DOE/EIS-01440 U.S. DEPARTMENT OF ENERGY Office of New Production Reactors Washington, DC 20585 Draft Environmental Impact Statement for the Siting, Construction, and Operation of New Production Reactor Capacity Volume 3: Sections 7-12 Appendices A·C April 1991 DOCUMENT CONTENTS VOLUME1 Summary VOLUME 2 Foreword Section 1 Introduction Section 2 Analysis of Programmatic Alternatives Section 3 Project Alternatives, Including No Action Section 4 Affected Environment of Alternative Sites Section 5 Environmental Consequences Section 6 Environmental Regulations and Permit Requirements VOLUME 3 Section 7 References Section 8 List of Preparers Section 9 List of Recipients Section 10 Acronyms, Abbreviations, and Units of Measure Section 11 Glossary Section 12 Index Appendix A Heavy-Water Reactor Technology Appendix B Light-Water Reactor Technology Appendix C Modular High-Temperature Gas-Cooled Reactor Technology VOLUME 4 Appendix D Geologic Resources Appendix E Air Resources and Noise Appendix F Water Resources Appendix G Biotic Resources Appendix H · Radiological Impacts of Normal Operations Appendix I Radiological Impacts of Postulated Nonsevere Accidents Appendix J Radiological Impacts of Postulated Severe Accidents Appendix K Impacts from Transportation of Radioactive Materials Appendix L Methodology for Nonradioactive Hazardous Material Accident Assessment Appendix M Waste Management Appendix N Socioeconomics Appendix 0 Decontamination and Decommissioning Appendix P Waste Stream Composition Data Appendix Q Cultural Resources Appendix R Supplemental Evaluation of Environmental Impacts for a Six-Module 450-MWt MHTGR Production Complex V3 - iii CONTENTS -VOLUME 3 DOCUMENT CONTENTS . V3 - iii CONTENTS - VOLUME 3 . V3 - v FIGURES - VOLUME 3 ................................................V3 - xiii TABLES - VOLUME 3 .................................................V3 - xvi 7 REFERENCES . 7-1 8 LIST OF PREPARERS . 8-1 9 LIST OF RE CIPIENTS . 9-1 10 ACRONYMS AND ABBREVIATIONS. 10-1 11 GLC>SSAR Y . 11-1 12 INDEX . 12-1 APPENDIX A: HEAVY-WA TER REA CTOR TE CHNOLOGY . A-1 A.1 Overview . A-3 A.1.1 Introduction . A-3 A.1.2 Safety and Safety Assurance . A-4 A.1.2.1 New Facilities . A-4 A.1.2.2 Existing Facilities . A-4 A.1.2.3 Specific Requirements Met by the HWR . A-5 A.1.3 Heavy-Water Reactor Technology . A-5 A.1.3.1 Reactor . A-5 A.1.3.2 Fuel and Tritium-Target Cycle . A-5 A.1.3.3 Fuel/Plutonium-Target Cycle . A-6 A.1.3.4 Waste Management . A-9 A.2 Heavy-Water Reactor Technology at SRS . A-10 A.2.1 Introduction . A-10 A.2.1.1 New and Existing Facilities Required for the NP R . A-10 A.2.1.2 Location . A-10 A.2.1.3 Existing Facilities, Utilities, and On-site Transportation . A-10 A.2.2 Heavy-Water Reactor Facility . A-12 A.2.2.1 Plant Structures . A-12 A.2.2.2 Nu clear Reactor Systems . A-14 A.2.2.3 Engineered Safety Features . A-14 A.2.2.4 Reactor Containment . A-14 A.2.2.5 Fuel and Target Handling . A-15 A.2.2.6 Heavy-Water Processing . A-15 A.2.2.7 Power Conversion System . A-16 V3 -v CONTENTS - VOLUME 3 (Confd) A.2.2.8 Utilities . A-16 A.2.2.9 Heat Dissipation Systems . A-17 A.2.2.10 Waste Management . A-22 A.2.3 Fuel and Tritium-Target Fabrication . A-26 A.2.3.1 Facility Description . A-26 A.2.3.2 Fuel and Target Description . A-26 A.2.3.3 Process Description . A- 26 A.2.3.4 Process Effluents and Wastes . A-26 A.2.4 Fuel/Plutonium-239 Target Fabrication . A- 27 A.2.4.1 Facility Description . A-27 A.2.4.2 Fuel/ Target Description . A-28 A.2.4.3 Process Description . A-28 A.2.4.4 Process Effluents and Wastes . A-29 A.2.5 Spent Fuel Processing . A-29 A.2.5.1 Facility Description . A-30 A.2.5.2 Process Description . A-30 A.2.5.3 Process Effluents and Wastes . A-3 1 A.2.6 Tritium-Target Processing . A-3 1 A.2.6.1 Facility Description . A-3 1 A.2.6.2 Process Description . A-3 2 A.2.6.3 Process Effluents and Wastes . A-3 2 A.2.7 Fuel/Plutonium-Target Processing . A-33 A.2.7.1 Facility Description . A-33 A.2.7.2 Process Description . A-33 A.2.7.3 Process Effluents and Wastes . A-33 A.2.8 Plant Operation . A-3 4 A.2.9 Sitewide Waste Management . A-3 4 A.2.9.1 Was.te Management Facilities . A-37 A.2.9.2 Liquid Waste Processing . A-38 A.2.9.3 Solid Waste Processing . A-3 9 A.3 Heavy-Water Reactor Technology at Hanford . A-40 A.3.1 Introduction . A-40 A.3.1.1 New and Existing Facilities Required for the NP R . A-40 A.3.1.2 Location . A- 41 A.3.1.3 Existing Facilities, Utilities, and On-site Transportation . A-4 1 A.3.2 Heavy-Water Reactor Facility . A-4 1 A.3.2.l Plant Structures . A-4 1 A.3.2.2 Heat Dissipation Systems . A-43 A.3.2.3 Electric System . A-45 A.3.3 Fuel and Tritium-Target Fabrication . A-45 A.3.3.1 Facility Description . A-45 A.3.3. 2 Fuel and Target Description . A-47 A.3.3.3 Process Description . A-47 A.3.3.4 Process Effluents and Wastes . A-47 A.3.4 Fuel/Plutonium-Target Fabrication . A-47 A.3.4.1 Facility Description . A- 48 A.3.4.2 Fuel/ Target Description . A-48 A.3.4.3 Process Description . A-48 V3 - vi CONTENTS - VOLUME 3 (Confd) A.3.4.4 Process Effluents and Wastes . A-48 A.3.5 Spent Fuel Processing . A-48 A.3.5.l Facility Description . A-48 A.3.5.2 Process Description . A-50 A.3.5.3 Process Effluents and Wastes . A-53 A.3.6 Tritium-Target Processing . A-55 A.3.6.1 Facility Description . A-55 A.3.6. 2 Process Description . A-55 A.3.6.3 Process Effluents and Wastes . A-55 A.3.7 Fuel/Plutonium-Target Processing . A-56 A.3.7. 1 Facility Description . A- 56 A.3.7. 2 Process Description . A-56 A.3.7.3 Process Effluentsand Wastes . ..