Advanced Criteria Search

IMPORTANT NOTE. This Advanced Search capability is available to search the Safety Standards Series and most of the Nuclear Security Series publications. Use the topical search capability for these Series.


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This search capability provides you with very sophisticated search criteria. You may select also a combination of several criteria. When the  is displayed, it means that further sub-criteria are available should you wish to further refine your search. Because we have marked the e-version of the documents with these criteria as metadata, it is advised to use these primarily for defining your search and not the box with the full text search.

  •  Governmental, Legal and Regulatory Infrastructure for Safety
    •  National policy and strategy
      •  General
      •  National policy and strategy for decommissioning
      •  National policy and strategy for waste management
      •  Governmental responsibility for the disposal of radioactive waste
      •  International obligations and arrangements for international cooperation
    •  Legal and regulatory framework
      •  General
      •  Responsibilities of the regulatory bodies specific to occupational exposure
      •  Responsibilities of the government and the regulatory body specific to public exposure
      •  Responsibilities of the government specific to medical exposure
      •  Responsibilities of the regulatory body specific to medical exposure
      •  Responsibility of the regulatory body for the disposal of radioactive waste
      •  Responsibility of the regulatory body for the management of radioactive waste
      •  Emergency preparedness and response
      •  Waste management
      •  Decommissioning
      •  Protective actions to reduce existing or unregulated radiation risks
      •  Responsibilities of the government specific to existing exposure situations
      •  Responsibilities for remediation of areas with residual radioactive material
      •  Interfaces of safety with nuclear security and accounting and control
      •  Responsibility for safety
      •  Competence of all parties
      •  Provision of technical services
      •  Coordination of different authorities
    •  Regulatory Body
      •  Establishment of a regulatory body
      •  Independence of the regulatory body
      •  Organizational structure of the regulatory body
      •  Staffing and competence of the regulatory body
      •  Liaison of the regulatory body with advisory bodies and support organizations
      •  Use of external experts by the regulatory body
      •  Management system of the regulatory body
      •  Liaison between the regulatory body and authorized parties
      •  Stability and consistency of regulatory control
    •  Regulatory processes
      •  Demonstration of safety
      •  Review by the regulatory body
      •  Authorization/Notification
      •  Inspection
      •  Enforcement
      •  Establishing and revising regulation and guides
      •  Safety related records
      •  Regulatory control of radioactive discharges
      •  Feedback of operating experience, reporting incidents
      •  Communication and consultation with interested parties
  •  Leadership and Management for Safety
    •  Responsibility for safety
    •  Leadership
    •  Management systems
      •  General
      •  Integrated management system
    •  Goals, strategies, plans and policies
    •  Interested parties
    •  Graded approach
    •  Documentation of the management systems
    •  Resources required for safety
      •  Competence building, including strategy and infrastructure for education and training
      •  Material and financial resources
    •  Management of processes and activities
      •  Change management
      •  Communication
      •  Documents and records management
      •  General
      •  Management of supply chain
      •  Quality management
    •  Management of supply chain
    •  Measurement, assessment and improvement of management systems
      •  Identification of non-conformances
      •  Improvement and corrective actions
      •  Measurement and assessment
    •  Safety culture
  •  Radiation Protection and safety of radiation sources
    •  Definitions
    •  Principles of radiation protection
    •  Legal and regulatory framework
      •  General
      •  Responsibilities of the regulatory bodies specific to occupational exposure
      •  Responsibilities of the government and the regulatory body specific to public exposure
      •  Responsibilities of the government specific to medical exposure
      •  Responsibilities of the regulatory body specific to medical exposure
      •  Responsibilities of the government specific to existing exposure situations
      •  Responsibilities for remediation of areas with residual radioactive material
