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103 CONSEQUENCE ANALYSIS amount of radionuclides released to the atmosphere as given in Table 4.1.1-12 of DOE/ET-0029. The amounts given in this table are based on release fractions given in Table 6.2.6 for accident number 6.2.8 in DOE/ET-0028. An examination of the release fractions and cask inven- tories given in DOE/ET-0028 indicates that the amount of radionuclides given in DOE/ET-0029, and hence the dose reported in Appendix N, are in error. There are three sources of error. Mixed fission products and actinides have been excluded from the release, the amount of 85 Kr released is underestimated, and the amount of 13 7 Cs released has been overestimated. Finally, the following discussion shows that the amount of 13 4 Cs and 1 3 7 Cs released for accident number 6.2.8 has been overestimated. The discussion on page 6.2.14 of DOE/ET- 0028 indicates that 6 x 10 -4 of the cesium inventory may be available for release as a result of fuel rod perforation in a high temperature environment. This result is taken from Supplement II to WASH-1238. According to Table 6.2.6 of DOE/ET-0028, the availability fraction is divided in half between 13 4 Cs and 13 7 Cs. Table 3.3.8 of DOE/ET-0028 shows a cask inventory of 1.7 x 105 curies and 9.4 x 104 curies per MTHM for 13 4 Cs and 137Cs, respectively. Since a cask contains 4 MTHM, this results in 6.8 x 105 curies of 13 4 Cs and 3.8 x 10 5 of 137Cs in a cask. Applying the availability fraction of 3 x 10 - 4 for each isotope yields 204 curies of 13 4 Cs and 114 curies of 13 7 Cs available for release. Since in accident number 6.2.8, 50% of fuel rods are perforated, this results in 102 curies of 13 4 Cs and 57 curies of 13 7Cs being released in this accident. Table 4.1.1-12 of DOE/ET-0029 shows 200 curies of 134 13 7 Cs and 110 curies of Cs being released. Perhaps the fact that only 50% of the rods are perforated was not taken into account. We recommend that the radiation dose to the maximum individual resulting from this accident be reevaluated in light of the above comments. (208-NRC) Response This comment raises three main issues. First is that population doses have been omitted from the discussion of severe accidents in the draft Statement. Second, population densities used to evaluate radiological consequences of spent fuel accidents are inappro- priate for accidents in urban areas. Last, release fractions used for a severe spent fuel accident are in error. Each of these issues is discussed below. The format used in the final Statement to discuss consequences of predisposal accidents presents both maximum individual and population doses from umbrella source terms. A defini- tion for umbrella source terms is given in Section 3.2.7 of this report. Transportation accident impacts are described in Section 4.8.1. The population density used for accident consequence analysis is 130 persons/km 2 and is based on an average of populous U.S. regions. Population doses vary approximately lin- early with population density. It higher population densities are assumed, high doses would result. Current interim NRC rules prohibit the transport of spent fuel through highly pop- ulated areas.
104 CONSEQUENCE ANALYSIS Three sources of error are identified in the discussion of the release fractions. The first is that releases of mixed fission products and actinides have been omitted. WASH-1238 (AEC 1972) states that actinides available for release in the pellet-clad gap would be neg- ligible compared to other nuclides. Mixed fission products were conservatively assumed available for release due to leaching of fuel pellet surfaces. The leaching mechanism could only occur if clad failure occurs before the loss of cask coolant. This is not the case in Accident 6.2.8 (DOE/ET-0028). Actinide and fission product releases from the fuel may be possible following an impact that disrupts the fuel pellets and cladding. Accident 6.2.7 in DOE/ET-0028 discusses this possibility. Second, this comment states that the amount of 85 Kr released is understated by Table 4.1.1-12 of DOE/ET-0029. The stated value in the table is low by 400 Ci of 85 Kr. The effect of this error is less than 1% of the doses reported in DOE/ET-0029. The last part of this comment relates to the release fraction for Cs. The release fraction, 6 x 10- 4 of all cesium was obtained from NUREG-0069 (NRC 1976b). Half of the fuel elements are assumed to rupture in the accident. This results in a release fraction for all cesium isotopes of 3 x 10 - 4 . Multiplying this value by the various isotope inven- tories yields the releases reported in Table 4.1.1-12 of DOE/ET-0029. Draft p. N.4 Issue The consequences presented in p. N.4 for severe accidents are based on the dose received by persons from radionuclides released to the atmosphere. Since severe accidents may cause a reduction in shielding efficiency, doses resulting from radiation emanating directly from the cask should also be evaluated. The description of severe accidents in Table 6.2.6 of DOE/ET-0028 indicates a small opening will exist in the cask. Accident number 6.2.8 is based on number 6.2.7. Number 6.2.8 assumes that no emergency action is taken to cool the cask involved in the 6.2.7 accident. This results in 50% of the fuel rods being perforated in number 6.2.8 instead of only 1% being perforated in number 6.2.7, in addition to 100% of the coolant being released in both accidents. Thus, release fractions in number 6.2.8 should be 50 times higher than in number 6.2.7. Indeed, for 85 Kr, 1291, and 3 H the release fractions given are 50 times higher for number 6.2.8 than for 6.2.7. However, although mixed fission products and actinides are reportedly released in number 6.2.7, only 134Cs and 1 3 7 Cs are reported as being released in number 6.2.8. This can also be seen in Tables 4.1.1-10 and 4.1.1-12 of DOE/ET-0029 which gives the actual number of curies released. Note that Table 4.1.1-10 gives the curies released for accident number 6.2.6, a moderate accident in which only 5% of the cavity coolant is released and only 0.25% of the fuel rods exhibit cladding failure. The table shows fission products such as 90Sr and 95 Nb and the actinides such as 239 Pu and 242 Cm being released. Table 4.1.1-12, which lists the radionuclides released for accident number 6.2.8, the severe accident does not contain any of the
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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
