Management of Commercially Generated Radioactive Waste - U.S. ...

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REFERENCES FOR SECTION 4.3 4.47 Aaron, W. S., T. C. Quinby and E. H. Kobisk. 1978. Cermet High-Level Waste Forms, ORNL/TM-6404, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Aaron, W. S., T. C. Quinby and E. H. Kobisk. 1979. "Development and Characterization of Cermet Forms for Radioactive Waste," Presented at the International Symposium on the Scientific Basis for Nuclear Waste Management, Materials Research Society, Boston, Massachusets, November 27-30, 1979. Bond, W. D. and R. E. Leuze. 1975. Feasibility Studies of the Partitioning of Commercial High-Level Wastes Generated in Spent Nuclear Fuel Reprocessing: Annual Program Report for FY 1974, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Bonniand, R., A. Jovan and C. Sombret. 1978. "Large-Scale Waste Glass Production," pp. 155-197 in Proceedings of the Conference on High-Level Radioactive Solid Waste Forms, NUREG/CP-0005 Leslie Casey, Ed., U.S. Nuclear Regulatory Commission, Washington, D.C. Borduin, L. E. and A. L. Toboas. 1980. USDOE Radioactive Waste Incineration Technology: Status Review, LA-UR-80-692, Los Alamos Scientific Laboratory, Los Alamos, New Mexico. Buckingham, J. S., ed. 1967. Waste Management Technical Manual, ISO-100, Isochem Inc., Richland, Washington. Burger, L. L. and R. D. Scheele. 1978. Tritium Removal Alternative for the Purex Process, PNL-2080-14. Pacific Northwest Laboratory, Richland, Washington. Campbell, D. 0. and E. H. Gift. 1978. Proliferation-Resistant Nuclear Fuel Cycles, ORNL/TM-6392. Oak Ridge National Laboratory, Oak Ridge, Tennessee. Campbell, M. H., ed. 1976. High-Level Radioactive Waste Managment, Advances in Chemistry Series, Number 153, American Chemical Society. Chikalla, T. D. and J. E. Mendel, eds. 1979. Ceramics in Nuclear Waste Management, CONF-790420, U.S. Department of Energy, Washington, D.C. Code of Federal Regulations. Title 10, Part 50, Appendix F. Cooperstein, R., ed. 1976. The Management of Radioactive Waste: Waste Partitioning as an Alternative, NR-CONF-001. Nuclear Regulatory Commission, Washington, D.C. Croff, A. G., et al. 1977. A Preliminary Assessment of Partitioning and Transmutation as a Radioactive Waste Management Concept, ORNL/TM-5808. Oak Ridge National Laboratory, Oak Ridge, Tennessee. De,.A. K., B. Luckscheiter, W. Lutze, G. Malow and E. Schiewer. 1976. "Development of Glass Ceramics for the Incorporation of Fission Products," Ceramic Bulletin 55:500-503. Dix, G. P. 1975. "The Beneficial Utilization of Nuclear Waste Products," Waste Management 75, pp. 153-75, University of Arizona, Tucson, Arizona. Gombert, D. H., S. Cole and J. R. Berreth. Vitrification of High-Level ICPP Calcined Wastes, ICP-1177. Idaho National Engineering Laboratory, Idaho Falls, Idaho. Groenier, W. S. 1977. Current Positions and Status of Voloxidation Process at ORNL, ORNL/CR-77/67. Oak Ridge National Laboratory, Oak Ridge, Tennessee. Guber, W., M. Hussain, L. Kahl, W. Muller and J. Saidl. 1979. Development and Characterization of the Glass-Ceramic VCP15 for Immobilization of High-Level Liquid Radioactive Waste, CONF-790420. U.S. Department of Energy, Washington, D.C., pp. 188-192.
4.48 Harries, B. R. et al. 1979. Design Integration Study, Spent LWR Fuel Recycle Complex, Conceptual Design, Coprocessing Case (A-2), DP-CFP-79-121, Savannah River Laboratory, Aiken, South Carolina. Idaho National Engineering Laboratory. 1978. Calcined Solids Retrieval and Handling, ACI-224. Idaho Falls, Idaho. pp. 30-31. Jardine, L. J. and M. J. Steindler. 1978. A Review of Metal-Matrix Encapsulation of Solidified Radioactive High-Level Waste, ANL-78-19. Argonne National Laboratory, Argonne, Illinois. Kelley, J. A. 1975. Evaluation of Glass as a Matrix for Solidif' ation of Savannah River Plant Waste, (DP-1397). Savannah River Laboratory, Aiken, South Carolina. Kupfer, M. J. 1979. Vitrification of Hanford Radioactive Defense Wastes, RHO-SA-89. Rockwell Hanford Operations, Richland, Washington. Lamb, K. M. 1978. Final Report: Development of a Metal Matrix for Incorporating High- Level Commercial Waste, ICP-1144. Idaho National Engineering Laboratory, Idaho Falls, Idaho. Lamb, K. M., S. J. Priebe, H. S. Cole and B. D. Taki. 1979. "A Pelleted Waste Form for High-Level ICPP Wastes," pp. 224-228, CONF-790420. Lokken, R. 0. 1978. A Review of Radioactive Waste Immobilization in Concrete, PNL-2654, Pacific Northwest Laboratory, Richland, Washington. McCarthy, G. G., ed. 1979. Scientific Basis for Nuclear Waste Management, Volume 1. Plenum Press, New York. McCarthy, G. J. 1977. "High-Level Ceramics: Materials Considerations, Process Simulation, and Product Characterization," Nuclear Technology 32:92-105. McCarthy, G. J. 1979. "Ceramics from Defense High-Level Wastes," Nuclear Technology, Letter to the Editor. McCarthy, G. J. 1979. "Crystal Chemistry and Phase Equilibria in the Synthetic Minerals of Ceramic Waste Forms: Fluorite and Monazite Structure Phases," Presented at the International Symposium on the Scientific Basis for Nuclear Waste Management, Materials Research Society, Boston, MA, November 27-30, 1979. McCarthy, G. J. and M. T. Davidson. 1975. "Ceramic Nuclear Waste Forms: 1, Crystal Chemistry and Phase Formation, Ceramic Bulletin 54(9): 782-786. Mendel, J. E. 1978. The Storage and Disposal of Radioactive Waste as Glass in Canisters, PNL-2764. Pacific Northwest Laboratory, Richland, Washington. Mendel, J. E., et al. 1975. A Program Plan for Comprehensive Characterization of Solidified High-Level Wastes, BNWL-1940. Pacific Northwest Laboratory, Richland, Washington. Merritt, W. F. 1977. "High-Level Waste Glass: Field Leach Test," Nuclear Technology 32:88-89. Moore, J. G., E. Newman and G. C..Rogers. 1979. Radioactive Waste Fixation in FUETAP (Formed Under Elevated Temperature and Pressure) Concretes-Experimental Program and Initial Results, ORNL/TM-6573. Oak Ridge National Laboratory, Oak Ridge, Tennessee. National Academy of Sciences. 1978. Radioactive Wastes at the Hanford Reservation: A Technical Review, Washington, D.C. Nelson, R. D., W. A. Ross, 0. F. Hill, J. E. Mendel, M. D. Merz and R. P. Turcotte. Materials Characterization Center Program Plan, PNL-3254. Pacific Northwest Laboratory, Richland, Washington.
