SC 45A - Instrumentation, control and electrical power systems of nuclear facilities

IEC/IEEE 63332-387:2024 defines the criteria for the application and testing of diesel generator (DG) units used as safety class standby power supplies in nuclear facilities. In general, the standard applies to new nuclear facilities as well as for upgrading or back-fitting of existing facilities. Existing facilities can voluntarily adopt the requirements to enhance the performance capabilities and reliability of the installed DG units. The standard can be used in applications where highly reliable onsite alternating current (AC) power source is required to maintain plant safety following an event with potential loss of offsite power for an extended duration.
This document provides the principal design criteria, the design features, testing, and qualification requirements for the individual DG units that enable them to meet their functional requirements as a part of the standby power supply under the conditions produced by the design basis events catalogued in the plant safety analysis.

IEC/IEEE 62582-1:2024 contains requirements for application of the other parts of IEC/IEEE 62582 related to specific methods for condition monitoring in electrical equipment important to safety of nuclear power plants. It also includes requirements which are common to all methods. The procedures defined in IEC/IEEE 62582 are intended for detailed condition monitoring.
IEC/IEEE 62582 specifies condition monitoring methods in sufficient detail to enhance the accuracy and repeatability, and provide standard formats for reporting the results. The methods specified are applicable to electrical equipment containing polymeric materials. Some methods are especially designed for the measurement of condition of a limited range of equipment whilst others can be applied to all types of equipment for which the polymeric parts are accessible.

IEC 63351:2024 specifies the basic principles and requirements for the application of a human factors engineering (HFE) programme to the design of the human-machine interfaces (HMI) throughout the lifetime of a nuclear facility. The focus of this document is on control rooms and control functions as discussed in the text.
This document focuses on the application of a human factors engineering (HFE) programme to the design of the human-machine interfaces throughout the lifetime of a nuclear facility, including consideration of plant modifications.
This document is applicable to nuclear facilities such as: nuclear power plants (NPPs), research reactors, uranium enrichment and nuclear fuel fabrication facilities, spent fuel storage and reprocessing facilities.

IEC TR 63486:2024 provides a cybersecurity framework for digital I&C programmable systems [2]. IEC 62645 [1] aligns strongly with the information security management system (ISMS) elements detailed within ISO/IEC 27001:2013 [2]. The ISO/IEC ISMS structure corresponds to the “I&C digital programmable system cybersecurity program” in the context (as defined in 5.2.1 of IEC 62645:2019 [1]).
The scope of this document is to capture the national and international cyber-risk approaches employed to manage cybersecurity risks associated with Instrumentation and Control (I&C) and Electrical Power Systems (EPS) at a Nuclear Power Plant (NPP).
This document summarizes an evaluation of cyber-risk approaches that are in use by nuclear facility operators to manage cybersecurity risks.
The scope of this document generally follows the exclusions of IEC 62645 which are:
- Non-malevolent actions and events such as accidental failures, human errors (except those stated above, such as impacting the performance of cybersecurity controls), and natural events. In particular, good practices for managing applications and data, including backup and restoration related to accidental failure, are out of scope.
This document summarizes key insights of the international and cyber-risk approaches used at NPPs regarding the application of ISO/IEC 27005:2018 [5]. The evaluation is based on 11 challenges to cybersecurity risk management and their applicability to NPP risk management. The challenges are detailed in Clause 7. This document also relates the risk management elements of IEC 62645 and IEC 63096.

IEC 63272:2024 specifies the performance and functional characteristics of the on-site AC interruptible power supply systems and applies to new nuclear facilities and newly installed or upgraded on-site AC interruptible power supply systems.
The specific design requirements for the components of the power supply system are defined by the IEC standards listed in the normative references and are outside the scope of this document.
The purpose of this document is to provide high level requirements for the design of on-site AC interruptible power supply systems as part of the overall electrical distribution system in a nuclear facility. This document defines the requirements for an electrical designer to establish the design of the AC interruptible electrical power supply for nuclear facilities. It is used in conjunction with Level 1 standard IEC 63046.

IEC 63298:2024 provide high level requirements and recommendations for the coordination of NPPs and the electric grid; see also item a) of the Introduction. The specific design requirements for components and equipment are covered by other specific IEC standards outside the scope of this document. This document also defines the coordination requirements to ensure that operating instructions for the electric grid and the NPP are developed to provide a means of safe and reliable operation. This document also defines the requirements for the development of a framework for any specific tests that may be deemed necessary for the electric grid and the NPP, such as testing of NPP regulation capabilities and load rejection to house load operation tests.

