Download
icp spent nuclear fuel examination n.
Skip this Video
Loading SlideShow in 5 Seconds..
ICP Spent Nuclear Fuel Examination PowerPoint Presentation
Download Presentation
ICP Spent Nuclear Fuel Examination

ICP Spent Nuclear Fuel Examination

149 Vues Download Presentation
Télécharger la présentation

ICP Spent Nuclear Fuel Examination

- - - - - - - - - - - - - - - - - - - - - - - - - - - E N D - - - - - - - - - - - - - - - - - - - - - - - - - - -
Presentation Transcript

  1. ICP Spent Nuclear Fuel Examination Barbara Beller for Kathleen Hain, PBS-12 FPD April 15, NSNFP Strategy Meeting

  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.

  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

  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.

  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).

  6. Gouge/Cut

  7. Damage/ Gouge

  8. Crack near Bottom of SST Element

  9. “Bulge” Dropped? (Al)

  10. Corrosion Suspect Dissimilar Metals of Weld Procedure (SST)

  11. Cut /Corrosion (Al)

  12. Dent/Corrosion/Pit (SST)

  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.

  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

  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