Document Center List of Standards on Nuclear Power Plants. Safety Radiation Protection, See 13.280
ICS Code 27.120.20
Return to ICS Index.Up to Level 2:
The following documents are a part of this series:
ASTM:
- ASTM-C1309 - Standard Practice for Performance Evaluation of In-Plant Walk-Through Metal Detectors
- ASTM-D5139 - Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants
- ASTM-D5163 - Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants
- ASTM-D5498 - Standard Guide for Developing a Training Program for Personnel Performing Coating and Lining Work Inspection for Nuclear Facilities
- ASTM-D7108 - Standard Guide for Establishing Qualifications for a Nuclear Coatings Specialist
- ASTM-D7167 - Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power Plant
- ASTM-D7301 - Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
- ASTM-D7491 - Standard Guide for Management of Non-Conforming Coatings in Coating Service Level I Areas of Nuclear Power Plants
- ASTM-D8104 - Standard Guide for Determining Coating Qualification Test Data Applicability
- ASTM-E1035 - Standard Practice for Determining Neutron Exposures for Nuclear Reactor
Vessel Support Structures - ASTM-E1214 - Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
- ASTM-E1281 - Standard Guide for Nuclear Facility Decommissioning Plans
- ASTM-E1819 - Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities
- ASTM-E1892 - Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities
- ASTM-E2420 - Standard Guide for Post-Deactivation Surveillance and Maintenance of Radiologically Contaminated Facilities
- ASTM-E2421 - Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities
- ASTM-E3104 - Standard Specification for Strippable & Removable Coatings to Mitigate Spread of Radioactive Contamination
- ASTM-E3105 - Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination
- ASTM-E482 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
- ASTM-E853 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
- ASTM-E854 - Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance
- ASTM-E909 - Master Matrix for Development of Standards to Assist in Safeguarding of Nuclear Materials (Withdrawn 1989)
- ASTM-E944 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
BSI:
- BS-7517 - Nuclear power plants. Control rooms. Operator controls
- BS-7674 - Nuclear power plants. Instrumentation and control systems important for safety. Requirements for electrical supplies
- BS-EN-60671 - Nuclear power plants. Instrumentation and control systems important to safety. Surveillance testing
- BS-EN-60709 - Nuclear power plants. Instrumentation and control systems important to safety. Separation
- BS-EN-60780-323 - Nuclear facilities. Electrical equipment important to safety. Qualification
- BS-EN-60880 - Nuclear power plants. Instrumentation and control systems important to safety. Software aspects for computer-based systems performing category A functions
- BS-EN-60964 - Nuclear power plants. Control rooms. Design
- BS-EN-60965 - Nuclear power plants. Control rooms. Supplementary control room for reactor shutdown without access to the main control room
- BS-EN-60965-TC - Tracked Changes. Nuclear power plants. Control rooms. Supplementary control room for reactor shutdown without access to the main control room
- BS-EN-60987 - Nuclear power plants. Instrumentation and control important to safety. Hardware design requirements for computer-based systems
- BS-EN-60987-TC - Tracked Changes. Nuclear power plants. Instrumentation and control important to safety. Hardware design requirements for computer-based systems
- BS-EN-61226 - Nuclear power plants. Instrumentation and control important to safety. Classification of instrumentation and control functions
- BS-EN-61227 - Nuclear power plants. Control rooms. Operator controls
- BS-EN-61500 - Nuclear power plants. Instrumentation and control important to safety. Data communication in systems performing category A functions
- BS-EN-61513 - Nuclear power plants. Instrumentation and control important to safety. General requirements for systems
- BS-EN-61772 - Nuclear power plants. Control rooms. Application of visual display units (VDUs)
- BS-EN-61839 - Nuclear power plants. Design of control rooms. Functional analysis and assignment
- BS-EN-62138 - Nuclear power plants. Instrumentation and control important for safety. Software aspects for computer-based systems performing category B or C functions
- BS-EN-62241 - Nuclear power plants. Main control room. Alarm functions and presentation
- BS-EN-62340 - Nuclear power plants. Instrumentation and control systems important to safety. Requirements for coping with common cause failure (CCF)
- BS-EN-62566 - Nuclear power plants. Instrumentation and control important to safety. Development of HDL-programmed integrated circuits for systems performing category A functions
- BS-EN-62765-1 - Nuclear powers plants. Instrumentation and control important to safety. Management of ageing of sensors and transmitters
- BS-EN-62808 - Nuclear power plants. Instrumentation and control systems important to safety. Design and qualification of isolation devices
- BS-EN-62808-TC - Nuclear power plants. Instrumentation and control systems important to safety. Design and qualification of isolation devices
- BS-EN-IEC-60709 - Nuclear power plants. Instrumentation, control and electrical systems important to safety. Separation
- BS-EN-IEC-60964 - Nuclear power plants. Control rooms. Design
- BS-EN-IEC-60987 - Nuclear power plants. Instrumentation and control important to safety. Hardware design requirements for computer-based systems
- BS-EN-IEC-61225 - Nuclear power plants. Instrumentation, control and electrical power systems. Requirements for static uninterruptible DC and AC power supply systems