IEC/IEEE 62582-3:2024 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using tensile elongation techniques in the detail necessary to produce accurate and reproducible measurements. This document includes the requirements for the selection of samples, the measurement system and conditions, and the reporting of the measurement results. The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes requirements for the application of the other parts of IEC/IEEE 62582 and some elements which are common to all methods. This document applies to non-energised equipment. This document is published as an IEC/IEEE Dual Logo standard. This second edition cancels and replaces the first edition published in 2012.
This edition includes the following technical changes with respect to the previous edition:
a) Updated best practices relating to condition monitoring using the tensile elongation method.
b) Updated bibliography, references and context.

IEC TR 63415:2023 provides an overview over the formalized modelling and designing of cybersecure architectures to apply for I&C system cybersecurity enforcement at NPPs. The plant-specific risk assessment can use the techniques covered by this TR. This document considers the complex problem of NPP I&C architecture synthesis to address particular issues:
- asset classification,
- barrier measures assignment,
- the information transfer and links conformity with security requirements.
This document provides guidance on creating a comprehensive security model applicable to NPP I&C systems that describes NPP I&C cybersecurity architecture and aids in accomplishing the main tasks of I&C system secure design, which are:
- specification of system designs with increased determinism that enhance security,
- mapping of the security requirements into the security architecture of the I&C system,
- definition of the security requirements for information exchange between components within the I&C system, operators and other systems,
- assistance in the determination of the security degree assignment with a model-based technique considering asset properties and formal grouping of the assets,
design and establishment of security zones boundaries.

IEC TR 63468:2023 overviews the fundamentals of artificial intelligence (AI) as it could potentially be applied within nuclear facilities and identifies proven or potential applications, with the objective to foster better understanding and adoption of AI technologies within such facilities. With the objective of supporting future standard development work of IEC SC 45A in this technical area, this document takes the initiative to propose a structure for SC 45A standard series on nuclear AI applications and recommends setting up a new dedicated working group to be responsible for and coordinate standard development efforts in this particular area, taking into account its cross-cutting nature.

IEC 60951-1:2022 provides general guidance on the design principles and performance criteria for equipment to measure radiation and fluid (gaseous effluents or liquids) radioactivity levels at nuclear facilities during and after design basis accidents (DBA) and design extension conditions (DEC), including severe accident (SA). This document is limited to equipment for continuous monitoring of radioactivity in design basis accidents (DBA), design extension conditions (DEC), including severe accident (SA) and post-accident conditions. The purpose of this document is to lay down general requirements and give examples of acceptable methods for equipment for continuous monitoring of radioactivity within the facility during and after design basis accidents (DBA), design extension conditions (DEC), including severe accident (SA) in nuclear facilities. This third edition cancels and replaces the second edition published in 2009.The main technical changes with regard to the previous edition are as follows.
- title modified.
- to be consistent with the categorization of the accident condition.
- to update the references to new standards published since the second edition.
- to update the terms and definitions.

IEC 62397:2022 describes the requirements for resistance temperature detectors (RTDs) suitable for applications in I&C systems important to safety of nuclear power plants. The requirements of RTDs include design, materials, manufacturing, testing, calibration, procurement, and inspection. RTDs used for safety applications in Nuclear Power Plants can be categorized into direct-immersed and thermowell-mounted RTDs.
This standard describes the requirements for the design, material selection, procurement, construction, and testing of resistance temperature detectors (RTDs) used in nuclear power plants (NPPs). These RTDs may be used in both the nuclear safety I&C systems and/or in the non-safety-related instrumentation systems.
This second edition cancels and replaces the first edition, published in 2007; it also cancels and replaces the first edition of IEC 61224:1993. This edition includes the following significant technical changes with respect to the previous edition.

IEC 62705:2022 gives requirements for the lifecycle management of radiation monitoring systems (RMS) and gives guidance on the application of existing IEC standards covering the design and qualification of systems and equipment. The purpose of this document is to lay down requirements for the lifecycle management of RMSs and give application guidance. This document is intended to be consistent with the latest versions of International Standards dealing with radiation monitors, sampling of radioactive materials, instruments calibration, hardware and software design, classification, and qualification. This document is applicable to RMSs installed in nuclear facilities intended for use during normal operation, anticipated operational occurrences (AOO), design basis accidents (DBA) and design extension conditions (DEC), including severe accidents (SA). This second edition cancels and replaces the first edition published in 2014. This edition includes the following significant technical changes with respect to the previous edition:
- modification of the title.
- to be consistent with the categorization of the accident condition.
- to update the references to new standards published since the first edition.
- to update the terms and definitions.

