This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-15 and provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facility and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods beyond the original design lifetime of the storage facility that have become necessary owing to delays in the development of disposal facilities and the reduction in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. Guidance is provided on all stages in the lifetime of a spent fuel storage facility, from planning through siting and design to operation and decommissioning. The revision was undertaken by amending, adding and/or deleting specific paragraphs addressing recommendations and findings from studying the accident at the Fukushima Daiichi nuclear power plant in Japan.

• 1. INTRODUCTION
  • Background
  • Objective
  • Scope
  • Structure
• 2. PROTECTION OF HUMAN HEALTH AND THE ENVIRONMENT
• 3. ROLES AND RESPONSIBILITIES
  • General
  • Responsibilities of the government
  • Responsibilities of the regulatory body
  • Responsibilities of the operating organization
  • Responsibilities of the spent fuel owner
  • Accounting for and control of nuclear material and physical protection systems
• 4. MANAGEMENT SYSTEM
  • General
  • Spent fuel management
  • Resource management
  • Process implementation
• 5. SAFETY CASE AND SAFETY ASSESSMENT
  • General
  • Documentation of the safety case
• 6. GENERAL SAFETY CONSIDERATIONS FOR THE STORAGE OF SPENT NUCLEAR FUEL
  • General
  • Design of spent fuel storage facilities
    • Design process
    • Siting
    • Defence in depth
    • Structural integrity
    • Structural and mechanical loads
    • Thermal loads and processes
    • Time dependent material processes
    • Subcriticality
    • Heat removal
    • Confinement of radioactive material
    • Radiation protection
    • Layout
    • Handling
    • Ventilation systems
    • Communications
    • Instrumentation and control
    • Fire protection
    • Radioactive waste management
    • Lighting
    • Monitoring
    • Emergency preparedness
    • Support systems
  • Commissioning of spent nuclear fuel storage facilities
    • General
    • Commissioning stages
  • Operation of spent nuclear fuel storage facilities
    • General
    • Operational aspects
    • Maintenance, inspection and testing
    • Operational radiation protection
    • Characterization and acceptance of spent nuclear fuel
    • Fuel integrity
    • Record of documents
    • Retrieval of spent fuel
    • Transport after storage
    • Storage beyond the original design lifetime
  • Decommissioning of spent nuclear fuel storage facilities
• Appendix I SPECIFIC SAFETY CONSIDERATIONS FOR WET OR DRY STORAGE OF SPENT NUCLEAR FUEL
  • Subcriticality
    • Heat removal
    • Confinement of radioactive material
    • Radiation protection
    • Structure and layout
    • Materials
    • Handling
    • Subcriticality
    • Radiation protection
    • Heat removal
    • Confinement
    • Shielding
    • Dropping of loads
    • Subcriticality
    • Heat removal
    • Confinement of radioactive material
    • Radiation protection
    • Structure and layout
    • Materials
    • Handling
    • Subcriticality
    • Heat removal
    • Confinement
    • Shielding
    • Dropping of loads
• Appendix II CONDITIONS FOR SPECIFIC TYPES OF FUEL AND ADDITIONAL CONSIDERATIONS
• REFERENCES
• Annex I SHORT TERM AND LONG TERM STORAGE
• Annex II OPERATIONAL AND SAFETY CONSIDERATIONS FOR WET AND DRY STORAGE FACILITIES FOR SPENT NUCLEAR FUEL
• Annex III EXAMPLE OF THE SECTIONS IN OPERATING PROCEDURES FOR A SPENT NUCLEAR FUEL STORAGE FACILITY
• Annex IV SITE CONDITIONS, PROCESSES AND EVENTS FOR CONSIDERATION IN A SAFETY ASSESSMENT (EXTERNAL NATURAL PHENOMENA)
• Annex V SITE CONDITIONS, PROCESSES AND EVENTS FOR CONSIDERATION IN A SAFETY ASSESSMENT (EXTERNAL HUMAN INDUCED PHENOMENA)
• Annex VI POSTULATED INITIATING EVENTS FOR CONSIDERATION IN A SAFETY ASSESSMENT (INTERNAL PHENOMENA)
• CONTRIBUTORS TO DRAFTING AND REVIEW