Instrumentation, Control and Electrical Power Systems of Nuclear Facilities

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 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 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.

IEC TR 62987:2015(E) provides guidance on nuclear-specific issues when applying failure modes and effects analysis (FMEA) and related methods to instrumentation and control systems important to safety in nuclear power plants. The information in this Technical Report complements, for nuclear power plant applications, the procedure for FMEA in IEC 60812.

IEC TR 62918:2014 describes the state of wireless technology for industrial applications in fossil and chemical plants and discusses the specific issues to be addressed in order to apply wireless technologies to nuclear power plants.

Gives guidelines for the instrumentation and control systems of interim storage and final repository of nuclear fuel and waste. Covers storage at all types of facilities, such as, fuel fabrication plants, nuclear power plants, reprocessing facilities, interim storage facilities, encapsulation facilities and final repositories for operational waste and spent nuclear fuel.

IEC/TR 62096:2009 is intended to support owners of a nuclear power plant in the decision-making process and in the preparation for partial or complete modernization of the I&C. For this, it provides a summary of the motivating factors for I&C modernization, the principal options for the elaboration of different scenarios for I&C modernization, the technical and economic criteria for the selection of a long term I&C strategy, the principal aspects to be taken into account for a detailed technical feasibility study. This new edition includes the following significant technical changes with respect to the previous edition:
- update on references, taking into account standards published since the previous edition;
- update on the terminology, incorporation of a number of clarifications proposed by National Committees.

IEC/TR 61838:2009 provides a survey of some of the methods by which probabilistic risk assessment results can be used to establish "risk-based" classification criteria, so as to allow FSEs to be placed within the four categories established within IEC 61226. The safety principles and the usefulness of a risk-based approach to classification are discussed and a description of four different approaches is presented. The main technical changes in this second edition with regard to the previous edition are as follows:
- to update the references and the terminology;
- to take into account the progress done since edition 1.

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.