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FINAL DOE/EIS-0046F Volume 1 of 3 U
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* Development of conventionally min
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vi Locations of DOE Regional Office
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viii CONTENTS (contd) 1.6.3 Acciden
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CONTENTS (contd) REFERENCES FOR SEC
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xii CONTENTS (contd) 4.4.3.1 Vault
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xiv CONTENTS (contd) 4.9.3 Detailed
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xvi CONTENTS (contd) 5.3.3 Effect o
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xviii CONTENTS (contd) 6.1.2 Rock M
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XX CONTENTS (contd) 6.2.1.2 Very De
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xxii CONTENTS (contd) 6.2.5.5 Islan
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xxiv FIGURES (contd) 4.3.10 Process
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xxvi VOLUME 1 TABLES 1.1.1 Total Sp
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xxviii TABLES (contd) 4.7.7 Dose to
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XXX TABLES (contd) 5.4.20 Selected
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xxxii TABLES (contd) 6.1.20 Estimat
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xxxiv TABLES (contd) 7.4.2 Comparis
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1.2 The DOE is proposing a program
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106 ---- - 104 104 : 10 Ce- S - \ -
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1.2 THE PROGRAMMATIC ALTERNATIVES 1
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ELEVATOR SHAFT FOR SPENT FUEL OR FU
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1.10 Once licensing approvals are o
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1.12 example, a large labor force b
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1.14 water transport to the biosphe
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1.16 .1.4 ALTERNATIVE ACTION--BALAN
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1.18 1.4.5 Ice Sheet Disposal Conce
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1.20 Space disposal is of interest
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1.6 PREDISPOSAL SYSTEMS(a) 1.22 Aft
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1.24 1.7 ENVIRONMENTAL IMPACTS OF P
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1.26 1.7.1 System Radiological Impa
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1.28 TABLE 1.7.5. Comparison of Hea
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1.30 alternative program. The range
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1.32 * Resource commitments also in
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REFERENCES FOR CHAPTER 1 1.34 Code
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PLUTONIUM-URANIUM FUELFABRICATION 2
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2.4 With regard to receipt and stor
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Plan, including a summary of the pu
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2.8 The main body of the text (Volu
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2.10 2.3 OTHER DECISIONS CONCERNING
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2.12 The second major decision proc
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2.14 Using a general conceptual des
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3.1 CHAPTER 3 DESCRIPTION OF PROGRA
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3.3 The Interagency Review Group (I
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3.5 3.1.2 Alternative Action--Paral
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3.2 BASES FOR THE ANALYSIS 3.7 A nu
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3.9 ENRICHED NUER WATER BASIN SPENT
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3.11 wastes also result. These are
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500 400 300 5 200 -_J 100 - 3.13 CA
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3.15 3.2.4 Ecological and Atmospher
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3.17 nue impacts can be provided in
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3.19 quencies, source terms can be
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3.21 ownership. The constant dollar
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3.23 quences to the public followin
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REFERENCES FOR SECTION 3.2 3.25 Cla
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3.3.1.1 Cosmic Radiation 3.27 Cosmi
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3.29 surfaces, and 25 mrem/yr to bo
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3.31 Part 20 of the Code of Federal
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3.33 finding and listed radionuclid
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REFERENCES FOR SECTION 3.3 3.35 Tit
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3.37 One such hazard index is based
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3.39 Since long-term repository con
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3.41 those data that can reasonably
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3.5 NONTECHNICAL ISSUES 3.43 Many o
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3.45 the repository. Some feel that
Page 129 and 130: 3.47 cooperative agreement with the
Page 131 and 132: 3.49 Inspection, the regular checki
Page 133 and 134: REFERENCES FOR SECTION 3.5 3.51 Cod
Page 135 and 136: SPENT AT REACTOR AWAY FROM FUEL STO
Page 137 and 138: 4.4 4.1.2 Predisposal System for th
Page 139 and 140: 4.6 TABLE 4.1.3. Example Predisposa
Page 141 and 142: ONCE-THROUGH CYCLE SPENT FUEL STORA
Page 143 and 144: 4.10 TABLE 4.2.1. Classification of
Page 145 and 146: 4.12 BWR fuel models that account f
Page 147 and 148: TABLE 4.2.3. Selected Radionuclide
Page 149 and 150: 4.16 TABLE 4.2.5. Selected Radionuc
Page 151 and 152: 4.18 ENCAPSULATION SPENT FUEL WATER
Page 153 and 154: 4.20 Combustible wastes produced du
Page 155 and 156: 4.22 methods described in Chapter 6
Page 157 and 158: 4.24 1) vitrification by in-can mel
Page 159 and 160: 4.26 Some partitioning options may
Page 161 and 162: 4.28 wells. The 90 Sr leach rate de
Page 163 and 164: 4.30 Another synthetic mineral conc
Page 165 and 166: 4.32 Center has been set up to prov
Page 167 and 168: 4.34 FUEL ASSEMBLY SHEAR RETRIEVE U
Page 169 and 170: 4.36 may be contact-handled. The qu
Page 171 and 172: 4.38 4.3.3.4 Immobilization of Wet
Page 173 and 174: HEPA FILTER 4.40 CHARCOAL FILTER -
Page 175 and 176: 4.3.4.2 Gaseous Radionuclide Recove
Page 177 and 178: 4.44 treatment options at an FRP an
Page 179: 4.46 TABLE 4.3.2. Estimated Quantit
Page 183 and 184: 4.50 U.S. Energy Research and Devel
Page 185 and 186: 4.52 4.4.1.1 Water Basin Storage of
Page 187 and 188: 4.54. The exhaust air is monitored
Page 189 and 190: 4.56 but double-walled tanks have b
Page 191 and 192: 4.58 The storage yard is monitored
Page 193 and 194: 4.60 A similar approach was examine
Page 195 and 196: REFERENCES FOR SECTION 4.4 4.62 Atl
Page 197 and 198: 4.64 These existing casks were desi
Page 199 and 200: 4.5.3.1 Fuel Residue Transport 4.66
Page 201 and 202: REFERENCES FOR SECTION 4.5 4.68 Per
Page 203 and 204: 4.70 flanges, and disconnecting ele
Page 205 and 206: TABLE 4.6.1. Volumes and Radionucli
Page 207 and 208: TABLE 4.6.3. Radionuclides Released
Page 209 and 210: 4.76 4.7 ENVIRONMENTAL IMPACTS OF P
Page 211 and 212: 4.78 4.7.1.2 Nonradiological Efflue
Page 213 and 214: 4.80 The expected socioeconomic imp
Page 215 and 216: TABLE 4.7.5. Resource Commitments f
Page 217 and 218: 4.84 (those to which nearly all wor
Page 219 and 220: 4.86 TABLE 4.7.8. Example Reprocess
Page 221 and 222: 4.88 TABLE 4.7.9. Selected Social S
Page 223 and 224: 4.90 4.8 ACCIDENT IMPACTS FOR PREDI
Page 225 and 226: 4.92 Severe accidents resulting fro
Page 227 and 228: 4.94 with a colocated spent fuel pa
Page 229 and 230: 4.96 such as blowers, pumps, etc. T
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4.98 occur once per year due to imp
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REFERENCES FOR SECTION 4.8 Code of
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TABLE 4.9.1. Unit Costs of Predispo
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TABLE 4.9.2. Unit Costs of Predispo
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4.106 TABLE 4.9.3. Predisposal Unit
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4.108 $109/kg HM, which is comparab
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4.110 TABLE 4.9.7 Subsystems(a) Was
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4.112 4.10 SAFEGUARDS INCLUDING PHY
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4.114 1976). It is assumed that one
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4.116 The physical protection requi
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REFERENCES FOR SECTION 4.10 4.118 C
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5.2 This section provides an overvi
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5.4 breakdown into component minera
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5.6 geologic setting may require ex
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5.8 releases so that substantial nu
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Hole Sleeve 5.10 The function of ho
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5.12 integral part of this plan is
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5.2 STATUS OF TECHNOLOGY AND R&D 5.
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5.16 Gravity analysis can detect sm
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5.18 (Witherspoon 1977). Pulse inje
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5.20 Potentially active faults can
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5.22 release rate of the nuclides.
