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

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Draft p. 3.1.90<br />

Issue<br />

152<br />

WASTE MANAGEMENT OPERATIONS<br />

To say that "all" the fission product tritium is released in reprocessing is not<br />

true. A large proportion <strong>of</strong> the tritium is bound to the Zircaloy cladding as the hydride.<br />

Only if the fuel is first roasted, as in voloxidation, will the hydride decompose, oxidize<br />

to water, and thus be removed from the cladding. (181)<br />

Response<br />

It was noted in the draft Statement, "the reference FRP operation results in the<br />

release to the atmosphere <strong>of</strong> essentially all the tritium present in the spent fuel." DOE<br />

meant the fuel itself (U0 2 ), but can see now that the wording could be construed as<br />

including the cladding. The wording in the final Statement (Section 4.3.4.2), "...the<br />

tritium present in the U0 2 portion <strong>of</strong> the spent fuel is released...," should be clearer.<br />

Based on discussions with personnel at Oak Ridge National Laboratory, the tritium bound<br />

to the cladding will be released during voloxidation only if a temperature higher than that<br />

currently planned for use with LWR fuels is employed.<br />

Draft p. 3.1.90<br />

Issue<br />

Several commenters noted that the storage and separation <strong>of</strong> 85 Kr may create a greater<br />

hazard than allowing it to disperse and the rationale for 85 Kr storage should be given.<br />

(6, 35, 154) One commenter recommended decay interval storage <strong>of</strong> 8 5 Kr. (28)<br />

Response<br />

Direct release <strong>of</strong> 85Kr versus its separation and storage did receive additional dis-<br />

cussion in the final Statement (see Section 4.4.4 and 4.7).<br />

The rationale for the storage <strong>of</strong> 85 Kr for 50 years before it is released is that the<br />

radioactive decay reduces the amount present after 50 years to only about 4% <strong>of</strong> that present<br />

initially; a factor <strong>of</strong> 25 reduction: in the amount released is thus achieved. The 50-year<br />

storage period is not necessarily optimum. However, it is well within our technical capa-<br />

bility, and reduces total krypton released to within EPA standards which limit 85 Kr<br />

releases to 50,000 Ci/GWe-yr (10 CFR 190.10).<br />

Draft p. 3.1.191<br />

Issue<br />

The quantity <strong>of</strong> 85Kr released to the air should be related to gigawatts <strong>of</strong> elec-<br />

tricity produced for comparison with uranium fuel cycle standards. (113-EPA)

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