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

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Response<br />

100<br />

CONSEQUENCE ANALYSIS<br />

The format for this environmental impact statement does not include a detailed descrip-<br />

tion <strong>of</strong> potential accidents for each waste treatment and storage technology. Individual<br />

accidents are described in DOE/ET-0028. Section 5.1 <strong>of</strong> that report discusses the storage<br />

<strong>of</strong> high-level liquid wastes. Section 5.2 discusses the storage <strong>of</strong> fuel residues.<br />

The release <strong>of</strong> 85Kr discussed on page M.52 <strong>of</strong> the draft Statement is due to antici-<br />

pated leakage from the pressurized storage cylinders. Large cylinder failures also contri-<br />

bute to this number. The total 85 Kr release <strong>of</strong> 2.2 x 107 curies over 30 years is less<br />

than that allowed in 40 CFR 190. Up to 50,000 curies per Gigawatt year <strong>of</strong> electrical gen-<br />

eration is allowed in that regulation.<br />

Accidents related to spent fuel storage are discussed in Section 4.8 <strong>of</strong> this final<br />

Statement. Further discussion is given in Section 5.7 <strong>of</strong> DOE/ET-0028. The basis for acci-<br />

dent analyses in this Statement is discussed in final Section 3.2. Sabatoge was not con-<br />

sidered in the development <strong>of</strong> accident scenarios. Credible loss <strong>of</strong> coolant accidents in the<br />

water basin storage <strong>of</strong> spent fuel, including tank failures, would result in no significant<br />

releases to the spent fuel facility.<br />

Draft Appendix N<br />

Issue<br />

The largest accident consequences presented in the GEIS occur during the transportation<br />

<strong>of</strong> radioactive wastes. Much <strong>of</strong> the detailed analysis is contained in DOE/ET-0029 as stated.<br />

An examination <strong>of</strong> these two documents reveals that accident release fractions, curie amount<br />

<strong>of</strong> isotopes that may be released, and doses to affected individuals are provided. However,<br />

some important details concerning accident assumptions are not given. These detailed<br />

assumptions involve the fraction <strong>of</strong> released material that is aerosolized in respirable<br />

form. Also missing are resuspension factors. In Appendix B, DOE/ET-0029, reference is<br />

given to other reports and computer codes that may contain these factors. These assumptions<br />

need to be outlined directly in DOE/ET-0029 so that factors in the degree <strong>of</strong> realism <strong>of</strong> the<br />

accident analysis can be more easily evaluated and the conclusion compared to other study<br />

results. (208-NRC)<br />

Response<br />

It was assumed that 100% <strong>of</strong> the released material was airborne and respirable. Resus-<br />

persion factors were not used. The release was assumed to last the length <strong>of</strong> time given for<br />

each accident. Released material was calculated directly as the product <strong>of</strong> release fraction<br />

times inventory. Additional information can be found in DOE/ET-0028.

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