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1. Legal and Governmental Framework
1-1 Legislation and regulations
1-1-1 Laws
1-1-2 Conventions
1-1-2-1 Early notification
1-1-2-2 Assistance
1-1-2-3 Nuclear liability
1-1-2-4 Nuclear safety
1-1-2-5 Joint Convention on Waste and Spent Fuel
1-1-3 Regulations and guides
1-2 Organization and authorities
1-2-1 Regulatory body
1-2-1-1 Regulatory framework
1-2-1-2 Regulatory reports
1-2-2 Operating organization
1-2-3 Response organization
1-2-3-1 Civil defence
1-2-3-2 Public health authorities
1-2-3-3 Technical support organization
1-2-3-4 Local municipality
1-2-3-5 Fire brigade
1-2-3-6 Police
1-2-4 Coordination and command
1-2-5 Independent evaluation of Accident & Consequences
2. Nuclear Instllation Status (NIS)
2-1 Site condition
2-1-1 Natural conditions
2-1-1-1 Earthquakes
2-1-1-1-1 Geotechnical conditions
2-1-1-1-2 Seismological conditions
2-1-1-2 Surface faulting
2-1-1-3 Meteorological events
2-1-1-3-1 Tornadoes
2-1-1-3-2 Cyclones
2-1-1-3-3 Winds
2-1-1-3-4 Snowing
2-1-1-3-5 Rain
2-1-1-3-6 Atmospheric dispersion
2-1-1-3-7 Sandstorm
2-1-1-3-8 Forest and steppe fire
2-1-1-4 Water reservoirs and flooding
2-1-1-4-1 Seas and lakes
2-1-1-4-2 Rivers
2-1-1-4-3 High tide
2-1-1-4-4 Storm surge
2-1-1-4-5 Seiche
2-1-1-4-6 Wind waves
2-1-1-4-7 Tsunami
2-1-1-4-8 Surface water dispersion
2-1-1-4-9 Subsurface water
2-1-1-5 Geotechnical hazards
2-1-1-5-1 Slope instability
2-1-1-5-2 Mines
2-1-1-5-3 Water wells
2-1-1-5-4 Oil and gas wells
2-1-1-5-5 Soil liquefaction
2-1-1-5-6 Groundwater
2-1-1-6 Complex natural disasters
2-1-2 Human induced event
2-1-2-1 Aircraft crashes
2-1-2-2 Explosions
2-1-2-3 Pipelines
2-1-2-4 Artificial reservoirs
2-1-2-5 Terrorism and sabotage
2-1-2-6 Complex human induced events
2-1-3 Regional infrastructure
2-1-3-1 Demographic
2-1-3-2 Industry
2-1-3-3 Agriculture
2-1-3-4 Substations and transmission lines
2-1-3-5 Transport
2-1-3-6 Communication infrastructure
2-2 Design
2-2-1 Layout
2-2-2 Design basis
2-2-3 Reactor core
2-2-4 Reactor coolant systems
2-2-5 Containment system
2-2-6 Reactor shutdown system
2-2-7 Reactivity control
2-2-7-1 Control rod system
2-2-7-2 Boron injection system
2-2-7-3 Poison control
2-2-7-4 Regulating systems
2-2-8 Instrumentation and control (I&C)
2-2-9 Power supply
2-2-10 Communication systems
2-2-11 Balance of the plant
2-2-12 Auxiliary systems
2-2-13 Steam and power conversion system
2-2-14 Heating, ventilation and air-conditioning systems (HVAC)
2-2-15 Radioactive waste management
2-2-16 Nuclear fuel management
2-2-17 Radiation protection and radiation monitoring
2-2-18 Fire protection
2-2-19 Water protection
2-2-20 Physical security
2-2-21 Safety structures, systems and components (SSCs)
2-2-22 Accident management SSCs
2-2-23 Essential support systems
2-3 Operation
2-3-1 Utility
2-3-1-1 Organization structure, roles and responsibilities
2-3-1-2 Staffing
2-3-1-3 Personnel training
2-3-1-4 Operational procedures
2-3-1-5 Performance indicators
2-3-1-6 Radioactive discharges
2-3-1-7 Radiation protection
2-3-1-8 Communication means (external)
2-3-1-9 Configuration management
2-3-2 Fuel management
2-3-2-1 Fresh fuel
2-3-2-2 Spent fuel
2-3-2-3 Fuel material accountancy and safeguards
2-3-3 Waste management
2-3-3-1 Liquid waste
2-3-3-2 Solid waste
2-3-4 Long term operation management
2-3-4-1 Modification
2-3-4-2 Ageing management
2-3-4-3 Periodic safety review (PSR)
3. Accident Management