- BS-EN-IEC-61226 - Nuclear power plants. Instrumentation, control and electrical power systems important to safety. Categorization of functions and classification of systems
- BS-EN-IEC-61500 - Nuclear power plants. Instrumentation and control systems important to safety. Data communication in systems performing category A functions
- BS-EN-IEC-62003 - Nuclear power plants. Instrumentation, control and electrical power systems. Requirements for electromagnetic compatibility testing
- BS-EN-IEC-62138 - Nuclear power plants. Instrumentation and control systems important to safety. Software aspects for computer-based systems performing category B or C functions
- BS-EN-IEC-62465 - Nuclear power plants. Instrumentation and control important to safety. Management of ageing of electrical cabling systems
- BS-EN-IEC-62566-2 - Nuclear power plants. Instrumentation and control systems important to safety. Development of HDL-programmed integrated circuits
- BS-EN-IEC-62645 - Nuclear power plants. Instrumentation, control and electrical power systems. Cybersecurity requirements
- BS-EN-IEC-62646 - Nuclear power plants. Control rooms. Computer-based procedures
- BS-EN-IEC-62855 - Nuclear power plants. Electrical power systems. Electrical power systems analysis
- BS-EN-IEC-62859 - Nuclear power plants. Instrumentation and control systems. Requirements for coordinating safety and cybersecurity
- BS-EN-IEC-62954 - Nuclear power plants. Control rooms. Requirements for emergency response facilities
- BS-EN-IEC-62988 - Nuclear power plants. Instrumentation and control systems important to safety. Selection and use of wireless devices
- BS-EN-IEC-63047 - Nuclear instrumentation. Data format for list mode digital data acquisition used in radiation detection and measurement
- BS-EN-IEC/IEEE-60980-344 - Nuclear facilities. Equipment important to safety. Seismic qualification
- BS-EN-IEC/IEEE-62582-6 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-EN-ISO-21613 - (U, Pu)O2 Powders and sintered pellets. Determination of chlorine and fluorine
- BS-EN-ISO-23133 - Nuclear criticality safety. Nuclear criticality safety training for operations.
- BS-IEC-60462 - Nuclear instrumentation. Photomultiplier tubes for scintillation counting. Test procedures
- BS-IEC-60515 - Nuclear power plants. Instrumentation important to safety. Radiation detectors. Characteristics and test methods
- BS-IEC-60568 - Nuclear power plants. Instrumentation important to safety. In-core instrumentation for neutron fluence rate (flux) measurements in power reactors
- BS-IEC-60671 - Nuclear Power Plants, Instrumentation & Control Systems Impoortant To Safety, Surveill
- BS-IEC-60709 - Nuclear Power Plants, Instrumentation & Control Systems Important To Safety, Separatio
- BS-IEC-60737 - Nuclear power plants. Instrumentation important to safety Temperature sensors (in-core and primary coolant circuit). Characteristics and test methods
- BS-IEC-60768 - Nuclear power plants. Instrumentation important to safety. Equipment for continuous in-line or on-line monitoring of radioactivity in process streams for normal and incident conditions
- BS-IEC-60772 - Nuclear power plants. Instrumentation systems important to safety. Electrical penetration assemblies in containment structures
- BS-IEC-60780 - Nuclear power plants. Electrical equipment of the safety system. Qualification
- BS-IEC-60880 - Nuclear power plants. Instrumentation and control systems important to safety. Software aspects for computer-based systems performing category A functions
- BS-IEC-60880-2 - Software for computers important to safety for nuclear power plants
- BS-IEC-60951-1 - Nuclear facilities. Instrumentation systems important to safety. Radiation monitoring for accident and post-accident conditions
- BS-IEC-60951-2 - Nuclear power plants. Instrumentation important to safety. Radiation monitoring for accident and post-accident conditions
- BS-IEC-60951-3 - Nuclear power plants. Instrumentation important to safety. Radiation monitoring for accident and post-accident conditions
- BS-IEC-60951-4 - Nuclear power plants. Instrumentation important to safety. Radiation monitoring for accident and post-accident conditions
- BS-IEC-60964 - Nuclear Power Plants, Control Rooms, Design
- BS-IEC-60965 - Nuclear Power Plants, Control Rooms, Supplementary Control Points for Reactor Shutdown
- BS-IEC-60987 - Nuclear power plants. Instrumentation and control important to safety. Hardware design requirements for computer-based systems
- BS-IEC-60988 - Nuclear power plants. Instrumentation important to safety. Acoustic monitoring systems for detection of loose parts: Characteristics, design criteria and operational procedures
- BS-IEC-61225 - Nuclear power plants. Instrumentation and control systems important to safety. Requirements for electrical supplies
- BS-IEC-61226 - Nuclear Power Plants, Instrumentation & Control Important To Safety, Classification Of
- BS-IEC-61227 - Nuclear power plants. Control rooms. Operator controls
- BS-IEC-61468 - Nuclear power plants. Instrumentation systems important to safety. In-core instrumentation: Characteristics and test methods of self-powered neutron detectors
- BS-IEC-61497 - Nuclear power plants. Electrical interlocks for functions important to safety. Recommendations for design and implementation
- BS-IEC-61500 - Nuclear Power Plants, Instrumentation & Control Important To Safety, Data Communicatio
- BS-IEC-61504 - Nuclear facilities. Instrumentation and control systems important to safety. Centralized systems for continuous monitoring of radiation and/or levels of radioactivity
- BS-IEC-61513 - Nuclear power plants. Instrumentation and control important to safety. General requirements for systems
