IEC/TC 45 - IEC_TC_45

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.

IEC 61577-4:2009 concerns the System for Test Atmospheres with Radon (STAR) needed for testing, in a reference atmosphere, the instruments measuring radon and RnDP. Provides guidance for those facing problems associated with the production of equipment for setting up reference atmospheres for radon and its decay products.

IEC 61577-3:2011 describes the specific requirements for instruments measuring the volumetric activity of airborne short-lived radon decay products and/or their ambient potential alpha-energy concentration outdoors, in dwellings, and in workplaces including underground mines. This standard applies practically to all types of electronic instruments that are based on grab sampling, continuous sampling technique and electronic integrating measurement methods. This new edition includes the following significant technical changes with respect to the previous edition: - implementation of new requirements and tests concerning radiation detection performance; - implementation of new requirements and tests concerning environmental performance; - harmonization of the requirements and tests concerning electrical and mechanical performance with other standards in the area of radiation protection instrumentation.

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.

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.

IEC 60846-1:2009 specifies the design requirements and the performance characteristics of dose equivalent (rate) meters intended for the determination of ambient dose equivalent (rate) and directional dose equivalent (rate) as defined in ICRU Report 47. Applies to dose equivalent (rate) meters and/or monitors for the measurement of ambient dose equivalent (rate) and/or directional dose equivalent (rate) from external beta, X and gamma radiation.

IEC 62598:2011 applies to the manufacture and installation of electrical measuring systems and instruments utilizing radioactive sources (radiometric gauges, hereinafter called gauges). It also applies to source housings intended for use in the aforementioned measuring systems. This standard applies to equipment, which is not related to power production or to the fuel cycle. It specifies constructional requirements for the design of instruments utilizing radioactive sources in regard of radiation protection. This standards cancels and replaces IEC 60405.

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 colour, and to improve the coverage of back-fit or upgrade applications; - present examples of good practice.

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; - alignment with new editions of IEC 60880, IEC 61226, IEC 62138, IEC 62340 and IEC 60987; - alignment with significant advances of software engineering techniques; - integration of requirements for staff training.

IEC 61526:2010 specifies general characteristics, general test procedures, radiation characteristics as well as electrical, mechanical, safety and environmental characteristics. The only requirements specified for associated readout systems are those which affect its accuracy of readout of the personal dose equivalent and alarm settings and those which concern the influence of the reader on the dosemeter. This new edition includes the following significant technical changes with regard to the previous one: - improved determination of constancy of the dose response and statistical fluctuations; - abolition of classes of personal dose equivalent meters in relation to retention of stored information; - inclusion of usage categories of personal dosemeters.

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 application of the test equipment and its interface with the systems important to safety. The main change with respect to the previous edition includes an extension of the scope to cover all systems important to safety, and a requirement gradation for systems and equipment performing category A, B and C functions.

IEC 62363:2008 is applicable to portable and transportable contamination meters and monitors designed for the direct measurement or the direct detection of surface contamination by photon radiation emitting radionuclides. Lays down standard requirements and gives examples of acceptable methods, and also specifies general characteristics, general test conditions, radiation characteristics, electrical safety, environmental characteristics, and the requirements of the identification certificate for photon contamination meters and monitors.

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.

Defines technical requirements for equipment for monitoring of alpha-, beta- or gamma-emitting radionuclides in liquid effluents and surface waters, provides general guidance as to the possible detection capability of such equipment and indicates when and where its uses may be practicable.

Defines mechanical and operational characteristics, minimum performance characteristics and general test procedures for personnel monitoring equipment. Applies to contamination warning assemblies, meters and monitors used for the monitoring of radioactive contamination on the surface of personnel whether they be clothed or not.

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.

Specifies the classification, general design requirements, performance characteristics and test procedures for in vivo counting systems for detecting trace amounts of radionuclides in the bodies of persons working in nuclear power plants, laboratories and facilities handling radionuclides, and inhabitants living on territory which may be contaminated. The purpose is to determine the dose equivalent to organs and the effective dose of internal radiation for the whole body.

Lays down mandatory general requirements and gives examples of acceptable methods for equipment for continuous monitoring of radioactivity in gaseous effluents. Specifies general characteristics, general test procedures, radiation, electrical, safety and environmental characteristics and the identification and certification of the equipment.

