Table 4-73. Worker radiological doses and resulting health effects associated with implementation of alternative B.a
Individual involved worker | ||||
Average annual dose (rem)b | 0.025 | 0.036 | 0.058 | |
Associated probability of a fatal cancer | 1.0x10-5 | 1.5x10-5 | 1.4x10-5 | 2.3x10-5 |
30-year dose to average worker (rem) | 0.75 | 1.1 | 1.1 | 1.7 |
Associated probability of a fatal cancer | 3.9x10-4 | 4.4x10-4 | 4.3x10-4 | 6.9x10-4 |
All involved workersc,b | ||||
Annual dose (person-rem) | 79 | 76 | 144 | |
Associated number of fatal cancers | 0.021 | 0.032 | 0.030 | 0.058 |
30-year dose (person-rem) | 1,600 | 2,400 | 2,300 | 4,300 |
Associated number of fatal cancers | 0.62 | 0.95 | 0.91 | 1.7 |
Individual uninvolved workerd,b | ||||
Annual dose at 100 meterse (rem)
(associated probability of a fatal cancer) | 1.0x10-5 (4.1x10-9) | 0.0054f
(2.1x10-6) | 0.0037f
(1.5x10-6) | 0.088f
(3.5x10-5) |
Annual dose at 640 meters (rem)
(associated probability of a fatal cancer) | 2.9x10-7 (1.1x10-10) | 2.1x10-4g
(8.4x10-8) | 1.7x10-4g
(6.8x10-8) | 0.0026f
(1.0x10-6) |
30-year dose at 100 meters (rem)
(associated probability of a fatal cancer) | 3.0x10-4 (1.2x10-7) | 0.16f
(6.4x10-5) | 0.11f
(4.5x10-5) | 2.7f
(0.0011) |
30-year dose at 640 meters (rem) (associated probability of a fatal cancer) | 8.6x10-6 (3.4x10-9) | 0.0063g
(2.5x10-6) | 0.0051g
(2.0x10-6) | 0.077f
(3.1x10-5) |
a. Supplemental facility information is provided in Appendix E.
b. Annual individual worker doses can be compared with the annual regulatory dose limit of 5 rem (10 CFR 835) and with the SRS administrative exposure guideline of 0.8 rem. Operational procedures will ensure that the dose to the maximally exposed worker will remain as far below the regulatory dose limit as is reasonably achievable.
c. The number of involved workers is estimated to be 2,154 for the expected waste forecast, 2,134 for the minimum waste forecast, and 2,501 for the maximum waste forecast.
d. Doses conservatively assume 80 hours per week of exposure.
e. To convert to feet, multiply by 3.28.
f. Dose is due to emissions from the transuranic waste characterization/certification facility.
g. Dose is due to emissions from the Consolidated Incineration Facility.
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