- BS-IEC-61772 - Nuclear power plants. Control rooms. Application of visual display units (VDUs)
- BS-IEC-61838 - Nuclear Power Plants, Use of Probabilistic Safety Assessment for the Classification Of
- BS-IEC-61839 - Nuclear power plants. Design of control rooms. Functional analysis and assignment
- BS-IEC-61888 - Nuclear power plants. Instrumentation important to safety. Determination and maintenance of trip setpoints
- BS-IEC-62003 - Nuclear power plants. Instrumention, control and electrical power systems. Requirements for electromagnetic compatibility testing
- BS-IEC-62138 - Nuclear Power Plants, Instrumation & Control Important for Safety, Software Aspects Fo
- BS-IEC-62241 - Nuclear power plants. Main control room. Alarm functions and presentation
- BS-IEC-62340 - Nuclear Power Plants, Instrumentation & Control Systems Important To Safety, Requireme
- BS-IEC-62342 - Nuclear power plants. Instrumentation and control systems important to safety. Management of ageing
- BS-IEC-62385 - Nuclear power plants. Instrumentation and control important to safety. Methods for assessing the performance of safety system instrument channels
- BS-IEC-62397 - Nuclear power plants. Instrumentation and control important to safety. Resistance temperature detectors
- BS-IEC-62465 - Nuclear power plants. Instrumentation and control important to safety. Management of ageing of electrical cabling systems
- BS-IEC-62566 - Nuclear power plants. Instrumentation and control important to safety. Development of HDL-programmed integrated circuits for systems performing category A functions
- BS-IEC-62566-2 - Nuclear power plants. Instrumentation and control important to safety. Development of HDL-programmed integrated circuits
- BS-IEC-62645 - Nuclear power plants. Instrumentation, control and electrical power systems. Cybersecurity requirements
- BS-IEC-62646 - Nuclear power plants. Control rooms. Computer-based procedures
- BS-IEC-62651 - Nuclear power plants. Instrumentation important to safety.Thermocouples: characteristics and test methods
- BS-IEC-62671 - Nuclear power plants. Instrumentation and control important to safety. Selection and use of industrial digital devices of limited functionality
- BS-IEC-62705 - Nuclear facilities. Instrumentation and control important to safety. Radiation monitoring systems (RMS): Characteristics and lifecycle
- BS-IEC-62705-TC - Tracked Changes. Nuclear facilities. Instrumentation and control important to safety. Radiation monitoring systems (RMS): Characteristics and lifecycle
- BS-IEC-62765-1 - Nuclear powers plants. Instrumentation and control important to safety. Management of ageing of sensors and transmitters. Pressure transmitters
- BS-IEC-62765-2 - Nuclear powers plants. Instrumentation and control important to safety. Management of ageing of sensors and transmitters
- BS-IEC-62808 - Nuclear power plants. Instrumentation and control systems important to safety. Design and qualification of isolation devices
- BS-IEC-62855 - Nuclear power plants. Electrical power systems. Electrical power systems analysis
- BS-IEC-62859 - Nuclear power plants. Instrumentation and control systems. Requirements for coordinating safety and cybersecurity
- BS-IEC-62887 - Nuclear power plants. Instrumentation systems important to safety. Pressure transmitters: Characteristics and test methods
- BS-IEC-62954 - Nuclear power plants. Control rooms. Requirements for emergency response facilities
- BS-IEC-62988 - Nuclear power plants. Instrumentation and control systems important to safety. Selection and use of wireless devices
- BS-IEC-63046 - Nuclear power plants. Electrical power system. General requirements
- BS-IEC-63047 - Nuclear instrumentation. Data format for list mode digital data acquisition used in radiation detection and measurement
- BS-IEC-63096 - Nuclear power plants. Instrumentation, control and electrical power systems. Security controls
- BS-IEC-63147 - Criteria for accident monitoring instrumentation for nuclear power generating stations
- BS-IEC-63186 - Nuclear power plants. Instrumentation and control systems important to safety. Criteria for seismic trip system
- BS-IEC-63260 - Guide for incorporating human reliability analysis into probabilistic risk assessments for nuclear power generating stations and other nuclear facilities
- BS-IEC-63272 - Nuclear facilities. Electrical power systems. AC interruptible power supply systems
- BS-IEC-63298 - Nuclear Power Plants. Electrical power systems. Coordination and interaction with electric grid
- BS-IEC/IEEE-60780-32 - Nuclear facilities. Electrical equipment important to safety. Qualification
- BS-IEC/IEEE-60980-344 - Nuclear facilities. Equipment important to safety. Seismic qualification
- BS-IEC/IEEE-62582-1 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62582-2 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62582-3 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62582-4 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62582-4-TC - Tracked Changes. Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62582-5 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62582-6 - Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods
- BS-IEC/IEEE-62646 - Nuclear power plants. Control rooms. Computer based procedures
- BS-ISO-14943 - Nuclear energy. Nuclear fuel technology. Administrative criteria related to criticality safety
- BS-ISO-15080 - Nuclear facilities. Ventilation penetrationsfor shielded enclosures
- BS-ISO-16117 - Nuclear criticality safety. Estimation of the number of fissions of a postulated criticality accident
- BS-ISO-16659-1 - Ventilation systems for nuclear facilities. In-situ efficiency test methods for iodine traps with solid sorbent
