APPENDIX E ESTIMATION OF HEALTH EFFECTS FOR NORMAL AND ACCIDENT CONDITIONS
TABLE OF CONTENTS
ESTIMATION OF HEALTH EFFECTS FOR NORMAL AND ACCIDENT CONDITIONS E-1
E.1 RECEPTOR CHARACTERISTICS E-1
E.1.1 INDIVIDUAL RECEPTORS E-2
E.1.2 POPULATION RECEPTORS E-3
E.2 AIRBORNE CONCENTRATIONS AT RECEPTORS UNDER NORMAL CONDITIONS E-9
E.2.1 EMISSION RATES OF HAZARDOUS MATERIALS E-9
E.2.2 ATMOSPHERIC DISPERSION FACTORS AND RECEPTOR CONCENTRATIONS E-9
E.3 AIRBORNE CONCENTRATIONS AT RECEPTORS UNDER ACCIDENT CONDITIONS E-12
E.3.1 CONCENTRATIONS OF RADIONUCLIDES AND TOXIC CHEMICALS IN WASTE E-14
E.3.1.1 Radionuclides E-14
E.3.1.2 Toxic Chemicals E-20
E.3.2 AIRBORNE DISPERSION FACTORS AND CONCENTRATIONS AT RECEPTORS E-20
E.4 DOSE AND HEALTH EFFECTS E-22
E.4.1 RADIOLOGICAL HEALTH EFFECTS E-22
E.4.2 TOXIC CHEMICAL HEALTH EFFECTS E-24
APPENDIX E REFERENCES E-29
LIST OF TABLES
E-1 Release Points Used to Determine Distances to Receptor Locations E-2
E-2 Distance to Receptor Locations Along the Existing Boundary E-4
E-3 Distance to Receptor Locations Along the Potential New Boundary E-5
E-4 Atmospheric Dispersion Factors for Accidental Releases From the 200
West Area E-6
E-5 Atmospheric Dispersion Factors for Accidental Releases From the 200
East Area E-7
E-6 Distribution of Off-Site Population Within 80 Kilometers (50 Miles)
of the Hanford Site E-8
E-7 Radionuclide Emissions from the NTF E-10
E-8 Chemical Emissions from the NTF E-11
E-9 Maximum 24-Hour and Annual Ground Level Concentrations for Emissions
from Two DSTs E-13
E-10 Radionuclide Concentrations in SWL E-15
E-11 Radionuclide Concentrations in 102-SY Slurry and West Area Facility
Waste E-16
E-12 Radionuclide Concentrations in Tank 101-SY Slurry E-17
E-13 Radionuclide Concentrations in Bounding Slurry Waste E-18
E-14 Concentrations of Toxic Chemicals in Tank Wastes E-21
E-15 Intake Parameters and Values E-26
E-16 Toxicological Health Effects from NTF Emissions E-27
APPENDIX E ESTIMATION OF HEALTH EFFECTS FOR NORMAL AND ACCIDENT CONDITIONS
This appendix provides information to support the evaluation of human health effects presented in Chapter 5 of this EIS. The characterization of receptor locations for airborne effluents is discussed in Section E.1. Calculation of the concentrations of airborne effluents at these receptors is discussed in Section E.2 for normal conditions and in Section E.3 for accident conditions. Conversion of these airborne concentrations to health effects is discussed in Section E.4.
E.1 RECEPTOR CHARACTERISTICS
The term receptor refers to individuals or populations that could be exposed to radiation, radioactive materials, or toxic chemicals. Population and individual receptors may include involved workers, uninvolved workers, and members of the general public. This section provides the distances from release points of interest to locations occupied by these receptors and describes how receptor populations were determined. Because of the number of alternatives and options within the alternative considered in this EIS, a single release point is sometimes used to represent release points for several nearby facilities. Table E-1 lists the facilities used as release points to determine distances to receptor locations and the additional facilities assumed to be represented by each release point. This combination of release points has no effect on individual worker receptors or off-site population receptors which are assumed to be at fixed distances from the release point, and has a negligible effect on distances to individual off- site receptors where the displacement of release points are a small fraction of the distance to the receptor. As discussed in Section E.1.2, maximally exposed uninvolved worker population receptor locations are selected on the basis of population-weighting of -/Qs. The relative positions of potential release points and occupied structures had no significant effects on the result of combining release points. Individual receptors are discussed in Section E.1.1 and population receptors are discussed in Section E.1.2.
Release Points Used to Determine Distances to Receptor Locations
Release Point Other Facilities Represented
200 West Area
241-SY Tank Farm ITRS, PPSS,
HLW Load/Unload Facility,
DCRT 244-S (Salt Well Receiver Tank)
NTF RCSTS Diversion Box #1
ECSTS Diversion Box 241-UX-251 None
200 East Area
NTF Site "D" RCSTS Diversion Box #2,
ECSTS Diversion Box 241-ER-151
NTF Site "E" None
241-A Tank Farm 244-A Lift Station
(RCSTS Termination Point),
HLW Load/Unload Facility
E.1.1 INDIVIDUAL RECEPTORS
Individual receptors are the maximally exposed involved worker, maximally exposed uninvolved worker, and maximally exposed member of the general public. The maximally exposed involved worker is assumed to be at the center of a 10-meter radius hemisphere. The hemisphere is centered on the release point. Several of the facilities (e.g., the HLW Load/Unload Facility) and some of the equipment [(e.g., the 19,000-L (5,000-gal) tanker trailer truck and 38,000-L (10,000-gal) rail tanker car] considered in this EIS have not yet been designed. In other cases, the locations of workers in the immediate vicinity of a release point are difficult to determine. For these reasons, the maximally exposed uninvolved worker is assumed to be located 100 m (330 ft) from the release point. This is the minimum distance that -/Qs calculated by the Gaussian plume models commonly used for this type of assessment can be considered reliable. Two sets of receptor locations are used to represent the maximum off-site individual. This is a hypothetical individual that remains at the site boundary for the entire duration of the release. In the case of normal conditions, the individual is assumed to be present for 8,760 hr/yr. The first set of receptors is located along the existing site boundary. Distances for some of the release points shown in Table E-1 to this boundary are listed in Table E-2. In the future, land beyond Highways 240 and 24 to the west and south and land beyond the Columbia River to the north may be transferred to other agencies and become outside the site boundary. Table E-3 shows distances from the release points of interest to the potential new boundary which is the nearest in a given direction of the existing boundary, Highways 240 and 24, and the Columbia River.
E.1.2 POPULATION RECEPTORS
Because the total number of workers involved in many of the activities of the alternatives at any time are not known, involved worker populations are not specifically evaluated. Exposures to workers in the involved population are bounded by those exposures received by the maximally exposed individual worker. The assessment of health effects of accidents on uninvolved worker populations is a two-step process. This process was simplified by the facts that all accidental releases under the alternatives considered would be ground level releases and that no large structures that could cause building wake effects were identified in the vicinity of the release points. This allowed a polar grid of -/Qs to be calculated as described in Section E.3.2. This grid was then used with facility layouts for the 200 Areas and building occupancy data derived from the Hanford Site telephone book to locate the maximally exposed uninvolved worker population and the location with the highest product of -/Q and number of workers. The locations of maximum uninvolved worker populations are shown in Tables E-4 and E-5 by distance and direction from each release point. The population distribution shown in Table E-6 was used to assess health effects to the off-site population for both normal and accident conditions. For accident conditions, the maximum off-site population was identified using the same procedure used for uninvolved workers. The locations of the maximum off-site population receptors are given in Tables E-4 and E-5.
