1. National Spent Nuclear Fuel Strategy Meeting April 15, 2009 Dawn Gillas Federal Program Manager Nuclear Material Programs Division DOE-SR SRS Spent Nuclear Fuel Acceptance Criteria

2. 2 SRS SNF Acceptance Criteria  Environmental Impact Statements  L-Area Authorization Basis  Spent Fuel Engineering Review – DOE Appendix A and B  Nuclear Criticality Safety Review

3. 3 Environmental Impact Statement DOE/EIS-203F – Programmatic SNF Management EIS,  Existing and newly generated Al-clad spent nuclear fuel will be consolidated at SRS – FRR and DRR Al-clad fuel – INL Al-clad fuel

4. 4 Environmental Impact Statement DOE/EIS-0218F – FRR SNF EIS  Applies solely to the following types of reactor fuels: – Foreign research reactor spent nuclear fuel which contains uranium enriched in the United States. Al-clad fuel where the uranium-235 content is >/= 20 percent by weight – Fuel meat configured as U-Al alloy, uranium-oxide, or uranium- aluminide. – Fuels containing significant quantities of uranium-233 are excluded Al-clad fuel where the uranium-235 content is </= 20 percent by weight – Fuel meat configured as uranium-silicide, uranium-oxide, or uranium- aluminide.

5. 5 L-Area Authorization Basis  All fuel received and stored in accordance with: – Technical Safety Requirements: S-TSR-L-00002, Technical Safety Requirements, Savannah River Site, L-Material Storage Facilities (U) – Documented Safety Analysis: WSRC-SA-2004-00002, L-Area Material Storage Facilities, Documented Safety Analysis (U)

6. 6 Spent Fuel Engineering Review  WSRC-TR-98-00199 – Foreign and Domestic Research Reactor Fuel Program Instructions for Engineering Reviews of SNF Receipts and Storage. – Reactor operators prepare and submit Appendix A data, drawings, fuel cycle history, pre and post fuel irradiation data. – Spent Fuel Engineering performs a consistency check of the data by calculation. – ANL/RERTR/TM-26 – Nuclear Mass Inventory, Photon Dose rate and Thermal Decay Heat of Spent Research Reactor fuel Assemblies. – Review of Nuclear Criticality Safety Evaluation and Nuclear Safety Data Sheet

7. 7 DOE Appendix A  Appendix A: Spent Nuclear Fuel Acceptance Criteria – Detailed Fuel Element and Fuel Assembly Data – Fuel fabrication drawings – Fuel condition statement – Summary of Reactor fuel cycle – Pre and Post irradiation radionuclide data – Used for FRR and DRR fuel data (no “contract” for DRR)

8. 8 DOE Appendix B  Appendix B: Transportation (Cask) Acceptance Criteria – FRR only – Shipment and transportation package requirements – Criteria for identification of Failed Fuel, Degraded Fuel or Materially Damaged Fuel – Radionuclide (SIP) test for failed fuel – Radiological survey requirements

9. 9 Nuclear Criticality Safety Review  WSMS-CRT-01-0116 – Nuclear Criticality Safety Methods Manual – Nuclear Criticality Safety Evaluation – Nuclear Safety Data Sheet Fuel is critically safe for cask unloading and storage Analysis can be cask specific – unload cask underwater, unload cask using the Shielded Transfer System, unload cask in air by hand (fresh or zero burn up) Storage system specific Safe for on site transfer  Nuclear Safety Data Sheet Approved by DOE-SR