IEC 60910:2022 provides requirements for primary and secondary containment parameter monitoring that enable the operator to identify developing deviations from normal operation. The operator can then take corrective action at an early stage to prevent a minor failure from developing into a serious plant failure or an accident condition. This document is directed towards monitoring the primary and secondary containment under normal conditions only.
This second edition cancels and replaces the first edition, published in 1988. This edition includes the following significant technical changes with respect to the previous edition:
a. Modification of title;
b. Integration of new technology and knowledge;
c. Drafting directed towards monitoring conditions in containment under normal conditions.

IEC 60951-3:2022 provides general guidance on the design principles and performance criteria for equipment for continuous high range area gamma monitoring in nuclear facilities for accident and post-accident conditions. This document categorizes accident conditions into design basis accidents (DBA) and design extension conditions (DEC), including severe accident (SA). The purpose of this document is to lay down general requirements for equipment for continuous high range area gamma monitoring of radiation within the facility during and after accident conditions in nuclear facilities. This document is applicable to installed dose rate meters that are used to monitor high levels of gamma radiation during and after an accident. This third edition cancels and replaces the second edition published in 2009.The main technical changes with regard to the previous edition are as follows:
- Title modified.
- To be consistent with the categorization of the accident condition.
- To update the references to new standards published since the second edition.
- To update the terms and definitions.
This standard is to be read in conjunction with IEC 60951-1.

IEC/IEEE 62582-4:2022 specifies methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using oxidation induction techniques in the detail necessary to produce accurate and reproducible measurements. It includes the requirements for sample preparation, the measurement system and conditions, and the reporting of the measurement results. This second edition cancels and replaces the first edition published in 2011, and its Amendment 1:2016. This edition includes the following significant technical changes with respect to the previous edition:
- Consideration of publication of IEC/IEEE 60780-323;
- An example added in Annex B and update;
- Annex C added.

IEC/IEEE 62582-2:2022 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using the indenter measurement technique in the detail necessary to produce accurate and reproducible measurements. It includes the requirements for the selection of samples, the measurement system and measurement conditions, and the reporting of the measurement results. This document is intended for application to non-energised equipment. This document is published as an IEC/IEEE Dual Logo standard. This second edition cancels and replaces the first edition published in 2011, and its Amendment 1:2016. This edition includes the following significant technical changes with respect to the previous edition:
- Modification of the title;
- Consideration of publication of IEC/IEEE 60780-323.

IEC TR 63400:2021 is intended to augment that description to enable users of individual IEC SC 45A standards to obtain a more comprehensive understanding of the overall structure of the series and its relationship with other standards bodies and standards. This document outlines the scope of the IEC SC 45A standards series and describes the basic structure of the IEC SC 45A standards series, with particular reference to a hierarchy of levels and subdivision into a set of broad topic areas. it presents the structure of the IEC SC 45A standards series in diagrammatic form.

IEC 63186:2021 specifies the minimum requirements for the design of the seismic trip system, and the components thereof, used in a nuclear power plant to mitigate seismic effects. This system is intended to shut down the reactor in operation automatically before it is significantly impacted by the vibratory ground motion incurred by strong earthquakes. This document is applicable to both the design of new built plants and the upgrading of plants in operation. It may be used for the design of other types of nuclear facilities where normal operation shall be stopped in case of strong seismic motions.

IEC 61468:2021 applies to in-core neutron detectors, viz. self-powered neutron detectors (SPNDs), which are intended for application in systems important for nuclear reactor safety: protection, instrumentation and control. This document contains SPND characteristics and test methods. In this document, the main sources of errors, and the possibilities for their minimization are also considered. This document contains requirements, recommendations and instructions concerning selection of SPND type and characteristics for various possible applications.
This document about SPNDs uses the basic requirements of IEC 61513 and IEC 60568 and complements them with more specific provisions in compliance with IAEA Safety Guides.
This second edition cancels and replaces the first edition, published in 2000, and its Amendment 1, published in 2003.
This edition includes the following significant technical changes with respect to the previous edition:
a. Title modified.
b. Justify the requirements for SPND characteristics in terms of influencing factors.
c. Align the terminology with the current state of the regulatory framework.