- BS-ISO-18195 - Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)
- BS-ISO-20041-1 - Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations
- BS-ISO-21243 - Radiation protection. Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies. General principles and application to dicentric assay
- BS-ISO-21613 - (U, Pu)O2 Powders and sintered pellets. Determination of chlorine and fluorine
- BS-ISO-23133 - Nuclear criticality safety. Nuclear criticality safety training for operations
- BS-ISO-23466 - Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
- BS-ISO-23467 - Ice plug isolation of piping in nuclear power plant
- BS-ISO-24389-1 - Management of radioactive waste from nuclear facilities
- BS-ISO-24390 - Nuclear energy. Nuclear fuel technology. Methodologies for radioactivity characterization of very low-level waste (VLLW) generated by nuclear facilities
- BS-ISO-4917-1 - Design of nuclear power plants against seismic events
- BS-ISO-4917-3 - Design of nuclear power plants against seismic events
- BS-ISO-4917-4 - Design of nuclear power plants against seismic events
- BS-ISO-4917-6 - Design of nuclear power plants against seismic events
- BS-ISO-7753 - Nuclear criticality safety. Use of criticality accident alarm systems for operations
- PD-IEC-61838 - Nuclear power plants. Instrumentation and control important to safety. Use of probabilistic safety assessment for the classification of functions
- PD-IEC-62096 - Nuclear power plants. Instrumentation and control important to safety. Guidance for the decision on modernization
- PD-IEC-62918 - Nuclear power plants. Instrumentation and control important to safety. Use and selection of wireless devices to be integrated in systems important to safety
- PD-IEC-62987 - Nuclear power plants. Instrumentation and control systems important to safety. Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems
- PD-IEC-63084 - Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety
- PD-IEC-63123 - Nuclear power plants. Instrumentation, control and electrical power systems. Guidance for the application of IEC 63147:2017/IEEE Std 497TM-2016 in the IAEA / IEC framework
- PD-IEC- 63123 - Nuclear power plants. Instrumentation, control and electrical power systems. Guidance for the application of IEC 63147:2017/IEEE Std 497$UT$UM-2016 in the IAEA / IEC framework
- PD-IEC-63214 - Nuclear power plants. Control rooms. Human factors engineering
- PD-IEC-63335 - Nuclear power plants. Instrumentation and control systems, control rooms and electrical power systems. Specific features of small modular reactors and needs regarding standards
- PD-IEC-63400 - Nuclear facilities. Instrumentation, control and electrical power systems important to safety. Structure of the IEC SC 45A standards series
- PD-IEC-63415 - Nuclear Power plants. Instrumentation and control systems. Use of formal security models for I&C security architecture design and assessment
- PD-IEC-63468 - Nuclear facilities. Instrumentation and control, and electrical power systems. Artificial Intelligence applications
- PD-IEC-63486 - Nuclear facilities. Instrumentation, control and electrical power systems. Cybersecurity risk management approaches
IEC:
- IEC-1250 - Nuclear reactors - Instrumentation and control systems important for safety - Detection of leakage in coolant systems
- IEC-1343 - Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core
- IEC-1510 - RBMK nuclear reactors - Proposals for instrumentation and control improvements
- IEC-1771 - Nuclear power plants - Main control-room - Verification and validation of design
- IEC-60515 - Nuclear power plants - Instrumentation important to safety - Radiation detectors - Characteristics and test methods
- IEC-60568 - Nuclear power plants - Instrumentation important to safety - In-core instrumentation for neutron fluence rate (flux) measurements in power reactors
- IEC-60671 - Nuclear power plants - Instrumentation and control systems important to safety - Surveillance testing
- IEC-60709 - Nuclear power plants - Instrumentation, control and electrical power systems important to safety - Separation
- IEC-60737 - Nuclear power plants - Instrumentation important to safety - Temperature sensors (in-core and primary coolant circuit) - Characteristics and test methods
- IEC-60768 - Nuclear power plants - Instrumentation important to safety - Equipment for continuous in-line or on-line monitoring of radioactivity in process streams for normal and incident conditions
- IEC-60772 - Nuclear power plants - Instrumentation systems important to safety - Electrical penetration assemblies in containment structures
- IEC-60780 - Nuclear power plants - Electrical equipment of the safety system - Qualification
- IEC-60880 - Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
- IEC-60880-2 - Part 2: Software Aspects of Defence Against Common Cause Failures, Use of Software Tools &
- IEC-60910 - Nuclear power plants - Instrumentation important to safety - Containment monitoring for early detection of developing deviations from normal operation in light water reactors
- IEC-60951-1 - Nuclear facilities - Instrumentation systems important to safety - Radiation monitoring for accident and post-accident conditions - Part 1: General requirements
- IEC-60951-1-RL - Nuclear facilities - Instrumentation systems important to safety - Radiation monitoring for accident and post-accident conditions - Part 1: General requirements
- IEC-60951-2 - Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 2: Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation air
- IEC-60951-3 - Nuclear facilities - Instrumentation systems important to safety - Radiation monitoring for accident and post-accident conditions - Part 3: Equipment for continuous high range area gamma monitoring
