Title: International Safety Standards for the Storage of Spent Fuel
1International 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
2Developments since 1994
- Safety standards developments
- Increased enrichment
- Increased burn up
- Advanced fuel design
- MOX
- Re-racking
- Burn up credit
- Storage gt design lifetimes
3(No Transcript)
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- 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
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)
7GENERAL
- 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
10OBJECTIVE
- Up-to-date guidance on design, operation and
safety case for all storage facilities - Consider different fuel types NPP RRs
- Different periods, including gt 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
11SCOPE
- 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
12Basic Safety Standards
- Workers and public
- Present and future generations
- Normal and accident conditions
- Justification
- Dose and risk limitation - constraints
- Optimization of protection
13Safety Case
14Assessments
? 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
Non radiological Environmental Impact
Non-radiological Operational Safety
Site / Engineering
Management System
Radiological impact
Scenarios
Models
Calculations
Limits, controls conditions
Integration of Safety Arguments Normal operation,
anticipated operational ocurrences, accidents,
waste treatment and waste product
15Conclusion
- Guidance on
- Roles and responsibilities
- Design
- Operation
- Decommissioning
- Safety case
- Need for inter-comparison and harmonization of use
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