Table A-20
LLNL Livermore Site
Low-Level Radioactive Waste Generation
for the Selected Facilities1990 Data
a
| Building Number | Contaminated Materialb | Contaminant | ||
| Pounds | Gallons | Radionuclide | Curies | |
| 121 | 6 | Co-60 | 1.00 × 10-9 | |
| 2 | Po-210 | 1.00 × 10-6 | ||
| 131 | 138 | < 1 | U-238
U-238 |
1.00 × 10-8 1.00 × 10-8 |
| 141 | 3 | H-3 | 1.00 × 10-3 | |
| 151 | 106 | 5 | Am-241
Am-241 |
3.04 × 10-7 2.20 × 10-8 |
| 10 | 177 | Ba-140 Ba-140 |
1.00 × 10-6 9.24 × 10-3 | |
| 37 | 20 | Ce-141
Ce-141 |
2.00 × 10-8 2.78 × 10-5 | |
| < 1 | Cf-250 | 5.10 × 10-7 | ||
| 118 | Cs-137 | 1.50 × 10-5 | ||
| 160 | Eu-152 | 7.00 × 10-7 | ||
| 956 | 14 | H-3
H-3 |
1.00 × 10-3 3.28 × 10-3 | |
| 115 | I-131 | 8.02 × 10-4 | ||
| 3,018 | 535 | MFP
MFP |
9.39 × 10-1
2.00 × 10-1 | |
| < 1 | Nb-95 | 5.01 × 10-3 | ||
| 5 | Pu-238 | 8.60 × 10-7 | ||
| 21 | Ra-226 | 3.95 × 10-4 | ||
| 1 | Rb-83 | 1.00 × 10-4 | ||
| 2900d | Ru-105 | 5.59 × 10-5 | ||
| 1 | Th-230 | 1.00 × 10-6 | ||
| < 1 | Th-232 | 4.58 × 10-6 | ||
| 7 | 1 | U-238
U-238 |
8.63 × 10-5 4.30 × 10-5 | |
| 1 | Y-88 | 1.00 × 10-7 | ||
| 161 | 110 | U-238 | 5.00 × 10-6 | |
| 169 | 600 | U-238 | 1.33 × 10-5 | |
| 175 | 785 | Am-241 | 1.40 × 10-5 | |
| 1,800 | Cs-137 | 1.00 × 10-2 | ||
| 4,000 | MFPc | 4.00 × 10-2 | ||
| 5 | U-235 | 1.07 × 10-5 | ||
| 14,010 | 123 | U-238
U-238 |
4.54 × 10-2
5.00 × 10-3 | |
| 177 | 370 | U-235 | 2.15 × 10-5 | |
| 4,852 | 15 | U-238 U-238 |
5.46 × 10-2
2.35 × 10-5 | |
| 179 | 5 | 3 | U-238
U-238 |
2.66 × 10-8
3.33 × 10-9 |
| 212 | 2,000 | Ce-144 | 1.00 × 10-12 | |
| 700 | Co-60 | 1.00 × 10-9 | ||
| 222 | 8 | H-3 | 3.10 × 10-1 | |
| 2 | Ni-63 | 1.00 × 10-7 | ||
| 281 | Th-232 | 5.69 × 10-5 | ||
| < 1 | U-234 | 1.80 × 10-5 | ||
| 5 | U-235 | 2.72 × 10-5 | ||
| 359 | 13 | U-238
U-238 |
2.00 × 10-4
1.89 × 10-5 | |
| 226 | < 1 | U-235 | 4.28 × 10-6 | |
| 725 | U-238 | 7.10 × 10-6 | ||
| 227 | 2 | 10 | U-238
U-238 |
1.00 × 10-6 3.33 × 10-9 |
| 231 | 2 | Ba-133 | 3.00 × 10-6 | |
| < 1 | P-32 | 1.00 × 10-3 | ||
| 2 | Pu-239 | 4.00 × 10-6 | ||
| < 1 | U-235 | 8.56 × 10-6 | ||
| 960 | < 1 | U-238
U-238 |
8.75 × 10-6
3.33 × 10-7 | |
| 232 | 3 | U-238 | 3.33 × 10-7 | |
| 235 | 20 | < 1 | Th-232
Th-232 |
5.45 × 10-9 1.09 × 10-8 |
| 550 | 6705 | U-238
U-238 |
3.28 × 10-5
7.11 × 10-2 | |
| 241 | 3 | Co-57 | 8.00 × 10-3 | |
| 112 | Co-60 | 2.26 × 103 | ||
