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Weapons of Mass Destruction (WMD)

Table 4-78. Cumulative maximum SRS boundary-line ground-level concentrations for criteria pollutants (in micrograms per cubic meter of air). a







Criteria pollutant





Averaging time


Concentrations due to existing sitewide emissionsb (µg/m3)




Background concentrationsc (µg/m3)



Increased concentrations, alternative Bb,d
(µg/m3)


Increased concentrations, plutonium solutionse
(µg/m3)


Increased concentrations, spent nuclear fuelf
(µg/m3)
Increased concentrations, interim management nuclear materialsg (µg/m3)




Regulatory standardsh
(µg/m3)




Percent
of standardi (%)
Nitrogen oxides
 Annual6 80.79 0.3211.1 1.3100 27.5
Sulfur dioxide3 hours 82334 3.822.7 3.50.040 1,30066.7
24 hours 19617 0.810.33 0.490.0089 36558.8
Annual
143 0.050.006 0.020.00056 8021.3
Carbon monoxide1 hour 171
NAj
31.4522 3768 40,0000.8
8 hours
22
NA
27.072.7 5.116 10,0000.7
Total suspended particulates
Annual13 302.01 0.005<0.01
(k)
7560.0
Particulate matter24 hours 5134 4.610.16 0.4
(k)
15060.5
less than 10 microns in diameter
Annual3 220.10 0.0050.01
(k)
5050.2
Lead
Quarterly
4.0x10-4
0.011
2.8x10-5
(k)
(k)
(k)
1.50.8
Gaseous fluorides12 hours 2.0
NA
0.0019
0.0450.4 0.183.7 71.0
(as hydrogen24 hours 1.0
NA
9.3x10-4
0.0240.1 0.0952.9 42.1
fluoride)1 week 0.4
NA
7.0x10-5
0.00940.1 0.0371.60 34.2
Monthly 0.1
NA
9.0x10-5
0.00260.02 0.0100.80 16.6

a. The scope of cumulative impacts as displayed in this table is based on the best information available in 1994. DOE recognizes that other actions may be underway.

b. Source: Stewart (1994).

c. SCDHEC (1992)

d. Alternative B includes Defense Waste Processing Facility and Consolidated Incineration Facility operation.

e. Preferred alternative from F-Canyon Plutonium Solutions EIS (DOE 1994c).

f. Alternative 5 from the Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs EIS (DOE 1995d).

g. Preferred alternative from the Draft Interim Management of Nuclear Materials EIS (DOE 1995c).

h. SCDHEC (1976).

i. Percent of standard = 100 ¥ (actual + background + increment) divided by regulatory standard.

j. NA = not available.

k. Not reported.

Table4-80.Estimated maximum annual cumulative radiological doses and resulting health effects to offsite population and facility workers.



Offsite maximally exposed individual (rem)
Total collectivea (to 80­kilometer population) (person-rem)
All Workers
(person-rem)




Activity


Dose from airborne releasesb


Dose from aqueous releasesb



Total
doseb



Fatal cancer riskc


Dose from airborne releasesd
Dose from aqueous releasesd


Total dosed


Latent cancers fatalitiese




Dosed


Latent cancer fatalitiese
Waste Management-Alternative B 3.2x10-5 6.9x10-7 3.3x10-5 1.7x10-8 1.5 0.00681.5 7.5x10-4 81 0.032
Current SRS practices 1.1x10-4 1.4x10-4 2.5x10-4 1.3x10-7 7.6 1.59.1 0.0046 2630.11
Interim management of nuclear materialsf 0.000972.4x10-5 0.000995.0x10-7 40 0.0940 0.02 1270.051
Stabilization of plutonium solutionsg 8.61x10-6 2.9x10-7 8.9x10-6 4.5x10-9 0.38 3.7E-40.38 1.9x10-4 131 0.052
Defense Waste Processing Facilityh 1.0x10-6
NAi
 1.0x10-6 5.0x10-10 0.07
NAj
0.07 3.5x10-5 118 0.047
Plant Vogtlek3.7x10-7 1.7x10-4 1.7x10-4 8.5x10-8 0.047 0.00970.057 2.9x10-5
NA
NA
SRS spent nuclear fuell 4.0x10-4 1.0x10-4 5.0x10-4 2.5x10-7 16.0 2.418.4 0.0092 790.032
Total0.0015 4.4E-040.0020 9.9E-07 664.0 700.035 799 0.32

a. Collective dose: for the 80-kilometer (50-mile) population after atmospheric releases; for downstream users of Savannah River water after liquid releases.

b. Dose in rem.

c. Probability of an excess fatal cancer.

d. Dose in person-rem.

e. Incidence of excess latent fatal cancers.

f. Preferred alternative from the Draft Interim Management of Nuclear Materials EIS (DOE 1995c).

g. Source: DOE (1994c).

h. Source: DOE (1994d)

i. NA = not applicable. There are no direct radioactive releases to surface water from the Defense Waste Processing Facility operations.

j. NA = not applicable.

k. NRC (1994).

l. Highest values from Appendix C of DOE (1995d).