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3.47 cooperative agreement with the
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3.49 Inspection, the regular checki
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REFERENCES FOR SECTION 3.5 3.51 Cod
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SPENT AT REACTOR AWAY FROM FUEL STO
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4.4 4.1.2 Predisposal System for th
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4.6 TABLE 4.1.3. Example Predisposa
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ONCE-THROUGH CYCLE SPENT FUEL STORA
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4.10 TABLE 4.2.1. Classification of
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4.12 BWR fuel models that account f
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TABLE 4.2.3. Selected Radionuclide
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4.16 TABLE 4.2.5. Selected Radionuc
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4.18 ENCAPSULATION SPENT FUEL WATER
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4.20 Combustible wastes produced du
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4.22 methods described in Chapter 6
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4.24 1) vitrification by in-can mel
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4.26 Some partitioning options may
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4.28 wells. The 90 Sr leach rate de
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4.30 Another synthetic mineral conc
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4.32 Center has been set up to prov
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4.34 FUEL ASSEMBLY SHEAR RETRIEVE U
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4.36 may be contact-handled. The qu
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4.38 4.3.3.4 Immobilization of Wet
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HEPA FILTER 4.40 CHARCOAL FILTER -
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4.3.4.2 Gaseous Radionuclide Recove
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4.44 treatment options at an FRP an
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4.46 TABLE 4.3.2. Estimated Quantit
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4.48 Harries, B. R. et al. 1979. De
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4.50 U.S. Energy Research and Devel
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4.52 4.4.1.1 Water Basin Storage of
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4.54. The exhaust air is monitored
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4.56 but double-walled tanks have b
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4.58 The storage yard is monitored
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4.60 A similar approach was examine
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REFERENCES FOR SECTION 4.4 4.62 Atl
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4.64 These existing casks were desi
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4.5.3.1 Fuel Residue Transport 4.66
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REFERENCES FOR SECTION 4.5 4.68 Per
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4.70 flanges, and disconnecting ele
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TABLE 4.6.1. Volumes and Radionucli
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TABLE 4.6.3. Radionuclides Released
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4.76 4.7 ENVIRONMENTAL IMPACTS OF P
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4.78 4.7.1.2 Nonradiological Efflue
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4.80 The expected socioeconomic imp
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TABLE 4.7.5. Resource Commitments f
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4.84 (those to which nearly all wor
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4.86 TABLE 4.7.8. Example Reprocess
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4.88 TABLE 4.7.9. Selected Social S
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4.90 4.8 ACCIDENT IMPACTS FOR PREDI
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4.92 Severe accidents resulting fro
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4.94 with a colocated spent fuel pa
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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
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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
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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
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6.107 Shale deposits in the United
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6.109 Waste Preparation Technology.
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6.111 to shallow ground water or to
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6.113 may be conveniently divided i
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6.115 repositories (Section 5.5) an
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6.117 The geologic formation in whi
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6.1.7.1 Concept Summary 6.119 6.1.7
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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
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6.127 TABLE 6.1.21. Annual Routine
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6.129 TABLE 6.1.25. Transportation
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Socioeconomic Impacts 6.131 Socioec
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6.133 Results of a long-term risk c
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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
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° 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
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6.147 (Bechtel 1979a). (See Table 6
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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
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6.157 Bell, W. J. 1971. An Analysis
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6.159 Environmental Protection Agen
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6.161 Lynn, R. D. and Z. E. Arlin.