Distance to Receptor Locations Along the Existing Boundary
Area 200 East 200 West
NTF Site "E" NTF Site "D" A Tank Farm NTF SY Tank Farm
Facilities
RCSTS DB#2 244-A Lift RCSTS DB#1 DCRT 244-S
Direction Distance (m)
S 17,990 18,910 19,840 13,060 13,090
SSW 15,950 16,160 17,230 13,270 13,340
SW 17,970 17,620 17,610 15,530 14,750
WSW 17,820 18,900 21,250 13,290 12,620
W 17,460 18,500 20,940 13,020 12,430
WNW 17,900 18,950 22,000 13,260 12,780
NW 19,130 19,850 21,030 16,820 16,300
NNW 18,960 19,640 21,210 17,730 17,370
N 22,160 23,050 24,800 19,820 19,100
NNE 26,550 25,940 23,280 28,240 28,230
NE 21,120 20,400 17,640 26,330 26,890
ENE 18,520 17,450 15,060 23,070 23,670
E 18,310 17,310 15,460 23,000 23,670
ESE 22,520 21,470 18,980 27,520 28,230
SE 25,890 25,660 23,020 22,330 22,900
SSE 20,670 20,460 20,240 18,660 17,470
DB = Diversion Box
1 m = 3.3 ft
Distance to Receptor Locations Along the Potential New Boundary
Area 200 East 200 West
NTF Site "E" NTF Site "D" A Tank Farm NTF SY Tank Farm
Facilities
RCSTS DB#2 244-A Lift RCSTS DB#1 DCRT 244-S
Direction Distance (m)
S 7,970 8,330 9,560 3,400 3,800
SSW 7,320 7,760 9,040 3,980 3,800
SW 7,320 7,750 9,030 4,320 3,950
WSW 8,900 9,250 9,870 4,860 4,060
W 9,660 10,660 12,890 5,180 4,300
WNW 12,920 14,090 16,480 6,610 5,420
NW 11,140 11,710 12,670 10,330 9,260
NNW 10,640 11,350 12,870 11,280 11,100
N 12,000 12,910 15,560 11,280 11,110
NNE 14,950 14,500 12,920 14,840 13,920
NE 13,790 12,780 10,650 18,270 19,150
ENE 13,450 12,570 10,720 17,880 18,710
E 15,010 14,320 12,600 20,310 21,040
ESE 22,720 21,560 18,960 27,270 28,230
SE 25,200 25,340 22,980 8,910 7,790
SSE 10,050 10,640 12,830 5,060 4,300
DB = Diversion Box
1 m = 3.3 ft
Atmospheric Dispersion Factors for Accidental Releases
From the 200 West Area
-/Q (s/m3)a
Release Point Receptor 0-2 Hr 0-8 Hr 8-24 Hr
Averaging Averaging Averaging
241-SY Tank Farm Maximum Uninvolved Worker (100 m) 1.09 x 10-2 6.78 x 10-3 NA
ITRS
Load/Unload Facility
DCRT 244-S
Maximum Uninvolved Worker Population 1.41 x 10-4 7.31 x 10-5 NA
(575 Workers, NNW @ 1,300 m) (8.11 x 10-2) (4.20 x 10-2)
Maximum Off-site Individual - Existing 1.42 x 10-5 6.20 x 10-6 4.10 x 10-6
Boundary (W @ 12,430 m)
Maximum Off-site Individual - Potential 4.30 x 10-5 2.02 x 10-5 1.38 x 10-5
Boundary (W @ 4,300 m)
Maximum Off-site Population b 3.42 x 10-6 1.28 x 10-6 1.01 x 10-6
(3.32 x 10-1) (1.21 x 10-1) (7.39 x 10-2)
NTF Maximum Uninvolved Worker (100 m) 1.09 x 10-2 6.78 x 10-3 NA
RCSTS Diversion Box 1
Maximum Uninvolved Worker Population 1.01 x 10-4 5.12 x 10-5 NA
(625 Workers, NW @ 1,750 m) (6.31 x 10-2) (3.20 x 10-2)
Maximum Off-site Individual - Existing 1.35 x 10-5 5.89 x 10-6 3.89 x 10-6
Boundary (W @ 13,020 m)
Maximum Off-site Individual - Potential 4.55 x 10-5 2.22 x 10-5 1.55 x 10-5
Boundary (S @ 3,400 m)
ECSTS Diversion Box Maximum Off-site Population b 3.42 x 10-6 1.28 x 10-6 1.01 x 10-6
(241-UX-251) (3.32 x 10-1) (1.21 x 10-1) (7.39 x 10-2)
Maximum Uninvolved Worker (100 m) 1.09 x 10-2 6.78 x 10-3 NA
Maximum Uninvolved Worker Population 1.41 x 10-4 7.31 x 10-5 NA
(575 Workers, NNW @ 1,300 m) (8.11 x 10-2) (4.20 x 10-2)
Maximum Off-site Individual - Existing 1.42 x 10-5 6.20 x 10-6 4.10 x 10-6
Boundary (W @ 12,430 m)
Maximum Off-site Individual - Potential 4.30 x 10-5 2.02 x 10-5 1.38 x 10-5
Boundary (W @ 4,300 m)
Maximum Off-site Population b 3.42 x 10-6 1.28 x 10-6 1.01 x 10-6
(3.32 x 10-1) (1.21 x 10-1) (7.39 x 10-2)
aPopulation-weighted -/Qs (persons-s/m3) are given in parentheses.
bThe maximum population for 0-2 hr and 0-8 hr releases is 94,203 at 64 to 80 km (40 to 50 mi) west. The
maximum population for 8-24 hr releases is 73,156 at 48 to 64 km (30 to 40 mi) southeast. -/Qs are calculated at
the midpoint of the distance interval.