    •  Responsibility for safety
    •  Integrated management system
    •  Graded approach
    •  Authorization/Notification
    •  Exemption and clearance
    •  Justification of practices
    •  Optimization of protection and safety/Constraint
    •  Dose limits
    •  Dose limits for planned exposure situations
    •  Responsibilities for the safety assessment
    •  Verification of compliance
    •  Prevention and mitigation of accidents (general)
    •  Feedback of operating experience, reporting incidents
    •  Safety of radiation generators and radioactive sources
    •  Categories for sealed sources used in common practices
    •  Register of radioactive sources
    •  management of disused sources
    •  Import/export of sources
    •  Non medical imaging
    •  Occupational exposure
      •  Protection against occupational exposure
      •  Compliance by workers
      •  Cooperation between employers and registrants and licensees
      •  controlled and supervised areas
      •  Monitoring, assessing and recording of occupational exposure
      •  Workers health surveillance
      •  Information, instruction and training
      •  No benefits as substitutes for measures for protection and safety
      •  Pregnant women, embryo or foetus, breast-fed infants and persons under 18 years
    •  Public exposure
      •  Radioactive waste and discharges
      •  Source monitoring and environmental monitoring (all situations)
      •  Consumer products
    •  medical exposure
      •  Responsibilities of registrants and licensees to medical exposure
      •  Justification of medical exposures
      •  Optimization of protection and safety related to medical exposures
      •  Release of patients after radionuclide therapy
      •  Unintended and accidental medical exposures
      •  Records and periodic reviews for medical exposures
    •  Emergency situations
      •  Emergency preparedness and response
      •  Criteria for emergency preparedness and response/Reference levels
      •  Protecting emergency workers and helpers
      •  Transition to an existing exposure situation
    •  Existing exposure situations
      •  Justification for and optimization in existing exposure situations
      •  Reference level
      •  Exposure due to radon indoors
      •  Radionuclides in commodities
      •  Exposure in workplaces
    •  Control of orphan sources
  •  Safety Assessment
    •  Graded approach
    •  Scope of the safety assessment
    •  Responsibilities for the safety assessment
    •  Management of the safety assessment
    •  Purpose of the safety assessment
    •  Preparation of the safety assessment
    •  Assessment of the possible radiation risks
    •  Assessment of safety functions
    •  Assessment of site characteristics
    •  Assessment of provisions for radiation protection
    •  Assessment of engineering aspects
    •  Assessment of human factors
    •  Assessment of safety over the lifetime of a facility or activity
    •  Assessment of defence in depth
    •  Criticality safety/ reactivity control
    •  Scope of the safety analysis
    •  Deterministic and probabilistic approaches
      •  General
      •  Deterministic safety assessment
      •  PSA level 1
      •  PSA level 2
    •  Criteria for judging safety
    •  Uncertainty and sensitivity analysis
    •  Validation and verification of computer codes
    •  Use of operational experience
    •  Documentation of the safety assessment
      •  Format and content of the safety analysis report
    •  Independent verification
    •  Use of the results of the safety assessment
      •  General
      •  Maintenance, testing, surveillance and inspection programmes
      •  Operational procedures
      •  Staff competence
    •  Maintenance of the safety assessment
    •  Periodic safety review
  •  Safety of the Predisposal Management of Radioactive Waste
    •  Legal and regulatory framework
    •  National policy and strategy for waste management
    •  Responsibility of the regulatory body for the management of radioactive waste
    •  Responsibility for safety
    •  Interfaces of safety with nuclear security and accounting and control
    •  Interdependences among all steps in predisposal waste management
    •  Integrated management system
    •  Radioactive waste generation and control
    •  Characterization and classification of radioactive waste
    •  Processing of radioactive waste
    •  Storage of radioactive waste
    •  Radioactive waste acceptance criteria
    •  Preparation of the safety assessment
    •  Scope of the safety assessment
    •  Documentation of the safety assessment
    •  Radioactive waste and discharges
    •  Siting
    •  Design
      •  Design for radiation protection
      •  Instrumentation and control
      •  Provision for construction and commissioning