- IEC-60951-3-RL - Nuclear facilities - Instrumentation systems important to safety - Radiation monitoring for accident and post-accident conditions - Part 3: Equipment for continuous high range area gamma monitoring
- IEC-60951-4 - Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 4: Equipment for continuous in-line or on-line monitoring of radioactivity in process streams
- IEC-60964 - Nuclear power plants - Control rooms - Design
- IEC-60964-RL - Nuclear power plants - Control rooms - Design
- IEC-60965 - Nuclear power plants - Control rooms - Supplementary control room for reactor shutdown without access to the main control room
- IEC-60986 - Short-circuit temperature limits of electric cables with rated voltages from 6 kV (Um = 7,2 kV) up to 30 kV (Um = 36 kV)
- IEC-60987 - Nuclear power plants - Instrumentation and control important to safety - Hardware requirements
- IEC-60987-AM1 - Amendment 1 - Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems
- IEC-60988 - Nuclear Power Plants - Instrumentation Important To Safety - Acoustic Monitoring Syste
- IEC-61225 - Nuclear power plants - Instrumentation, control and electrical power systems - Requirements for static uninterruptible DC and AC power supply systems
- IEC-61226 - Nuclear power plants - Instrumentation, control and electrical power systems important to safety - Categorization of functions and classification of systems
- IEC-61227 - Nuclear power plants - Control rooms - Operator controls
- IEC-61453 - Nuclear instrumentation - Scintillation gamma ray detector systems for the assay of radionuclides - Calibration and routine tests
- IEC-61468 - Nuclear power plants - Instrumentation systems important to safety - In-core instrumentation: Characteristics and test methods of self-powered neutron detectors
- IEC-61468-1 - Amendment 1 - Nuclear power plants - In-core instrumentation - Characteristics and test methods of self-powered neutron detectors
- IEC-61500 - Nuclear power plants - Instrumentation and control systems important to safety - Data communication in systems performing category A functions
- IEC-61500-RL - Nuclear power plants - Instrumentation and control systems important to safety - Data communication in systems performing category A functions
- IEC-61501 - Nuclear reactor instrumentation - Wide range neutron fluence rate meter - Mean square voltage method
- IEC-61502 - Nuclear power plants - Pressurized water reactors - Vibration monitoring of internal structures
- IEC-61504 - Nuclear facilities - Instrumentation and control systems important to safety - Centralized systems for continuous monitoring of radiation and/or levels of radioactivity
- IEC-61505 - Nuclear Reactor Instrumentation - Boiling Water Reactors (Bwr) - Stability Monitoring
- IEC-61513 - Nuclear power plants - Instrumentation and control important to safety - General requirements for systems
- IEC-61772 - Nuclear power plants - Control rooms - Application of visual display units (VDUs)
- IEC-61838 - Nuclear power plants - Instrumentation and control important to safety - Use of probabilistic safety assessment for the classification of functions
- IEC-61839 - Nuclear power plants - Design of control rooms - Functional analysis and assignment
- IEC-61888 - Nuclear power plants - Instrumentation important to safety - Determination and maintenance of trip setpoints
- IEC-61963 - Nuclear Power Plants - Main Control Room - Comparison of IEC 60964 To Similar Standard
- IEC-62003 - Nuclear power plants - Instrumentation, control and electrical power systems - Requirements for electromagnetic compatibility testing
- IEC-62096 - Nuclear power plants - Instrumentation and control important to safety - Guidance for the decision on modernization
- IEC-62117 - Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown
- IEC-62118 - Nuclear Reactor Instrumentation - Pressurized Water Reactor (Pwr) of Vver Design - Mo
- IEC-62138 - Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category B or C functions
- IEC-62138-RL - Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category B or C functions
- IEC-62235 - Nuclear facilities - Instrumentation and control systems important to safety - Systems of interim storage and final repository of nuclear fuel and waste
- IEC-62241 - Nuclear power plants - Main control room - Alarm functions and presentation
- IEC-62247 - Nuclear Power Plants - Main Control Room Design - a Review of the Application of IEC-60964
- IEC-62340 - Nuclear power plants - Instrumentation and control systems important to safety - Requirements for coping with common cause failure (CCF)
- IEC-62342 - Nuclear power plants - Instrumentation and control systems important to safety - Management of ageing
- IEC-62385 - Nuclear power plants - Instrumentation and control important to safety - Methods for assessing the performance of safety system instrument channels
- IEC-62397 - Nuclear power plants - Instrumentation and control important to safety - Resistance temperature detectors
- IEC-62465 - Nuclear power plants - Instrumentation and control important to safety - Management of ageing of electrical cabling systems
- IEC-62566 - Nuclear power plants - Instrumentation and control important to safety - Development of HDL-programmed integrated circuits for systems performing category A functions
- IEC-62566-2 - Nuclear power plants - Instrumentation and control systems important to safety - Development of HDL-programmed integrated circuits - Part 2: HDL-programmed integrated circuits for systems performing category B or C functions
- IEC-62645 - Nuclear power plants - Instrumentation, control and electrical power systems - Cybersecurity requirements
- IEC-62646 - Nuclear power plants - Control rooms - Computer-based procedures