NA = Not Applicable
1 m = 3.3 ft
Atmospheric Dispersion Factors for Accidental Releases
From the 200 East Area
-/Q (s/m3)a
Release Point Receptor 0-2 Hr 0-8 Hr 8-24 Hr
Averaging Averaging Averaging
NTF Site "E" Maximum Uninvolved Worker (100 m) 1.09 x 10-2 6.78 x 10-3 NA
Maximum Uninvolved Worker Population 1.33 x 10-4 7.36 x 10-5 NA
(890 Workers, ESE @ 1,750 m) (1.18 x 10-1) (6.55 x 10-2)
Maximum Off-site Individual - 1.63 x 10-5 7.28 x 10-6 4.86 x 10-6
Existing Boundary (E @ 18,310 m)
Maximum Off-site Individual - 1.98 x 10-5 8.95 x 10-6 6.01 x 10-6
Potential Boundary (E @ 15,010 m)
Maximum Off-site Populationc 3.42 x 10-6 1.28 x 10-6 1.01 x 10-6
(3.32 x 10-1) (1.21 x 10-1) (7.39 x 10-2)
NTF Site "D" Maximum Uninvolved Worker (100 m) 1.09 x 10-2 6.78 x 10-3 NA
RCSTS Diversion Box 2
ECSTS Diversion Box
(241-ER-151)
Maximum Uninvolved Worker Population 4.07 x 10-4 2.21 x 10-4 NA
(417 Workers, NNW @ 600 m) (1.70 x 10-1) (9.22 x 10-2)
Maximum Off-site Individual - 1.72 x 10-5 7.72 x 10-6 5.16 x 10-6
Existing Boundary (E @ 17,310 m)
Maximum Off-site Individual - 2.08 x 10-5 9.39 x 10-6 6.32 x 10-6
Potential Boundary (E @ 14,320 m)
Maximum Off-site Populationc 3.42 x 10-6 1.28 x 10-6 1.01 x 10-6
(3.32 x 10-1) (1.21 x 10-1) (7.39 x 10-2)
241-A Tank Farm Maximum Uninvolved Workerb (100 m) 1.09 x 10-2 6.78 x 10-3 NA
244-A Lift Station
Load/Unload
Facility
DCRT 244-A
Maximum Uninvolved Worker Populationb 1.87 x 10-3 1.11 x 10-3 NA
(161 Workers, SE @ 250 m) (3.01 x 10-1) (1.79 x 10-1)
Maximum Off-site Individual - 1.93 x 10-5 8.68 x 10-6 5.82 x 10-6
Existing Boundary (E @ 15,460 m)
Maximum Off-site Individual - 2.35 x 10-5 1.07 x 10-5 7.24 x 10-6
Potential Boundary (E @ 12,600 m)
Maximum Off-site Population c 3.42 x 10-6 1.28 x 10-6 1.01 x 10-6
(3.32 x 10-1) (1.21 x 10-1) (7.39 x 10-2)
aPopulation-weighted -/Qs (persons-s/m3) are given in parentheses.
bStructures occupied by uninvolved workers are nearer than 100 m.
cThe maximum population for 0-2 hr and 0-8 hr releases is 94,203 at 64 to 80 km (40 to 50 mi) west. The
maximum population for 8-24 hr releases is 73,156 at 48 to 64 km (30 to 40 mi) southeast. -/Qs are calculated at
the midpoint of the distance interval.
NA = Not Applicable
1 m = 3.3 feet.
Distribution of Off-Site Population Within 80 Kilometers (50 Miles) of the Hanford Site
Interval 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50
(mi)
Total
Midpoint 805 2,414 4,023 5,633 7,242 12,070 24,140 40,234 56,327 72,421
(m)
Direction
N 0 0 0 0 0 0 434 822 969 2,418 4,643
NNE 0 0 0 0 0 0 268 1,030 5,220 17,567 24,085
NE 0 0 0 0 0 0 393 6,176 2,658 1,145 10,372
ENE 0 0 0 0 0 0 423 1,217 1,652 664 3,956
E 0 0 0 0 0 0 452 1,373 1,416 751 3,992
ESE 0 0 0 0 0 0 289 1,674 270 767 3,000
SE 0 0 0 0 0 0 1,141 35,519 73,156 4,918 114,734
SSE 0 0 0 0 0 0 2,796 8,309 2,394 5,891 19,390
S 0 0 0 0 0 0 2,842 1,622 237 1,144 5,845
SSW 0 0 0 0 0 0 713 11,983 503 738 13,937
SW 0 0 0 0 0 0 1,308 19,589 1,132 637 22,666
WSW 0 0 0 0 0 0 1,956 5,406 16,336 7,525 31,223
W 0 0 0 0 0 0 771 1,295 6,269 94,203 102,538
WNW 0 0 0 0 0 0 641 1,087 1,189 2,375 5,292
NW 0 0 0 0 0 0 548 738 784 809 2,879
NNW 0 0 0 0 0 0 544 909 876 4,979 7,308
Total 0 0 0 0 0 0 15,519 98,749 115,061 146,531 375,860
Source: PNL 1993
E.2 AIRBORNE CONCENTRATIONS AT RECEPTORS UNDER NORMAL CONDITIONS
This section discusses calculations to estimate the concentrations of potentially hazardous materials released under normal conditions. Normal emissions from existing facilities at the Hanford Site are reported annually (WHC 1994a, DOE 1994a) and provide the basis for evaluating the no action alternative. Data on normal emissions specific to the other alternative actions are not available, with the exception of emissions from the NTF. Health effects of emissions from other facilities are evaluated qualitatively in Section 5 by comparison to those from existing emissions. Section E.2.1 characterizes the emission rates of hazardous materials from the NTF. Section E.2.2 identifies the atmospheric dispersion factors applied to these emissions and the resulting concentrations at receptor locations.
E.2.1 EMISSION RATES OF HAZARDOUS MATERIALS
Emission rates of hazardous materials from the NTF are available for a nominal case and an extreme case (DOE 1994b, WHC 1994b). Emissions of radionuclides are shown in Table E-7. Emissions of chemicals are shown in Table E-8. The nominal case is representative of emissions expected from the NTF under the alternatives in this EIS. The extreme case is intended to bound future uses of the NTF. The principal difference between the two cases is the assumed tank heat load. The nominal case assumes two tanks, each with a load of 32,000 watts (110,000 BTU/hr). The extreme case assumed a load of 32,000 watts (110,000 BTU/hr) for one tank and 205,000 watts (700,000 BTU/hr) for the other. A greater variety of organic compounds are assumed to be emitted and at a higher rate under the extreme case.
E.2.2 ATMOSPHERIC DISPERSION FACTORS AND RECEPTOR CONCENTRATIONS
Atmospheric concentrations at receptors of interest were estimated for the NTF. The CAP88-PC program (DOE 1992) was used for radionuclides and the ISCST2 program (EPA-A5D/4-92-008) for hazardous chemicals. The NTF primary ventilation stack would be 46 m (150 ft) tall and 1.8 m (6 ft) in diameter. CAP88-PC was used to estimate average annual concentrations in the 16 compass directions at distances ranging from 100 to 80,000 m (0.06 to 50 mi). Maximum
Radionuclide Emissions from the NTF
Emissions (Ci/yr)
Radionuclide
Nominal Casea Extreme Caseb
3H 7.13 x 10-1 1.77 x 100
90Sr 7.93 x 10-8 5.96 x 10-7
90Y 7.77 x 10-8 5.83 x 10-7
106Ru NA 2.48 x 10-6
106Rh NA 2.46 x 10-6
113Sn NA 4.45 x 10-6
125Sb NA 2.21 x 10-5
129I 3.54 x 10-5 7.17 x 10-5
137Cs 2.27 x 10-9 1.51 x 10-8
137mBa 2.18 x 10-9 1.41 x 10-8
239Pu 1.92 x 10-11 3.70 x 10-11
Source: DOE 1994b
aNominal Case assumes two tanks at 32,000 watts (110,000 BTU/hr) and a
discharge of 0.5 m3/s (1,000 scfm).
bExtreme Case assumes one tank at 32,000 watts (110,000 BTU/hr), one
tank at 205,000 watts (700,000 BTU/hr), and a discharge of 0.5 m3/s (1,000
scfm).