| 12 | Cs-134 | 1.00 × 10-3 | ||
| 5 | H-3 | 2.00 × 10-5 | ||
| < 1 | Nb-95 | 3.00 × 10-3 | ||
| 18 | Tc-99 | 1.36 × 10-2 | ||
| 3 | Th-232 | 1.09 × 10-8 | ||
| 3,184 | 165 | U-234
U-234 |
2.29 × 10-1
3.00 × 10-6 | |
| 80 | U-235 | 2.14 × 10-8 | ||
| 764 | 20 | U-238
U-238 |
9.99 × 10-3
1.42 × 10-6 | |
| 251 | 6,501 | 3305 | Am-241
Am-241 |
1.14 × 10-3
7.73 × 10-5 |
| 100 | Am-242m | 2.50 × 10-4 | ||
| 65 | Am-243 | 1.00 × 10-7 | ||
| 1 | 56 | Cf-250
Cf-250 |
1.00 × 10-9
1.00 × 10-5 | |
| 10 | Cm-244 | 2.00 × 10-9 | ||
| 10 | Cm-246 | 1.00 × 10-5 | ||
| 130 | Pu-238 | 2.10 × 10-6 | ||
| 600 | Pu-239 | 4.80 × 10-11 | ||
| 3 | U-235 | 4.26 × 10-7 | ||
| 255 | 1 | U-238 | 4.70 × 10-5 | |
| 292 | 2,700 | Co-60 | 2.00 × 10-6 | |
| 2,900 | H-3 | 2.20 × 10-2 | ||
| 298 | 624 | H-3 | 3.84 × 10-3 | |
| < 1 | Th-232 | 6.00 × 10-3 | ||
| 120 | U-238 | 2.41 × 10-3 | ||
| 321 | 153 | 130 | U-238
U-238 |
5.00 × 10-6
1.60 × 10-2 |
| 321A | 3 | Po-210 | 1.90 × 10-7 | |
| 321C | 2,000 | C-14 | 1.00 × 10-4 | |
| 10 | Th-232 | 6.70 × 10-5 | ||
| 9,371 | 378 | U-238
U-238 |
3.10 × 10-2
2.66 × 10-6 | |
| 322 | 150 | Pu-239 | 6.13 × 10-5 | |
| 331 | < 1 | H-3 | 7.90 × 10-1 | |
| 18,796 | 36 | H-3
H-3 |
5.64 × 10-2
4.06 × 10-1 | |
| 2,342 | U-238 | 2.40 × 10-6 | ||
| 332 | 4 | Ba-133 | 1.00 × 10-3 | |
| 1,500 | H-3 | 2.10 × 10-8 | ||
| 1,500 | MFP | 3.60 × 10-5 | ||
| 57,156 | 5 | Pu-239 Pu-239 |
7.01 × 10-3
8.28 × 10-4 | |
| 3,000 | U-238 | 1.47 × 10-5 | ||
| 332B | 150 | Pu-238 | 1.00 × 10-8 | |
| 8,430 | Pu-239 | 2.04 × 10-3 | ||
| 341e | 30 | Ir-192 | 3.00 × 10-7 | |
| 25 | MFP | 1.00 × 10-3 | ||
| 527 | 5 | U-238
U-238 |
3.34 × 10-4
3.33 × 10-7 | |
| 343 | 3 | Ni-63 | 1.00 × 10-8 | |
| 361 | 338 | 13 | C-14
C-14 |
3.75 × 10-3
2.00 × 10-1 |
| 3 | Co-60 | 1.81 × 10-8 | ||
| 296 | 66 | H-3
H-3 |
2.05 × 10-2 4.63 × 10-2 | |
| 1 | Ni-63 | 2.00 × 10-4 | ||
| 1,526 | P-32 | 9.71 × 10-2 | ||
| 2 | 300 | P-32
P-32 |
2.50 × 10-4
3.01 × 10-2 | |
| 1 | Pu-239 | 1.00 × 10-8 | ||
| 305 | S-35 | 5.14 × 10-3 | ||
| 31 | U-238 | 2.52 × 10-4 | ||
| 362 | 10 | C-14 | 2.50 × 10-8 | |
| 363 | 35 | C-14 | 3.10 × 10-6 | |
| 15 | P-32 | 2.00 × 10-3 | ||
| 364 | 2,000 | Co-60 | 3.40 × 10-1 | |
| 365 | 195 | 35 | C-14
C-14 |
1.66 × 10-5
4.00 × 10-4 |
| 30 | S-35 | 2.00 × 10-6 | ||
| 366 | 14 | C-14 | 1.02 × 10-4 | |
| 2 | 5 | S-35
S-35 |
1.00 × 10-5
4.00 × 10-5 | |
