Reactors 258

3.16. Decommissioning 259

3.16.1. Baseline Conditions and PPE/SPE Values and Assumptions 259

3.16.2. Decommissioning Impacts 261

4. SUMMARY OF FINDINGS 268

4.1. Unavoidable Adverse Environmental Impacts and Irreversible and Irretrievable Commitments of Resources 296

4.2. Relationship between Short-Term Use of the Environment and Long-Term Productivity 296

4.3. No-Action Alternative Conclusion 297

4.4. Cost Benefit 297

5. REFERENCES 299

APPENDIX A. CONTRIBUTORS TO THE ENVIRONMENTAL IMPACT STATEMENT 332

APPENDIX B. OUTREACH 334

APPENDIX C. CHRONOLOGY OF NRC STAFF ENVIRONMENTAL REVIEW CORRESPONDENCE RELATED TO THE GENERIC ENVIRONMENTAL... 340

APPENDIX D. DISTRIBUTION LIST 343

APPENDIX E. COMMENTS RECEIVED ON THE ENVIRONMENTAL REVIEW 344

APPENDIX F. LAWS, REGULATIONS, AND OTHER AUTHORIZATIONS 493

APPENDIX G. PLANT PARAMETER ENVELOPE AND SITE PARAMETER ENVELOPE 522

APPENDIX H. GREENHOUSE GAS EMISSIONS ESTIMATES FOR A REFERENCE 1,000 MWE REACTOR 544

APPENDIX I. SEVERE ACCIDENTS 551

Tables 13

Table 1-1. Issues Discussed in the Generic Environmental Impact Statement 43

Table 3-1. National Ambient Air Quality Standards for Six Criteria Pollutants 70

Table 3-2. Plant Parameter Envelope Values for Greenhouse Gas Emissions 73

Table 3-3. Construction Worker Individual and Collective Doses 164

Table 3-4. Maximally Exposed Individual Doses 167

Table 3-5. Total Population and Collective Natural Background Doses in 50 mi Radius 169

Table 3-6. Aquatic Nonhuman Biota Doses 171

Table 3-7. Terrestrial Nonhuman Biota Doses 171

Table 3-8. Level of Service Value Descriptions 203

Table 3-9. Light-Water Reactor Fuel Fabrication Capacity 218

Table 3-10. WASH-1248 Fuel Fabrication Environmental Impacts (AEC 1974-TN23) 219

Table 3-11. Number of Truck Shipments and One-Way Shipping Distances for Unirradiated Fuel 240

Table 3-12. Radiological Impacts Under Normal Conditions of Transporting Unirradiated Fuel from WASH-1238 and New Reactor Sites 241

Table 3-13. Nonradiological Impacts of Transporting Unirradiated Fuel 243

Table 3-14. Summary of Radioactive Waste Shipments and One-Way Shipping Distances 245

Table 3-15. Low-Level Radioactive Waste by Volume 246

Table 3-16. Low-Level Radioactive Waste by Activity 247

Table 3-17. Annual Nonradiological Impacts of Transporting Waste from the Site 249

Table 3-18. Incident-Free Radiological Impacts for Shipping Spent Nuclear Fuel to the Yucca Mountain Site 251

Table 3-19. Radiological Accident Impacts for Shipping Spent Nuclear Fuel to the Yucca Mountain Site 252

Table 3-20. Nonradiological Accident Impacts for Shipping Spent Nuclear Fuel to the Yucca Mountain Site 253

Table 3-21. Summary of the Environmental Impacts from Decommissioning Nuclear Power Facilities (NRC 2002-TN665) 262

Table 4-1. Summary of Findings and Mitigation 269

Figures 12

Figure 3-1. SMALL Surface Water Use Impacts for Plant Withdrawals of 6,000 gpm or Less Compared to the 95 Percent Exceedance Discharge... 100

Figure 3-2. Representative Radiological Exposure Pathways to Human 161

Figure 3-3. Representative Radiological Exposure Pathways to Nonhuman Biota 162

Figure 3-4. Options of the Current Fuel Cycle which Includes the Table S-3 Uranium Fuel Cycle 209

Appendix Tables 13

Table A-1. U.S. Nuclear Regulatory Commission Preparers 332

Table A-2. Pacific Northwest National Laboratory Preparers 333

Table D-1. Distribution List 343

Table E-1. Individuals Providing Comments on the Draft GEIS and/or Proposed Rule Package 345

Table E-2. Comment Categories 348

Table F-1. State Environmental Requirements 506

Table F-2. Federal, State, and Local Permits and Other Requirements 508

Table G-1. Plant Parameter Envelope and Site Parameter Envelope for New Reactors 523

Table H-1. Green House Gas Emissions from Equipment Used in Building and Decommissioning (MT CO₂(e)) 545

Table H-2. Workforce Green House Gas Footprint Estimates 545

Table H-3. Annual Number of Shipments for the Reference 1,000 MWe Reactor 547

Table H-4. Nuclear Power Plant Life-Cycle Green House Footprint 548

Table I-1. 1996 License Renewal Generic Environmental Impact Statement Core Damage Frequency and Population Dose Risk Value... 596

Table I-2. 2024 Subsequent License Renewal Generic Environmental Impact Statement Severe Accident Mitigation Alternative Core Damage... 597

Table I-3. NUREG-1150 Core Damage Frequency and Population Dose Risk Values 598

Table I-4. Early Site Permits Core Damage Frequency and Population Dose Risk Values 598

Table I-5. License for New Reactor Core Damage Frequency and Population Dose Risk Values 598

Table I-6. Non-Light-water Reactors Core Damage Frequency and Population Dose Risk Values 599

Table I-7. Maximum Benefit Estimates (per unit) 599

Appendix Figures 12

Figure I-1. Relationship Between Various Risk-Informed Guidance Documents 560

Figure I-2. Typical Role of Accident Management Procedures and Guidelines (NRC 2024-TN12156) 564

Figure I-3. Power Reactor Severe Accident Analysis Results of Population Dose Risk Versus Core Damage Frequency 583

Figure I-4. The 1996 LR GEIS Exposure Index Values at 10 mi and 150 mi Versus Reactor Power 586

Figure I-5. SAMA Mitigation Maximum Benefit Estimates in Environmental Impact Statements for New and Operating Reactors 594