Lays down specific standard requirements, including technical characteristics and general test conditions, and gives examples of acceptable methods for noble gas effluent monitors.

Establishes specific standard requirements, including technical characteristics and general test conditions and gives examples of acceptable methods for the tritium effluent monitors.

Establishes specific standard requirements, including technical characteristics and general test conditions, and gives examples of acceptable methods for aerosol effluent monitors.

Lays down specific standard requirements, including technical characteristics and general test conditions, and gives examples of acceptable methods for iodine monitors.

Defines an installed monitor for the control and detection of radioactivity of gamma emitters contained in recyclable or non-recyclable materials transported by vehicle, the conceptual requirements, general characteristics, mechanical characteristics, environmental conditions, minimal requirements, test procedures and documentation.

Lays down standard requirements and gives examples of acceptable methods, and also specifies general characteristics, general test conditions, radiation characteristics, electrical safety, environmental characteristics, and the requirements of the identification certificate for alpha, beta and alpha/beta contamination meters and monitors.

IEC 62387:2012 applies to all kinds of passive dosimetry systems that are used for measuring the personal dose equivalent (for whole body dosimetry), the personal dose equivalent (for eye lens dosimetry), the personal dose equivalent (for both whole body and extremity dosimetry), the ambient dose equivalent (for environmental dosimetry), or the directional dose equivalent (for environmental dosimetry). This standard applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv and in wide energy ranges. The dosimetry systems usually use electronic devices for the data evaluation and thus are often computer controlled.

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.

Applies to dosimetry systems that are capable of evaluating doses in the required quantity and unit (Sv) from readout signals in any quantity and unit. The only correction that may be applied to the evaluated dose (indicated value) is the one resulting from natural background radiation using extra dosemeters.

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 review the requirements; - to update the references to new IEC standards published since the first issue; - to align the standard with new editions of the relevant IAEA documents.

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 communication; - to restrict the scope to communication in systems performing category A functions.

Defines the performance of installed monitors used for the detection of gamma and neutron radiation emitters contained in objects/ containers or vehicles, general characteristics, mechanical characteristics, environmental requirements, test procedures and documentation. Such monitors are used to monitor vehicles, cargo containers, people, or packages and are typically located at national and international borders, but may be used at any location where there is a need for this type of monitoring.

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.

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 significantly in the intervening years and introduces consistency with the latest revisions of relevant IAEA documents.

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. The main changes with respect to the previous edition are listed below: - to introduce a definition for 'non-hazardous stable state'; - to clarify limits of categories; - to clarify requirements related to equipment used for beyond design events.

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.

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.

Specifies requirements for hand-held photon spectrometers, in particular for the detectors, the electronic multi-channel analyzers, the identification software, the radionuclide libraries, and the instrument display. Also specifies general characteristics, general test procedures, radiation characteristics, as well as electrical, mechanical, safety, and environmental characteristics.

Specifies constructional requirements for the design of instruments and the radiation protection to be provided in the case of radiometric gauges. Special attention is drawn to the stability of the source housing in the event of fire.

Specifies requirements for the dosemeter and, if supplied, for its associated readout system. Specifies general characteristics, general test procedures, radiation characteristics as well as electrical, mechanical, safety and environmental characteristics. Also specifies classes of personal dose equivalent meters in relation to retention of stored information.

Specifies the design requirements and the performance characteristics of dose equivalent (rate) meters intended for the determination of ambient dose equivalent (rate) and directional dose equivalent (rate) as defined in ICRU Report 47.

Specifies requirements for the performance characteristics of neutron ambient dose equivalent (rate) meters, and prescribes the methods of testing in order to determine compliance with this standard. Specifies general characteristics, general test procedures, radiation characteristics, electrical, mechanical, safety and environmental characteristics, and also the identification certificate

Defines the terms specific to the CAMAC modular instrumentation and digital interface system which forms the subject of several IEC standards. It includes also other terms whose use is well established and those of corresponding characteristics of the NIM system of instrumentation.

Applicable to equipment used for prospecting radioactive ores or minerals responding to radioactive excitation, and for underground studies.

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

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.

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.

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

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.

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

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.

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.