| 391 | 90 | H-3 | 4.40 × 10-4 | |
| 412 | 5 | C-14 | 1.00 × 10-4 | |
| 950 | Eu-152 | 5.80 × 10-2 | ||
| 45 | Ra-226 | 8.00 × 10-8 | ||
| 310 | Sr-90 | 4.00 × 10-6 | ||
| 2 | U-238 | 6.66 × 10-7 | ||
| 419 | 55 | Co-57 | 5.80 × 10-9 | |
| 30 | Co-60 | 3.10 × 10-9 | ||
| 11,430 | 189 | U-238 U-238 |
1.75 × 10-3
1.39 × 10-6 | |
| 490 | 1,153 | 150 | U-238
U-238 |
8.93 × 10-2
4.25 × 10-4 |
| 491 | 321 | U-238 | 2.81 × 10z | |
| 493 | 1 | U-238 | 1.80 × 10-6 | |
b Quantities shown in pounds include the total of the contaminated material, the contaminant, and, if appropriate, the waste container. Consistent with the definition of radioactive waste, quantities of radionuclide contaminants are determined to be too small to be economically recoverable.
c Mixed Fission Products.
d Liquid in retention tanks before treatment by Hazardous Waste Management.
e Experiments producing these low-level wastes occur infrequently with an average time between them of 2–3 years.
Table A-21
LLNL Site 300 Low-Level
Radioactive Waste Generation
for the Selected Facilities1990 Dataa,b
| Building Number | Contaminated Material | Contaminant | ||
| Pounds | Gallons | Radionuclide | Curies | |
| 801, 850, 851 | 140,000 kg (× 2.2 lb/kg » 300,000 lb) | |||
a The low-level radioactive waste generation data is based on
quantities received by Waste Management from January 1, 1990 through December
31, 1990. The data presented in this table is for the selected facilities
described in Appendix A.
b The waste management facilities, where waste is repackaged
and consolidated, are not shown in this table.
Table A-22
SNL, Livermore Low-Level
Radioactive Waste Generation
for the Selected Facilities 1990 Dataa
b
| Building Number | Contaminated Material | Contaminant | ||
| Pounds | Gallons | Radionuclide | Curies | |
| 906 | 4 | 0 | depleted uranium | 1×10-3 |
| 913 | 291 | 0 | depleted uranium | 1.679×10-4 |
| 916 | 81 | 0 | depleted uranium | 8.53×10-5 |
| 961 | 338 | 0 | depleted uranium | 1.1×10-3 |
| 966 | 10 | 0 | depleted uranium | 1.8×10-6 |
| 968b | 7580 | 0 | tritium | 15,853 |
| 973 | 5 | 0 | depleted uranium | 1×10-6 |
| 979 | 205 | 0 | depleted uranium | 2.27×10-3 |
| 983 | 10 | 0 | depleted uranium | 0.10 |
b During 1990, approximately 7400 gals of water contaminated with 22.7 Ci of tritium was evaporated at the Tritium Research Laboratory.