Ci = Curie
NA = Not Applicable. Assumed not to be present.
Chemical Emissions from the NTF
Emissions (g/s)
Chemical
Nominal Case a Extreme Case b
Acetone 2.2 x 10-3 2.3 x 10-3
Benzene NA 5.7 x 10-6
1-Butanol 1.4 x 10-2 1.4 x 10-2
Carbon Tetrachloride NA 4.3 x 10-8
2-Hexanone 5.8 x 10-5 1.7 x 10-4
4-Methyl-2-Pentanone 4.1 x 10-3 1.2 x 10-2
Kerosene 1.4 x 10-10 1.7 x 10-2
Tributyl Phosphate 1.4 x 10-10 4.1 x 10-10
Ammonia 3.4 x 10-6 4.9 x 10-6
Ag 2.8 x 10-15 2.8 x 10-15
As 1.8 x 10-13 1.8 x 10-13
Ba 9.1 x 10-16 9.1 x 10-16
Ca 6.1 x 10-15 6.1 x 10-15
Cu 1.4 x 10-15 1.4 x 10-15
Mg 1.2 x 10-15 1.2 x 10-15
Na 3.3 x 10-11 3.3 x 10-11
Pb 4.1 x 10-15 4.1 x 10-15
Sb 5.6 x 10-15 5.6 x 10-15
Se 3.6 x 10-15 3.6 x 10-15
AlO2 1.2 x 10-11 1.2 x 10-11
OH- 5.1 x 10-12 5.1 x 10-12
F- 9.8 x 10-13 9.8 x 10-13
Fe(OH)3 1.7 x 10-12 1.7 x 10-12
Cr(OH)3 4.6 x 10-13 4.6 x 10-13
Source: WHC 1994b
aNominal Case assumes two tanks at 32,000 watts (110,000 BTU/hr) and a
discharge of 0.5 m3/s (1,000 scfm).
bExtreme Case assumes one tank a 32,000 watts (100,000 BTU/hr), one tank
at 205,000 watts (700,000 BTU/hr), and a discharge of 0.5 m3/s (1,000 scfm).
g/s = grams/second
NA = Not Applicable. Assumed not to be present.
concentrations were found to occur at a distance of 200 m (660 ft) from the
stack. A joint frequency distribution based on 5 years of Hanford specific
meteorology data at a height of 61 m (200 ft) (PNL 1993) was used in
conjunction with the population distribution shown in Table E-6. A flat
terrain was assumed. Since the inhalation doses reported in Section 5.4.9.2
are the primary parameters of interest and are reported directly by the code,
airborne concentrations are not tabulated here.
ISCST2 was used to calculate 1-hour and 24-hour averaged concentrations at
locations of interest using built-in joint frequency distributions considered
to represent "worst case" dispersion conditions. ISCST2 was also given
terrain elevation information extracted by hand from topographic maps. The
program considers the effect of stack-tip downwash and found maximum
concentrations of chemicals at 400 m (1,300 ft) for a 24-hour averaging
period. Concentrations of individual chemicals are shown in Table E-9.
E.3 AIRBORNE CONCENTRATIONS AT RECEPTORS UNDER ACCIDENT CONDITIONS
Airborne concentrations of hazardous materials under accident conditions were
estimated by multiplying the quantity of respirable material released by the
concentrations of hazardous materials in the waste as in equation 1.
where:
Cair = concentration of contaminant in air (Ci/m3 for radionuclides, -g/m3
for chemicals)
Cwaste = concentration of contaminant in waste (Ci/L for radionuclides, mg/L
for chemicals)
CF = unit conversion factor for chemical (103 -g/mg)
RV = respirable volume released (L)
RD = release duration (s)
-/Q = air dispersion factor (s/m3).
Maximum 24-Hour and Annual Ground Level Concentrations for Emissions from Two DSTs
ASILs
24-Hour Concentration (-g/m3) Annual Concentration (-g/m3) WAC 173-460-150
Extreme Case, Distance From Distance From Distance From Distance From
2 Tank Emissions Source, On-site Source, Off-site Source, On-site Source, Off-site 24-Hr ASIL Annual ASIL
Chemical (g/s) 400m 10,771m 200m 12,978m (-g/m3) (-g/m3)
Acetone 2.3x10-3 4.1x10-2 3.4x10-3 1.3x10-2 1.0x10-2 5.9x103 NA
Benzene 5.7x10-6 1.0x10-4 8.3x10-6 3.2x10-5 2.5x10-5 NA 1.2x10-1
1-Butanol 1.4x10-2 2.5x10-1 2.0x10-2 7.9x10-2 6.2x10-2 5.0x102 NA
Carbon Tetrachloride 4.3x10-8 7.6x10-7 6.3x10-8 2.4x10-7 1.9x10-7 NA 6.7x10-2
2-Hexanone 1.7x10-4 3.0x10-3 2.5x10-4 9.7x10-4 7.5x10-4 6.7x101 NA
4-Methyl-2-Pentanone (MIBK) 1.2x10-2 2.1x10-1 1.8x10-2 6.8x10-2 5.3x10-2 6.8x101 NA
Normal Paraffin Hydrocarbon 1.7x10-2 3.0x10-1 2.5x10-2 9.7x10-2 7.5x10-2 NA NA
(Kerosene)
Tributyl Phosphate 4.1x10-10 7.2x10-9 6.0x10-10 2.3x10-9 1.8x10-9 7.3 NA
Ammonia 4.9x10-6 8.7x10-5 7.2x10-6 2.8x10-5 2.2x10-5 1.0x102 NA
Ag 2.8x10-15 4.9x10-14 4.1x10-15 1.6x10-14 1.2x10-14 3.0x10-2 NA
As 1.8x10-13 3.2x10-12 2.6x10-13 1.0x10-12 8.0x10-13 2.3x10-2 NA
Ba 9.1x10-16 1.6x10-14 1.3x10-15 5.2x10-15 4.0x10-15 1.7 NA
Ca 6.1x10-15 1.1x10-13 8.9x10-15 3.5x10-14 2.7x10-14 1.7x101 NA
Cu 1.4x10-15 2.5x10-14 2.0x10-15 7.9x10-15 6.2x10-15 3.3 NA
Mg 1.2x10-15 2.1x10-14 1.8x10-15 6.8x10-15 5.3x10-15 3.3x10-1 NA
Na 3.3x10-11 5.8x10-10 4.8x10-11 1.9x10-10 1.5x10-10 6.7 NA
Pb 4.1x10-15 7.2x10-14 6.0x10-15 2.3x10-14 1.8x10-14 5.0x10-1 NA
Sb 5.6x10-15 9.9x10-14 8.2x10-15 3.2x10-14 2.5x10-14 1.7 NA
Se 3.6x10-15 6.4x10-14 5.3x10-15 2.0x10-14 1.6x10-14 6.7x10-1 NA
A1O2 1.2x10-11 2.1x10-10 1.8x10-11 6.8x10-11 5.3x10-11 6.7 NA
OH- 5.1x10-12 9.0x10-11 7.5x10-12 2.9x10-11 2.3x10-11 NA NA
F- 9.8x10-13 1.7x10-11 1.4x10-12 5.6x10-13 4.3x10-12 5.3 NA
Fe(OH)3 1.7x10-12 3.0x10-11 2.5x10-12 9.6x10-12 7.5x10-12 3.3 NA
Cr(OH)3 4.6x10-13 8.1x10-12 6.7x10-13 2.6x10-12 2.0x10-12 1.7 NA
NA = Not applicable
This section describes the hazardous material inventories used and the
procedure used to estimate -/Qs used as described in Section E.4 to estimate
health effects. Concentrations of radionuclides and toxic chemicals by waste
type are described in Section E.3.1. Dispersion factors utilized for
determining concentrations at receptor locations are identified in Section
E.3.2.