      •  Supporting systems
      •  Waste packages
    •  Commissioning programme
    •  Operation
      •  Containment of radioactive waste
      •  Criticality safety
      •  Emergency preparedness
      •  Maintenance, testing, surveillance and inspection programmes
      •  Operational limits and conditions
      •  Operational procedures
      •  Radiation monitoring
      •  Radioactive decay heat
    •  Decommissioning plan
  •  Safety of the Decommissioning
    •  Legal and regulatory framework
    •  National policy and strategy for decommissioning
    •  Responsibility for safety
    •  Selecting a decommissioning strategy
    •  Decommissioning plan
    •  Optimization of protection and safety
    •  Financing of decommissioning
    •  Integrated management system
    •  Graded approach
    •  Safety assessment for the decommissioning
    •  Conduct of decommissioning
    •  Completion of decommissioning, termination of authorization and release from regulatory control
    •  Radioactive waste management
    •  Emergency preparedness and response
  •  Preparedness and response for a nuclear or radiological accident
    •  Goals of emergency preparedness and response
    •  Establishing an emergency management system / legal and regulatory framework / assignment of responsibilities
      •  General
      •  Responsibilities of operating organizations
    •  Responsibilities / coordination of International organizations
    •  Hazard assessment/Emergency preparedness categories
    •  Protection strategy including generic criteria
    •  Managing emergency response operations
    •  Identifying and notifying a nuclear or radiological emergency and activating an emergency response
    •  Taking mitigatory actions (on-site and interface with off-site)
    •  Taking urgent/early protective actions and other response actions (both on-site and off-site and interface)
    •  Instructing, warning and informing the public affected or potentially affected
    •  Protecting emergency workers and helpers
    •  Managing the medical response
    •  General public communications
    •  Managing radioactive waste in a nuclear or radiological emergency
    •  Mitigating non-radiological consequences
    •  Requesting, providing and receiving international assistance
    •  Terminating the emergency
      •  Transition to a planned or an existing exposure situation
    •  Analysing the emergency and the emergency response
    •  Organization and staffing
    •  Coordination of emergency preparedness and response
    •  Plans and procedures
    •  Logistical support and facilities
    •  Training, drills and exercises
    •  Quality management programme
  •  Site Evaluation for safety
    •  Applying the safety principles and concepts
    •  Graded approach
    •  Management systems
    •  Responsibility for safety
    •  General requirements
      •  Evaluation process
      •  Confirmation of site suitability
      •  Site safety objectives
      •  Site and regional characteristics
      •  Site protection measures
      •  Data collection for natural hazards
      •  Insufficiency of historical data
      •  Evaluation of human induced external hazards
      •  Potential effects of the nuclear installation on population and the environment
      •  Feasibility of implementing emergency plans
    •  Hazard specific requirements
      •  Seismic ground motion and fault displacement
      •  Volcanic hazards
      •  Meteorological events
      •  Flooding hazards
      •  Geotechnical hazards
      •  Human induced hazards
      •  Hazards affecting the adequacy of an ultimate heat sink
    •  Site Characteristics and potential effects of the nuclear installation
      •  General
      •  Atmospheric dispersion
      •  Dispersion through surface water
      •  Dispersion through groundwater
      •  Population distribution
      •  Use of land and water
      •  Ambient radioactivity
    •  Monitoring and periodic re-evaluation
  •  Design of NPPs, RRs and FCFs for safety (select also the type of installation)
    •  Applying the safety principles and concepts
    •  Management of safety in design
      •  Responsibilities in the management of safety in design
      •  Management system for design
      •  Integrity of design of the plant throughout the lifetime
    •  Principal technical requirements
      •  Fundamental safety functions
      •  Radiation protection objective
      •  Design objective
      •  Application of defence in depth
      •  Interfaces of safety with nuclear security and accounting and control
      •  Proven engineering practices
      •  Safety assessment and design iteration
      •  Provision for construction/commissioning
      •  Features to facilitate radioactive waste management and decommissioning
    •  Design basis