Table A-23
LLNL Livermore Site
Radioactive Materials Inventory for the Selected Facilities 1991 Dataa,o
| Building Number | Radionuclide | Form | Quantityb (curies) | Status |
| 121 | Cd-109 | Solid | 0.01 | Sealed source |
| Cm-244 | Solid | 2.00×10-3 | Sealed source | |
| Fe-55 | Solid | 2.50×10-2 | Sealed source | |
| 131 | Am-241 | Solid | 0.49 | Sealed source |
| Cd-109 | Solid | 0.04 | Sealed source | |
| H-3 | 2.00 | Sealed assemblies | ||
| Po-210 | Solid | 2.40×10-2 | Sealed source | |
| Th | Solid | 0.06 | In vault | |
| U (depleted) | Solid | 0.60 | In vault | |
| 141 | Po-210 | Solid | 2.40×10-2 | Sealed source |
| 151x | Am-241 | Solid | 0.08 | Sealed source |
| Cd-109 | Solid | 2.40×10-2 | Sealed source | |
| Cs-137 | Liquid | 0.01 | In process | |
| MFPc | Solid/gas/ liquid | 1.50 | In process | |
| 175/177 | U (natural) | Oxide | 4.20×10-2 | Storage |
| U (depleted) | Oxide | 1.80×10-3 | Storage | |
| U (enriched, 1.4%) | Solid | 1.10×10-2 | Storage | |
| U (enriched, 93%) | Solid | 1.20×10-3 | Storage | |
| U (natural) | Solid | 1.20 | Storage | |
| U (depleted) | Solid | 0.34 | Storage | |
| 190 | Am-241 | Solid | 1.11x10-5 | Sealed source |
| Co-60 | Solid | 1.43x10-4 | Sealed source | |
| H-3 | Tritiated titanium targets | < 20.00 | (Future) | |
| Pu-238 | Solid | 2.73x10-2 | Sealed source | |
| Pu-239 | Solid | 1.50 | Sealed source | |
| 191 | U (depleted) | Solid | 8.00×10-3 | (Future) |
| 194 | Am-241 | Solid | 1.24x10-5 | Sealed source |
| Cf-252 | Solid | 0.01 | Sealed source | |
| Cm-244 | Solid | 1.08x10-6 | Sealed source | |
| Co-60 | Solid | 0.20 | Sealed source | |
| Na-22 | Solid | 0.06 | Sealed source | |
| Pu-238 | Solid | 0.03 | Sealed source | |
| Pu-239 | Solid | 1.50 | Sealed source | |
| Sr-90 | Solid | 0.01 | Sealed source | |
| 212 | Am-241 | Solid | 1.20x10-2 | Sealed source |
| Ba-133 | Solid | 9.00x10-4 | Sealed source | |
| Cm | Solid | 1.50x10-2 | Sealed source | |
| Cm-244 | Solid | 3.70x10-3 | Sealed source | |
| Fe-55 | Solid | 2.00x10-4 | Sealed source | |
| 222 | Cd-109 | Solid | 5.00×10-3 | Sealed source |
| H-3 | Solid | 0.95 | Sealed source | |
| Ni-63 | Solid | 4.00 | Sealed source | |
| Th | Solid | 2.40x10-4 | 90% storage, 10% in process | |
| ThO2 | Solid | 7.00x10-4 | 90% storage, 10% in process | |
| U (natural) | Solid | 2.10x10-4 | 90% storage, 10% in process | |
| U (depleted) | Solid | 1.30×10-3 | 90% storage, 10% in process | |
| UD2 | Solid | 6.50×10-3 | 90% storage, 10% in process | |
| Tc-99 | Solid | 0.40 | Storage | |
| 227 | U (depleted) | Solid | 3.50x10-4 | 90% storage, 10% in process |
| 231 | Am-241 | Solid | 31.00 | Sealed source/storage |
| Co-60 | Solid | 286.00 | Sealed source/storage | |
| Cs-137 | Solid | 4.90 | Sealed source/storage | |
| H-3 | Gas/solid | 203.00 | Sealed source/storage | |
| Kr-85 | Gas | 0.55 | Sealed source/storage | |
| Ni-63 | Solid | 1.40×10-2 | Sealed source/storage | |
| Pm-147 | Solid | 17.10 | Sealed source/storage | |