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6.163 Sandia Laboratories. 1980. Su
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6.165 6.2 COMPARISON OF ALTERNATIVE
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6.167 fuel assemblies would be appr
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6.169 A reprocessing fuel cycle wou
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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
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6.177 6.2.2.7 Long-Term Maintenance
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6.179 deep hole, island mined repos
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6.181 6.2.3.4 The Concept Should be
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Timing 6.183 The timing of implemen
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TABLE 6.2.6. Performance of Propose
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6.187 As discussed in Section 6.2.1
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6.189 design might well be limited
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6.191 6.2.4.4 Conformance with Fede
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6.193 appears not to significantly
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TABLE 6.2.8. Estimated Resource Com
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6.197 space disposal in an intermed
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REFERENCES FOR SECTION 6.2 6.199 Co
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6.2 annual throughput or a common e
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6.4 are identified for well injecti
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6.1.1.1 Concept Summary 6.6 6.1.1 V
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6.8 Recycle Geologic Facilitie UF6
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6.10 The canister would have to pro
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6.12 storage facility (Bechtel 1979
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6.14 Sealing. Standard oil field pr
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6.16 thermomechanical behavior woul
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6.18 Remote determinations of water
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6.20 TABLE 6.1.2. VDH Concept - Occ
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6.22 available at this time. Parame
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Potential Events 6.24 TABLE 6.1.6.
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6.26 TABLE 6.1.7. Long-Term Radiolo
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Waste-Type Compatibility 6.30 It is
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6.32 Predisposal Treatment of the W
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6.34 be: (1) the pipe and valve man
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6.36 The heat effects in the periph
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6.38 the necessary leaktightness of
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6.40 Data Base Development. Develop
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6.42 Radiological Impacts. During p
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6.44 1979a). In addition, with colo
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6.46 would be stored as a liquid, i
Page 603 and 604:
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Reactors 6.50 -|LWR| Waste Sources
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6.52 Precipitation Surface Faciliti
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6.54 6.1.3.3 Status of Technical De
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6.56 Moreover, although transportat
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6.58 International and Domestic Leg
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Sea Water Dilution 6.60 Discharge I
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Page 619 and 620:
Reactors 6.64 Waste Sources IF L W
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6.66 The ocean's benthic boundary l
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6.68 The total seabed area required
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6.70 Ion Transport in the Sediment.
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6.72 The SDP program plan has been
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6.74 TABLE 6.1.12. Estimated Dose C
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6.76 TABLE 6.1.13. Estimated Energy
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6.78 food chains and ultimate consu
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6.80 processed and disposed of, and
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Page 639 and 640:
6.84 Because the options for the wa
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Reprocessing Plant 6.86 Shielded Ce
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6.88 ,An important factor in this c
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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 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 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: 102 CONSEQUENCE ANALYSIS in additio
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 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 1309 and 1310: 14,6 WASTE MANAGEMENT OPERATIONS To
Page 1311 and 1312: Response 148 -WASTE MANAGEMENT OPER
Page 1315 and 1316: Draft p. 3.1.90 Issue 152 WASTE MAN
Page 1317 and 1318:
Response 1.54 WASTE MANAGEMENT OPER
Page 1319 and 1320:
156 WASTE MANAGEMENT OPERATIONS AFR
Page 1321 and 1322:
Draft p. 3.1.85 Issue 158 WASTE MAN
Page 1323 and 1324:
Response 160 WASTE MANAGEMENT OPERA
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
Page 1399 and 1400:
Page 1401 and 1402:
Draft pp. 3.1.24, 33 and 235 Issue
Page 1403 and 1404:
Page 1405 and 1406:
242 GEOLOGIC CONSIDERATIONS selecti
Page 1407 and 1408:
244 GEOLOGIC CONSIDERATIONS The Tek
Page 1409 and 1410:
Response The text was changed. Draf
Page 1411 and 1412:
Page 1413 and 1414:
Page 1415 and 1416:
252 GEOLOGIC CONSIDERATIONS made. T
Page 1417 and 1418:
Page 1419 and 1420:
256 GEOLOGIC CONSIDERATIONS effects
Page 1421 and 1422:
Page 1423 and 1424:
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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Page 1441 and 1442:
Page 1443 and 1444:
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
Page 1459 and 1460:
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
Page 1467 and 1468:
304 COMPARATIVE ASSESSMENT Draft p.
Page 1469 and 1470:
Response 306 COMPARATIVE ASSESSMENT
Page 1471 and 1472:
Draft p. 4.9 Issue 308 COMPARATIVE
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Page 1475 and 1476:
Page 1477 and 1478:
314 ALTERNATIVE DISPOSAL CONCEPTS g
Page 1479 and 1480:
316 ALTERNATIVE DISPOSAL CONCEPTS h
Page 1481 and 1482:
Response 318 ALTERNATIVE DISPOSAL C
Page 1483 and 1484:
Draft Appendix P Issue 320 ALTERNAT
Page 1485 and 1486:
Draft p. 1.25 Issue 322 ALTERNATIVE
Page 1487 and 1488:
Draft p. 3.3.7 Issue 324 ALTERNATIV
Page 1489 and 1490:
Draft p. 3.3.30 Issue 326 ALTERNATI
Page 1491 and 1492:
Page 1493 and 1494:
Response 330. ALTERNATIVE DISPOSAL
Page 1495 and 1496:
332 ALTERNATIVE DISPOSAL CONCEPTS A
Page 1497 and 1498:
334 ALTERNATIVE DISPOSAL CONCEPTS D
Page 1499 and 1500:
Draft p. 3.4.13 Issue Response 336
Page 1501 and 1502:
Issue 338 ALTERNATIVE DISPOSAL CONC
Page 1503 and 1504:
Draft Section 3.5 Issue 340 ALTERNA
Page 1505 and 1506:
Page 1507 and 1508:
Page 1509 and 1510:
346 ALTERNATIVE DISPOSAL CONCEPTS o
Page 1511 and 1512:
348 ALTERNATIVE DISPOSAL CONCEPTS S
Page 1513 and 1514:
Page 1515 and 1516:
Draft p. 1.27 Issue 352 ALTERNATIVE
Page 1517 and 1518:
354 ALTERNATIVE DISPOSAL CONCEPTS W
Page 1519 and 1520:
356 ALTERNATIVE DISPOSAL CONCEPTS e
Page 1521 and 1522:
Response Jbb ALTERNATIVE DISPOSAL C
Page 1523 and 1524:
Page 1525 and 1526:
Page 1527 and 1528:
Page 1529 and 1530:
Page 1531 and 1532:
368 ALTERNATIVE DISPOSAL CONCEPTS T
Page 1533 and 1534:
Draft p. 3.6.18 Issue Response 37U
Page 1535 and 1536:
Page 1537 and 1538:
Page 1539 and 1540:
Page 1541 and 1542:
Draft Section 3.7 Issue 378 ALTERNA
Page 1543 and 1544:
Page 1545 and 1546:
Page 1547 and 1548:
Page 1549 and 1550:
386 ALTERNATIVE DISPOSAL CONCEPTS W
Page 1551 and 1552:
Page 1553 and 1554:
Page 1555 and 1556:
Page 1557 and 1558:
Page 1559 and 1560:
Page 1561 and 1562:
398 ALTERNATIVE DISPOSAL CONCEPTS T
Page 1563 and 1564:
400 ALTERNATIVE DISPOSAL CONCEPTS E
Page 1565 and 1566:
Draft p. 3.10.18 Issue 402 ALTERNAT
Page 1567 and 1568:
Draft p. 3.10.27 Issue 404 ALTERNAT
Page 1569 and 1570:
Page 1571 and 1572:
408 HEARING BOARD REPORT AND RESPON
Page 1573 and 1574:
410 Safeguards of the Nuclear Regul
Page 1575 and 1576:
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
Page 1603 and 1604:
440 Interagency Review Group. 1978.
Page 1605 and 1606:
U.S. Nuclear Regulatory Commission.
Page 1607 and 1608:
A.1 APPENDIX A LIST OF RESPONDENTS
Page 1609 and 1610:
A.3 COMMENTER DATE RECEIVED 12. Ms.
Page 1611 and 1612:
A.5 COMMENTER DATE RECEIVED 34. Mr.