E.3.1 CONCENTRATIONS OF RADIONUCLIDES AND TOXIC CHEMICALS IN WASTE
A total of five types of wastes are considered in this EIS: . Salt well liquid (SWL) . West Area Facility Waste (WAFW) . Tank 101-SY slurry (101-SY) . Tank 102-SY slurry (102-SY) . Bounding slurry waste (BSW). The basis for the radionuclide concentrations assigned to these wastes is discussed in Section E.3.1.1. Information on the concentrations of toxic chemicals in these wastes is discussed in Section E.3.1.2.
E.3.1.1 Radionuclides
- The radionuclide concentrations in SWL, WAFW, 101-SY,
102-SY, and BSW are described as follows:
. Salt well liquid - SWL is drainable liquid collected and pumped from
salt wells installed in SSTs. Radionuclide concentrations in SWL vary
from tank to tank in the SST tank farms. Savino and Hey (WHC 1994c)
have derived radionuclide concentration estimates for various SST and
DST wastes. The estimates are based on data obtained for laboratory
analyses of samples of tank solids and liquids. Mean concentrations and
concentrations corresponding to various "percentiles" are provided. One
of these data sets is called "100 percentile of all SST liquids
inventory" and consists of the highest concentration of each
radionuclide measured in all samples of liquids from SSTs. Radionuclide
concentrations are shown in Table E-10. Unit dose factors included in
Tables E-10 through E-13 are discussed in Section E.4.1.
Radionuclide Concentrations in SWL
Concentration Unit Inhalation CEDEa
Radionuclide (Ci/L) (rem/L)
14C 9.7 x 10-7 1.9 x 10-3
60Co 1.1 x 10-4 2.2 x 10+1
90Sr 2.0 x 10-2 3.9 x 10+3
90Y 2.0 x 10-2 1.7 x 10+2
99Tc 1.1 x 10-4 9.4 x 10-1
106Ru 2.7 x 10-8 1.2 x 10-2
125Sb 1.4 x 10-6 1.7 x 10-2
129I 1.1 x 10-7 1.7 x 10-2
134Cs 3.0 x 10-6 1.2 x 10-1
137Cs 2.0 x 10-1 5.4 x 10+3
144Ce 1.1 x 10-9 4.1 x 10-4
154Eu 4.6 x 10-2 1.2 x 10+4
155Eu 2.0 x 10-3 7.7 x 10+1
238Pu 7.8 x 10-5 2.2 x 10+4
239Pu 1.8 x 10-4 5.2 x 10+4
241Pu 1.4 x 10-3 6.9 x 10+3
241Am 1.5 x 10-4 6.6 x 10+4
2.9 x 10-1 1.7 x 10+5
Source: (WHC 1994c)
aCommitted Effective Dose Equivalent
Radionuclide Concentrations in 102-SY Slurry
and West Area Facility Waste
Concentration Unit Inhalation
Radionuclide (Ci/L) CEDE (rem/L)
3H 2.3 x 10-7 2.0 x 10-5
14C 5.6 x 10-7 1.1 x 10-3
60Co 6.6 x 10-5 1.3 x 101
79Se 4.6 x 10-6 4.3 x 10-2
90Sr 2.8 x 10-2 5.5 x 103
90Y 2.8 x 10-2 2.4 x 102
94Nb 2.9 x 10-7 1.1 x 10-1
99Tc 1.3 x 10-5 1.1 x 10-1
137Cs 3.3 x 10-2 9.7 x 102
144Ce 9.8 x 10-4 3.5 x 102
154Eu 5.2 x 10-4 1.4 x 102
155Eu 5.7 x 10-4 2.2 x 101
237Np 5.4 x 10-7 3.3 x 102
238Pu 2.4 x 10-4 6.6 x 104
239Pu 2.1 x 10-3 6.1 x 105
241Am 1.6 x 10-2 6.6 x 106
244Cm 2.0 x 10-5 4.7 x 103
1.1 x 10-1 7.3 x 106
Radionuclide Concentrations in Tank 101-SY Slurry
Concentration Unit Inhalation CEDE
Radionuclide (Ci/L) (rem/L)
14C 1.7 x 10-6 3.3 x 10-3
59Ni 1.3 x 10-7 1.1 x 10-4
63Ni 3.6 x 10-5 7.8 x 10-2
79Se 3.8 x 10-7 3.5 x 10-3
90Sr 2.3 x 10-2 4.5 x 10+3
93mNb 6.8 x 10-6 2.0 x 10-1
99Tc 2.0 x 10-4 1.6 x 10+0
137Cs 5.7 x 10-1 1.7 x 10+4
237Np 4.5 x 10-8 2.8 x 10+1
239Pu 1.1 x 10-5 3.3 x 10+3
241Am 1.7 x 10-4 7.1 x 10+4
242Cm 4.7 x 10-7 7.6 x 10+0
244Cm 1.0 x 10-5 2.4 x 10+3
5.9 x 10-1 9.8 x 10+4
Source: WHC 1993a
Radionuclide Concentrations in Bounding Slurry Waste
Concentration Unit Inhalation CEDE
Radionuclide (Ci/L) (rem/L)
14C 5.6 x 10-6 1.1 x 10-2
60Co 5.6 x 10-3 1.1 x 10+3
79Se 1.5 x 10-7 1.4 x 10-3
90Sr 2.7 x 10+1 5.3 x 10+6
90Y 2.7 x 10+1 2.3 x 10+5
99Tc 1.1 x 10-1 9.4 x 10+2
106Ru 2.2 x 10-6 9.8 x 10-1
125Sb 2.5 x 10-3 3.0 x 10+1
129I 5.8 x 10-5 8.5 x 10+0
134Cs 3.5 x 10-4 1.4 x 10+1
137Cs 3.2 x 10+0 9.3 x 10+4
144Ce 1.5 x 10-8 5.6 x 10-3
147Pm 1.0 x 10-3 3.8 x 10+1
154Eu 1.8 x 10-1 4.6 x 10+4
155Eu 1.4 x 10-3 5.6 x 10+1
237Np 2.9 x 10-4 1.8 x 10+5
238Pu 1.7 x 10-3 4.6 x 10+5
239Pu 1.5 x 10-2 4.6 x 10+6
241Pu 4.2 x 10-2 2.0 x 10+5
241Am 1.0 x 10-1 4.3 x 10+7
242Cm 3.0 x 10-8 4.8 x 10-1
244Cm 5.9 x 10-4 1.4 x 10+5
5.8 x 10+1 5.4 x 10+7
Source: WHC 1994c
This set of concentrations is hypothetical. No single SST contains
liquid where the concentration of each radionuclide is as high as shown
in Table E-10. To the extent that the samples are representative of SST
liquids, this set of data provides a conservative bound on radionuclide
concentrations that would be expected to be encountered in SWL.
