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

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4.92<br />

Severe accidents resulting from extreme impacts and a prolonged loss <strong>of</strong> cooling to a<br />

design load <strong>of</strong> fuel assemblies could release significant amounts <strong>of</strong> radioactive material.<br />

Such an accident was estimated to occur once every 50,000 years. Seventy-year accumulated<br />

doses to the maximum-exposed individual <strong>of</strong> 130 rem and 140 man-rem to local populations<br />

excluding the maximum-exposed individual would result from such an accident involving<br />

6-month cooled fuel. However, with fuel that has been cooled for several years before ship-<br />

ment (as planned for the once-through fuel cycle), an accident <strong>of</strong> this severity is not<br />

plausible. In a separate study <strong>of</strong> fuel transportation accidents (DOE/EIS-0015), it is<br />

reported that a maximum-exposed individual would receive a 50-yr accumulated dose <strong>of</strong> only<br />

about 0.4 rem from such an accident involving 4-yr cooled fuel (0.6 rem for a 70-yr dose).<br />

4.8.1.2 Radiological Impacts from Unpackaged Spent Fuel Storage Accidents<br />

The example concept for interim spent fuel storage is a 3000-MTHM capacity away-from-<br />

reactor storage facility (AFR). Eighteen accidents were postulated for the receipt and<br />

storage <strong>of</strong> unpackaged spent fuel at an AFR: eight minor, seven moderate and three severe.<br />

Accident details are described in DOE/ET-0028, Section 5.7. Eight accidents were determined<br />

to have potential for release <strong>of</strong> radioactive material. Four <strong>of</strong> the eighteen accidents relate<br />

to the operation <strong>of</strong> <strong>of</strong>f-gas systems at the AFR. These accidents are not discussed here<br />

because releases from this system would be smaller than accidental releases from the dissol-<br />

ver <strong>of</strong>f-gas system in the fuel reprocessing plant (Section 4.8.2.1) that were designated as<br />

the umbrella source terms. (Those releases result in an estimated 70-yr accumulated dose to<br />

the maximum-exposed individual <strong>of</strong> 2 x 10 -3 rem.)<br />

Releases resulting from minor accidents were added to expected annual operational<br />

releases for this facility based on their estimated frequencies.<br />

Moderate accidents include fuel-handling mistakes, dropped transport casks and uncon-<br />

trolled venting <strong>of</strong> rail casks. Releases from these accidents are smaller than those from a<br />

packaging facility accident, which is designated as the umbrella source term discussed in<br />

Section 4.8.1.3. (Those releases result in less than 3 x 10 -5 rem accumulated dose to the<br />

maximum-exposed individual during the 70 years after the accident.)<br />

A strike by a design-basis tornado, a criticality event in storage, and a loss <strong>of</strong> cool-<br />

ing were considered severe accidents at an AFR. The postulated criticality is estimated to<br />

occur only once every 100,000 years and results in an estimated 70-yr dose to the maximum-<br />

exposed individual <strong>of</strong> 5 x 10-2 rem.<br />

4.8.1.3 Radiological Impacts Due. to Accidents at a Fuel Packaging Facility<br />

A fuel packaging facility (FPF) will be required to prepare fuel for disposal in the<br />

once-through cycle. The fuel packaging facility may be colocated with either the AFR, a<br />

packaged fuel storage facility or a spent fuel disposal facility. Radiological impacts<br />

that result from accidents at the packaging facility are not dependent on its location.

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