Page 1613 and 1614:
A.7 COMMENTER DATE RECEIVED 54. Edw
Page 1615 and 1616:
A.9 COMMENTER DATE RECEIVED 79. Wal
Page 1617 and 1618:
A.11 . COMMENTER- . .... . .... DAT
Page 1619 and 1620:
A. 13 COMMENTER DATE RECEIVED 132.
Page 1621 and 1622:
A.15 COMMENTER DATE RECEIVED 157. F
Page 1623 and 1624:
A.17 COMMENTER DATE RECEIVED 183. R
Page 1625 and 1626:
A.19 COMMENTER DATE RECEIVED 208. J
Page 1627 and 1628:
A.21 COMMENTER DATE RECEIVED LETTER
Page 1629 and 1630:
Page 1631 and 1632:
Page 1633 and 1634:
Page 1635 and 1636:
Page 1637 and 1638:
Page 1639 and 1640:
Page 1641 and 1642:
Page 1643 and 1644:
North Carolina: A.37 COMMENTER DATE
Page 1645 and 1646:
APPENDIX B INDEX FOR COMMENT LETTER
Page 1647 and 1648:
B.2 Letter Topic Area Pages 1 Costs
Page 1649 and 1650:
B.4 Letter Topic Area Pages 30 (Con
Page 1651 and 1652:
B.6 Letter Topic Area Pages 57 Gene
Page 1653 and 1654:
B.8 Letter Topic Area Pages 102 Gen
Page 1655 and 1656:
B.10 Letter Topic Area Pages 133 Wa
Page 1657 and 1658:
B.12 Letter Topic Area Pages 160 Ge
Page 1659 and 1660:
B.14 Letter Topic Area Pages. 198 W
Page 1661 and 1662:
8.16 Letter Topic Area Pages 215 Wa
Page 1663 and 1664:
C.1 APPENDIX C STATE AND FEDERAL AG
Page 1665 and 1666:
State Of Idaho /' .DIVISION OF BUDG
Page 1667 and 1668:
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
Page 1675 and 1676:
(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
Page 1681 and 1682:
,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
Page 1691 and 1692:
10 22. (Page 3.1.6, sixth paragraph
Page 1693 and 1694:
14 15 43. (Page 3.1.40, physical pr
Page 1695 and 1696:
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
Page 1701 and 1702:
30 The consequence analysis as it b
Page 1703 and 1704:
34 United States Department of the
Page 1705 and 1706:
-4- -5- -4- An important criterion
Page 1707 and 1708:
-8- -9- Modeling of Groundwater Mod
Page 1709 and 1710:
-12- -13- Reasonable bounds for the
Page 1711 and 1712:
3 Page 3.1.30. Third paragraph, fir
Page 1713 and 1714:
7 8 also include at least generaliz
Page 1715 and 1716:
11- 12 Page 3.1.6, par. 3, line 2:
Page 1717 and 1718:
15 shaft and borehole sealing; larg
Page 1719 and 1720:
1.9 20 Page 3.1.106. par. 3: What w
Page 1721 and 1722:
UNITED STATES NUCLEAR REGULATORY CO
Page 1723 and 1724:
INDEX TO GEIS COMMENTS 1. GENERAL..
Page 1725 and 1726:
1-3 Comment Number Comment 1-4 .5 T
Page 1727 and 1728:
1-7 Comment Comment Number Number ,
Page 1729 and 1730:
2-1 2-2 Comment Comment Number Numb
Page 1731 and 1732:
Comment Number 2-5 d. Transportatio
Page 1733 and 1734:
2-9 2-10 Comment Comment Number Num
Page 1735 and 1736:
C ~, "0 '0 , ' 0omment C Numb1 0 .3
Page 1737 and 1738:
Comment Number 2-17 Comment Number
Page 1739 and 1740:
3-1 3-2 Comment Number Comment Numb
Page 1741 and 1742:
3-5 3-6 Comment Number Comment Numb
Page 1743 and 1744:
Comment Number 3-9 Comment Number i
Page 1745 and 1746:
3-13 Comment Comment Number Number
Page 1747 and 1748:
Comment Number 3-17 3-18 Comment Nu
Page 1749 and 1750:
3-21 3-22 Comment Comment Number Nu
Page 1751 and 1752:
3-25 Comment Number Comment Number
Page 1753 and 1754:
3-29 3-30 Comment .. Comment "'umbe
Page 1755 and 1756:
3-33 Comment Comment Number ,lumber
Page 1757 and 1758:
3-37 3-38 Comment Number Comment Nu
Page 1759 and 1760:
3-41 3-42 Comment Comment Number Nu
Page 1761 and 1762:
Comment Number 4-3 Comment Number I
Page 1763 and 1764:
4-7 4-8 Comment Comment Number Numb
Page 1765 and 1766:
Comnent ,iumoer 4-11 Comment Number
Page 1767 and 1768:
5-2 Comment lNumber Comment 5-3 5-3
Page 1769 and 1770:
Dr. Cblin A. Heath nivision of Wast
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