3-1 Accident management planning (Preparation)
3-1-1 Safety analysis results
3-1-1-1 External initiating events
3-1-1-2 Internal initiating events
3-1-2 Accident management strategy
3-1-2-1 Roles and responsibilities
3-1-2-2 Prevention of malfunction progression
3-1-2-3 Accident management guidelines
3-1-2-4 Personnel training
3-2 Accident management implementation
3-2-1 Safety function maintenance
3-2-2 Confining of radioactivity
3-2-3 Power supply maintenance
3-2-4 Ultimate heat sink maintenance
3-2-5 I&C for accident management
3-2-6 Long term safe condition
3-2-7 Communication for accident management
3-2-8 Fire protection
3-2-9 Water resistance
4. Emergency Preparedness and Response
4-1 Emergency preparedness
4-1-1 Hazard assessment
4-1-1-1 Methodology
4-1-1-2 Precautionary action zone
4-1-1-3 Urgent protective action planning zone
4-1-1-4 Broad planning
4-1-1-5 Food restriction zone
4-1-2 Protection strategy
4-1-2-1 Generic criteria and reference level
4-1-2-2 Operational criteria
4-1-2-3 Processes and actions
4-1-3 Training and drills
4-1-4 Exercise
4-1-5 Logistical support and facilities
4-1-5-1 Equipment and supplies
4-1-5-2 Infrastructure (facilities) on-site
4-1-5-3 Infrastructure (facilities and locations) off-site
4-1-6 Plans and procedures
4-1-6-1 Facility plans and procedures
4-1-6-2 Local and regional plans and procedures
4-1-6-3 National plan and procedures
4-1-6-4 Bilateral and multilateral arrangements
4-2 Emergency response
4-2-1 Notifying
4-2-1-1 Emergency classification
4-2-1-2 Notification points
4-2-2 Communication
4-2-2-1 With public and mass media
4-2-2-2 Among involved organizations and responders
4-2-3 Protective actions
4-2-3-1 Evacuation of non-essential personnel on-site
4-2-3-2 Evacuation of population
4-2-3-3 Sheltering
4-2-3-4 Iodine thyroid blocking
4-2-3-5 Relocation
4-2-3-6 Access restrictions
4-2-3-7 Decontamination
4-2-3-8 Food and commodities restrictions
4-2-3-9 Land use restrictions
4-2-3-10 Actions to prevent inadvertent ingestion
4-2-3-11 Actions to protect trade and commercial interest
4-2-4 Emergency workers
4-2-4-1 Designation and registration
4-2-4-2 Provision of information
4-2-4-3 Access regime
4-2-4-4 Personal protection
4-2-4-5 Monitoring equipment
4-2-4-6 Medical care provision
4-2-4-7 Iodine thyroid blocking
4-2-4-8 Decontamination
4-2-4-9 Protection of eyes
4-2-4-10 Health surveillance
4-2-4-11 Guidance levels
4-3 Monitoring and assessment
4-3-1 On-site monitoring
4-3-1-1 Radiation survey instruments
4-3-1-2 Radiation survey methodology
4-3-1-3 Occupational dose monitoring
4-3-1-4 Individual dose reconstruction
4-3-1-5 Radiation survey of environment
4-3-2 Off-site monitoring
4-3-2-1 Radiation survey instruments
4-3-2-2 Radiation survey methodology
4-3-2-3 Population dose monitoring
4-3-2-4 Radiation survey of environment
4-3-2-5 Radiation survey of foods, drinking water and other commodities
4-3-2-6 Radiation survey of biota
4-4 Decontamination and recovery
4-4-1 On-site decontamination
4-4-1-1 Limitation of radioactivity spread
4-4-1-2 Building decontamination
4-4-1-3 Site decontamination
4-4-1-4 HVAC decontamination
4-4-1-5 Electrical, I&C decontamination
4-4-1-6 Waste management
4-4-1-7 Dust suppression
4-4-1-8 Secondary contamination
4-4-2 Off-site decontamination
4-4-2-1 Dust suppression
4-4-2-2 Building decontamination
4-4-2-3 Area decontamination
4-4-2-4 Settlement decontamination
4-4-2-5 Waste management
4-4-3 Transition to long term recovery
