Instrumentation, Control and Electrical Power Systems of Nuclear Facilities
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Technical committeeTypeAcronymIEC 63186CommitteePublished year2021Description
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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.
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Technical committeeTypeAcronymIEC 63147CommitteePublished year2017Description
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.Technology -
Technical committeeTypeAcronymIEC 63096CommitteePublished year2020Description
IEC 63096:2020 provides a catalogue of highly recommended and optional security controls graded (see Clause 5 to Clause 20) in line with the security degrees defined by IEC 62645. These are intended for nuclear I&C programmable digital systems and architecture including related activities (I&C platform development, project engineering, operation and maintenance).
This document is intended to be used for designing I&C systems for new NPPs, and modernizing and modifying I&C systems for existing NPPs throughout the I&C programmable digital systems lifecycle. It may also be applicable to other types of nuclear facilities.
This document addresses the whole scope of nuclear I&C programmable digital systems, both safety and non-safety classified. The scope of this document also includes sensors, actuators and electrical systems that belong to the I&C control loop. It is also applicable to those parts of electrical systems covered by IEC 63046, which rely on digital programmable technology. For better readability the terms “nuclear I&C programmable digital systems”, “I&C system” or “I&C platform” used in this document implicitly include electrical systems if the electrical system includes a programmable digital systems.Technology -
Technical committeeTypeAcronymIEC 63046CommitteePublished year2020Description
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.
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Technical committeeTypeAcronymIEC 62988CommitteePublished year2018Description
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.
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Technical committeeTypeAcronymIEC 62954CommitteePublished year2019Description
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.Technology -
Technical committeeTypeAcronymIEC 62887CommitteePublished year2018Description
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.
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Technical committeeTypeAcronymIEC 62859CommitteePublished year2016Description
IEC 62859:2016+A1:2019 provides a framework to manage the interactions between safety and cybersecurity for nuclear power plant (NPP) systems, taking into account current IEC standards addressing these issues and the specifics of nuclear I&C programmable digital systems. This standard establishes requirements and guidance to:
- integrate cybersecurity provisions in nuclear I&C architectures and systems, which are fundamentally tailored for safety;
- avoid potential conflicts between safety and cybersecurity provisions;
- aid the identification and the leveraging of the potential synergies between safety and cybersecurity.
This consolidated version consists of the first edition (2016) and its amendment 1 (2019). Therefore, no need to order amendments in addition to this publication.Technology -
Technical committeeTypeAcronymIEC 62855CommitteePublished year2016Description
IEC 62855:2016 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. This standard is intended to be used:
- for verification of the design of new nuclear power plants;
- for demonstrating the adequacy and impact of major modifications of electrical power systems in operating nuclear power plants;
- and where there is a requirement to assess and establish operating limits and constraints for existing plants.Technology -
Technical committeeTypeAcronymIEC 62808CommitteePublished year2015Description
IEC 62808:2015+A1:2018 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). This consolidated version consists of the first edition (2015) and its amendment 1 (2018). Therefore, no need to order amendment in addition to this publication.
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