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5.24 5.2.3.1 Excavation and Undergr
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REFERENCES FOR SECTION 5.2 5.26 Alg
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5.28 Office of Nuclear Waste Manage
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5.30 TABLE 5.3.1. Conceptual Reposi
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BLDG EXCLUSION ZONE AGRICULTURAL FE
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5.34 areas occupy 650 to 730 ha, wi
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5.36 emplacement. Beyond this initi
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5.38 In the case of reprocessing cy
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5.40 sealed in an appropriately siz
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5.3.2.5 Retrievability 5.42 These c
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5.44 erations permit, as opposed to
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5.46 5.4 ENVIRONMENTAL IMPACTS RELA
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and no significant impacts are expe
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5.50 3 TABLE 5.4.6. Particulate Con
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5.52 5.4.3 Radiological Effects The
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5.54 chlorosis of young trifoliate
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5.56 the environment. Discharge of
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5.58 of wastes, placement of waste
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5.60 TABLE 5.4.15 Total Quantities
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5.62 TABLE 5.4.16 Estimated Manpowe
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5.64 TABLE 5.4.18. Selected Expecte
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5.66 5.4.6.6 Environmental Effects
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5.68 The 70-yr worldwide population
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5.70 The spoils piles could have an
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5.72 5.5 LONG-TERM ENVIRONMENTAL CO
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5.74 Fuel Reprocessing Waste Spent
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5.76 TABLE 5.5.1. First-Year Whole-
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5.78 The population dose from a met
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5.80 be from 4 x 10 - 3 to 3 x 10 -
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5.82 Seventy-year whole-body dose c
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5.84 Dilution Dilution Element Fact
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5.86 this conversion, a regional po
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5.88 probability that the drill (0.
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5.90 a few years. For purposes of t
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5.92 dose commitments are less than
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5.6 COST OF GEOLOGIC DISPOSAL 5.94
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5.96 kilogram of disposal in a basa
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5.98 5.6.5 Comparison with Other Co
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REFERENCES FOR SECTION 5.6 5.100 Be
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REFERENCES FOR SECTION 5.7 5.102 Co
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5.104 5.9 SHORT-TERM USES OF THE EN
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6.1 Chapter 6 ALTERNATIVE CONCEPTS
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6.3 Concept Summary. The concept su
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mined geologic repository, are not
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Reactors Waste Sources LWR Fuel Cyc
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6.1.1.2 System and Facility Descrip
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6.11 bridge crane would remove the
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6.13 For oil field rotary drilling,
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6.15 diameter of approximately 48 c
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6.17 * An improved understanding of
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Health Impacts 6.19 Radiological Ef
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6.21 The occupational hazards durin
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Resource Consumption 6.23 The consu
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6.25 evaluated only on the basis of
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6.1.1.7 Safeguards 6.27 As noted, t
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I* LWR Reactors 6.29 Waste Sources
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Spent and 6.31 Recycle Facilities N
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6.33 Drilling/Mining System. The re
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6.35 cause of the limited time, the
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6.37 are identical with those used
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6.39 Fracturing During Cooling. Dur
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6.41 Implementation Time and Estima
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6.43 TABLE 6.1.8. Occupational Dose
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6.45 TABLE 6.1.9. Estimated Energy
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6.47 radioactivity transport, movem
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6.49 Various options to be consider
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Reactor 6.51 Recycle Facilities Spe
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6.53 Repository Facility. The layou
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6.55 * Development of criteria for
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6.57 species that recolonize an isl
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6.59 Radionuclides might be sorbed
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6.61 Quantitative estimates of thes
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6.1.4.2 System and Facility Descrip
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6.65 RH-TRU and other Recycle TRU w
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6.67 Canisters HLW 2,380 Cladding H
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6.69 Waste Form. The waste form and
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6.71 Transportation. Transportation
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6.73 TABLE 6.1.11. Radiological Imp
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Socioeconomic Impacts 6.75 Because
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6.77 wastes (Deese 1976). This trea
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6.79 In each case, only those costs
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6.81 total costs are estimated to b
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Waste Sources Reactors Fuel Cycles
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Reactor Spent 6.85 M i n ed Recycle
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6.87 It appears possible, as an alt
Page 445 and 446:
6.89 deployment of the concept desi
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6.91 * The capability for correctiv
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6.93 Other possible land impacts co
Page 451 and 452:
6.95 6.1.5.5 Potential Impacts over
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6.97 described for the mined geolog
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6.99 TABLE 6.1.18. Operating Costs
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6.101 Isolation from the biosphere
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6.103 S Fuel R e farication Note: L
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6.105 would permit different isolat
Page 463 and 464:
6.107 Shale deposits in the United
Page 465 and 466:
6.109 Waste Preparation Technology.
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6.111 to shallow ground water or to
Page 469 and 470:
6.113 may be conveniently divided i
Page 471 and 472:
6.115 repositories (Section 5.5) an
Page 473 and 474:
6.117 The geologic formation in whi
Page 475 and 476:
6.1.7.1 Concept Summary 6.119 6.1.7
Page 477 and 478:
The cycle continues by: 6.121 Spent
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6.123 6.1.7.3 Status of Technical D
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Implementation Time 6.125 The long
Page 483 and 484:
6.127 TABLE 6.1.21. Annual Routine
Page 485 and 486:
6.129 TABLE 6.1.25. Transportation
Page 487 and 488:
Socioeconomic Impacts 6.131 Socioec
Page 489 and 490:
6.133 Results of a long-term risk c
Page 491 and 492:
6.135 TABLE 6.1.28. Operating Costs
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6.137 REACTORS Domestic Civilian F
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HLW From Fuel Processing Facility 6
Page 497 and 498:
° 6.141 OTV/ORBIT 0.85 AU INSERTIO
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6.143 Waste Form. The waste form wo
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Implementation Time 6.145 With the
Page 503 and 504:
6.147 (Bechtel 1979a). (See Table 6
Page 505 and 506:
6.149 Regarding on- or near-pad acc
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6.151 * Public Sector.Economy. Curr
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6.153 * "Treaty on Principles Gover
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6.155 charges to DOE as a Space Shu
Page 513 and 514:
6.157 Bell, W. J. 1971. An Analysis
Page 515 and 516:
6.159 Environmental Protection Agen
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6.161 Lynn, R. D. and Z. E. Arlin.
Page 519 and 520:
6.163 Sandia Laboratories. 1980. Su
Page 521 and 522:
6.165 6.2 COMPARISON OF ALTERNATIVE
Page 523 and 524:
6.167 fuel assemblies would be appr
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6.169 A reprocessing fuel cycle wou
Page 527 and 528:
6.2.1.9 Space 6.171 In the space di
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Radiological Effects 6.173 TABLE 6.
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Non-Radiological Environmental Effe
Page 533 and 534:
6.177 6.2.2.7 Long-Term Maintenance
Page 535 and 536:
6.179 deep hole, island mined repos
Page 537 and 538:
6.181 6.2.3.4 The Concept Should be
Page 539 and 540:
Timing 6.183 The timing of implemen
Page 541 and 542:
TABLE 6.2.6. Performance of Propose
Page 543 and 544:
6.187 As discussed in Section 6.2.1
Page 545 and 546:
6.189 design might well be limited
Page 547 and 548:
6.191 6.2.4.4 Conformance with Fede
Page 549 and 550:
6.193 appears not to significantly
Page 551 and 552:
TABLE 6.2.8. Estimated Resource Com
Page 553 and 554:
6.197 space disposal in an intermed
Page 555 and 556:
REFERENCES FOR SECTION 6.2 6.199 Co
Page 557 and 558:
6.2 annual throughput or a common e
Page 559 and 560:
6.4 are identified for well injecti
Page 561 and 562:
6.1.1.1 Concept Summary 6.6 6.1.1 V
Page 563 and 564:
6.8 Recycle Geologic Facilitie UF6
Page 565 and 566:
6.10 The canister would have to pro
Page 567 and 568:
6.12 storage facility (Bechtel 1979
Page 569 and 570:
6.14 Sealing. Standard oil field pr
Page 571 and 572:
6.16 thermomechanical behavior woul
Page 573 and 574:
6.18 Remote determinations of water
Page 575 and 576:
6.20 TABLE 6.1.2. VDH Concept - Occ
Page 577 and 578:
6.22 available at this time. Parame
Page 579 and 580:
Potential Events 6.24 TABLE 6.1.6.
