National Spent Nuclear Fuel Strategy Meeting April 15, 2009

Dawn GillasFederal Program ManagerNuclear Material Programs DivisionDOE-SR

SRS Spent Nuclear Fuel Acceptance Criteria

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SRS SNF Acceptance Criteria

Environmental Impact Statements L-Area Authorization Basis Spent Fuel Engineering Review

– DOE Appendix A and B

Nuclear Criticality Safety Review

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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

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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.

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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)

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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

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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)

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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

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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