      •  Categorization / Normal operation, Anticipated operational occurrences and accident conditions
      •  Design basis for items important to safety
      •  Design limits
      •  Postulated initiating events
      •  Internal hazards
      •  External hazards
      •  Engineering design rules
      •  Design basis accidents
      •  Design extension conditions/combination of failures
      •  Physical separation and independence of safety systems
      •  Safety classification
      •  Reliability of items important to safety
      •  Common cause failures
      •  Single failure criterion
      •  Fail-safe design
      •  Support service systems
      •  Operational limits and conditions for safe operation
    •  Design for safe operation over the lifetime of the plant
      •  Calibration, testing, maintenance, repair, replacement, inspection and monitoring of items important to safety
      •  Qualification of items important to safety
      •  Ageing management
    •  Human factors/Man machine interface
      •  Man machine interface
    •  Safety systems, and safety features for design extension conditions, of units of a multiple unit nuclear power plant
    •  Systems containing fissile material or radioactive material
    •  Nuclear power plants used for cogeneration of heat and power, heat generation or desalination
    •  Escape routes from the installation
    •  Communication systems at the installation
    •  Control of access to the installation
    •  Prevention of unauthorized access to, or interference with items important to safety
    •  Prevention of harmful interactions of systems important to safety
    •  Interactions between the electrical power grid and the plant
    •  Safety analysis of the plant design
      •  General
      •  Deterministic approach
      •  Probabilistic approach
    •  Reactor core and associated features
      •  Performance of fuel elements and assemblies
      •  Structural capability of the reactor core
      •  Control of the reactor core
      •  Reactor shutdown
    •  Reactor coolant systems
      •  Design of reactor coolant systems
      •  Overpressure protection of the reactor coolant pressure boundary
      •  Inventory of reactor coolant
      •  Cleanup of reactor coolant
      •  Removal of residual heat from the reactor core
      •  Emergency cooling of the reactor core
      •  Heat transfer to an ultimate heat sink
    •  Containment structure and containment system
      •  Containment system for the reactor
      •  Control of radioactive releases from the containment
      •  Isolation of the containment
      •  Access to the containment
      •  Control of containment conditions
    •  Instrumentation and control systems
      •  Provision of instrumentation
      •  Control systems
      •  Protection system
      •  Reliability and testability of instrumentation and control systems
      •  Use of computer based equipment in systems important to safety
      •  Separation of protection systems and control systems
      •  Control room
      •  Supplementary control room
    •  On-site emergency response facilities
    •  Emergency power supply and alternate power sources
    •  Supporting systems and auxiliary systems
      •  Performance of supporting systems and auxiliary systems
      •  Heat transport systems
      •  Process sampling systems and post-accident sampling systems
      •  Compressed air systems
      •  Air conditioning systems and ventilation systems
      •  Fire protection systems
      •  Lighting systems
      •  Overhead lifting equipment
    •  Other power conversion systems
      •  for NPPs: Steam supply system, feedwater system and turbine generators
    •  Treatment of radioactive effluents and radioactive waste
      •  Systems for treatment and control of waste
      •  Systems for treatment and control of effluents
    •  Fuel handling and storage systems
    •  Occupational radiation protection
      •  Design for radiation protection
      •  Means of radiation monitoring
  •  Commissioning and Operation of NPPs, RRs and FCFs for safety (select also the type of installation)
    •  Safety objective and principles
    •  The management and organizational structure of the operating organization
      •  Responsibility for safety
      •  Safety policy
      •  Management system
      •  Structure and functions of the operating organization
      •  Staffing of the operating organization
      •  Qualification and training of personnel
      •  Performance of safety related activities
        •  General
        •  Human factor
      •  Monitoring and review of safety performance
      •  Records and reports
    •  Operation
      •  Operational limits and conditions - Operating instructions
      •  Control of configuration
      •  Equipment qualification
