Table 4-32. Worker radiological doses and resulting health effects associated with implementation of alternative A.a
Individual involved worker | ||||
Average annual dose (rem)b | 0.025 | 0.033 | 0.032 | 0.047 |
Associated probability of a fatal cancer | 1.9x10-5 | |||
30-year dose to average worker (rem) | 0.75 | 0.99 | 0.96 | 1.4 |
Associated probability of a fatal cancer | 3.0x10-4 | 4.0x10-4 | 3.9x10-4 | 5.7x10-4 |
All involved workersc | ||||
Annual doseb (person-rem) | 52 | 70 | 67 | 113 |
Associated number of fatal cancers | 0.021 | 0.028 | 0.027 | 0.045 |
30-year dose (person-rem) | 1,600 | 2,100 | 2,000 | 3,400 |
Associated number of fatal cancers | 0.62 | 0.84 | 0.81 | 1.4 |
Individual uninvolved workerb,d | ||||
Annual dose at 100 metere (rem) (associated probability of a fatal cancer) | 1.0x10-5
(4.1x10-9) | 0.0054
(2.1x10-6) | 3.7x10-3
(1.5x10-6) | 0.088
(3.5x10-5) |
Annual dose at 640 meters (rem) (associated probability of a fatal cancer) | 2.9x10-7
(1.1x10-10) | 1.6x10-4
(6.2x10-8) | 1.1x10-4
(4.3x10-8) | 0.0026
(1.0x10-6) |
30-year dose at 100 meters (rem) (associated probability of a fatal cancer) | 3.0x10-4
(1.2x10-7) | 0.16
(6.4x10-5) | 0.11
(4.5x10-5) | 2.7
0.0011 |
30-year dose at 640 meters (rem) (associated probability of a fatal cancer) | 8.6x10-6
(3.4x10-9) | 0.0047
(1.9x10-6) | 0.0033
(1.3x10-6) | 0.077
(3.1x10-5) |
a. Supplemental facility information is provided in Appendix E.
b. Annual individual worker doses can be compared with the regulatory dose limit of 5 rem (10 CFR 835) and with the SRS administrative exposure guideline of 0.8 rem. Operational procedures ensure that the dose to the maximally exposed worker remains as far below the regulatory dose limit as is reasonably achievable.
c. The number of involved workers is estimated to be 2,123 for the expected waste forecast; 2,104 for the minimum waste forecast; and 2,379 for the maximum waste forecast.
d. Dose is due to emissions from the transuranic waste characterization/certification facility except for the no-action alternative. Doses conservatively assume 80 hours per week of exposure. Exposures for a typical 40-hour work week would be approximately 50 percent of doses given in the table.
e. To convert to feet, multiply by 3.28.
Table 4-33. Radiological doses associated with implementation of alternative A and resulting health effects to the public.a
|
| ||||||||
Expected waste forecast | |||||||||
Offsite MEIe | |||||||||
Annual, millirem | 1.2x10-4 | 6.9x10-4 | 4.1x10-10 | 0.011 | 0.012 | ||||
30 years, millirem | 0.0037 | 0.021 | 0.025 | 1.2x10-8 | 0.33 | 0.021 | 0.35 | ||
Population | |||||||||
Annual, person-rem | 0.56 | 0.0068 | 0.57 | ||||||
30 years, person-rem | 17 | 0.20 | 17 | ||||||
Minimum waste forecast | |||||||||
Offsite MEI | |||||||||
Annual, millirem | 0.0057 | 0.0064 | |||||||
30 years, millirem | 0.17 | 0.19 | |||||||
Population | |||||||||
Annual, person-rem | 0.27 | 0.0068 | 0.28 | ||||||
30 years, person-rem | 8.2 | 0.20 | 8.4 | ||||||
Maximum waste forecast | |||||||||
Offsite MEI | |||||||||
Annual, millirem | 0.08 | 0.081 | |||||||
30 years, millirem | 2.4 | 2.4 | |||||||
Population | |||||||||
Annual, person-rem | 3.4 | 0.0068 | 3.4 | ||||||
30 years, person-rem | 100 | 0.20 | 100 |
a. Supplemental facility information is provided in Appendix E.
b. For atmospheric releases, the dose is to the population within 80 kilometers (50 miles) of SRS. For aqueous releases, the dose is to the people using the Savannah River from SRS to the Atlantic Ocean.
c. The doses to the public from total SRS operations in 1993 were 0.25 millirem to the offsite maximally exposed individual and 9.1 person-rem to the regional population. These doses, when added to the incremental doses associated with the waste management alternative given in this table, are assumed to equal total SRS doses. Source: Arnett, Karapatakis, and Mamatey (1994).
d. For the offsite maximally exposed individual, probability of a latent fatal cancer; for the population, number of fatal cancers.
e. MEI = maximally exposed individual.
g. Atmospheric releases for MEI and population include contribution from off-site facilities, which contribute less than 0.01% to the atmospheric releases reported here.
Table 4-34. Estimated number of excess latent cancers in the offsite population from nonradiological carcinogens emitted under alternative A.
|
(mg/m3) | (mg/m3) | (mg/m3) |
waste forecastf | ||||
Acetaldehyde | ||||||||
Acrylamide | ||||||||
Acrylonitrile | ||||||||
Arsenic Pentoxide | ||||||||
Asbestos | ||||||||
Benzene | ||||||||
Benzidine | ||||||||
Bis(chloromethyl)ether | ||||||||
Bromoform | ||||||||
Carbon Tetrachloride | ||||||||
Chlordane | ||||||||
Chloroform | ||||||||
Cr(+6) Compounds | ||||||||
Formaldehyde | ||||||||
Heptachlor | ||||||||
Hexachlorobenzene | ||||||||
Hexachlorobutadiene | ||||||||
Hydrazine | ||||||||
1,1,2,2-Tetrachloroethane | ||||||||
1,1,2-Trichloroethane | ||||||||
Toxaphene | ||||||||
1,1-Dichloroethene | ||||||||
Methylene Chloride | ||||||||
a. Source: EPA (1994).
b. Maximum annual boundary-line concentration.
c. Source: Stewart (1994).
d. Latent cancer probability equals unit risk factor times concentration times 30 years divided by 70 years.
e. Micrograms per cubic meter of air.
f. Under the maximum waste forecast, wastewater would be treated in the containment building, which would lower the amount of wastewater going to the Consolidated Incineration Facility. Therefore, slightly higher impacts may occur in the expected waste forecast than in the maximum waste forecast.
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