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 ...view more

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This document 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. Activities that are mainly system level activities (for example, integration, validation and installation) are not ...view more

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    • Corrigendum
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See the scope of the revised IEC 60709 in 45A/1113/CDV that was unchanged for the preparation of the proposal of FDIS to be circulated in parallel in CENELEC.

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See the scope of IEC 62646:2016. Adoption of IEC 62646 is to be done without modification

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IEC 60964:2018 is available as IEC 60964:2018 RLV which contains the International Standard and its Redline version, showing all changes of the technical content compared to the previous edition.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 systemat...view more

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See the scope of IEC 62465:2010. Adoption of IEC 62465 is to be done without modification.

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See the technical scope of the amendment of IEC 62808 in 45A/1134/CDV that was unchanged for the preparation of the proposal of FDIS to be circulated in parallel in CENELEC.

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    • Amendment
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See the scope of the revised IEC 60709 in 45A/1113/CDV that was unchanged for the preparation of the proposal of FDIS to be circulated in parallel in CENELEC.

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IEC/IEEE 60780-323:2016 describes the basic requirements for qualifying electrical equipment important to safety and interfaces (electrical and mechanical) that are to be used in nuclear facilities. The principles, methods, and procedures described are intended to be used for qualifying equipment, maintaining and extending qualification, and updating qualification, as required, if the equipment is modified. The qualification requirements in this standard, when met, demonstrate and document the a...view more

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IEC 62765-1:2015 provides strategies, technical requirements, and recommended practices for the management of ageing to ensure that ageing of pressure transmitters important to safety in nuclear power plants (NPPs) 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 standard is aligned with IEC 62342, which provides guidance on ageing management for I&C systems important to safety in NPPs. This st...view more

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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 ...view more

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IEC 60965:2016 establishes requirements for the Supplementary Control Room provided to enable the operating staff of nuclear power plants to shut down the reactor, where previously operating, and maintain the plant in a safe shut-down state in the event that control of the safety functions can no longer be exercised from the Main Control Room, due to unavailability of the Main Control Room or its facilities. The design has to ensure that the Supplementary Control Room is protected against the ha...view more

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IEC 61227:2008 identifies the Human-Machine Interface (HMI) requirements for discrete controls, multiplexed conventional systems, and soft control systems. To be used with IEC 60964 and IEC 61772. Is intended for application to the design of new main control rooms in nuclear power plants designed to IEC 60964. This new edition takes into account the fact that computer design engineering techniques have advanced significantly during recent years.

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Provides the functional requirements for the alarm systems in the main control room of nuclear power plants. Establishes the human factors requirements and the design guidelines for alarm presentation for the main control room of nuclear power plants.

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Is applicable to computer-system hardware for systems of Class 1 and 2 (as defined by IEC 61513) in nuclear power plants. This new edition reflects recent developments in computer system hardware design, the use of pre-developed hardware and changes in terminology.

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Specifies functional analysis and assignment procedures for the design of the control-room system for nuclear power plants and gives rules for developing criteria for the assignment of functions. Supplements IEC 60964. Is applicable to the design of new control-rooms or to backfits to existing control-rooms.

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IEC 62566:2012 provides requirements for achieving highly reliable 'HDL-Programmed Devices' (HPD), for use in I&C systems of nuclear power plants performing functions of safety category A 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 FPGAs or similar micro-electronic technologies.

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IEC 61772:2009 supplements IEC 60964 and presents design requirements for the application of VDUs in main control rooms of nuclear power plants. Assists the designer in specifying VDU applications including displays on individual workstations and larger displays for group-working or distant viewing. The main technical changes with respect to the previous edition are as follows: - expand the previous text to cover the use of large screen displays, to provide improved recommendations on the use of...view more

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Instrumentation and control (I&C) systems important to safety may be implemented using conventional hard-wired equipment, computer-based (CB) equipment or by using a combination of both types of equipment (see Note 1). IEC 61513:2011 provides requirements and recommendations for the overall I&C architecture which may contain either or both technologies. The main technical changes with regard to the previous edition are as follows: - alignment with the latest revisions of IAEA documents; - alignm...view more

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Lays down principles for testing I&C systems performing category A, B and C functions, per IEC 61226, during normal power operation and shutdown, so as to check the functional availability especially with regard to the detection of faults that could prevent the proper operation of the functions important to safety. Covers the possibility of testing at short intervals or continuous surveillance, as well as periodic testing at longer intervals. It also establishes basic rules for the design and ap...view more

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IEC 61500:2009 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 second edition is intended to accomplish the following: - to change the focus from multiplexed data transmission to data communicati...view more

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Defines the technical requirements to be met for I&C systems important to safety and their cables, in order to achieve adequate physical separation between redundant sections of a system and between a system and another system.

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Gives requirements related to the avoidance of CCF of I&C systems that perform category A functions; additionally requires the implementation of independent I&C systems to overcome CCF, while the likelihood of CCF is reduced by strictly applying the overall safety principles of IEC SC 45A (notably IEC 61226, IEC 61513, IEC 60880 and IEC 60709); gives an overview of the complete scope of requirements relevant to CCF.