| Pu-238 | Solid | 10.50 | Sealed source/storage | |
| Pu-239 | Solid | 36.90 | Sealed source/storage | |
| U (natural) | Solid | 1.30×10-2 | Storage | |
| U (depleted) | Solid | 2.10 | Storage | |
| U-235d | Solid | <1,200 kgd (<0.5 Ci) | Storage | |
| 233 | Th-232 | Solid | 0.47 | In vault |
| U (depleted) | Solid | 0.47 | In vault | |
| 235 | Th-232 | Solid | 3.00 kg | Storage |
| U (depleted) | Solid | 0.83 | Storage | |
| 239p | Am-241 | Solid | 29.20 | Sealed source |
| Co-60 | Solid | 1319.00 | Sealed source | |
| Kr-85 | Solid | 4.08x10-3 | Sealed source | |
| Ir-192 | Solid | <0.50 | Sealed source | |
| 241 | Po-210 | Solid | 3.00×10-3 | Sealed source |
| Tc-99 | Solid | 0.34 | In vault | |
| ThO2 | Rods | 2.20x10-4 | In vault | |
| U (depleted) | Metal | 2.20x10-5 | In process | |
| UD (depleted) | Solid | 1.70×10-3 | In vault | |
| UH (depleted) | Solid | 1.50×10-2 | In vault | |
| UO2 (depleted) | Solid | 8.80x10-5 | In vault | |
| U (depleted) | Metal | 3.10×10-2 | In vault | |
| 251y | Am-241 | Solid | 700.00 | Storage |
| Cm-244 | Solid | 2,000.00 | Storage | |
| Misc.f | Solid | 5.00 | Research | |
| Pu-238 | Solid | 4,600.00 | Storage | |
| Pu-239 | Solid | 10.00 | Storage | |
| U-232 | Solid | 35.00 | Storage | |
| U-233 | Solid | 4.00 | Storage | |
| Cm-244 | Oxide | 400.00 | In process | |
| Am-241 | Oxide | 200.00 | In process | |
| 255Wq | Cd-109 | Solid | 2.00×10-3 | Sealed source |
| Dy-159 | Solid | 0.05 | Sealed source | |
| Fe-55 | Solid | 3.50×10-2 | Storage | |
| H-3 | Solid/gas | 160.00 | Sealed source | |
| Pm-147 | Solid | 3.50 | Sealed source | |
| 255Eq | Am-241 | Solid | 13.00 | Sealed source |
| Cf-252 | Solid | 0.30 | Sealed source | |
| Co-57 | Solid | 6.00×10-3 | Sealed source | |
| Co-60 | Solid | 6800.00 | Sealed source | |
| Cs-137 | Solid | 414.90 | Sealed source | |
| H-3 | Gas | 0.05 | Bottled gas | |
| Kr-85 | Gas | 0.05 | Sealed source | |
| Pu-238 | Solid | 80.00 | Sealed source | |
| Sr-90 | Solid | 0.05 | Sealed source | |
| 292 | Am-241 | Solid | 1.62x10-5 | Sealed source |
| Co-60 | Solid | 7.75x10-5 | Sealed source | |
| Bi-207 | Solid | 9.54x10-5 | Sealed source | |
| 298 | H-3 | Gas | 5.00 mgh | In process |
| H-3 | Gas/Liq/Solid | 5.00 gi | (Future) | |
| U-238 (D-38) | Solid | 0.10 | In process | |
| 321r | U (depleted) | Solid | 0.14 | In vault |
| 327p | Am-241 | Solid | 14.60 | Sealed source |
| Cd-109 | Solid | 0.03 | Sealed source | |
| Cs-137 | Solid | 3.0×10-3 | Sealed source | |
| Pm-147 | Solid | 5.40×10-2 | Sealed source | |
| Ir-192 | Solid | 7.50 | Sealed source | |
| 331j | H-3 | Gas | 50,000.00 | Storage |
| H-3 | Gas | 20,000.00 | In process | |
| 332k,s | Plutoniumk | Solid | 700.00 kgk | Storage/In use |
| Uranium (Natural and Depleted) | Solid | 300.00 kgw | Storage/In use | |
| 334k | Am-241 | Solid | 1.21x10-5 | Amersham Kit #2023 |
| Ba-133 | Solid | 1.06x10-5 | Amersham Kit #2023 | |