- IEC-62651 - Nuclear power plants - Instrumentation important to safety - Thermocouples: characteristics and test methods
- IEC-62671 - Nuclear power plants - Instrumentation and control important to safety - Selection and use of industrial digital devices of limited functionality
- IEC-62705 - Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle
- IEC-62705-RL - Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle
- IEC-62765-1 - Nuclear powers plants - Instrumentation and control important to safety - Management of ageing of sensors and transmitters - Part 1: Pressure transmitters
- IEC-62765-2 - Nuclear power plants - Instrumentation and control important to safety - Management of ageing of sensors and transmitters - Part 2: Temperature sensors
- IEC-62808 - Nuclear power plants - Instrumentation and control systems important to safety - Design and qualification of isolation devices
- IEC-62808-AM1 - Amendment 1 - Nuclear power plants - Instrumentation and control systems important to safety - Design and qualification of isolation devices
- IEC-62855 - Nuclear power plants - Electrical power systems - Electrical power systems analysis
- IEC-62859 - Nuclear power plants - Instrumentation and control systems - Requirements for coordinating safety and cybersecurity
- IEC-62859-AM1 - Amendment 1 - Nuclear power plants - Instrumentation and control systems - Requirements for coordinating safety and cybersecurity
- IEC-62887 - Nuclear power plants - Instrumentation systems important to safety - Pressure transmitters: Characteristics and test methods
- IEC-62918 - Nuclear power plants - Instrumentation and control important to safety - Use and selection of wireless devices to be integrated in systems important to safety
- IEC-62954 - Nuclear power plants - Control rooms - Requirements for emergency response facilities
- IEC-62987 - Nuclear power plants - Instrumentation and control systems important to safety - Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems
- IEC-62988 - Nuclear power plants - Instrumentation and control systems important to safety - Selection and use of wireless devices
- IEC-63046 - Nuclear power plants - Electrical power system - General requirements
- IEC-63084 - Nuclear power plants - Instrumentation and control important to safety - Platform qualification for systems important to safety
- IEC-63096 - Nuclear power plants - Instrumentation, control and electrical power systems - Security controls
- IEC-63123 - Nuclear power plants - Instrumentation, control and electrical power systems - Guidance for the application of IEC 63147:2017/IEEE Std 497. -2016 in the IAEA / IEC framework
- IEC-63147 - Criteria for accident monitoring instrumentation for nuclear power generating stations
- IEC-63214 - Nuclear power plants - Control rooms - Human factors engineering
- IEC-63260 - Guide for incorporating human reliability analysis into probabilistic risk assessments for nuclear power generating stations and other nuclear facilities
- IEC-63272 - Nuclear facilities - Electrical power systems - AC interruptible power supply systems
- IEC-63298 - Nuclear power plants - Electrical power systems - Coordination and interaction with electric grid
- IEC-63335 - Nuclear power plants - Instrumentation and control systems, control rooms and electrical power systems - Specific features of small modular reactors and needs regarding standards
- IEC-63400 - Nuclear facilities - Instrumentation, control and electrical power systems important to safety - Structure of the IEC SC 45A standards series
- IEC-63415 - Nuclear Power plants - Instrumentation and control systems - Use of formal security models for I&C security architecture design and assessment
- IEC-63468 - Nuclear facilities - Instrumentation and control, and electrical power systems - Artificial Intelligence applications
- IEC-63486 - Nuclear facilities - Instrumentation, control and electrical power systems - Cybersecurity risk management approaches
- IEC-772 - Electrical penetration assemblies in containment structures for nuclear power generating stations
- IEC-860 - Warning equipment for criticality accidents
- IEC-910 - Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors
- IEC-911 - Measurements for monitoring adequate cooling within the core of pressurized light water reactors
- IEC-960 - Functional design criteria for a safety parameter display system for nuclear power stations
- IEC/IEEE-60780-323 - Nuclear facilities - Electrical equipment important to safety - Qualification
- IEC/IEEE-60980-344 - Nuclear facilities - Equipment important to safety - Seismic qualification
- IEC/IEEE-62582-1 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General
- IEC/IEEE-62582-1-RL - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 1: General
- IEC/IEEE-62582-2 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Indenter measurements
- IEC/IEEE-62582-2-AM1 - Amendment 1 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Indenter modulus
- IEC/IEEE-62582-2-RL - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 2: Indenter measurements
- IEC/IEEE-62582-3 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 3: Elongation at break
- IEC/IEEE-62582-3-RL - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 3: Elongation at break
- IEC/IEEE-62582-4 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques
- IEC/IEEE-62582-4-RL - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 4: Oxidation induction techniques
- IEC/IEEE-62582-5 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 5: Optical time domain reflectometry
- IEC/IEEE-62582-6 - Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 6: Insulation resistance