Table 4-81. Maximum SRS boundary-line concentrations (in micrograms per cubic meter of air) and cumulative public health impacts from carcinogenic emissions.




Pollutanta
Unit risk factor (latent cancers probability/µg/m3)b

SRS baseline (µg/m3)c


Alternative B (µg/m3)d


Spent nuclear fuel
(µg/m3)e
F-Canyon plutonium solutions
(µg/m3)
Interim management nuclear materials
(µg/m3)


Latent cancer probabilityf
Acetaldehyde2.2x10-6
N/A
1.4x10-7
N/Ag
N/A
N/A
1.3x10-13
Acrylamide0.0013
N/A
1.4x10-7
N/A
N/A
N/A
1.3x10-13
Acrylonitrile6.8x10-5 0.002
1.4x10-7
N/A
N/A
N/A
1.9x10-9
Arsenic pentoxide0.0043
N/A
7.1x10-7
N/A
N/A
N/A
6.7x10-13
Asbestos0.23
N/A
2.7x10-8
N/A
N/A
N/A
2.5x10-14
Benzene8.3x10-6 0.17
0.044
0.005
0.001
N/A
2.1x10-7
Benzidine0.067
N/A
1.4x10-7
N/A
N/A
N/A
1.3x10-13
Bis (chloromethyl) ether 0.062
N/A
1.4x10-7
N/A
N/A
N/A
1.3x10-13
Bromoform1.1x10-6 0.002
1.4x10-7
N/A
N/A
N/A
1.6x10-9
Carbon tetrachloride 1.5x10-5 2.6x10-4
1.2x10-5
N/A
N/A
N/A
2.6x10-10
Chlordane3.7x10-4 2.3x10-4
1.4x10-7
N/A
N/A
N/A
2.1x10-10
Chloroform2.3x10-5 0.62
0.003
N/A
N/A
N/A
5.9x10-7
Cr (+6) compounds0.012
N/A
4.9x10-9
N/A
N/A
N/A
4.4x10-15
Formaldehyde1.3x10-5 1.6x10-4
1.4x10-7
0.0013
N/A
N/A
1.3x10-9
Heptachlor0.0013
N/A
3.5x10-7
N/A
N/A
N/A
3.3x10-13
Hexachlorobenzene4.6x10-4
N/A
1.4x10-7
N/A
N/A
N/A
1.3x10-13
Hexachlorobutadlene 2.2x10-5
N/A
1.4x10-7
N/A
N/A
N/A
1.3x10-13
Hydrazine0.0049
N/A
1.4x10-7
N/A
N/A
N/A
1.3x10-13
1,1,2,2-Tetrachloroethane 5.8x10-5 9.9x10-5
2.8x10-6
N/A
N/A
N/A
9.6x10-11
1,1,2-Trichloroethane 1.6x10-5 0.002
1.4x10-7
N/A
N/A
N/A
1.9x10-9
Toxaphene3.2x10-4
N/A
3.5x10-7
N/A
N/A
N/A
3.3x10-13
1,1 Dichloroethene 5.0x10-5 6.3x10-6
2.7x10-5
N/A
N/A
N/A
3.1x10-11
Methylene chloride 4.7x10-7 1.31
1.4x10-7
0.0025
N/A
N/A
1.2x10-6
Total
2.0x10-6

a. Background values are not available because there is no ambient air monitoring existing for air toxics.

b. Source: EPA (1994).

c. Calculated maximum potential annual concentration from WSRC (1993b).

d. Alternative B includes Defense Waste Processing Facility and Consolidated Incineration Facility operations.

e. Spent nuclear fuel values are adjusted from 24-hour concentrations to annual concentrations.

f. Latent cancer probability adjusted for 30 years of waste management activities. Total probability for each pollutant equals unit risk factor x concentration x 30 years/70 years.

g. NA = not applicable.



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