Page 581 and 582:
6.26 TABLE 6.1.7. Long-Term Radiolo
Page 583 and 584:
Page 585 and 586:
Waste-Type Compatibility 6.30 It is
Page 587 and 588:
6.32 Predisposal Treatment of the W
Page 589 and 590:
6.34 be: (1) the pipe and valve man
Page 591 and 592:
6.36 The heat effects in the periph
Page 593 and 594:
6.38 the necessary leaktightness of
Page 595 and 596:
6.40 Data Base Development. Develop
Page 597 and 598:
6.42 Radiological Impacts. During p
Page 599 and 600:
6.44 1979a). In addition, with colo
Page 601 and 602:
6.46 would be stored as a liquid, i
Page 603 and 604:
Page 605 and 606:
Reactors 6.50 -|LWR| Waste Sources
Page 607 and 608:
6.52 Precipitation Surface Faciliti
Page 609 and 610:
6.54 6.1.3.3 Status of Technical De
Page 611 and 612:
6.56 Moreover, although transportat
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6.58 International and Domestic Leg
Page 615 and 616:
Sea Water Dilution 6.60 Discharge I
Page 617 and 618:
Page 619 and 620:
Reactors 6.64 Waste Sources IF L W
Page 621 and 622:
6.66 The ocean's benthic boundary l
Page 623 and 624:
6.68 The total seabed area required
Page 625 and 626:
6.70 Ion Transport in the Sediment.
Page 627 and 628:
6.72 The SDP program plan has been
Page 629 and 630:
6.74 TABLE 6.1.12. Estimated Dose C
Page 631 and 632:
6.76 TABLE 6.1.13. Estimated Energy
Page 633 and 634:
6.78 food chains and ultimate consu
Page 635 and 636:
6.80 processed and disposed of, and
Page 637 and 638:
Page 639 and 640:
6.84 Because the options for the wa
Page 641 and 642:
Reprocessing Plant 6.86 Shielded Ce
Page 643 and 644:
6.88 ,An important factor in this c
Page 645 and 646:
6.90 * Radioactivity of water at ic
Page 647 and 648:
6.92 Occupational casualties from t
Page 649 and 650:
6.94 glass, before transportation t
Page 651 and 652:
6.96 Specific areas of concern, as
Page 653 and 654:
6.98 TABLE 6.1.17. Capital Costs Fo
Page 655 and 656:
Page 657 and 658:
6.102 cases, the injection liquid w
Page 659 and 660:
6.104 heated to above 100 C) (EPA 1
Page 661 and 662:
6.106 capabilities, primarily perfo
Page 663 and 664:
6.108 volume of geologic data (stra
Page 665 and 666:
6.110 With the basic technology for
Page 667 and 668:
Summary 6.112 Major uncertainties,
Page 669 and 670:
Natural System Impacts 6.114 Effect
Page 671 and 672:
6.116 natural gas storage, freshwat
Page 673 and 674:
6.118 for a facility to perform rem
Page 675 and 676:
Reactors 6.120 -- ILWRl Waste Sourc
Page 677 and 678:
Predisposal Treatment 6.122 In a fu
Page 679 and 680:
6.124 * The use of commercial power
Page 681 and 682:
6.126 6.1.7.4 Impacts of Constructi
Page 683 and 684:
6.128 TABLE 6.1.23. Occupational Ra
Page 685 and 686:
6.130 TABLE 6.1.26. Summary Effects
Page 687 and 688:
6.132 waste treatment facility woul
Page 689 and 690:
6.134 more than 100 times for fresh
Page 691 and 692:
Page 693 and 694:
6.138 quirements, high costs, and p
Page 695 and 696:
6.140 The shielded waste container
Page 697 and 698:
6.142 Retrievability/Recovery. Unti
Page 699 and 700:
6.144 Rescue Technology. Remote aut
Page 701 and 702:
6.146 6.1.8.4 Impacts of Constructi
Page 703 and 704:
6.148 TABLE 6.1.30 Short Term (Pree
Page 705 and 706:
6.150 In general, normal operation
Page 707 and 708:
6.152 Critical Resources. Estimated
Page 709 and 710:
6.154 The potential hazard from the
Page 711 and 712:
REFERENCES FOR SECTION 6.1 6.156 Aa
Page 713 and 714:
6.158 Cohen, J. J. et al. 1972. "In
Page 715 and 716:
6.160 Holilster, J. C. and R. J. We
Page 717 and 718:
6.162 Pardue, W. M. 1977. Prelimina
Page 719 and 720:
6.164 White, D. E. 1965. "Saline Wa
Page 721 and 722:
6.166 TABLE 6.2.1. Disposition of P
Page 723 and 724:
6.168 Spent fuel assemblies would b
Page 725 and 726:
6.170 A waste processing facility w
Page 727 and 728:
S\ 6.172 the spectrum of waste prod
Page 729 and 730:
6.174 unit of electrical power by n
Page 731 and 732:
6.176 policies" suggesting that con
Page 733 and 734:
6.178 6.2.3 Application of Performa
Page 735 and 736:
6.180 factory performance of the is
Page 737 and 738:
6.182 development of methods for pr
Page 739 and 740:
6.184 standard of judgement as to p
Page 741 and 742:
6.186 tion of facilities. The failu
Page 743 and 744:
6.188 The mined repository and very
Page 745 and 746:
6.190 relative to waste treatment a
Page 747 and 748:
TABLE 6.2.7. Estimated costs of Var
Page 749 and 750:
6.194 hole concept following packag
Page 751 and 752:
Radiological Effects TABLE 6.2.9. S
Page 753 and 754:
6.2.5.4 Space Disposal 6.198 The pr
Page 755 and 756:
7.1 CHAPTER 7 SYSTEM IMPACTS OF PRO
Page 757 and 758:
7.3 adoption of this strategy was t
Page 759 and 760:
7.5 these low-growth conditions. Th
Page 761 and 762:
7.7 By combining the ORIGEN to matc
Page 763 and 764:
7.9 Four types of waste management
Page 765 and 766:
7.3 SYSTEM LOGISTICS 7.11 To develo
Page 767 and 768:
7.13 7.3.1 Repository Inventory Acc
Page 769 and 770:
250 200- 150 100 - 2 _ 50- 250 1990
Page 771 and 772:
E 400 7.17 DCASE 5 S/ CASE 4 S300 z
Page 773 and 774:
7.19 TABLE 7.3.2. Comparison of Awa
Page 775 and 776:
7.21 wastes do become substantial f
Page 777 and 778:
TABLE 7.3.6. Comparison of Total Tr
Page 779 and 780:
7.25 TABLE 7.3.8. Maximum (and mini
Page 781 and 782:
7.27 The number of equivalent 30-ye
Page 783 and 784:
7.29 TABLE 7.3.10. Number of 800-he
Page 785 and 786:
TABLE 7.3.12. Plutonium Disposition
Page 787 and 788:
TABLE 7.3.13. Total Radioactivity I
Page 789 and 790:
7.35 reprocessing cycle wastes are
Page 791 and 792:
7.37 TABLE 7.3.18 Principal Contrib
Page 793 and 794:
7.39 TABLE 7.4.2 Comparison of 70-Y
Page 795 and 796:
7.41 for discrimination in the sele
Page 797 and 798:
7.43 TABLE 7.5.1 Resource Commitmen
Page 799 and 800:
TABLE 7.5.3 Comparison of Relative
Page 801 and 802:
7.47 1980). (This schedule actually
Page 803 and 804:
7.49 TABLE 7.6.4. Comparison of Lev
Page 805 and 806:
7.51 TABLE 7.6.8. Comparison of Lev
Page 807 and 808:
7.53 Unit costs for the present inv
Page 809 and 810:
8.1 CHAPTER 8 GLOSSARY OF KEY TERMS
Page 811 and 812:
8.3 Cask: A container that provides
Page 813 and 814:
FPF: Fuel packaging facility. 8.5 F
Page 815 and 816:
8.7 Kaolinite: A common clay consis
Page 817 and 818:
8.9 Primary Wastes: Untreated initi
Page 819 and 820:
8.11 Transportation: Movement of ma
Page 821 and 822:
iii VOLUME 2 CONTENTS APPENDIX A -
Page 823 and 824:
V CONTENTS (contd) K.2 REMOVAL OF E
Page 825 and 826:
vii FIGURES (contd) K.1.11 Very-Nea
Page 827 and 828:
ix TABLES (contd) A.1.20 Spent Fuel
Page 829 and 830:
xi TABLES (contd) A.3.9b Heat Gener
Page 831 and 832:
xi11 TABLES (contd) A.9.3c Reposito
Page 833 and 834:
xv TABLES (contd) P.2.4 Uranyl Phos
Page 835 and 836:
TABLE A.1.1. Spent Fuel Logistics f
Page 837 and 838:
Page 839 and 840:
Page 841 and 842:
Page 843 and 844:
Page 845 and 846:
A. 12 TABLE A.1.11. Spent Fuel Logi
Page 847 and 848:
A.14 TABLE A.1.13. Spent Fuel Logis
Page 849 and 850:
A.16 TABLE A.1.15. Spent Fuel Logis
Page 851 and 852:
TABLE A.1.16. (Contd) REPOSITo0R SH
Page 853 and 854:
TABLE A.1.17. (Contd) RFPPnrESS RSI
Page 855 and 856:
TABLE A.1.18. (Contd) FPanCnr.EsS Y
Page 857 and 858:
TABLE A.1.19. (Contd) cFPonrES StHI
Page 859 and 860:
TABLE A.1.20. (Contd) RA*CTO9 YEAP
Page 861 and 862:
TABLE A.1.22. Number of Containers
Page 863 and 864:
A.2 RADIOACTIVE INVENTORY TABLES A.