IEC/IEEE 63113:2021 provides criteria for spent fuel pool instrumentation for nuclear power generating stations and other nuclear facilities. The document applies to water filled spent fuel pools where the water volume is necessary to prevent a release of fission products that exceeds allowed operational limits. The purpose of this document is to establish design, performance, qualification, and display criteria for spent fuel pool instrumentation for normal operation, anticipated operational occurrences, design basis events, and design extension conditions (including severe accident conditions).

IEC TR 63335:2021 identifies a number of issues of particular importance to light water Small Modular Reactors (SMRs), which are not currently adequately addressed by existing IEC SC 45A standards, and that could be considered when revising existing publications or that could be the object of new work item proposals. Whether each of these issues will indeed be addressed, and if so in which publication, will be the decision of each SC 45A working group. Though there are a number of advanced Generation IV SMR projects underway, their specific needs are not covered by this document.

IEC 60987:2021 provides requirements and recommendations for the hardware aspects of I&C systems whatever the technology and applies for all safety classes in a graded manner (as defined by IEC 61513). The requirements defined within this document guide, in particular, the selection of pre-existing components, hardware aspects of system detailed design and implementation and equipment manufacturing.
This third edition cancels and replaces the second edition published in 2007. This edition includes the following significant technical changes with respect to the previous edition:
a) Title modified;
b) Take account of the fact that hardware requirements apply to all I&C technologies, including conventional hardwired equipment, programmable digital equipment or by using a combination of both types of equipment;
c) Align the standard with the new revisions of IAEA documents SSR-2/1, which include as far as possible an adaptation of the definitions;
d) Replace, as far as possible, the requirements associated with standards published since the edition 2.1, especially IEC 61513, IEC 60880, IEC 62138, IEC 62566 and IEC 62566‑2;
e) Review the existing requirements and update the terminology and definitions;
f) Extend the scope of the standard to all hardware (computerized and non-computerized) and to all safety classes 1, 2 and 3;
g) Complete, update the IEC and IAEA references and vocabulary;
h) Check possible impact of other IAEA requirements and recommendations considering extension of the scope of SC 45A;
i) Highlight the use of IEC 62566 and IEC 62566-2 for HPD development;
j) Introduce specific activities for pre-existing items (selection, acceptability and/or mitigation);
k) Introduce clearer requirements for electronic module-level design, manufacturing and control;
l) Complete reliability assessment methods;
m) Introduce requirements when using automated tests or control activities;
n) Complete description of manufacturing control activities (control process, assessment of manufactured equipment, preservation of products);
o) Define and ensure the inclusion of a graded approach for dealing with the 3 different classes of equipment and related requirements.

IEC 63046:2020 provides requirements and recommendations for the overall Electrical Power System. In particular, it covers interruptible and uninterruptible Electrical Power Systems including the systems supplying the I&C systems; This document is consistent and coherent with IEC 61513. Like IEC 61513, this document also highlights the need for complete and precise requirements, derived from the plant safety goals. Those requirements are prerequisites for generating the comprehensive requirements for the overall Electrical Power System architecture, and for the electrical power supply sub-systems. This document establishes the high level specification and requirement to implement a suitable Electrical Power System in a NPP that supports reactor systems important to safety. It also enables electrical energy production providing the transmission grid with active and reactive power and electro-mechanical inertia.

IEC/IEEE 60980-344:2020 describes methods for establishing seismic qualification procedures that will yield quantitative data to demonstrate that the equipment can meet its performance requirements. This document is applicable to electrical, mechanical, instrumentation and control equipment/components that are used in nuclear facilities. This document provides methods and documentation requirements for seismic qualification of equipment to verify the equipment’s ability to perform its specified performance requirements during and/or after specified seismic demands. This document does not specify seismic demand or performance requirements. Other aspects, relating to quality assurance, selection of equipment, and design and modification of systems, are not part of this document. As seismic qualification is only a part of equipment qualification, this document is used in conjunction with IEC/IEEE 60780-323.
The seismic qualification demonstrates equipment’s ability to perform its safety function(s) during and/or after the time it is subjected to the forces resulting from at least one safe shutdown earthquake (SSE/S2). This ability is demonstrated by taking into account, prior to the SSE/S2, the ageing of equipment and the postulated occurrences of a given number of lower intensity operating basis earthquake (OBE/S1). Ageing phenomena to be considered, if specified in the design specification, are those which could increase the vulnerability of equipment to vibrations caused by an SSE/S2.