      •  Operating procedures
      •  Operation control rooms and control equipment
      •  Material conditions and housekeeping
      •  Core management and fuel handling
      •  Accident management programme
      •  Emergency preparedness
      •  Fire safety
      •  Non-radiation-related safety/industrial safety
      •  Radiation protection
      •  Chemistry programme
      •  Management of modifications
      •  Feedback of operating experience, reporting incidents
      •  Periodic safety review
      •  Maintenance, testing, surveillance and inspection programmes
      •  Outage management
      •  Ageing management
      •  Programme for long term operation
      •  Management of radioactive waste
      •  Interfaces of safety with nuclear security and accounting and control
    •  Commissioning programme
    •  Decommissioning plan
    •  For Research Reactors
      •  Graded approach for Research Reactors
      •  Utilization and modification of Research Reactors
      •  Provision for extended shutdown of Reserach Reactors
      •  Experimental devices in Research Reactors
    •  For Fuel Cycle Facilities
      •  Graded approach for Fuel Cycle Facilities
      •  Criticality safety in Fuel Cycle Facilities
      •  Radiolysis
      •  Non radiological hazards
      •  Industrial and Chemical safety
      •  Radioactive decay heat
  •  Safe Disposal of radioactive waste
    •  Governmental responsibility for the disposal of radioactive waste
    •  Responsibility of the regulatory body for the disposal of radioactive waste
    •  Responsibility of the regulatory body for the management of radioactive waste
    •  Responsibility for safety
    •  Management systems
    •  General safety approach and design concept
      •  Application of the fundamental safety principles
      •  Radiation protection in the operational period
      •  Radiation protection in the post-closure period
      •  Environmental and non-radiological concerns
      •  Importance of safety in the development and operation of a disposal facility
      •  Passive means for the safety
      •  Understanding of a disposal facility and confidence in safety
      •  Multiple safety functions
      •  Containment of radioactive waste
      •  Isolation of radioactive waste
      •  Surveillance and control of passive safety features
      •  Interfaces of safety with nuclear security and accounting and control
      •  Waste acceptance in a disposal facility
    •  Safety case and safety assessment
      •  Preparation, approval and use of the safety case and safety assessment
      •  Scope of the safety case and safety assessment
      •  Documentation of the safety case and safety assessment
    •  Development, operation and closure
      •  Framework. Step by step development and evaluation
      •  Site characterization for a disposal facility
      •  Design of a disposal facility
      •  Construction of a disposal facility
      •  Operation of a disposal facility
      •  Closure of a disposal facility
    •  Monitoring programmes at a disposal facility
    •  The period after closure and institutional controls
  •  Safe transport of radioactive material
    •  Definitions
    •  General provisions
      •  Radiation protection
      •  Emergency response
      •  Management system
      •  Compliance assurance
      •  Non-compliance
      •  Special arrangement
      •  Training
    •  Activity limits and classification
      •  General provisions
      •  Basic radionuclide values
      •  Determination of basic radionuclide values
      •  Classification of material
      •  Classification of packages
      •  Special arrangement
    •  Requirements and controls for transport
      •  Requirements before the first shipment
      •  Requirements before each shipment
      •  Transport of goods
      •  Other dangerous properties of content
      •  Requirements and controls for contamination and for leaking packages
      •  Requirements and controls for transport of excepted packages
      •  Requirements and controls for transport of LSA material and SCO in industrial packages or unpackages
      •  Determination of transport index
      •  Criticality safety index. Limits on transport index, criticality safety index and radiation levels
      •  Categories
      •  Marking, labelling and placarding
      •  Consignor's responsibilities
      •  Transport and storage in transit
      •  Custom operation
      •  Undeliverable consignments
      •  Retention and availability of transport documents by carriers
    •  Requirements for radioactive material and for packagings and packages
      •  Requirements for radioactive material
      •  Requirements for material excepted from fissile classification
      •  General requirements for all packagings and packages