Page 865 and 866:
TABLE A.2.1b. Radioactivity Invento
Page 867 and 868:
Page 869 and 870:
Page 871 and 872:
Page 873 and 874:
Page 875 and 876:
Page 877 and 878:
Page 879 and 880:
Page 881 and 882:
Page 883 and 884:
TABLE A.3.la. Heat Generation Rates
Page 885 and 886:
TABLE A.3.2a. Heat Generation Rates
Page 887 and 888:
Page 889 and 890:
Page 891 and 892:
TABLE A.3.5a. Heat'Generation Rates
Page 893 and 894:
Page 895 and 896:
Page 897 and 898:
Page 899 and 900:
Page 901 and 902:
A.4' HAZARD INDEX TABLES A.68 The t
Page 903 and 904:
A.70 TABLE A.4.1b. Hazard Index--On
Page 905 and 906:
A. 72 TABLE A.4.2b. Hazard Index--O
Page 907 and 908:
A.74 TABLE A.4.3b. Hazard Index--On
Page 909 and 910:
A.76 TABLE A.4.4b. Hazard:Index--On
Page 911 and 912:
A. 78 TABLE A.4.5b. Hazard Index--O
Page 913 and 914:
A.80 TABLE A.4.6b. Hazard Index--Re
Page 915 and 916:
Page 917 and 918:
A. 84 TABLE A.4.8b. Hazard Index--R
Page 919 and 920:
Page 921 and 922:
A.88 TABLE A.5.la. Whole-Body Dose
Page 923 and 924:
TABLE A.5.2a. Whole-Body Dose to th
Page 925 and 926:
A.6 RESOURCE COMMITMENTS A.92 Resou
Page 927 and 928:
TABLE A.6.2. Resource Commitments w
Page 929 and 930:
A.7 TRANSPORTATION REQUIREMENTS A.9
Page 931 and 932:
TABLE A.7.2. Transportation Require
Page 933 and 934:
TABLE A.8.1. Cost Estimates for Tre
Page 935 and 936:
A. 102 TABLE A.8.3. Cost Estimates
Page 937 and 938:
A.9 SUPPLEMENTARY SYSTEM COST DATA
Page 939 and 940:
TABLE A.9.1b. Allocation of Total-S
Page 941 and 942:
TABLE A.9.2a. Allocation of Total-S
Page 943 and 944:
TABLE A.9.2c. Allocation of Total-S
Page 945 and 946:
TABLE A.9.3b. Repository Media Effe
Page 947 and 948:
TABLE A.9.4a. Repository Media Effe
Page 949 and 950:
TABLE A.9.4c. Repository Media Effe
Page 951 and 952:
A.118 TABLE A.9.6. Estimated Resear
Page 953 and 954:
TABLE A.10.1. Repository Requiremen
Page 955 and 956:
B.1 APPENDIX B GEOLOGIC DISPOSAL SU
Page 957 and 958:
B.3 Erosion by wind energy is a mec
Page 959 and 960:
B.5 properties. The emplacement med
Page 961 and 962:
B.7 Rocks are named and described a
Page 963 and 964:
B.9 Through isotopic ratio dating,
Page 965 and 966:
B.4 HYDROLOGIC CONSIDERATIONS B.11
Page 967 and 968:
B.13 and the field measurement of h
Page 969 and 970:
B.6 MULTIPLE GEOLOGIC BARRIERS B.15
Page 971 and 972:
8.17 Salt deposit structures can be
Page 973 and 974:
B.19 TABLE B.6.1. Average Chemical
Page 975 and 976:
B.7 THE SITE SELECTION PROCESS B.21
Page 977 and 978:
B.23 CANDIDATE REGIONS FROM STAGE I
Page 979 and 980:
B.25 CONTINENTAL U.S. STAGE I DATA
Page 981 and 982:
B.27 Office of Waste Isolation. 197
Page 983 and 984:
C.2 the year of intake, and charge
Page 985 and 986:
C.2 DERIVED LIMITS AND ACTION LEVEL
Page 987 and 988:
C.6 boundary (e.g., evacuation). Th
Page 989 and 990:
C.8 Taylor, L. S. 1973. The Origin
Page 991 and 992:
D.2 employed here except that the p
Page 993 and 994:
0.4 and 75 radionuclides. A summary
Page 995 and 996:
D.6 farther than 2600 ft is negligi
Page 997 and 998:
D.8 Baker's analysis indicated that
Page 999 and 1000:
D.2.2.1 Dose Conversion Factors for
Page 1001 and 1002:
D.12 The concentration during the n
Page 1003 and 1004:
REFERENCES FOR APPENDIX D D.14 Atom
Page 1005 and 1006:
E.1 APPENDIX E RADIOLOGICALLY RELAT
Page 1007 and 1008:
warrants use in determining public
Page 1009 and 1010:
E.5 The Reactor Safety Study(a) (RS
Page 1011 and 1012:
E.2 GENETIC EFFECTS E.! It is known
Page 1013 and 1014:
E.3 CONCLUSIONS E.9 For this Statem
Page 1015 and 1016:
E.11 TABLE E.4.1. Comparison of Tra
Page 1017 and 1018:
E.13 E.6 SPECIFIC CONSIDERATION OF
Page 1019 and 1020:
E.15 In summary, it may be conclude
Page 1021 and 1022:
REFERENCES FOR APPENDIX E E.17 Atom
Page 1023 and 1024:
E.19 Shtukkenberg, Y. M. 1968. "Phy
Page 1025 and 1026:
F.2 REGIONAL DEMOGRAPHY AND LAND US
Page 1027 and 1028:
F.3 GEOLOGY F.4 The area in which t
Page 1029 and 1030:
70 600 - 150 500 - F.6 40 =30 20 CL
Page 1031 and 1032:
F.5 METEOROLOGY F.8 The general cli
Page 1033 and 1034:
F.10 F.6 PATHWAY PARAMETERS RELEVAN
Page 1035 and 1036:
G.1 APPENDIX G REFERENCE SITES FOR
Page 1037 and 1038:
Population G.3 Table G.2.1 Selected
Page 1039 and 1040:
H.1 APPENDIX H HAZARD INDICES The t
Page 1041 and 1042:
H.3 number of MPI in the environmen
Page 1043 and 1044:
H.5 Rochlin, G. I. 1977. "Nuclear W
Page 1045 and 1046:
Defense HLW(b) TABLE I.1.1. Compari
Page 1047 and 1048:
Defense TRU Waste On hand as of Sep
Page 1049 and 1050:
K.1 THERMAL CRITERIA K.1 APPENDIX K
Page 1051 and 1052:
subsequent precipitation of mineral
Page 1053 and 1054:
K.5 Step 5: Make near-field rock me
Page 1055 and 1056:
K.7 TABLE K.1.2. Thermal Load Limit
Page 1057 and 1058:
K.9 TABLE K.1.4 Thermal Loadings Ac
Page 1059 and 1060:
K.11 TEMPERATURE VS. DEPTH 400 -.-.