. West Area Facility Waste - WAFW consists of routine wastes from the T-
Plant, S-Plant, and the PFP laboratories. Wastes from T-Plant account
for most of the volume and wastes from the PFP laboratories account for
the majority of the radioactivity in these wastes. Waste from the PFP
laboratories contains approximately 5 to 10 percent solids by weight and
is considered to be TRU waste although average TRU concentrations are
slightly below the threshold of 100 nCi/g of TRU. All of these wastes
are currently transferred to Tank 102-SY for storage. Since TRU
nuclides, particularly 241Am, control inhalation dose from most solids-
bearing tank wastes (see Section E.4), WAFW is assigned the same
radionuclide concentrations as 102-SY slurry. These concentrations are
shown in Table E-11.
. Tank 101-SY Slurry - Under the new storage alternative, the entire
contents of Tank 101-SY would be mixed, retrieved with in-line dilution,
and stored in new tanks. The radionuclide concentrations shown in Table
E-12 are based on "Window E" core samples from Tank 101-SY and are
volume-weighted to reflect the contributions of the convective and non-
convective layers in the tank. These concentrations do not reflect
dilution.
. Tank 102-SY Slurry - Several alternative actions include retrieval of
the sludge in Tank 102-SY. The sludge would be mixed with at least
twice its volume of diluent (2:1 dilution) and retrieved with either of
two systems. For this EIS, the entire volume of supernatant now in the
tank would be used as diluent. This would provide a 3.6:1 dilution.
The resultant radionuclide concentrations are shown in Table E-11 and
are based on concentration data from Tank Characterization Report for
Double-Shell Tank 241-SY-102 (WHC 1995a).
. Bounding Slurry Waste - BSW is a hypothetical waste used to estimate the
maximum impacts that could occur during possible future uses of the
facilities and systems considered in this EIS. BSW is a composite
consisting of one-third by volume of the "100 percentile of all solids
inventory" and two-thirds "100 percentile of all liquids inventory"
developed by Savino and Hey. Each "100 percentile inventory" consists
of the highest concentration of each radionuclide measured in any tank
solid and any tank liquid. Most of the radionuclides are in tank solids
and 33 percent by volume is a very high solids content relative to the
capabilities of current and planned transfer pumps and pipelines.
Accordingly, to the extent that the samples in the database used by
Savino and Hey are representative of tank solids and liquids, the
radionuclide concentrations shown in Table E-13 provide a conservative
bound on radionuclide concentrations that would be expected to be
encountered in the systems considered in this EIS (WHC 1994c).
E.3.1.2 Toxic Chemicals
- The chemical characteristics of tank wastes is less well-known than the radiological characteristics. Although a program to determine the chemical characteristics of tank wastes is being vigorously pursued, much of the information being generated is intended to support the design of a waste treatment system. As an example of the analytes and ranges of concentrations of chemicals that have been seen, chemical concentrations in SWL and BSW, based on information currently available, are shown in Table E-14. Although characterization reports have been issued for about 20 tanks, including Tanks 101-SY and 102-SY, much of the available information is based on historical records such as invoices for orders of chemicals and process information rather than on analysis of samples. In keeping with the quantity and quality of data currently available, a qualitative approach has been taken in most cases to estimating airborne concentrations of chemicals and their corresponding health effects. This approach is discussed in Section E.4.2.
E.3.2 AIRBORNE DISPERSION FACTORS AND CONCENTRATIONS AT RECEPTORS
This section describes calculation of -/Qs necessary to evaluate health effects. The PAVAN computer code (NUREG 1991) developed by the NRC to evaluate airborne releases during nuclear power reactor accidents was used to estimate -/Qs for the short-duration releases (0 to 24 hours) from accidents associated with the alternatives considered in this EIS.
Concentrations of Toxic Chemicals in Tank Wastes
Concentration (g/L)
Chemical
SWL BSW
Ammonia 1.1 6.9
Sb 0.037 0.61
As 0.003 1.9
Ba 0.053 13
Be 0.0003 0.048
Cd 0.05 8.7
Ca 1.1 33
Ce 1.75 2.0
Cr+3 16 34
Co 0.0013 0.22
Cyanide 5.3 8.9
Dy NA 0.03
La 0.19 12
Hg 0.084 6.8
Nd 0.14 2.4
Oxalate NA 92
Se 0.080 1.2
NaOH 180 211
Na 250 323
Te NA 0.31
Tl 0.25 4.5
Total Organic
Carbon (TOC) 40 52
U 1.4 96
V 0.0041 0.05
Source: WHC 1995b
NA = Not Available
PAVAN uses the Guassian plume model to calculate -/Qs from a user-supplied
joint frequency distribution. -/Qs are calculated for averaging times of 0 to
2 hours, 0 to 8 hours, 8 to 24 hours and 1 to 4 days. Average annual -/Qs are
also calculated. PAVAN uses three different techniques to estimate -/Qs over
these averaging times. The direction-dependent logarithmic interpolation
method described in Regulatory Guide 1.145 (NRC 1982) provides -/Qs in each
direction that would not be exceeded more than 0.5 percent of the total time.
-/Qs calculated with this method were found to be highest (most conservative)
and were used for assessment of accident health effects.
The joint frequency distribution (PNL 1993) input to PAVAN to calculate -/Qs
for accidents is the same as that input to CAP88-PC to assess health effects
for normal conditions. Table E-4 shows -/Qs for accidental releases from the
200 West Area and Table E-5 shows -/Qs for releases from the 200 East Area.
The tables include information on receptor distance and direction, and include
population-weighted -/Qs. The averaging times of 0 to 2 hour, 0 to 8 hour,
and 8 to 24 hour correspond to durations of exposures of workers and the
general public as discussed in Appendix F.
E.4 DOSE AND HEALTH EFFECTS
Consequences to the workers and the offsite public from radionuclides and toxic chemicals are measured as dose and health effects. Section E.4.1 characterizes the methodology applied to assessing radiological health effects and Section E.4.2 describes the methodology applied to assessing toxic chemical health effects.