      •  Additional requirements for packages transported by air
      •  Requirements for excepted packages
      •  Requirements for industrial packages
      •  Requirements for packages containing uranium hexafluoride
      •  Requirements for Type A packages
      •  Requirements for Type B(U) packages
      •  Requirements for Type B(M) packages
      •  Requirements for Type C packages
      •  Requirements for packages containing fissile material
    •  Test procedures
      •  Demonstration of compliance
      •  Leaching test for LSA-III material and low dispersible radioactive material
      •  Tests for special form radioactive material
      •  Tests for low dispersible radioactive material
      •  Tests for packages
    •  Approval and administrative requirements
      •  General
      •  Approval of special form radioactive material and low dispersible radioactive material
      •  Approval of material excepted from fissile classification
      •  Approval of package designs
      •  Approval of alternative activity limits for an exempt consignment of instruments or articles
      •  Transitional arrangements
      •  Notification and registration of serial numbers
      •  Approval of shipments
      •  Approval of shipments under special arrangement
      •  Competent authority certificates of approval
      •  Contents of certificates of approval
      •  Validation of certificates
  •  Governmental, Legal and Regulatory Infrastructure and Framework for Nuclear Security
    •  General
    •  Policy, Strategy and Objectives of Nuclear Security Regime
    •  Infrastructure
      •  General
      •  Capacity building
    •  Legal Framework (State Responsibilities)
      •  General
      •  Defining roles and responsibilities
      •  Offences and penalties/sanctions
      •  Graded approach to laws and regulations
      •  Import/Export of radioactive material and radioactive sources
      •  Import/Export of nuclear material
      •  International transport
      •  International Treaties
      •  Defining material and facilities subject to the nuclear security regime
      •  National radiological emergency plan
      •  National register of radioactive sources
      •  National Threat Assessment
      •  Coordination among competent authorities
      •  Coordinating body for MORC
      •  National framework for confidentiality
      •  Detection Architecture/Strategy
      •  National Response Framework for nuclear security events
    •  Regulatory Body
      •  General
      •  Independence of the regulatory body
      •  Authority, competence and resources for the Regulatory Body
      •  Establishing regulations
      •  Licensing and granting authorizations
      •  Evaluation of nuclear security measures/inspections
    •  Responsibility of a Competent Authority (incl. Regulatory Body)
      •  Implementation of the legislative framework
      •  Reporting of Nuclear Security Events
      •  National detection architecture implementation
      •  National Response Plan
    •  Risk management for Graded Approach
      •  Classification of Nuclear Security Events using a Graded Approach
      •  Categorization of Nuclear Material (Unauthorized Removal)
      •  Categorization of Radioactive Sources (Unauthorized Removal)
      •  Threshhold for Unacceptable Radiological Consequences (Sabotage)
      •  Threshhold for High Radiological Consequences (Sabotage)
    •  International Cooperation and Assistance
      •  Information Exchange
      •  Location and recovery of nuclear and radioactive material
      •  Technical cooperation and assistance
      •  Recovery and return of seized material
      •  National point of contact
    •  Nuclear Forensics
    •  Interface with Nuclear Safety
  •  Sustainability of Nuclear Security Regime
    •  General
    •  Management System for Security
      •  Security Policy
      •  Clear roles and responsibilities
      •  Communication and coordination
      •  Interface with the Regulator
      •  Provision of Resources
      •  Quality Assurance
      •  Documentation of procedures and work management
      •  Change management
      •  Human Resources Development
      •  Training and Qualification
      •  Contingency plans and drills
      •  Information Security
      •  Trustworthiness
      •  Work Environment
      •  Feedback process and Reporting of incidents
      •  Inventory of material or sources
      •  Performance Measurement
      •  Operations and maintenance
      •  Self-assessmnet
    •  Establishment of Sustainability Program
    •  Nuclear Security Culture
  •  Security of Material and Facilities: Activities/Responsibilities of License Holders
    •  Security systems for facilities and activities against threat
      •  Unauthorized Removal
      •  Sabotage
    •  Facility-level Target Identification
      •  Limited Area