IEC 61031:2020 applies to the design, location and application of installed equipment for monitoring local gamma radiation dose rates within nuclear facilities during normal operation and anticipated operational occurrences. High range area gamma radiation dose rate monitoring equipment for accident conditions currently addressed by IEC 60951-1 and IEC 60951-3 is not within the scope of this document. This document does not apply to the measurement of neutron dose rate. Additional equipment for neutron monitoring may be required, depending on the plant design, if the neutron dose rate makes a substantial contribution to the total dose equivalent to personnel.
This document provides guidelines for the design principles, the location, the application, the calibration, the operation, and the testing of installed equipment for continuously monitoring local gamma radiation dose rates in nuclear facilities under normal operation conditions and anticipated operational occurrences. These instruments are normally referred to as area radiation monitors. Portable instruments are also used for this purpose but are not covered by this document.

IEC 63260:2020 provides a structured framework for the incorporation of human reliability analysis (HRA) into probabilistic risk assessments (PRAs).
This document is to enhance the analysis of human-system interactions in PRAs, to help ensure reproducible conclusions, and to standardize the documentation of such assessments. To do this, a specific HRA framework is developed from standard practices to serve as a benchmark to assess alternative ways of incorporating HRA into PRA. This standard is an adoption of IEEE 1082-2017 by IEC.

IEC 62566-2:2020 provides requirements for achieving highly reliable HDL-Programmed Devices (HPDs), for use in I&C systems of nuclear power plants performing functions of safety category B or C as defined by IEC 61226.
The programming of HPDs relies on Hardware Description Languages (HDL) and related software tools. They are typically based on blank Field Programmable Gate Arrays (FPGAs) or similar micro-electronic technologies such as Programmable Logic Devices (PLD), Complex Programmable Logic Devices (CPLDs), etc. General purpose integrated circuits such as microprocessors are not HPDs.
This document provides requirements on:
a) a dedicated HPD life-cycle addressing each phase of the development of HPDs, including specification of requirements, design, implementation, integration and validation, as well as verification activities associated with each phase,
b) planning and complementary activities such as modification and production,
c) selection of pre-developed components. This includes micro-electronic technologies and Pre-Developed Blocks (PDBs),
d) tools used to design, implement and verify HPDs.

IEC 61226:2020 establishes, for nuclear power plants , a method of assignment of the functions specified for the plant into categories according to their importance to safety. Subsequent classification of the I&C and electrical power systems performing or supporting these functions, based on the assigned category, then determines relevant design criteria.
The design criteria, when applied, ensure the achievement of each function in accordance to its importance to safety. In this document, the criteria are those of functionality, reliability, performance, environmental qualification (e.g. seismic) and quality assurance (QA).
This edition includes the following significant technical changes with respect to the previous edition:
- to align on IAEA requirements, recommendations and terminology, particularly to take into account the replacement of NS-R-1 by SSR 2/1 and publication of SSG 30;
- to extend the scope to electrical power systems;
- to move the detailed requirements applying to functions and I&C systems to a normative annex, which will be removed after updating IEC 61513.

IEC 62003:2020 establishes requirements for electromagnetic compatibility testing of instrumentation, control, and electrical equipment supplied for use in systems important to safety at nuclear power plants and other nuclear facilities. The document lists the applicable IEC standards (principally the IEC 61000 series) which define the general test methods, and provides the necessary application-specific parameters and criteria to ensure that nuclear safety requirements are met.
This second edition cancels and replaces the first edition published in 2009. This edition includes the following significant technical changes with respect to the previous edition:
a) title modified.
b) expand the scope to encompass Electromagnetic Magnetic Compatibility (EMC) considerations for electrical equipment.
c) provide guidance for addressing the use of wireless technology.
d) enhance the description of the electromagnetic environment to provide clarification when selecting custom test levels or for test exemptions.
e) include example information to be contained within an EMC test plan.
f) provide guidance for characterization of the electromagnetic environment at the point of installation within a nuclear facility.

IEC 62645:2019 establishes requirements and provides guidance for the development and management of effective computer security programmes for I&C programmable digital systems. Inherent to these requirements and guidance is the criterion that the power plant I&C programmable digital system security programme complies with the applicable country’s requirements.
This document defines adequate measures for the prevention of, detection of and reaction to malicious acts by digital means (cyberattacks) on I&C programmable digital systems. This includes any unsafe situation, equipment damage or plant performance degradation.
This second edition cancels and replaces the first edition published in 2014. This edition includes the following significant technical changes with respect to the previous edition:
a) to align the standard with the new revisions of ISO/IEC 27001;
b) to review the existing requirements and to update the terminology and definitions;
c) to take account of, as far as possible, requirements associated with standards published since the first edition;
d) to take into account the fact that cybersecurity techniques, but also national practices evolve.