E.4.1 RADIOLOGICAL HEALTH EFFECTS
The health effects of exposure to radiation can take many forms. Effects from acute radiation exposures range from nausea and fatigue to hemorrhage and death. Acute exposures can also cause temporary or permanent sterility. Approximately half of the people receiving an acute whole body dose of 100 to 200 rads would be expected to experience the milder acute effects and approximately half of the people receiving an acute whole body dose of 500 rads would be expected to die within 60 days. The rad is a unit of radiation absorbed dose and is equivalent to 100 ergs/g of exposed material. Health effects of chronic exposures to low levels of radiation are expressed over longer periods of time. These effects can include fatal and non-fatal cancer, and heritable autosomal and chromosomal damage and congenital abnormalities. Chronic effects are usually expressed in terms of rem. A rem is a unit of effective dose and is defined as the product of an absorbed dose in rads and a quality factor specific to the type of radiation involved. In this EIS, "dose" means CEDE. A committed dose equivalent is the dose equivalent (rem) that will be received by an organ or tissue over a 50-year period following the intake. The CEDE is the weighted sum of the committed dose equivalents to each organ and tissue. The intake considered in this document is inhalation. Risk coefficients or factors for chronic exposures to low levels of radiation are derived from data for exposures of large groups of individuals to large doses over a relatively short time. DOE recommends that health effects of radiation exposures be evaluated in terms of LCFs using risk factors of 4 x 10-4 LCF/person-rem for workers and 5 x 10-4 LCF/person-rem for the general population. These factors reflect the different sensitivities to radiation based on sex and age and are taken from the Preamble to 10 CFR Part 20 (56 FR 22363). The most appropriate application of these risk factors is to large groups of people receiving low chronic doses of radiation over long periods of time. Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements (DOE 1993) includes examples where these factors are applied to individuals to estimate ICR. ICR is the increase in the probability that an individual will develop fatal cancer. This practice is not universally accepted but is used in this EIS. To apply these risk factors, dose must first be estimated. This was accomplished using the GENII computer program (PNL 1988a, PNL 1988b, PNL 1988c) to calculate unit dose factors (rem/L). These factors give the dose in rem that corresponds to inhalation of the radioactive material contained in 1 L (0.26 gal) of tank waste. Unit dose factors based on the PNL default radionuclide solubilities provided with GENII are shown in Tables E-10 through E-13. Dose (CEDE) from a given accidental release is calculated as: where: RVol = volume of respirable tank waste released during exposure period (L) BR = breathing rate (m3/sec) -/Q = atmospheric dispersion factor (s/m3) U = unit dose factor (rem/L). Respirable volumes released during accidents are discussed in Appendix F. A breathing rate of 3.33 x 10-4 m3/sec was used for all receptors except the maximally exposed involved worker for which a value of 7.2 x 10-4 m3/sec was used.
E.4.2 TOXIC CHEMICAL HEALTH EFFECTS
Exposure to toxic chemicals can induce development of systemic toxic effects
and cancers.
The Hanford Site has developed risk acceptance guidelines for toxic chemicals
based on permissible exposure limits-time weighted average (PEL-TWA) and ERPG.
These guidelines are intended for the evaluation of accidents. Comparative
evaluations performed during development of these guidelines led to the
conclusion that, based on radiological and chemical risk acceptance
guidelines, chemical releases may be more limiting than radiological releases
of tank wastes only when release durations are shorter than 2 minutes 40
seconds. Since the shortest release duration of the accidents considered in
this EIS is 30 minutes, effects of toxic chemicals have not been evaluated for
most accidents. The exception is a "flash" release of toxic gases during
drawdown of a tank.
A methodology for estimating systemic and carcinogenic effects from exposure
data is described in Risk Assessment Guidance for Superfund. Volume 1. Human
Health Evaluation Manual (Part A) (EPA 1989). The remainder of this section
describes the methodology and applies it to normal emissions from the NTF.
Systemic toxic effects are evaluated in terms of a Hazard Quotient (HQ).
The HQ for a chemical is the ratio of the exposure level (E) or intake of the
chemical to the Reference Dose (RfD) for the chemical:
If the HQ exceeds 1.0, there may be concern for potential health effects.
The EPA methodology considers three exposure durations, each with its own RfD:
. Chronic exposures (7 year to lifetime exposures)
. Subchronic exposures (2 week to 7 year exposures)
. Acute (less than 2 week exposures).
When dealing with exposures from multiple chemicals, HQs may be summed for
each exposure duration for screening purposes. This is expected to
overestimate the potential for health effects due to differences in the nature
and significance of effects induced by exposures to different chemicals.
Carcinogenic effects are evaluated in terms of the incremental risk of
developing cancer (fatal and nonfatal) as the result of chronic exposure to a
chemical. At lower risk levels (ICR . 0.01, equation 4), the ICR is based on
the product of a chronic daily intake averaged over 70 years and a slope
factor (SF). At higher risk levels, risk is an exponential function of this
product. SFs are usually the upper 95th percentile confidence interval of the
dose response curve for the chemical.
where CDI = chronic daily intake.
ICR is considered to be additive for exposure to multiple chemicals.
Chronic daily intake (CDI) of airborne contaminants in the HQ and ICR
equations is calculated as:
where:
CDI = chronic daily intake of the contaminant (mg/kg-d)
C = contaminant concentration in air (mg/m3)
IR = daily intake rate (m3/d)
EF = exposure frequency (d/yr)
ED = exposure duration (yr)
BW = body weight (kg)
AT = averaging time (d).
As indicated in Table E-15, different parameter values are used for chronic
exposures to carcinogenic and non-carcinogenic contaminants.
Intake Parameters and Values
Parameter Non-carcinogenic Carcinogenic IR - Daily Intake Rate (m3/d) 10 20 EF - Exposure Frequency (d/yr) 365 365 ED - Exposure Duration (yr) 6 30 Conversion Factor (mg/-g) 0.001 0.001 BW - Body Weight (kg) 16 70 AT - Averaging Time (d) 2,190 25,550 Source: EPA 1989 Data on RfDs and SFs are available from a number of sources. The Integrated Risk Information System (IRIS) (EPA 1994) is the source of toxicity information preferred by EPA for Superfund risk assessments. Data from the IRIS for chronic exposures to chemicals released from the NTF is shown in Table E-16.