- IEC/IEEE-63113 - Nuclear facilities - Instrumentation important to safety - Spent fuel pool instrumentation
- IEC/IEEE-63332-387 - Nuclear facilities - Electrical power systems - Diesel generator units applied as standby power sources
ISO:
- ISO-11599 - Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste
- ISO-14943 - Nuclear fuel technology - Administrative criteria related to nuclear criticality safety
- ISO-15080 - Nuclear facilities - Ventilation penetrations for shielded enclosures
- ISO-16117 - Nuclear criticality safety - Estimation of the number of fissions of a postulated criticality accident
- ISO-16646 - Fusion installations - Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities
- ISO-16647 - Nuclear facilities - Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning
- ISO-16659-1 - Ventilation systems for nuclear facilities - In-situ efficiency test methods for iodine traps with solid sorbent - Part 1: General requirements
- ISO-17873 - Nuclear facilities - Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
- ISO-18195 - Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)
- ISO-20041-1 - Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations - Part 1: Sampling of tritium and carbon-14
- ISO-21243 - Radiation protection - Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies - General principles and application to dicentric assay
- ISO-21613 - (U, Pu)O2 Powders and sintered pellets - Determination of chlorine and fluorine
- ISO-21614 - Determination of carbon content of UO2, (U, Gd)O2 and (U, Pu)O2 powders and sintered pellets - Combustion in a high-frequency induction furnace - Infrared absorption spectrometry
- ISO-23133 - Nuclear criticality safety - Nuclear criticality safety training for operations
- ISO-23466 - Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
- ISO-23467 - Ice plug isolation of piping in nuclear power plant
- ISO-24389-1 - Management of radioactive waste from nuclear facilities - Part 1: General principles, objectives and practical approaches
- ISO-24390 - Nuclear energy - Nuclear fuel technology - Methodologies for radioactivity characterization of very low-level waste (VLLW) generated by nuclear facilities
- ISO-4233 - Reactor technology - Nuclear fusion reactors - Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
- ISO-4917-1 - Design of nuclear power plants against seismic events - Part 1: Principles
- ISO-4917-3 - Design of nuclear power plants against seismic events - Part 3: Civil structures
- ISO-4917-4 - Design of nuclear power plants against seismic events - Part 4: Components
- ISO-4917-6 - Design of nuclear power plants against seismic events - Part 6: Post-seismic measures
- ISO-6258 - Nuclear power plants -- Design against seismic hazards
- ISO-6527 - Nuclear power plants -- Reliability data exchange -- General guidelines
- ISO-7385 - Nuclear power plants -- Guidelines to ensure quality of collected data on reliability
- ISO-7753 - Nuclear criticality safety - Use of criticality accident alarm systems for operations
- ISO-8107 - Nuclear power plants - Maintainability - Terminology
Other SDOs:
- EN-60671 - Nuclear power plants - Instrumentation and control systems important to safety - Surveillance testing
- EN-60709 - Nuclear Power Plants - Instrumentation & Control Systems Important To Safety - Separat
- EN-60780-323 - Nuclear facilities. Electrical equipment important to safety. Qualification
- EN-60880 - Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
- EN-60964 - Nuclear Power Plants - Control Rooms - Design
- EN-60965 - Nuclear power plants - Control rooms - Supplementary control room for reactor shutdown without access to the main control room
- EN-60987 - Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems
- EN-61226 - Nuclear Power Plants - Instrumentation & Control Important To Safety - Classification
- EN-61227 - Nuclear power plants - Control rooms - Operator controls
- EN-61500 - Nuclear power plants - Instrumentation and control important to safety - Data communication in systems performing category A functions
- EN-61513 - Nuclear power plants - Instrumentation and control important to safety - General requirements for systems
- EN-61772 - Nuclear power plants - Control rooms - Application of visual display units (VDUs)
- EN-61839 - Nuclear power plants - Design of control rooms - Functional analysis and assignment
- EN-62138 - Nuclear Power Plants - Instrumentation & Control Important for Safety - Software Aspec
- EN-62241 - Nuclear power plants - Main control room - Alarm functions and presentation
- EN-62340 - Nuclear Power Plants - Instrumentation & Control Systems Important To Safety - Require
- EN-62566 - Nuclear power plants - Instrumentation and control important to safety - Development of HDL-programmed integrated circuits for systems performing category A functions
- EN-62765-1 - Nuclear powers plants. Instrumentation and control important to safety. Management of ageing of sensors and transmitters. Pressure transmitters
- EN-62808/A1 - Nuclear power plants - Instrumentation and control systems important to safety - Design and qualification of isolation devices (IEC 62808:2015/A1:2018)
- EN-IEC-60709 - Nuclear power plants - Instrumentation, control and electrical power systems important to safety - Separation (IEC 60709:2018)
- EN-IEC-60964 - Nuclear power plants - Control rooms - Design (IEC 60964:2018)
- EN-IEC-61500 - Nuclear power plants - Instrumentation and control systems important to safety - Data communication in systems performing category A functions (IEC 61500:2018)
- EN-IEC-62465 - Nuclear power plants - Instrumentation and control important to safety - Management of ageing of electrical cabling systems (IEC 62465:2010)