4-4-3-1 Transferring responsibilities, data and information
4-4-3-2 Consequence assessment
4-4-3-3 Conditions to be met
4-4-3-4 Stakeholder involvement
4-4-3-5 Adjusting protective actions
4-5 Medical response
4-5-1 Medical radiological triage
4-5-2 Immediate medical examination
4-5-3 Ambulance transportation
4-5-4 Medical treatment
4-5-5 Consultation
4-6 Emergency and response analysis
4-6-1 Reconstruction
4-6-2 Root causes analysis
4-6-3 Safety implications
4-6-4 Corrective actions
5. Scientific and Technical Support
5-1 Accident phenomena and progression
5-1-1 Zone diagnostics
5-1-1-1 Radiation survey/monitoring/energy spectra
5-1-1-2 Thermodynamic survey/monitoring
5-1-2 Fuel condition diagnostics
5-1-2-1 Sampling, samples
5-1-2-2 Experimental and/or numerical analysis/simulation
5-1-3 Reactor processes modelling
5-1-3-1 Theoretical modelling/analysis
5-1-3-2 Experimental modelling/analysis
5-1-3-3 Numerical modelling/analysis
5-2 Methods for decontamination
5-2-1 Methods for solid
5-2-2 Methods for liquid
5-2-3 Methods for gas
5-3 Waste management
5-3-1 Solid waste
5-3-2 Liquid waste
5-3-3 Gaseous waste
5-4 Robotics for emergency
5-4-1 Robotics for radiation survey
5-4-2 Robotics for restoration
5-4-3 Robotics for decontamination
5-5 Decommissioning
5-5-1 Radiation and engineering survey
5-5-2 Damaged fuel decommissioning programme
5-5-3 Decommissioning goals
5-5-4 Decommissioning planning
5-5-5 Radiological protection for decommissioning
5-5-6 Focused training programme
5-5-7 Environmental protection and remediation
5-5-8 Waste decommissioning programme
5-5-9 Safety regulation
5-5-10 Emergency response programme in decommissioning
5-5-11 Fuel material accountancy
5-6 Long term programme development
5-6-1 Prediction and prognosis
5-6-2 Territory zoning
5-6-3 Dose restriction
5-6-4 Hygienic standards
5-6-5 Countermeasures
5-6-6 Long term living on contaminated areas
6. Accident Consequences
6-1 Consequences for environment
6-1-1 Radioactivity releases to environment
6-1-1-1 Atmosphere (gaseous) releases
6-1-1-2 Liquid discharge
6-1-1-3 Radioactivity fallout/deposition
6-1-1-4 Environment contamination
6-1-2 Impact on environment
6-1-2-1 Impact on fauna
6-1-2-2 Impact on flora
6-1-2-3 Impact on aquatic environments
6-1-3 Impact on food
6-1-4 R&D in environmental protection and restoration
6-1-4-1 Tools for accident consequences analysis
6-1-4-2 Forecast of environmental condition
6-2 Environment restoration
6-2-1 Decontamination
6-2-1-1 Separation
6-2-1-2 Removal of the source
6-2-1-3 Containment
6-2-1-4 Immobilization
6-2-2 Recultivation
6-2-2-1 Physical measures
6-2-2-2 Chemical measures
6-2-3 Waste management
6-2-3-1 Solids
6-2-3-2 Liquids
6-2-3-3 Gases
6-2-3-4 Volume reduction
6-3 Health consequences
6-3-1 Effects
6-3-1-1 Deterministic effects
6-3-1-2 Stochastic effects
6-3-1-3 Non-cancer diseases
6-3-1-4 Psychological effects
6-3-1-5 Effects of low dose radiation exposure
6-3-2 Medical care
6-3-3 Epidemiology assessment
6-3-3-1 Cohorts
6-3-3-2 Methodology
6-4 Social and economic consequences
6-4-1 Impact on agriculture
6-4-1-1 Restrictions on use of rural land and forests
6-4-1-2 Restriction on shipment of agricultural products
6-4-2 Impact on industry
6-4-3 Economic losses
6-4-4 Insurance
6-4-5 Social effects
6-4-6 Political and legal effects
6-4-7 Life of refugees
6-4-8 Ethnocultural effects
6-4-9 Public communication
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