IEC TR 63214:2019 provides a summary of arguments and a technical basis for the development of a new Human Factors Engineering IEC standard and the alignment of IEC 60964. Based on the provided argumentation, the participating members will vote for such an approach. The proposed content of the new standard provides the basis for fruitful discussion within IEC SC 45A WG 8 and raises interest in the development of the new standard.
The scope of the new HFE IEC standard will follow a holistic approach towards the design of the plant-wide control rooms and all HMI, including e.g. the local control stations located throughout the plant. The general principle is to consider the complete nuclear installation design as a sociotechnical system, in a holistic and integrated way.

IEC/IEEE 62582-6:2019 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control cables using insulation resistance measurements in the detail necessary to produce accurate and reproducible results during simulated accident conditions. It includes the requirements for the measurement system and measurement procedure, and the reporting of the measurement results.
NOTE Measurement of insulation resistance during simulated accident conditions with the aim of determining the lowest value during the accident in order to assess cable performance involves special requirements given in this document. Methods for measurement under stable (non-accident) conditions are available in other international standards, e.g. IEC 62631-3-3.
The different parts of the IEC/IEEE 62582 series are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes requirements for the application of the other parts of the IEC/IEEE 62582 series and some elements which are common to all methods. Information on the role of condition monitoring in qualification of equipment important to safety is found in IEC/IEEE 60780-323.

IEC 61225:2019 specifies the performance and the functional characteristics of the low voltage static uninterruptible power supply (SUPS) systems in a nuclear power plant and, for applicable parts, in general for nuclear facilities. An uninterruptible power supply is an electrical equipment which draws electrical energy from a source, stores it and maintains supply in a specified form by means inside the equipment to output terminals. A static uninterruptible power supply (SUPS) has no rotating parts to perform its functions.
This third edition cancels and replaces the second edition published in 2005. This edition includes the following significant technical changes with respect to the previous edition:
a) the principal objective of this edition is to address the requirements on the static uninterruptible power supplies in nuclear power plants;
b) in addition to Instrumentation and Control (I&C) power supplies include all static uninterruptible power supplies;
c) emphasize that the static uninterruptible power supplies shall protect the connected equipment (loads) from transients on the on-site AC distribution system (the immunity concept);
d) in accordance with the defence-in-depth concept, this standard applies to static uninterruptible power supplies for all equipment, not only for equipment important to safety, with a graded approach to verification and validation;
e) addition of the requirement that, when batteries are connected in parallel under abnormal operating conditions, they shall be properly protected with isolation devices to avoid any failure that may impair more than one division of the uninterruptible power supply.

IEC TR 63192:2019 provides the comparison of the hazard analysis requirements between IAEA framework and NRC-IEEE framework of standards and guidance. The hazard analysis requirements in the different standards were compared with a set of comparison criteria, including the safety principle, the safety process, the definitions, the hazard analysis process, etc. This document includes the comparison results of the HA requirements of the safety control systems of other safety industries in Annex C.
For a nuclear power plant, the design safety and operation safety shall be analyzed, for example, to meet the IAEA Safety Requirements for Design (SSR-2/1) and Operation (SSR‑2/2). The scope of this document is to survey the state of the art in the hazard analysis for the design of I&C system of NPPs.

IEC 62765-2:2019 identifies minimum requirements and applicable practices for correcting and preventing any potential impacts on nuclear power plant (NPP) safety due to the ageing of temperature sensors, such as NPP resistance temperature detectors (RTDs) and thermocouples (TCs).
This document provides strategies, technical requirements, and recommended practices for the management of the ageing of temperature sensors important to safety in nuclear power plants (NPPs) to ensure that ageing can be identified and that suitable remedial actions are undertaken as necessary to demonstrate that the safety of the plant will not be impaired. This document is aligned with IEC 62342, which provides guidance on ageing management for instrumentation and control (I&C) systems important to safety in NPPs

IEC 62954:2019 presents the requirements for the on-site emergency response facilities (referred to hereinafter as the “ERF”) which are to be used in case of incidents or accidents occurring on the associated Nuclear Power Plant (NPP).
The ERF consists of the Emergency Response Centre (ERC), the Technical Support Centre (TSC) and the Operational Support Centre (OSC).
It establishes requirements for the ERF features and ERF I&C equipment to:
· coordinate on-site operational efforts with respect to safety and radioprotection;
· optimize the design in terms of environment control, lighting, power supplies and access control of the ERF;
· enhance the identification and resolution of potential conflicts between the traditional operational means and emergency means (MCR/SCR and ERF, operating staff and emergency teams, operational procedures and emergency procedures);
· aid the identification and the enhancement of the potential synergies between the traditional operational means and emergency means.