Toxicological Health Effects from NTF Emissions
Intake (mg/kg-d)
Concentration RfD SF
Chemical (-g/m3) (mg/kg-d) (mg/kg-d)-1 HQ ICR
Noncarcinogenic Carcinogenic
Acetone 1.00 x 10-02 NA NA 6.25 x 10-6 1.22 x 10-6 NA NA
Benzene 2.50 x 10-05 NA 2.90 x 10-02 1.56 x 10-8 3.06 x 10-9 NA 8.88 x 10-11
1-Butanol 6.20 x 10-02 NA NA 3.88 x 10-5 7.59 x 10-6 NA NA
Carbon Tetrachloride 1.90 x 10-07 NA 5.25 x 10-02 1.19 x 10-10 2.33 x 10-11 NA 1.22 x 10-12
2-Hexanone 7.50 x 10-04 NA NA 4.69 x 10-7 9.18 x 10-8 NA NA
4-Methyl-2-Pentanone 5.30 x 10-02 2.24 x 10-02 NA 3.31 x 10-5 6.49 x 10-6 1.48 x 10-03 NA
Kerosene 7.50 x 10-02 NA NA 4.69 x 10-5 9.18 x 10-6 NA NA
Tributyl Phosphate 1.80 x 10-09 NA NA 1.13 x 10-12 2.20 x 10-13 NA NA
Ammonia 2.20 x 10-05 2.86 x 10-02 NA 1.38 x 10-8 2.69 x 10-9 4.81 x 10-07 NA
Ag 1.20 x 10-14 NA NA 7.50 x 10-18 1.47 x 10-18 NA NA
As 8.00 x 10-13 NA 5.00 x 10+01 5.00 x 10-16 9.80 x 10-17 NA NA
Ba 4.00 x 10-15 1.43 x 10-04 NA 2.50 x 10-18 4.90 x 10-19 1.75 x 10-14 NA
Ca 2.70 x 10-14 NA NA 1.69 x 10-17 3.31 x 10-18 NA NA
Cu 6.20 x 10-15 NA NA 3.88 x 10-18 7.59 x 10-19 NA NA
Mg 5.30 x 10-15 NA NA 3.31 x 10-18 6.49 x 10-19 NA NA
Na 1.50 x 10-10 NA NA 9.38 x 10-14 1.84 x 10-14 NA NA
Pb 1.80 x 10-14 NA NA 1.13 x 10-17 2.20 x 10-18 NA NA
Sb 2.50 x 10-14 NA NA 1.56 x 10-17 3.06 x 10-18 NA NA
Se 1.60 x 10-14 NA NA 1.00 x 10-17 1.96 x 10-18 NA NA
AlO2 5.30 x 10-11 NA NA 3.31 x 10-14 6.49 x 10-15 NA NA
OH- 2.30 x 10-11 NA NA 1.44 x 10-14 2.82 x 10-15 NA NA
F- 4.30 x 10-13 NA NA 2.69 x 10-16 5.27 x 10-17 NA NA
Fe(OH)3 7.50 x 10-12 NA NA 4.69 x 10-15 9.18 x 10-16 NA NA
Cr(OH)3 2.00 x 10-12 NA NA 1.25 x 10-15 2.45 x 10-16 NA NA
Total 1.48 x 10-03 9.00 x 10-11
NA = not applicable
Specific information on continuous emissions of chemicals from facilities
considered in this EIS are available only for the NTF. Although this EIS
considers interim actions over a 5-year period, it is reasonable to assume
that these emissions could continue beyond that period. Accordingly, NTF
emissions are treated as chronic emissions based on the EPA guidance
(EPA 1989). Table E-16 shows HQ and ICR values for the maximum off-site
individual at the existing boundary calculated for NTF "extreme case"
emissions (see Section E.2). As indicated by the low values of HQ and ICR, no
non-carcinogenic systemic toxic and no carcinogenic health effects would be
expected from these emissions.
APPENDIX E REFERENCES
DOE, 1994a, Radionuclide Air Emission Report for the Hanford Site Calendar Year 1993, DOE/RL-94-51, United States Department of Energy, Richland, WA DOE, 1994b, National Emission Standards for Hazardous Air Pollutants Application for Approval to Construct Multi-Function Waste Tank Facility, Environmental Services, Westinghouse Hanford Company, DOE/RL-94-92, Rev. 0, UC-630, 721, United States Department of Energy, August 1994 DOE, 1993, Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements, Office of NEPA Oversight, U.S. Department of Energy DOE, 1992, User's Guide for CAP88-PC, Version 1.0,402-B-92-001, U.S. DOE, under Interagency Agreement DE-AIO1-90EH89071, U.S Environmental Protection Agency, Office of Radiation Programs, Las Vegas, NV EPA, 1994, Integrated Risk Information System (IRIS) Reference Guide. U.S. Department of Health and Human Services, Bethesda, MD EPA, 1989, Risk Assessment Guidance for Superfund Volume 1 Human Health Evaluation Manual (Part A), Office of Emergency and Remedial Response U.S. Environmental Protection Agency Washington, DC NRC, 1982, Atmospheric Dispersion Models For Potential Accident Consequence Assessments at Nuclear Power Plants, Regulatory Guide 1.145, U.S. Nuclear Regulatory Commission Regulatory Guide NUREG, 1991, PAVAN: An Atmospheric Dispersion Program for Evaluating Design Basis Accidental Releases of Radioactive Materials from Nuclear Power Stations, NUREG/CR-2858, Nuclear Regulatory Commission, Washington, D.C., Battelle Pacific Northwest Labs, Richland, WA PNL, 1993, Recommended Environmental Dose Calculation Methods and Hanford- Specific Parameters, PNL-3777 Rev 2, Pacific Northwest Laboratory, Richland, WA PNL, 1988a, GENII - The Hanford Environmental Radiation Dosimetry Software System, Napier, B. A., et al., Volume 1, Conceptual Representation, PNL-65684, Pacific Northwest Laboratory Operated for the U.S. Department of Energy by Battelle Memorial Institute PNL, 1988b, GENII - The Hanford Environmental Radiation Dosimetry Software System, Napier, B. A., et al., Volume 2, Users' Manual, PNL-65684, Pacific Northwest Laboratory Operated for the U.S. Department of Energy by Battelle Memorial Institute PNL, 1988c, GENII - The Hanford Environmental Radiation Dosimetry Software System, Napier, B. A., et al., Volume 3, Code Maintenance Manual, PNL-65684, Pacific Northwest Laboratory Operated for the U.S. Department of Energy by Battelle Memorial Institute WHC, 1995a, Tank Characterization Report for Double-Shell Tank 241-SY-102, WHC-SD-WM-ER-366, Rev. 0, June 9, 1995, Westinghouse Hanford Company, Richland, WA WHC, 1995b, CSTS PSAR, WHC-SD-W058-PSAR-001 Rev. 1, (DRAFT) Westinghouse Hanford Company, Richland, WA WHC, 1994a, Environmental Releases for Calendar Year 1993, WHC-EP-0527-3, UC- 630, U.S. DOE, Office of Environmental Restoration and Waste Management, DOE- AC06-87RL10930, Westinghouse Hanford Company, Richland, WA WHC, 1994b, Letter Report Tank Primary Ventilation Process Flow Diagram Description, W236A-T2-TR18, prepared for Westinghouse Hanford Company, Richland, WA by ICF Kaiser Hanford Company WHC, 1994c, Tank Farm HLW Compositions and Atmospheric Dispersion Coefficients for Use in ASA Consequence Assessments, WHC-SD-WM-SARR-016, Rev. by A.V. Savino and B.E. Hey, Westinghouse Hanford Company, Richland, WA WHC, 1993a, Tank 101-SY Window E Core Sample: Interpretation of Results, WHC- EP-0628, UC-610, U.S. DOE, Office of Environmental Restoration and Waste Management, Westinghouse Hanford Company, Richland, WA WHC, 1993b, Radionuclide and Chemical Inventories for the Double Shell Tanks, Oscarson, E. E. and Tusler, L.A., WHC-SD-WM-TI-543, July 1993
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