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

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159<br />

WASTE MANAGEMENT OPERATIONS<br />

recirculating, refrigerated air is provided for each cell to remove the heat and to provide<br />

improved leak detection and containment in case <strong>of</strong> leaks. Other storage concepts could<br />

doubtless be developed in which the use <strong>of</strong> refrigerated air would be unnecessary.<br />

Draft p. 3.1.92<br />

Issue<br />

If only 10% <strong>of</strong> the krypton is released in the dissolver, where does the rest go? Would<br />

it not be released during shearing and dissolution? (181)<br />

Response<br />

DOE agrees that all <strong>of</strong> the krypton would be released to a gas phase during shearing<br />

and dissolution. The statement that, "Ten percent <strong>of</strong> the inventory <strong>of</strong> 85 Kr is released<br />

in the dissolver <strong>of</strong>f-gases." was meant to convey the information that we assumed that 10% <strong>of</strong><br />

the 85 Kr was not removed by the dissolver <strong>of</strong>f-gas treatment process and was released to the<br />

atmosphere.<br />

Draft p. 3.1.178<br />

Issue<br />

Where do the releases in draft Table 3.1.58 come from? Why is there a factor <strong>of</strong> 50<br />

difference in routine releases to air between Cs and 90 Sr? (154)<br />

Response<br />

The releases in draft Table 3.1.58 are based on releases during transportation,<br />

receipt, storage and packaging <strong>of</strong> spent fuel based on data contained in the support docu-<br />

ments DOE/ET-0028 and -0029. The difference in release factions for 137 Cs and 90 Sr are due<br />

to the release fractions contained in DOE/ET-0028. These release fractions are based on the<br />

higher leachability <strong>of</strong> cesium compared to strontium. This causes the larger release frac-<br />

tion for cesium which results in larger source terms and larger doses.<br />

Draft p. 3.1.184<br />

Issue<br />

One commenter suggested that the document provide support for the statement that no<br />

releases <strong>of</strong> radioactivity would occur during planned operation <strong>of</strong> the extended spent fuel<br />

storage facility (dry caisson options). (208-NRC)

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