- EN-IEC-62646 - Nuclear power plants - Control rooms - Computer-based procedures (IEC 62646:2016)
- IEEE/IEC-62582-5 - IEEE/IEC Nuclear power plants -- Instrumentation and control important to safety -- Electrical equipment condition monitoring methods -- Part 5: Optical time domain reflectometry
- IEEE/IEC-62582-5-PDF - IEEE/IEC Nuclear power plants -- Instrumentation and control important to safety -- Electrical equipment condition monitoring methods -- Part 5: Optical time domain reflectometry - PDF Format
- ISO-15080-AM 1 - - Amendment 1
- SMS-ISO-2889 - General principles for sampling airborne radioactive materials
- SS-EN-ISO-15382 - Radiological protection - Procedures for monitoring the dose to the lens of the eye, the skin and the extremities (ISO 15382:2015)
- SS-EN-ISO-16647 - Nuclear facilities - Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning (ISO 16647:2018)
- SS-EN-ISO-20031 - Radiological protection - Monitoring and dosimetry for internal exposures due to wound contamination with radionuclides (ISO 20031:2020)
- SS-EN-ISO-21613 - (U, Pu)O2 Powders and sintered pellets - Determination of chlorine and fluorine (ISO 21613:2015)
- SS-EN-ISO-23133 - Nuclear criticality safety - Nuclear criticality safety training for operations (ISO 23133:2021)
- SS-EN-ISO-3925 - Unsealed radioactive substances - Identification and documentation (ISO 3925:2014)
- SS-EN-ISO-9978 - Radiation protection - Sealed sources - Leakage test methods (ISO 9978:2020)
- SS-ISO-11599 - Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste (ISO 11599:1997, IDT)
- SS-ISO-14943 - Nuclear fuel technology - Administrative criteria related to nuclear criticality safety (ISO 14943:2004, IDT)
- SS-ISO-15080-AM1 - Nuclear facilities - Ventilation penetrations for shielded enclosures - Amendment 1 (ISO 15080:2001/Amd 1:2019, IDT)
- SS-ISO-15382 - Radiological protection - Procedures for monitoring the dose to the lens of the eye, the skin and the extremities (ISO 15382:2015, IDT)
- SS-ISO-16117 - Nuclear criticality safety Estimation of the number of fissions of a postulated criticality accident (ISO 16117:2013, IDT)
- SS-ISO-16647 - Nuclear facilities - Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning (ISO 16647:2018, IDT)
- SS-ISO-17873 - Nuclear facilities - Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors (ISO 17873:2004, IDT)
- SS-ISO-18195 - Method for the justification of fire partitioning in water cooled nuclear power plants (NPP) (ISO 18195:2019, IDT)
- SS-ISO-19013-1 - Rubber hoses and tubing for fuel circuits for internal combustion engines - Specification - Part 1: Diesel fuels (ISO 19013-1:2019, IDT)
- SS-ISO-20031 - Radiological protection - Monitoring and dosimetry for internal exposures due to wound contamination with radionuclides (ISO 20031:2020, IDT)
- SS-ISO-20041-1 - Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations Part 1: Sampling of tritium and carbon-14 (ISO 20041-1:2022, IDT)
- SS-ISO-20042 - Measurement of radioactivity - Gamma-ray emitting radionuclides - Generic test method using gamma-ray spectrometry (ISO 20042:2019, IDT)
- SS-ISO-20956 - Radiological protection - Low dose rate calibration of instruments for environmental and area monitoring (ISO 20956:2023, IDT)
- SS-ISO-21243 - Radiation protection Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies General principles and application to dicentric assay (ISO 21243:2022, IDT)
- SS-ISO-21613 - (U, Pu)O2 Powders and sintered pellets - Determination of chlorine and fluorine (ISO 21613:2015, IDT)
- SS-ISO-21614 - Determination of carbon content of UO2, (U, Gd)O2 and (U, Pu)O2 powders and sintered pellets - Combustion in a high-frequency induction furnace - Infrared absorption spectrometry (ISO 21614:2008, IDT)
- SS-ISO-23018 - Group-Averaged Neutron and Gamma-Ray Cross Sections for Radiation Protection and Shielding Calculations for Nuclear Reactors (ISO 23018:2022, IDT)
- SS-ISO-23133 - Nuclear criticality safety Nuclear criticality safety training for operations (ISO 23133:2021, IDT)
- SS-ISO-23466 - Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants (ISO 23466, IDT)
- SS-ISO-23467 - Ice plug isolation of piping in nuclear power plant (ISO 23467:2020, IDT)
- SS-ISO-24390 - Nuclear energy Nuclear fuel technology Methodologies for radioactivity characterization of very low-level waste (VLLW) generated by nuclear facilities (ISO 24390:2023, IDT)
- SS-ISO-2919 - Radiological protection - Sealed radioactive sources - General requirements and classification (ISO 2919:2012, IDT)
- SS-ISO-3925 - Unsealed radioactive substances - Identification and documentation (ISO 3925:2014, IDT)
- SS-ISO-4233 - Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors (ISO 4233:2023, IDT)
- SS-ISO-7385 - Nuclear power plants - Guidelines to ensure quality of collected data on reliability
- SS-ISO-7503-1 - Measurement of radioactivity - Measurement and evaluation of surface contamination - Part 1: General principles (ISO 7503-1:2016, Corrected version 2018-02-15, IDT)
- SS-ISO-7503-2 - Measurement of radioactivity - Measurement and evaluation of surface contamination - Part 2: Test method using wipe-test samples (ISO 7503-2:2016, IDT)
- SS-ISO-7503-3 - Measurement of radioactivity - Measurement and evaluation of surface contamination - Part 3: Apparatus calibration (ISO 7503-3:2016, Corrected version 2018-02-15, IDT)
- SS-ISO-7753 - Nuclear criticality safety Use of criticality accident alarm systems for operations (ISO 7753:2023, IDT)
- SS-ISO-8107 - Nuclear power plants - Maintainability - Terminology
- SS-ISO-9271 - Decontamination of radioactively contaminated surfaces Testing of decontamination agents for textiles (ISO 9271:2023, IDT)
- SS-ISO-9978 - Radiation protection - Sealed sources - Leakage test methods (ISO 9978:2020, IDT)