      •  Protected Area
      •  Inner Area
      •  Vital Area
      •  Targets related to radioactive sources
    •  Consequence Assessment for Sabotage
    •  Developing and Implementing Security Plan
      •  Facility Security Plan
      •  Transport Security Plan
    •  Defence in Depth
      •  Compensatory measures
      •  Central Alarm Station
    •  Graded Approach to Implementation
    •  Deterrence Measures
    •  Detection and Assessment Measures
      •  General
      •  Surveillance
    •  Delay Measures
    •  Notification of Nuclear Security Event
    •  Response Measures and Contingency Plans
      •  Effectiveness of Nuclear Security System during a nuclear security event or emergency
      •  Mitigation and minimization of consequences
    •  Computer Security Measures
    •  Measures Against the Insider Threat
    •  Physical protection measures
      •  General
      •  Physical protection system design and evaluation
      •  Physical protection technologies and equipment
    •  Access Control
    •  Facilities (General)
    •  Nuclear Facilities
      •  Security Design of Instrumentation and Control (I&C) Systems
      •  Nuclear Material Accounting and Control (NMAC)
    •  Radiological Facilities
      •  General
      •  Inventory of Radioactive Sources
      •  Storage of Radioactive Material
    •  Transport (General)
      •  Security during transport
      •  Security during temporary storage
      •  Consideration of different modes of Transport
      •  Coordination during Transport
      •  Security Levels
    •  Transport of Nuclear Material
      •  General
      •  Transport Control Centre
    •  Transport of Radioactive Material
    •  Interface with Nuclear Safety
  •  Threat Assessment
    •  Threat assessment process
      •  General
      •  Continuous review of threat
    •  Design Basis Threat (DBT)
    •  Alternative Threat Statement
    •  Identification and assessment of nuclear security threats
      •  National-level facility targets
      •  National-level strategic locations
      •  Attributes and characteristics of threats
      •  Cyber Threats
      •  Insider Threats
      •  Major Public Events
  •  Material out of regulatory control (MORC)
    •  Security systems for MORC against threat
    •  Graded Approach to implementation
    •  Defence in Depth Approach
    •  Deterrence Measures
      •  General
      •  Public dissemination of information
    •  Planning, preparedness, and response for nuclear security events
      •  General
      •  Maintenance, Testing and Calibration of Equipment
      •  Crises management and communication
      •  Exercises and drills
      •  Mitigating or minimizing consequences
      •  Major Public Events
    •  National Detection System/Measures
      •  General
      •  Identification of Sources and Devices
      •  Border Controls
      •  Implementing Detection Architecture
      •  Alarm and Alert Assessment
      •  Deployment of detection instruments
      •  Designated points of exit and entry
      •  Medical surveillance
      •  Reporting material out of regulatory control
      •  Detection by instruments or information alert
      •  Nuclear Forensics
      •  Locating and Recovering Missing or Stolen Nuclear Material
      •  Notification of Nuclear Security Events
      •  Radiological Crime Scene Management
      •  Collection and handling of evidence
      •  Implementing the National Response Plan
    •  Computer Security Measures
    •  Measures Against the Insider Threat
    •  Interface with Nuclear Safety
  •  State
  •  Government
  •  Operators (licensee/ applicant)
  •  Operators (execution)
  •  Regulatory Body
  •  Other relevant authorities
  •  Guards and Response Forces
  •  Metal recycling and production industry
  •  Transport: Operator, consigner, shipper and/or carrier
  •  Siting/Site evaluation
  •  Design
  •  Construction
  •  Commissioning
  •  Operation
  •  Decommissioning
  •  Closure and post closure
  •  Removal from Regulatory Control
  •  Remediation for past activities
  •  Mining
  •  Nuclear Power Plants
  •  Research Reactors
  •  Fuel Cycle Facilities
    •  Conversion
    •  Enrichment
    •  U Fuel Fabrication
    •  Mox Fuel Fabrication
    •  Reprocessing
    •  Storage of spent fuel
    •  Fuel Cycle R&D
  •  Pre-disposal Waste Management Facilities
    •  High level waste
    •  Low and Intermediate level waste
    •  Storage of spent fuel
  •  Waste Disposal Facilities
  •  Radiation Facilities
    •  Gamma, Electron and X ray
    •  X ray generators and sources for non medical imaging
    •  Industrial Radiography
    •  Nuclear gauges
    •  Well Logging
    •  Radioisotope production
    •  Research and education
    •  Others
  •  Transport of Nuclear/Radioactive Material
  •  Consumer products
  •  Major Public Events