Page 1061 and 1062:
K.13 TEMPERATURE VS. DEPTH 400 --.
Page 1063 and 1064:
600 - K.15 TEMPERATURE VS. TIME 6.5
Page 1065 and 1066:
K.17 TEMPERATURE VS. TIME 6.5 YR. O
Page 1067 and 1068:
K.19 TABLE K.1.7. Thermal Loading L
Page 1069 and 1070:
K.21 TABLE K.1.11. Maximum Near-Fie
Page 1071 and 1072:
K.2 REMOVAL OF EMPLACED WASTE K.23
Page 1073 and 1074:
K.25 K.2.2 Recoverable Emplacement
Page 1075 and 1076:
K.27 TABLE K.3.1. Predominant Solut
Page 1077 and 1078:
K.29 TABLE K.3.4 Retention Time Ran
Page 1079 and 1080:
K.31 Neretnieks, I. 1977. Retardati
Page 1081 and 1082:
USGS/LASL-SLA L.2 Evaluation of the
Page 1083 and 1084:
L.2 HOST ROCK PROPERTIES L.4 Resear
Page 1085 and 1086:
L.3 THERMAL AND RADIATION EFFECTS L
Page 1087 and 1088:
Glossary of Acronyms Used in Append
Page 1089 and 1090:
M.I APPENDIX M. BIBLIOGRAPHY FOR SE
Page 1091 and 1092:
M.3 Bryant, E. A. et al. 1976. Oklo
Page 1093 and 1094:
M.5 Department of Energy (DOE). 197
Page 1095 and 1096:
M.7 Gorrell, T. C. 1979. Transmutat
Page 1097 and 1098:
Loeding, J. W. 1961. The Fluid Bed
Page 1099 and 1100:
M. 1 National Academy of Sciences (
Page 1101 and 1102:
M.13 Roberts, J. J. et al. 1978. Pl
Page 1103 and 1104:
M.15 Thompson, G. H. et al. 1979. A
Page 1105 and 1106:
N.1 APPENDIX N WASTES FROM THORIUM-
Page 1107 and 1108:
N.3 operation used to separate the
Page 1109 and 1110:
P.1 APPENDIX P MINERALS THAT COULD
Page 1111 and 1112:
P.3 One can usually establish only
Page 1113 and 1114:
P.5 * pH. Most minerals are leached
Page 1115 and 1116:
Element minerals P.7 TABLE P.1.4 Pl
Page 1117 and 1118:
P.1.2.1 Leaching rate P.9 If the le
Page 1119 and 1120:
P.11 Using Table P.1.6 as a guide,
Page 1121 and 1122:
P.13 * firing the calcine, at tempe
Page 1123 and 1124:
P.15 The reported rare earth conten
Page 1125 and 1126:
P.17 Although the pure di-calcium s
Page 1127 and 1128:
P.19 aluminosilicate framework stru
Page 1129 and 1130:
P.21 The stability of this group of
Page 1131 and 1132:
P.23 close association with albite,
Page 1133 and 1134:
P.25 complex carbonates of the alka
Page 1135 and 1136:
P.27 Ca(P04)3(0H) + 4H + - 5Ca 2+ +
Page 1137 and 1138:
P.29 Xenotime contains a high amoun
Page 1139 and 1140:
P.2.6.2 Uranate Minerals P.31 Urani
Page 1141 and 1142:
P.33 depending on the number of wat
Page 1143 and 1144:
P.3 MINERAL TABLES P.35 P.3.1 Hosts
Page 1145 and 1146:
P.37 TABLE P.3.1. (continued) Occur
Page 1147 and 1148:
Page 1149 and 1150:
Page 1151 and 1152:
P.43 The rankings, except for the t
Page 1153 and 1154:
P.45 Koreskawa 1954) and differenti
Page 1155 and 1156:
P.47 uranium or thorium. Reports of
Page 1157 and 1158:
REFERENCES FOR APPENDIX P P.49 Alex
Page 1159 and 1160:
P.51 Mitchell, R. S. 1972.. "Virgin
Page 1161 and 1162:
FINAL DOE/EIS-0046F Volume 3 of 3 U
Page 1163 and 1164:
SAFEGUARDS GROWTH SCENARIOS GEOLOGI
Page 1165 and 1166:
2 POLICY TOPIC AREAS KEY ISSUES . R
Page 1167 and 1168:
4 Volume 2 Section of Final Stateme
Page 1169 and 1170:
Issues 6 WASTE PROGRAM Several comm
Page 1171 and 1172:
8 WASTE PROGRAM * The multibarrier
Page 1173 and 1174:
Response 10 WASTE PROGRAM The objec
Page 1175 and 1176:
Issue 12 LICENSING AND THE DECISION
Page 1177 and 1178:
14 LICENSING AND THE DECISION-MAKIN
Page 1179 and 1180:
Response 16 SITING ISSUES While the
Page 1181 and 1182:
Response 18 SITING ISSUES In keepin
Page 1183 and 1184:
Issues 20 FUEL CYCLE ISSUES Several
Page 1185 and 1186:
Issue 22 ATTRIBUTION OF COSTS/RISKS
Page 1187 and 1188:
24 GENERAL COMMENTS In addition to
Page 1189 and 1190:
Draft p. iv Issue 26 ORGANIZATION A
Page 1191 and 1192:
Issue 28 ORGANIZATION AND PRESENTAT
Page 1193 and 1194:
Section of Final Statement 30 ORGAN
Page 1195 and 1196:
Response 32 ORGANIZATION AND PRESEN
Page 1197 and 1198:
Draft pp. iv and 1.2 Issue 34 SCOPE
Page 1199 and 1200:
Response 5.2). Issue 36 SCOPE Such
Page 1201 and 1202:
(167) 38 SCOPE The problems or cost
Page 1203 and 1204:
40 RADIOLOGICAL ISSUES presently re
Page 1205 and 1206:
Draft p. 2.2.3 Issue 42 RADIOLOGICA
Page 1207 and 1208:
Draft p. 2.3.3 Issue 44 RADIOLOGICA
Page 1209 and 1210:
46 RADIOLOGICAL ISSUES particles (h
Page 1211 and 1212:
48 RADIOLOGICAL ISSUES it has been
Page 1213 and 1214:
Draft p. 3.1.144 Issue 50 RADIOLOGI
Page 1215 and 1216:
Draft Appendix C Issue 52 RADIOLOGI
Page 1217 and 1218:
Response 54 RADIOLOGICAL ISSUES EPA
Page 1219 and 1220:
56 RADIOLOGICAL ISSUES The EPA risk
Page 1221 and 1222:
58 RADIOLOGICAL ISSUES Transuranium
Page 1223 and 1224:
60 RADIOLOGICAL ISSUES BEIR III (19
Page 1225 and 1226:
62 CONSEQUENCE ANALYSIS Risk define
Page 1227 and 1228:
64 CONSEQUENCE ANALYSIS Sr and Cs h
Page 1229 and 1230:
66 CONSEQUENCE ANALYSIS individual
Page 1231 and 1232:
Response 68 CONSEQUENCE ANALYSIS Th
Page 1233 and 1234:
70 CONSEQUENCE ANALYSIS been provid
Page 1235 and 1236:
72 CONSEQUENCE.ANALYSIS on a sound
Page 1237 and 1238:
Response 74 CONSEQUENCE ANALYSIS DO
Page 1239 and 1240:
Draft p. 3.1.100 Issue 76 CONSEQUEN
Page 1241 and 1242:
Page 1243 and 1244:
80 CONSEQUENCE ANALYSIS demonstrate
Page 1245 and 1246:
82 CONSEQUENCE ANALYSIS The followi
Page 1247 and 1248:
Response 84 iCONSEQUENCE ANALYSIS T
Page 1249 and 1250:
Draft pp. 3.1.148-155 Issue ,86 CON
Page 1251 and 1252:
Page 1253 and 1254:
Draft pp. 3.1.165-168 Issue 90 CONS
Page 1255 and 1256:
92 CONSEQUENCE ANALYSIS Note the as
Page 1257 and 1258:
94 CONSEQUENCE ANALYSIS are found i
Page 1259 and 1260:
96 CONSEQUENCE ANALYSIS Briefly, th
Page 1261 and 1262:
98 CONSEQUENCE ANALYSIS rates to be
Page 1263 and 1264:
Response 100 CONSEQUENCE ANALYSIS T
Page 1265 and 1266:
