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International Safety Standards for the Storage of Spent Fuel

International Safety Standards for the Storage of Spent Fuel. PHIL METCALF International Conference on Management of Spent Fuel from Nuclear Power Reactors Vienna 31 May – 4 June 2010. Developments since 1994. Safety standards developments Increased enrichment Increased burn up

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International Safety Standards for the Storage of Spent Fuel

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  1. International Safety Standards forthe Storage of Spent Fuel PHIL METCALF International Conference on Management of Spent Fuel from Nuclear Power Reactors Vienna 31 May – 4 June 2010

  2. Developments since 1994 • Safety standards developments • Increased enrichment • Increased burn up • Advanced fuel design • MOX • Re-racking • Burn up credit • Storage > design lifetimes

  3. Storage of Spent Nuclear Fuel Safety Case & Assessment Predisposal DS 248

  4. Government responsibilities • National policy & strategy • Regulatory responsibilities • Operator responsibilities • Safety/Security • Interdependences • Management systems • Waste minimization • Characterization and classification • Waste treatment • Waste storage • Waste acceptance for processing, storage and/or disposal • Prepare safety case and supporting safety assessment • Safety case scope and regulatory compliance • Safety case documentation • Periodic safety review • Facilities location and design • Facility construction and commissioning • Facilities operation, maintenance, emergency preparedness • Decommissioning • Nuclear safeguards • Existing facilities

  5. Storage of Spent Nuclear Fuel 1. INTRODUCTION 2. PROTECTION OF HUMAN HEALTH AND THE ENVIRONMENT 3. ROLES AND RESPONSIBILITIES GENERAL GOVERNMENT OPERATOR SAFEGUARDS & PHYSICAL PROTECTION SYSTEMS 4. MANAGEMENT SYSTEM SPENT FUEL MANAGEMENT RESOURCE MANAGEMENT PROCESS IMPLEMENTATION 5. SAFETY CASE AND SAFETY ASSESSMENT DOCUMENTATION OF THE SAFETY CASE 6. GENERAL SAFETY CONSIDERATIONS FOR STORAGE OF SPENT FUEL GENERAL DESIGN COMMISSIONING OPERATION DECOMMISSIONING

  6. APPENDICES I SPECIFIC SAFETY CONSIDERATIONS WET & DRY STORAGE II CONDITIONS FOR SPECIFIC FUEL TYPES ANNEXES I SHORT TERM AND LONG TERM STORAGE II OPERATIONAL SAFETY CONSIDERATIONS FOR WET AND DRY STORAGE III EXAMPLES OF OPERATING PROCEDURES IV RELATED IAEA SAFETY STANDARDS PUBLICATIONS V SAFETY ASSESSMENT (EXTERNAL NATURAL PHENOMENA) VI SAFETY ASSESSMENT (EXTERNAL HUMAN INDUCED PHENOMENA) VII POSTULATED INITIATING EVENTS (INTERNAL PHENOMENA)

  7. GENERAL • May be considered waste or resource – safety issues the same – differing circumstances; • Open fuel cycle – direct disposal • Closed fuel cycle – reprocessing • Uncertain • All involve storage – months to decades • Sometimes uncertain lifetime • Wet or dry storage (facility or casks)

  8. Safety ensured by: • Containment of radionuclides • Criticality safety • Heat removal • Radiation shielding • Inspection and retrievability • Functions ensured by • Proper siting/location • Design • Construction and commissioning • Operation • Decommissioning (considered in design)

  9. Storage not ultimate solution • Requires end point e.g. reprocessing or disposal to ensure safety • NPP design lifetime - few decades • +/-50 y experience of storage • +/-100 years design lifetimes used • Considering rate of industrial and institutional change, periods beyond 50 y deemed ‘long term’ in the context of this Safety Guide

  10. OBJECTIVE • Up-to-date guidance on design, operation and safety case for all storage facilities • Consider different fuel types NPP & RRs • Different periods, including > design lifetime • Guidance to meet Safety Requirements: • Safety of Nuclear Fuel Cycle Facilities • Predisposal Management of Radioactive Waste • Safety Assessment for Facilities and Activities • Management System for Facilities and Activities

  11. SCOPE • Co-located • Own sites • Not specifically operational storage • Water cooled, others e.g. gas cooled, RR • Degraded or failed fuel in canisters • No detailed guidance on physical protection • Security/safeguards interactions

  12. Basic Safety Standards • Workers and public • Present and future generations • Normal and accident conditions • Justification • Dose and risk limitation - constraints • Optimization of protection

  13. Safety Case DS 248 Safety Case & Assessment Predisposal

  14. Assessments  Stakeholder & Regulatory Involvement  • Safety Case Context • Safety objectives • Safety principles • Regulations • Safety Strategy • Waste treatment, minimization • Interdependencies • Shielding, containment, • Defence in depth  Management System  Management of uncertainty System Description Site and waste characteristics, Safety Functions, Design Options Iteration and design optimozatio Management System Non radiological Environmental Impact Non-radiological Operational Safety Site / Engineering Radiological impact Scenarios Models Calculations Limits, controls & conditions Integration of Safety Arguments Normal operation, anticipated operational ocurrences, accidents, waste treatment and waste product

  15. Conclusion • Guidance on: • Roles and responsibilities • Design • Operation • Decommissioning • Safety case • Need for inter-comparison and harmonization of use

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