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

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5.37<br />

might be considered adequate to meet the intent <strong>of</strong> the requirements proposed by the NRC.<br />

Additional details <strong>of</strong> retrieval and recovery operations are provided in Appendix K.<br />

5.3.1.6 Decommissioning<br />

As mentioned in Section 5.3.1.5, after the readily retrievable period, rooms that have<br />

been filled to capacity with spent fuel are backfilled. The technique selected for the con-<br />

ceptual repository is to fill the rooms with previously excavated crushed rock or with spe-<br />

cially selected backfill material. Standard earth-moving equipment will be used to do this.<br />

This technique was selected as the most economical, and it reduces the amount <strong>of</strong> mined rock<br />

stored on the surface. With this technique, the rooms are backfilled to within 0.6 m <strong>of</strong> the<br />

ceiling with crushed rock at approximately 60% <strong>of</strong> its original density. Other backfill<br />

materials and methods <strong>of</strong> emplacement are discussed in Koplick et al. (1979).<br />

After all rooms have been filled with spent fuel and are backfilled, the remainder <strong>of</strong><br />

the repository underground areas are decommissioned. All corridors and underground areas<br />

are backfilled in the same manner as emplacement rooms. After this is completed, the repos-<br />

itory shafts are decommissioned by filling to the surface and sealing. Combinations <strong>of</strong><br />

crushed rock, clay, and concrete may be used for this purpose. Because the procedures to<br />

be used are highly site and media specific, they are not described in this generic Statement<br />

(see Koplick et al. (1979)).<br />

Repository decommissioning is complete when the surface facilities are decontaminated,<br />

perhaps dismantled, and the repository location is monumented.<br />

5.3.2 Reprocessing Fuel Cycle Repository<br />

A geologic repository operating for disposal <strong>of</strong> fuel reprocessing wastes in the repro-<br />

cessing fuel cycle would be required to receive high-level waste (HLW) and various remotely<br />

handled TRU (RH-TRU) and contact-handled TRU (CH-TRU) wastes. The characteristics <strong>of</strong> these<br />

wastes from reprocessing commercial fuel are described in Section 4.3. Defense program<br />

wastes could be accommodated in geologic repositories in a manner similar to that described<br />

here for these commercial fuel cycle reprocessing wastes. Characteristics and quantities<br />

<strong>of</strong> these wastes are described in Appendix I. While these latter wastes differ from those<br />

from LWR fuel reprocessing, the differences (mainly older and cooler, smaller quantities <strong>of</strong><br />

high-atomic-number actinides and different chemical form) produce wastes with lower radia-<br />

tion intensities and lower heat output. Thus, repository placement criteria would be less<br />

stringent for defense wastes than those for commercial wastes and they could therefore be<br />

accommodated in the same repositories.<br />

5.3.2.1 Design Bases<br />

As described in Section 5.3.1.1 for the once-through fuel cycle repository, waste<br />

emplacement is subject to thermal loading criteria for a given type <strong>of</strong> waste and rock. The<br />

limits listed in Table 5.3.4 for the reprocessing fuel cycle repository are two-thirds <strong>of</strong><br />

the calculated permissible criteria described in Appendix K.

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