IEC 60964:2018 establishes requirements for the human-machine interface in the main control rooms of nuclear power plants. The document also establishes requirements for the selection of functions, design consideration and organization of the human-machine interface and procedures which are used systematically to verify and validate the functional design. These requirements reflect the application of human factors engineering principles as they apply to the human-machine interface during plant operational states and accident conditions (including design basis and design extension conditions), as defined in IAEA SSR-2/1 and IAEA NP-T-3.16. This third edition cancels and replaces the second edition published in 2009. This edition constitutes a technical revision. This edition includes the following significant technical changes with respect to the previous edition:
a) to review the usage of the term “task” ensuring consistency between IEC 60964 and IEC 61839;
b) to clarify the role, functional capability, robustness and integrity of supporting services for the MCR to promote its continued use at the time of a severe accident or extreme external hazard;
c) to review the relevance of the standard to the IAEA safety guides and IEC SC 45A standards that have been published since IEC 60964:2009 was developed;
d) to clarify the role and meaning of “task analysis”,
e) to further delineate the relationships with derivative standards (i.e. IEC 61227, IEC 61771, IEC 61772, IEC 61839, IEC 62241 and others of relevance to the control room design);
f) to consider its alignment with the Human Factors Engineering principles, specifically with the ones of IAEA safety guide on Human Factors (DS-492) to be issued.

IEC 62138:2018 specifies requirements for the software of computer-based instrumentation and control (I&C) systems performing functions of safety category B or C as defined by IEC 61226. It complements IEC 60880 which provides requirements for the software of computer-based I&C systems performing functions of safety category A. It is consistent with, and complementary to, IEC 61513. Requirements that are not specific to software are deferred to IEC 61513. This new edition includes the following significant technical changes with respect to the previous edition:
- align the standard with standards published or revised since the first edition, in particular IEC 61513, IEC 60880, IEC 62645 and IEC 62671;
- merge two clauses in order to avoid repetitions of text;
- introduce requirements on traceability in consistency with IEC 61513;
- introduce new annexes.

IEC 62808:2015 establishes requirements for the design, analysis and qualification of isolation devices used to ensure electrical independence of redundant safety system circuits, or between safety and lower class circuits, as specified in IEC 60709. This standard includes guidance on the determination of the maximum credible fault that is applied to the isolation devices. The maximum credible fault can be used as a basis for the test levels used in testing based on other standards (e.g. IEC TS 61000-6-5 or IEC 62003).

IEC 62887:2018 lays down specific requirements for nuclear applications of pressure transmitters including design, materials, manufacturing, testing, calibration and inspection. This document is applicable to general aspects of design, manufacturing and test methods for pressure transmitters used in instrumentation systems important to safety in all nuclear power plants (PWR, BWR, FBR, etc.). The consequences of nuclear conditions for pressure transmitters lead to onerous requirements regarding qualification.

IEC 60772:2018 applies to electrical penetration assemblies (EPAs) in containment structures of nuclear power plants. It covers the engineering safety requirements to be met in the design, calculation, qualification, fabrication, assembly, testing, and installation of EPAs. EPAs provide gas-tight and pressure-resistant penetrations through the containment for one or more electrical circuits. EPA requirements are divided into mechanical (e.g. containment integrity), and electrical or optical aspects regarding safety. The mechanical requirements are valid for all EPAs.
This new edition includes the following significant technical changes with respect to the previous edition:
a) Adaptation of terminology and definitions to current available IAEA and IEC glossaries.
b) Inclusion of various new definitions and requirements.

