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DOE1R1.-2001-29<br />
Draft l) Rcdlinc/StrikeowE<br />
prcmise for the Inadvertent intmder scenario was to<br />
ensure that the dose from a single acute exposure<br />
would not exceed 500 nuem. The 221-U Facility<br />
8<br />
9<br />
dose to an inadvertcnt inlruder in the presence of these<br />
types of contaminants is predicted to be above<br />
contains various levels of ndiologically contaminated<br />
equipment. fission products, contaminated building<br />
materials, and/or miscellaneous debris from the fuels<br />
10<br />
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12<br />
500 mrem for a single acute exposure for at least 500<br />
years.<br />
manufacturing process. The potential radiological<br />
Table 1. Representative Risks of 221-U Facility Contaminants.<br />
Contaminant<br />
Represenfatlvt-95S LiCL of<br />
'<br />
Human i:lealsh Risk b<br />
Nonndionuclides<br />
Contaminant Concenlrations (Industrial Scenarlo)<br />
Antimon 2.96+1-0.14 me/ke )J1=0.07+1-0.02<br />
Arie ni 50.3a/-23.3mJke NI=2+/-1:1CR-7.6xI7`+/.9.Sx10't<br />
jl&pRID<br />
Cadmium<br />
397 19 f1 ID:t.6g<br />
3.54+/.0.13 M:U<br />
111= 0.07 +/- 0.01<br />
III=0.33+/.001:1CRs1.7x 104 4-3.5 x 10's<br />
W' i<br />
l ead<br />
Mercury<br />
Sclcniurn<br />
SiLE<br />
Uranium<br />
2.100+/-349 ^/LS<br />
1.140+/-12S 3tSLp mc/ka<br />
1.190+/- 1173ri20 mclka<br />
0.2''_S+/.0.o5.y mg/Rg<br />
4 + mvJkg<br />
JjW_±L-J,4Q mgAcg<br />
HI=0A18+1-0.003<br />
Not Applicable; PRO = 353 mg/kg<br />
HI =50±/-S ;2^<br />
HI=O.oOrxt+/-o.0lx/i<br />
}u = 0.062 +/. 0.ais<br />
1. 4+/-<br />
HO=87+1-12<br />
TotallCRs2.Sx10++/-0.7x 04<br />
Radionuclides<br />
Americium-241<br />
Cesium-137<br />
6.4 x 10's+1- 3.1 x IO^S.32C,+7 pCi/g<br />
^ d^+ - 0.4 x pCVg<br />
ICR => 10'i+I•^<br />
ICR => 10' +/-<br />
Cobalt^fi 9.4 x 10' +/. 1.4 x l0'^ 437,000 pCi/g ICR s> 10' = +/- 0'-<br />
Europium-154 3.3 x 10''+/- 0.9 x 10' a3,6C-r6<br />
pCi/g ICR => 10' a +l- > 0'-<br />
Ncntunium-237 7.1 vi1 Q"+ l.4.6 x 10~ pCVg ICR => 10'=+/-> 10'-<br />
Plutonium-238 s a x I0'-+/- 0.9 x 10•'Z,qgg pCi/g It'R s 3.1- OeS x 10's3.3-a-iA'a<br />
Plutonium-239 J.4 x 10' +l-0.^3^3,;85+5 pCi/g ICR=> 1D+l-^jQ-<br />
Plutonium-240 3.3x 10"+/-0.6x_t0'!d,H3E+3 pCi/g ICR=>10+.><br />
Strontium-90<br />
Thorium-230<br />
2.3 +^ x lb ^iA3T+9<br />
pCi/g<br />
].1x 10'+l- 0.2 x 10't pCi/g<br />
ICR=> 10'<br />
LCM = 4<br />
+a><br />
0+- •<br />
Uranium-234 6. t x 10° 2^ +/- 2 x 10'I>i(rAOD pCJg ICR = - 6.I-a-iA's<br />
Uranium435 -':i,2G0 3 ^Vg ICR = 1.9 x 10' +/-1.1 x 10 s;a.{ a-i8^<br />
Uranium-238 4.0 x 10` +/- 1.1 x 10' 8B ^'Jg ICR= ItY^+/-O.R 2.8 x<br />
10^9.g w i9+<br />
TotallCR=>10's+- lo't<br />
'957 UCL vnluesBwe for individual contaminants were used to iweaninrI<br />
final feasibility study.<br />
sks as described in Appendix P-A-of the<br />
RJumerical values are not reported for risks greater than lo't because the linear equation for risk estimation Is only valid for<br />
eontaminant Intakes resulting in calculated risks below 104.<br />
iU =hazanlindrx<br />
liQ - haiani maxiem . aum of ha^ard^ndices<br />
ICR ainctementalearberrisk<br />
PRtI a pteiinilnary remediation goal<br />
I1Ci.= upper confidence limit<br />
13 Eeologleal Risk<br />
14 The 221-U Facility is within the industrial exclusive<br />
15 area Identified in the Ht:P E1S (DOFJEIS-0222-F).<br />
16 The area Immediately surrounding the 221-U Facility<br />
17 is highly disturbed and thus provides reduced-quality<br />
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7<br />
habitat for ecological communities and the<br />
establishment of food webs with a hierarchy of<br />
tcrrestrial receptors. In addition, there is little<br />
likelihood of ecological exposure to 221-U Facility<br />
contaminants via intrusion or releases at the present<br />
time. However, if remedial alternatives are not