Management of Commercially Generated Radioactive Waste - U.S. ...

4.85
TABLE 4.7.7. Dose to Regional Population Due to Operation of an FRP and a MOX-FFP
70-Year
Whole-Body (a)
Dose, man-rem
High-Level Wastes
Treatment--vitrification and encapsulation 8.6 x 102
Storage--water basin 1.2 x 10- 2
TRU Wastes
Treatment
Fuel residue--package without compaction 3.5 x 10- 5
Failed equipment and noncombustible waste--package
after decontamimation and disassembly of failed
equipment as required.
FRP 6.5 x 10- 3
MOX-FFP 1.2 x 10- 3
Combustible and compactable waste--incineration
FRP contact-handled 3.3 x 10-10
FRP remotely handled 2.8
MOX-FFP 1.6 x 10- 8
Wet wastes and particulate solids--cementation
FRP 1.1 x 10- 2
MOX-FFP 1.7 x 10- 4
Storage
uel residue--dry well 0
Other remotely handled--vault 0
Contact-handled--outdoor surface 0
Gaseous and Airborne Wastes
Treatment
FRP--filter and remove Ru, I, C, and Kr 8.3 x 10 3
MOX-FFP--filter 2.4 x 10- 5
Storage
Krypton at FRP site(b) 4.0 x 101
TOTAL 9.2 x 103
(a) The whole-body dose received by the same population over the 70-year
commitment period due to naturally occurring sources is 1 x 107 man-rem.
(b) The dose due to operation of the krypton storage facility is an 80-year
commitment which includes 30 years of collection plus 50 years of retention
before release.
3.7 x 10-6 man-rem/km per shipment of solidified HLW or fuel residue and 1.1 x 10 -6 man-
rem/km per shipment of other TRU wastes. The doses to the transport work force are
estimated to be 5 x 10-6 man-rem/km per shipment of solidified HLW or fuel residue and
5 x 10 - man-rem/km per shipment of other TRU wastes. Shipments of HLW and fuel residue
are assumed to be by rail and those of the other TRU wastes are assumed to be by truck.
Table 4.7.8 presents additional 70-year whole-body dose data. Included here are esti-
mates of the doses to the work force as well as to the regional population and also the
doses during transportation of the high-level and TRU wastes generated during the lifetimes
of the facilities.
Doses to the work force and the regional population during decommissioning will be 10%
of the 70-year total body dose resulting from operation of the facilities, assuming a safe
storage period of 30 years before dismantlement of the FRP.