IEC 60744:2018 provides requirements and recommendations for the design, construction and test of safety logic assemblies used in safety systems to perform category A safety functions (in accordance with IEC 61226). Safety logic assemblies include logic such as the hardwired logic assembly interfacing computer-based systems to switchgear, actuators or contactors to provide trip or engineered safety feature actuations. Safety logic assemblies are significant parts of a safety system and may include voting logic between redundant channels. This document provides a general description of safety logic assemblies for safety actuators control. The principles to meet dependability objectives are presented. The main features relating to the design requirements are described and explained.
This new edition includes the following significant technical changes with respect to the previous edition:
a) update of the references to standards published or revised since the issue of the first edition of the current standard, including IEC 61513 and IEC 61226;
b) additional requirements for operational and maintenance bypass use; requirements of voting logic; and others.

IEC 62988:2018 establishes requirements relevant to the selection and use of wireless devices in instrumentation and control (I&C) systems important to safety used in nuclear power plants (NPPs). Those I&C systems may fully consist of wireless devices. This document applies to the I&C of new NPPs and to backfit of I&C in existing NPPs. Every wireless device or wireless system that is important to safety is in the scope of this document. Both fixed and mobile devices and all data types (voice, process data, etc.) are included within the scope if they provide a safety classified function. This document restricts the use of wireless devices to systems supporting category C functions according to IEC 61226, excluding explicitly their use for categories A and B. Non-safety devices and systems may use this document as guidelines, for example to ensure that important to safety devices are not disturbed.

IEC 61500:2018 establishes requirements for data communication which is used in systems performing category A functions in nuclear power plants. It covers also interface requirements for data communication of equipment performing category A functions with other systems including those performing category B and C functions and functions not important to safety. This document gives requirements for functions and properties of on-line plant data communication by reference to IEC 60880 and IEC 60987, produced within the framework of IEC 61513. It requires categorisation of the communication functions in accordance with IEC 61226. This new edition includes the following significant technical changes with respect to the previous edition:
- the changes introduced to previously referenced standards have been confirmed to apply;
- relevant newly published standards have been referenced;
- lessons learned from several industrial applications have been incorporated.

IEC 60709:2018 is applicable to nuclear power plant instrumentation and control (I&C) and electrical systems and equipment, whose functions are required to be independent due to their contribution to:
a redundant or diverse safety group;
different defence in depth levels;
different safety classes and also with non-classified (NC) systems.  This standard is also applicable to temporary installations which are part of those I&C and *electrical systems important to safety (for example, auxiliary equipment for commissioning tests and experiments or mobile power supply systems).
This new edition includes the following significant technical changes with respect to the previous edition:
include requirements referring to the separation principle in electrical systems important to safety;
define separation criteria for I&C and electrical systems in a generic way;
align with the new revisions of IAEA documents and broaden the scope to include other aspects of separation.

IEC 63147:2017(E) contains the functional and design criteria for accident monitoring instrumentation for new plant designs and nuclear power generating stations desiring to perform design modifications. The purpose of this standard is to establish selection, design, performance, qualification, and display criteria for accident monitoring instrumentation for anticipated operational occurrences, design basis events, and severe accidents.
This standard applies to accident monitoring instrumentation intended for use during the following operations:
- As required for planned operator action related to accident mitigation,
- For assessing plant conditions, safety system performance, and making decisions related to plant response to abnormal events,
- For achieving and maintaining safe shutdown following an accident
This standard does not apply to the following:
- Accident monitoring instrumentation that is intended solely for historical recording or solely for maintenance purposes
- Other instrumentation that may be available during accident conditions.
This standard is an adoption of IEEE 497-2016 by IEC.
When applied in an IAEA / IEC environment this standard is to be used in conjunction with IEC TR 63123.

IEC TR 63123:2017(E) gives guidance for the application in the IAEA / IEC framework of IEC 63147:2017/IEEE 497 corresponding to the adoption without modification of IEEE 497:2016.

IEC TR 63084:2017(E) provides an assessment framework and activities for efficient and transparent qualification of I&C platforms for use in nuclear applications important to safety, according to nuclear standards and state of the art. The assessment aims at a pre-qualification of I&C platforms outside the framework of a specific plant design. Qualification is assumed to be pre-requisite for allowing the particular I&C platform to be used for implementation of the safety classified I&C system. It is to enable parties implementing particular plant specific I&C systems to concentrate on application functions, while for basic system functions to rely on platform qualification. Basic means of equipment qualification, as prescribed by the IEC/IEEE 60780-323, are through analysis, type testing and documented operational experience. Other documents applicable for qualification for nuclear use include IEC 61513, IEC 60880, IEC 62138, IEC 62566, IEC 62671 and IEC 61226.