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Idaho Cleanup Project_____________________
ICP Spent Nuclear Fuel Examination
Barbara Beller forKathleen Hain, PBS-12 FPD
April 15, NSNFP Strategy Meeting
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 2
History of SNF Examination• 1998 EM-60 memo to INL and SRS directed use of technically based criteria
for receipt of FRR SNF.– EM had little experience receiving FRR SNF.
– Criteria were based on National Spent Nuclear Fuel Program, Foreign Research Reactor Fuel Acceptance Criteria – Failed Fuel Report.
• Material control and accountability compliance requires verification of unique identifier for each SNF element.
• ICP cannot readily handle individual fuel elements to examine SNF at receiving/storage facility (CPP-603).
• ICP completes physical fuel examination at pre-loading and “accountability” at loading for both FRR and DRR SNF (2 trips). Tamper indicating device fixed, removed at receipt, buckets unloaded from cask.
• SNF identified as posing a potential risk to the receipt facility (at unloading or in the future i.e. 2035) is canned prior to loading.
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 3
Receipt Facility Considerations Leading to Examination
• Review of receipt of specific fuel against documented safety basis for fuel handling and storage at receipt facility.
• Evaluation of impact of (degraded) spent fuel condition on handling and interim storage at receipt facility.
• Planning and scheduling for fuel cask unloading, and handling for storage placement at receipt facility.
• Evaluation of monitoring of fuel under fuel management program for interim storage at receipt facility.
• Additional planning, as appropriate, for preparing fuel for ultimate disposition post-interim storage.
– Source Document:
Foreign Research Reactor Spent Fuel Return Program
U.S. DOE Experience in Planning, Receipt and Transportation
A Review and Lessons Learned
October, 2008
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 4
Elements of SNF Examination for Dry Storage by ICP Contractor• ICP contractor is responsible for operation of CPP-603 within the
approved nuclear safety authorization basis.
• Required Shippers Data review and approval required.
• Each SNF element is videotaped and written record of the visual inspection is completed (length, instrumentation, unusual attachments, as well as any damage).
• The unique fuel identifier is verified in addition to verification completed by the reactor site fuel handlers; tied to the fuel fabrication data.
• Any questions necessary for authorization basis compliance calculations are asked. (Any unexpected condition e.g. hose clamp.)
• Decision is made on which elements will require canning based on storage requirements at receipt facility.
• Coordinate with shipper concerning fuel position in basket.
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 5
Damaged or Compromised Spent Nuclear Fuel (SNF)• Normal reactor operations and fuel handling can result in damage to
SNF that may cause a release of radioactive contamination or fuel handling issues at receipt facility in the future.
• ICP has documented damage to the aluminum and stainless steel clad TRIGA and SNF received from Foreign Research Reactors (FRR) since 1997 and Domestic Research Reactors (DRR) since 2003:
– Corrosion, cuts, bulges, dents, scratches
• In addition, ICP requires canning of damaged SNF to prevent contamination of storage facilities, exposure to current and future workers and control during future characterization and packaging processes.
• On-site visual examination with the use of cameras is the method used to identify SNF that should be canned (360°, full length).
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 6
Gouge/Cut
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 7
Damage/ Gouge
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 8
Crack near Bottom of SST Element
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 9
“Bulge” Dropped? (Al)
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 10
Corrosion Suspect Dissimilar Metals of Weld Procedure (SST)
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 11
Cut /Corrosion (Al)
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 12
Dent/Corrosion/Pit (SST)
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 13
Early At Reactor Examination Pros
• Condition of SNF is known early enough to address any concerns.
• Loading issues can be resolved.– SNF is received in CPP-603 in a shipping basket and stored in the basket.
– SNF is not handled again until the basket is transferred to the future Idaho Spent Fuel Facility (TBD).
• Special equipment can be identified.
• Authorization basis issues can be resolved; SAR changes made and approved.
• Receipt procedures can be written to account for and issues unique to this shipment.
• Sufficient cans can be provided.
• Coordination with shipper.
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 14
Early At Reactor Examination Cons
• Expense– EM cost of travel to reactor and time at reactor.
– Reactor cost to handle SNF for examination; may be paid by NE/NNSA.
– Much of the work appears to be redundant.
• Contract interference– NE/NNSA contracts with reactor and shipper, remember Roles and Responsibility
– EM contract with receiver
• Political– Examination can be perceived as questioning nuclear regulation compliance
Idaho Cleanup Project
U.S. Department of EnergyIdaho Operations Office 15
New SNF Receipt Issue
• Regulatory Requirements and framework for fuel manufacturing, reactor operation and fuel storage.
• Documentation requirements are established – can data available fulfill our data needs?
• Is the paperwork available a “record” prepared under an acceptable QA program?
• Are the data needs different for and dependent on fuel disposition path (recycling or disposal)?
• References: 1) NRC Division of Spent Fuel Storage and Transportation, Interim Staff
Guidance - 1, Revision 2 Classifying the Condition of Spent Nuclear Fuel for Interim Storage and Transportation Based on Function
2) IAEA-TECDOC-1593
3) FRR Spent Fuel Return Program Lessons Learned October 2008
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