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^<br />

^<br />

1<br />

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4<br />

5<br />

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7<br />

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 />

11<br />

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 />

18<br />

19<br />

20<br />

21<br />

22<br />

23<br />

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

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