| Cd-109 | Solid | 1.00x10-6 | Sealed source | |
| Cf-252 | Solid | 2.40x10-3 | Sealed source | |
| Co-57 | Solid | 1.19x10-5 | Amersham Kit #2023 | |
| Co-60 | Solid | 1.20x10-5 | Amersham Kit #2023 | |
| Cs-137 | Solid | 1.50×10-2 | Sealed source | |
| H-3 | Gas | 2.00 | Sealed source | |
| Mn-54 | Solid | 1.08x10-5 | Amersham Kit #2023 | |
| Na-22 | Solid | 1.14x10-5 | Amersham Kit #2023 | |
| Ra-226 | Solid | 5.00×10-3 | Sealed source | |
| Th (natural) | Solid | 0.06 | Test configuration | |
| Th-228 | Solid | 8.00 x 10-7 | Amersham Kit #2023 | |
| U-235 | Solid | 0.36 | Test configuration | |
| U-238 (D-38) | Solid | 0.18 | Test configuration | |
| Y-88 | Solid | 1.13x10-5 | Amersham Kit #2023 | |
| Am-241 Be | Solid | 3.00×10-3 | Sealed source | |
| Co-60 | Solid | 5.00×10-3 | Sealed source | |
| Cs-137 | Solid | 1.15x10-5 | Amersham Kit #2023 | |
| Am-241 | Solid | 4.00×10-3 | Sealed source | |
| Am-241 | Solid | 4.06x10-5 | Amersham Kit | |
| Ba-133 | Solid | 1.21x10-5 | Amersham Kit | |
| Co-57 | Solid | 1.21x10-5 | Amersham Kit | |
| Co-60 | Solid | 1.17x10-5 | Amersham Kit | |
| Cs-137 | Solid | 1.17x10-5 | Amersham Kit | |
| Mn-54 | Solid | 1.17x10-5 | Amersham Kit | |
| Na-22 | Solid | 1.06x10-5 | Amersham Kit | |
| Y-88 | Solid | 1.25x10-5 | Amersham Kit | |
| 341l | U (depleted) | Solid | 4.00×10-3 | Metal |
| 362t | Ni-63 | Solid | 1.40×10-2 | Sealed source |
| 364 | Cs-137 | Solid | 4,220.00 | Sealed source |
| 391m | H-3 | Gas | 0.01 (5 mgh) | In process |
| H-3 | Gas/Liq/Solid | 5.00 gi | (Future) | |
| 412u | Am-241 | Solid | 1.43×10-1 | Sealed source |
| Co-57 | Solid | 7.80×10-3 | Sealed source | |
| 419 | Am-241 | Solid | 1.60 | Waste |
| Pu-239 | Solid | 2.00 | Waste | |
| 493v | U (natural) | Oxide | 2.20×10-2 | Storage |
| U (depleted) | Solid | 12.00 | Storage | |
| U (enriched, <2%) | Oxide | 0.07 | Storage | |
| U (depleted) | Oxide | 9.20×10-2 | Storage | |
| U (natural) | Solid | 4.00 | Storage | |
| Uranium | Solid/Oxide | <80,000 kgn | Present/future | |
| 514 | Cs-137 | Solid | 1.00 | Waste |
| H-3 | Solid | 10.00 | Waste | |
| Pu-239 | Solid | 3.00×10-3 | Waste | |
| U-235 | Solid | 2.00×10-3 | Waste | |
| U-238 (D-38) | Solid | 8.00 | Waste | |
| 612 | Co-60 | Solid | 10.00 | Waste |
| H-3 | Solid | 1.00x105 | Waste | |
| Pu-239 | Solid | 80.00 | Waste |
a The radioactive materials inventories for the selected facilities were obtained from LLNL in July 1991. These inventories were further modified by Laboratory input to reflect October 1991 quantities. Therefore, some radioactive materials listed in building description may not be present in the facility in October 1991 and hence do not appear in this table. This table shows typical quantities rather than maximum limits. These radioactive materials are subject to change as laboratory experimental requirement change. Buildings where typical or actual quantities are classified, maximum quantities or administrative limits are listed.