102 CONSEQUENCE ANALYSIS in additio
Page 1267 and 1268:
104 CONSEQUENCE ANALYSIS Three sour
Page 1269 and 1270:
106 CONSEQUENCE ANALYSIS would depe
Page 1271 and 1272:
Issue 108 CONSEQUENCE ANALYSIS A qu
Page 1273 and 1274:
Response 110 CONSEQUENCE ANALYSIS A
Page 1275 and 1276:
Response 112 CONSEQUENCE ANALYSIS T
Page 1277 and 1278:
Issue 114 DOSE CALCULATIONS Several
Page 1279 and 1280:
Draft p. 1.20 Issue 116 DOSE CALCUL
Page 1281 and 1282:
Response 118 DOSE CALCULATIONS In p
Page 1283 and 1284:
Response 120 DOSE CALCULATIONS Dilu
Page 1285 and 1286:
Response 122 DOSE CALCULATIONS The
Page 1287 and 1288:
Page 1289 and 1290:
Page 1291 and 1292:
Issue 128 RISK PERSPECTIVES Several
Page 1293 and 1294:
Response 130 RISK PERSPECTIVES * Th
Page 1295 and 1296:
132 RISK PERSPECTIVES Draft p. 1.16
Page 1297 and 1298:
Draft p. 3.1.64 Issue 134 RISK PERS
Page 1299 and 1300:
Draft Appendix H Issue 136 RISK PER
Page 1301 and 1302:
Response 138 RISK PERSPECTIVES EPA
Page 1303 and 1304:
Draft p. 3.1.55 Issue 140 WASTE MAN
Page 1305 and 1306:
Response 142 WASTE MANAGEMENT OPERA
Page 1307 and 1308:
Page 1309 and 1310:
14,6 WASTE MANAGEMENT OPERATIONS To
Page 1311 and 1312:
Response 148 -WASTE MANAGEMENT OPER
Page 1313 and 1314:
Page 1315 and 1316:
Page 1317 and 1318:
Response 1.54 WASTE MANAGEMENT OPER
Page 1319 and 1320:
156 WASTE MANAGEMENT OPERATIONS AFR
Page 1321 and 1322:
Page 1323 and 1324:
Page 1325 and 1326:
Draft pp. 1.11 Issue 162 WASTE MANA
Page 1327 and 1328:
164 WASTE MANAGEMENT OPERATIONS whi
Page 1329 and 1330:
166 WASTE MANAGEMENT OPERATIONS and
Page 1331 and 1332:
168 WASTE MANAGEMENT OPERATIONS are
Page 1333 and 1334:
Draft p. 1.4 Issue 170 WASTE MANAGE
Page 1335 and 1336:
Draft p. 1.10 Issue 172 WASTE MANAG
Page 1337 and 1338:
Page 1339 and 1340:
Page 1341 and 1342:
178 WASTE MANAGEMENT OPERATIONS Dra
Page 1343 and 1344:
180 WASTE MANAGEMENT OPERATIONS 3.
Page 1345 and 1346:
Draft p. 3.1.116 Issue 182 WASTE MA
Page 1347 and 1348:
184 WASTE MANAGEMENT OPERATIONS sta
Page 1349 and 1350:
DOE/ET-0028, pp. 7.4.43 and 7.5.46
Page 1351 and 1352:
Draft pp. v and 3.1.6 Issue 188 FUE
Page 1353 and 1354:
Draft pp 1.10, 1.23, 3.1.133 Issue
Page 1355 and 1356:
192 COSTS 3. The construction cost
Page 1357 and 1358:
Draft pp 3.1.210-212 Issue 194 COST
Page 1359 and 1360:
196 COSTS Title Basin Size Cost Est
Page 1361 and 1362:
Issue 198 COSTS An issue which need
Page 1363 and 1364:
200 SAFEGUARDS For the waste in the
Page 1365 and 1366:
202 SAFEGUARDS planning for assista
Page 1367 and 1368:
Draft pp. 1.10 and 2.1.2 Issue 204
Page 1369 and 1370:
Draft, p. 1.3 Issue (208-NRC) Respo
Page 1371 and 1372:
Page 1373 and 1374:
Response 210 GEOLOGIC CONSIDERATION
Page 1375 and 1376:
Page 1377 and 1378:
214 GEOLOGIC CONSIDERATIONS in thes
Page 1379 and 1380:
216 GEOLOGIC CONSIDERATIONS The rev
Page 1381 and 1382:
Draft p. 3.1.4 Issue 218 GEOLOGIC C
Page 1383 and 1384:
Page 1385 and 1386:
Page 1387 and 1388:
Draft p. 3.1.8 Issue (113-EPA) Resp
Page 1389 and 1390:
226 GEOLOGIC CONSIDERATIONS composi
Page 1391 and 1392:
Page 1393 and 1394:
Page 1395 and 1396:
232 GEOLOGIC CONSIDERATIONS 5. Figu
Page 1397 and 1398:
Draft p. 3.1.20 Issue 234 GEOLOGIC
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Page 1401 and 1402:
Draft pp. 3.1.24, 33 and 235 Issue
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242 GEOLOGIC CONSIDERATIONS selecti
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244 GEOLOGIC CONSIDERATIONS The Tek
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Response The text was changed. Draf
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252 GEOLOGIC CONSIDERATIONS made. T
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256 GEOLOGIC CONSIDERATIONS effects
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260 GEOLOGIC CONSIDERATIONS be mapp
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262 GEOLOGIC CONSIDERATIONS tectoni
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264 GEOLOGIC CONSIDERATIONS Since e
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Issue 266 GEOLOGIC CONSIDERATIONS S
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Issue 268 GEOLOGIC CONSIDERATIONS I
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270 GEOLOGIC CONSIDERATIONS the Nev
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Draft p. 3.1.6 Issue 272 MULTIBARRI
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Draft p. 3.1.40 Issue 274 MULTIBARR
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Draft Appendix L Issue 280 MULT.IBA
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282 MULTIBARRIERS FOR DISPOSAL cont
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Draft p. 1.6 Issue 284 SOCIOECONOMI
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Draft p. 3.1.25 Issue 286 SOCIOECON
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Draft p. 3.1.75 Issue 288 SOCIOECON
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290 SOCIOECONOMIC/SOCIOPOLITICAL IS
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292 SOCIOECONOMIC/SOCIOPOLITICAL IS
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294 RESOURCE REQUIREMENTS a site sp
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Response REFERENCE ENVIRONMENTS DOE
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Response 298 REFERENCE ENVIRONMENTS
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Draft pp. 1.1, 31, 35, 36 Issue 300
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302 COMPARATIVE ASSESSMENT 2. To st
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304 COMPARATIVE ASSESSMENT Draft p.