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IEC 61226:2009 establishes a method of classification of the information and command functions for nuclear power plants, and the instrumentation and control systems and equipment that provide those functions, into categories that designate the importance to safety of the function. The resulting classification then determines relevant design criteria. Is applicable to all the information and command functions and the instrumentation and control systems and equipment that provide those functions. ...view more

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IEC 60964:2009 provides functional design requirements to be used in the design of the main control room of a nuclear power plant to meet operational and safety requirements. Also provides functional interface requirements which relate to control room staffing, operating procedures, and the training programmes which, together with the human-machine interface, constitute the control room system. This new edition takes into account the fact that software engineering techniques advanced significant...view more

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Provides requirements for the software of computer-based instrumentation and control (I&C) systems of nuclear power plants performing functions of safety category A as defined by IEC 61226. Provides requirements for the purpose of achieving highly reliable software. Addresses each stage of software generation and documentation, including requirements specification, design, implementation, verification, validation and operation.

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Provides requirements for the software of computer-based I&C systems performing functions of safety category B or C as defined by IEC 61226. Complements IEC 60880 and IEC 60880-2, which provide requirements for the software of computer-based I&C systems performing functions of safety category A. Is also consistent with, and complementary to, IEC 61513.

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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 edit...view more

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See the scope of IEC 62645:2019. Adoption of IEC 62645:2019 is to be done without modification.

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See the scope of IEC 63046:2020. Adoption of IEC 63046:2020 is to be done without modification.

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See the scope of IEC/IEEE 60980-344:2020. Adoption of IEC/IEEE 60980-344:2020is to be done without modification.

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    • Standard
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See the scope of IEC 62859:2016 and of its Amendment1:2019. Adoption of IEC 62859:2016+Amdt1:2019 is to be done without modification.

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    • Standard
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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 includ...view more

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This document 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), as shown in Figure 1. It establishes requirements for the ERF features and ERF I&C equipment to: • coordinate on-site operational e...view more

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IEC 62855 provides the electrotechnical engineering guidelines for analysis of AC and DC electrical power systems in nuclear power plants (NPPs) in order to demonstrate that the power sources and the distribution systems have the capability for safe operation and shut down of the NPP, bringing it to a controlled state after an anticipated operational occurrence or accident conditions and finally reaching a safe state. The analytical studies discussed in this document provide assurance that the d...view more

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This part of IEC/IEEE 62582 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 w...view more

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This document establishes, for nuclear power plants2, 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 cri...view more

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IEC 60965:2009 establishes requirements for the supplementary control points provided to enable the operating staff of nuclear power plants to shut down the reactor and maintain the plant in a safe shut-down state in the event that control of the safety functions can no longer be exercised from the main control room, due to unavailability of the main control room or its facilities. The main technical changes with regard to the previous edition are as follows: - to clarify the definitions and rev...view more

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    • Standard
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Is applicable to computer-system hardware for systems of Class 1 and 2 (as defined by IEC 61513) in nuclear power plants. This new edition reflects recent developments in computer system hardware design, the use of pre-developed hardware and changes in terminology.

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Dimensions of the standard plug-in unit and rack-mounting unit; connector dimensions and pin arrangements.

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Defines a modular instrumentation system capable of linking transducers and other devices with digital controllers or computers. It consists of mechanical standards and signal standards sufficient to ensure compatibility between units from different sources of design and production. The CAMAC system is primarily designed for nuclear instrumentation but may be utilized also for other applications.

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Applies to equipment for the monitoring of radioactive substances within plant process streams of stationary nuclear power plants with light-water reactors during specified normal operation (routine operation) and during anticipated operational occurrences (incidents). Provides criteria for the design, selection, functional location, testing and calibration of stationary radiation equipment to be used for continuous monitoring of plant process streams.

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    • Standardization document
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Standard interface between a number of 'CAMAC' measuring instruments, display units, control units, actuators, data processing equipment (computers) and communication equipment.

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Characteristics of the 'parallel highway' for the CAMAC instrumentation and interface system described in HD 357.This highway provides for the high-speed transfer of data between CAMAC crates and computers or other controllers and for the interconnection of CAMAC crates in multicrate systems. Signal, timing and logical organization. Appendix: specifications of a standard crate controller.

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Gives the standard values for the diameters, heights and wall thickness of planchets made in well flat and dish-type configurations.

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Defines a method for incorporating more than one source of control into a CAMAC crate through auxiliary controllers located in normal stations in the crate. An auxiliary controller bus (ACB) and priority arbitration protocol are fully defined.

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Presents a set of software subroutines to provide a general capability for communications with CAMAC systems as defined in EN 60516. The subroutines are suitable for use with Fortran although they are not restricted to that language.

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Recommendations are presented for uniform practice with regard to block transfers in CAMAC modular instrumentation and digital interface systems of IEC 60516

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