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

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4.90<br />

4.8 ACCIDENT IMPACTS FOR PREDISPOSAL OPERATIONS<br />

The environmental impacts <strong>of</strong> accidents that occur during operation <strong>of</strong> predisposal sys-<br />

tems for both the once-through cycle and for the reprocessing cycle are described in this<br />

section. Potential accidents for the predisposal functions <strong>of</strong> treatment and/or packaging,<br />

transport, and storage are discussed here for both cycles.<br />

The environmental impacts <strong>of</strong> accidents described in this section are representative <strong>of</strong><br />

impacts from all postulated predisposal accidents. Using a methodology <strong>of</strong> accident identi-<br />

fication and classification that included an umbrella source term, we selected the largest<br />

source term in classified release categories for environmental impact analysis. Results <strong>of</strong><br />

this analysis are summarized here. Umbrella source terms are a conservative representation<br />

<strong>of</strong> releases that result from other accidents in their release category. A description <strong>of</strong><br />

the methodology used to develop and select umbrella source terms for impact analysis is<br />

given in Section 3.2.7. Unless specified otherwise, the maximum-exposed individual in the<br />

following discussion is considered to be a member <strong>of</strong> the general public, not a radiation<br />

worker. Accident impacts are generally greater to the public than to the workers.<br />

4.8.1 Accident Impacts for the Once-Through Cycle<br />

This section describes the impacts <strong>of</strong> postulated accidents for handling spent fuel<br />

until it is placed in the disposal facility. Operational and long-term accident impacts<br />

from spent fuel disposal are discussed in Sections 5.5 and 5.6.<br />

While extended storage <strong>of</strong> packaged spent fuel is not included in the example case, it<br />

may be desired if the operation <strong>of</strong> the disposal facility is delayed longer than is now<br />

expected. Therefore, analysis <strong>of</strong> accident impacts <strong>of</strong> packaged spent fuel storage are<br />

included as a contingency.<br />

4.8.1.1 Radiological Impacts from Spent Fuel Transportation Accidents<br />

Safety during transport <strong>of</strong> radioactive material depends primarily on shipping contain-<br />

ers. Shipping containers must meet standards established by the Department <strong>of</strong> Transpor-<br />

tation and the Nuclear Regulatory Commission. Containers holding significant amounts <strong>of</strong><br />

radioactive material must prevent loss or dispersal <strong>of</strong> radioactive contents, retain shield-<br />

ing efficiency, ensure nuclear criticality safety, and provide adequate heat dissipation<br />

under normal conditions <strong>of</strong> transport and under specified (hypothetical) accident damage test<br />

conditions (49 CFR 173.398). Improbable accidents that exceed the severity <strong>of</strong> hypothetical<br />

tests, accidents caused by equipment failures and accidents that are less severe than the<br />

test conditions were considered in this analysis to demonstrate the range <strong>of</strong> potential<br />

occurrences in a transportation environment. Impacts <strong>of</strong> these accidents are summarized<br />

below.<br />

Recent regulations for the shipment <strong>of</strong> spent fuel require that all shipments <strong>of</strong> spent<br />

fuel be escorted in transit; while severe accidents involving this material are still pos-<br />

sible, the chances <strong>of</strong> occurrence will be reduced with this required increased surveillance.<br />

Chances <strong>of</strong> a period <strong>of</strong> no action by emergency response personnel following an accident,

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