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Response 306 COMPARATIVE ASSESSMENT
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Draft p. 4.9 Issue 308 COMPARATIVE
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314 ALTERNATIVE DISPOSAL CONCEPTS g
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316 ALTERNATIVE DISPOSAL CONCEPTS h
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Response 318 ALTERNATIVE DISPOSAL C
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Draft Appendix P Issue 320 ALTERNAT
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Draft p. 1.25 Issue 322 ALTERNATIVE
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Draft p. 3.3.7 Issue 324 ALTERNATIV
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Draft p. 3.3.30 Issue 326 ALTERNATI
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Page 1493 and 1494:
Response 330. ALTERNATIVE DISPOSAL
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332 ALTERNATIVE DISPOSAL CONCEPTS A
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334 ALTERNATIVE DISPOSAL CONCEPTS D
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Draft p. 3.4.13 Issue Response 336
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Issue 338 ALTERNATIVE DISPOSAL CONC
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Draft Section 3.5 Issue 340 ALTERNA
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346 ALTERNATIVE DISPOSAL CONCEPTS o
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348 ALTERNATIVE DISPOSAL CONCEPTS S
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Draft p. 1.27 Issue 352 ALTERNATIVE
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354 ALTERNATIVE DISPOSAL CONCEPTS W
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356 ALTERNATIVE DISPOSAL CONCEPTS e
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Response Jbb ALTERNATIVE DISPOSAL C
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Page 1525 and 1526:
Page 1527 and 1528:
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Page 1531 and 1532:
368 ALTERNATIVE DISPOSAL CONCEPTS T
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Draft p. 3.6.18 Issue Response 37U
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Draft Section 3.7 Issue 378 ALTERNA
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386 ALTERNATIVE DISPOSAL CONCEPTS W
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398 ALTERNATIVE DISPOSAL CONCEPTS T
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400 ALTERNATIVE DISPOSAL CONCEPTS E
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Draft p. 3.10.18 Issue 402 ALTERNAT
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Draft p. 3.10.27 Issue 404 ALTERNAT
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Page 1571 and 1572:
408 HEARING BOARD REPORT AND RESPON
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410 Safeguards of the Nuclear Regul
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HEARING BOARD REPORT ON THE DEPARTM
Page 1577 and 1578:
Associated documents that came to t
Page 1579 and 1580:
Further, this sole statement of pur
Page 1581 and 1582:
Not even those in the scientific co
Page 1583 and 1584:
A common misconception is that hole
Page 1585 and 1586:
In sumnary, humanistic consideratio
Page 1587 and 1588:
4. EDITORIAL AND TERMINOLOGICAL Res
Page 1589 and 1590:
Several views of comparative risk n
Page 1591 and 1592:
Resp-nse Various spent fuel storage
Page 1593 and 1594:
Since current costs in developing a
Page 1595 and 1596:
multiple barrier concept, they shou
Page 1597 and 1598:
F. MISCELLMEOUS ITMS REQUIRING REVI
Page 1599 and 1600:
III. CONCLUSIONS Subject to the abo
Page 1601 and 1602:
, Draft Environmental Impact Staten
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440 Interagency Review Group. 1978.
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U.S. Nuclear Regulatory Commission.
Page 1607 and 1608:
A.1 APPENDIX A LIST OF RESPONDENTS
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A.3 COMMENTER DATE RECEIVED 12. Ms.
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A.5 COMMENTER DATE RECEIVED 34. Mr.
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A.7 COMMENTER DATE RECEIVED 54. Edw
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A.9 COMMENTER DATE RECEIVED 79. Wal
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A.11 . COMMENTER- . .... . .... DAT
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A. 13 COMMENTER DATE RECEIVED 132.
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A.15 COMMENTER DATE RECEIVED 157. F
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A.17 COMMENTER DATE RECEIVED 183. R
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A.19 COMMENTER DATE RECEIVED 208. J
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A.21 COMMENTER DATE RECEIVED LETTER
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North Carolina: A.37 COMMENTER DATE
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APPENDIX B INDEX FOR COMMENT LETTER
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B.2 Letter Topic Area Pages 1 Costs
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B.4 Letter Topic Area Pages 30 (Con
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B.6 Letter Topic Area Pages 57 Gene
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B.8 Letter Topic Area Pages 102 Gen
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B.10 Letter Topic Area Pages 133 Wa
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B.12 Letter Topic Area Pages 160 Ge
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B.14 Letter Topic Area Pages. 198 W
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8.16 Letter Topic Area Pages 215 Wa
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C.1 APPENDIX C STATE AND FEDERAL AG
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State Of Idaho /' .DIVISION OF BUDG
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STATE OF KANSAS TENNESSEE §beparim
Page 1669 and 1670:
B. 1JM PORTER H.T. SUTTON OFFICE OF
Page 1671 and 1672:
Dr. Colin A. Heath July 10, 1979 Pa
Page 1673 and 1674:
OFFICE OF THE GOVERNOR WILLIAM P. C
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(Office of file (aobernor Geoar Pus
Page 1677 and 1678:
as storage facilities begin to reac
Page 1679 and 1680:
C. Frank Harsche, III Socftary Juli
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,U - ,UNITED STATES DEPARTMENT OF C
Page 1683 and 1684:
-3- TO: PP/EC - R. Lehm FROM: OA/Dx
Page 1685 and 1686:
for promulgation as Federal guides
Page 1687 and 1688:
2 published since the Draft EIS was
Page 1689 and 1690:
6 Spec c The hazard indices discuss
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10 22. (Page 3.1.6, sixth paragraph
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14 15 43. (Page 3.1.40, physical pr
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18 74. (Page 3.1.106, third paragra
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22 23 101. (Page 3.6.1) The first p
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26 27 124. (Page D.8) - The model u
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30 The consequence analysis as it b
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34 United States Department of the
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-4- -5- -4- An important criterion
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-8- -9- Modeling of Groundwater Mod
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-12- -13- Reasonable bounds for the
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3 Page 3.1.30. Third paragraph, fir
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7 8 also include at least generaliz
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11- 12 Page 3.1.6, par. 3, line 2:
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15 shaft and borehole sealing; larg
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1.9 20 Page 3.1.106. par. 3: What w
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UNITED STATES NUCLEAR REGULATORY CO
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INDEX TO GEIS COMMENTS 1. GENERAL..
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1-3 Comment Number Comment 1-4 .5 T
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1-7 Comment Comment Number Number ,
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2-1 2-2 Comment Comment Number Numb
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Comment Number 2-5 d. Transportatio
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2-9 2-10 Comment Comment Number Num
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C ~, "0 '0 , ' 0omment C Numb1 0 .3
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Comment Number 2-17 Comment Number
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3-1 3-2 Comment Number Comment Numb
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3-5 3-6 Comment Number Comment Numb
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Comment Number 3-9 Comment Number i
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3-13 Comment Comment Number Number
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Comment Number 3-17 3-18 Comment Nu
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3-21 3-22 Comment Comment Number Nu
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3-25 Comment Number Comment Number
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3-29 3-30 Comment .. Comment "'umbe
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3-33 Comment Comment Number ,lumber
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3-37 3-38 Comment Number Comment Nu
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3-41 3-42 Comment Comment Number Nu
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Comment Number 4-3 Comment Number I
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4-7 4-8 Comment Comment Number Numb
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Comnent ,iumoer 4-11 Comment Number
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5-2 Comment lNumber Comment 5-3 5-3
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Dr. Cblin A. Heath nivision of Wast
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