b In curies unless otherwise noted.
c MFP: Mixed Fission Products—These nuclides arrive in Building 151 a few times a year and decay with an average half-life of about one week, so that the curies content quickly decreases.
d Enriched uranium (0.7% > U-235 < 5%) stored in Building 231 for both present and future activities.
f Typical research nuclides include Ac-227, U-234, Np-237, Pu-240, Pu-242, Am-242m, Am-243, Cm-243, Cm-246, Cm-248, Bk-249, Cf-249, Cf-250, Cf-252, Es-254, and Fm-257.
g All isotopes of plutonium plus uranium-233.
hThe current administrative limit between Buildings 298 and 391 is 5 mg.
i Under the Proposed Action (see Section 3.1 for description), the future administrative limit between Buildings 298 and 391 will be 5 g.
j Building 331 tritium (H-3) limit prior to 1992 was 300 g. Actual inventory as of September 1991 was 17 g. Tritium limit for proposed projects will be 5 g (no more than 10 g between Buildings 331, 298, and 391).
k The administrative limit for plutonium between Buildings 332 and 334 is 700 kg. LLNL is currently reducing the plutonium administrative limit for the combined Buildings 332 and 334 from 700 kg to 200 kg, with the inventory (actual inventory quantities are classified) being reduced accordingly. The reduction will be accomplished by shipping inventory to offsite DOE facilities and is targeted for completion during fiscal year 1993.
l Experiments in Building 341 using depleted uranium occur infrequently with an average time between them of 2–3 years. Buildings 341 and 343 may contain large quantities of depleted uranium in metal form for use in a number of commercial applications other than fuel for nuclear reactors. See Appendix A, Sections A.1.4.27 and A.1.4.28 for descriptions. Building 343 may contain sealed radioactive sources, natural thorium and natural uranium, and other non-fissile radioactive materials.
mBuilding 391 may contain thorium and deuterium.
n Building 493 uranium (natural and depleted) administrative limit is 80,000 kg (actual inventories may be classified).
o Building 132 opened in Fiscal Year 1992, and will contain sealed radioactive sources similar to Buildings 121 and 255W. Depleted uranium may also be present.
p Buildings 239 and 327 may contain enriched uranium, plutonium and/or uranium-233. See building description for limits.
q Building 255 may contain uranium-235, uranium-233, and plutonium-239. See building description for limits.
r Building 321 may contain thorium.
s Building 332 may contain enriched uranium (oralloy) in the metallurgical processing operations.
t The biomedical buildings (Building 361 through 367) may contain tritium, carbon-14, phosphorus-32, sulfur-35, strontium-85, and iodine-125.
u Building 412 may contain cobalt-60 sources and carbon-14.
v Other separator demonstration facilities (Buildings 490 and 491) may also contain uranium.
w Building 332 Uranium administrative limit is 300 kg (actual inventories may be classified).
x These values represent the maximum quantities in Building 151.
y These values represent the maximum quantities in Building 251, and therefore the administrative limits have been deleted.
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