This Safety Guide provides recommendations for ensuring radiation protection in the design of new nuclear power plants, design modifications to operating plants, and checking the adequacy of the radiation protection aspects of design at different stages in the lifetime of operating plants. It also provides recommendations for measures to be taken in the design for the protection of site personnel, the public and the environment, and outlines the methodologies used to calculate on-site and off-site radiological conditions and to verify that the design provides an adequate level of radiation protection during operating lifetime and decommissioning. The guide is intended primarily for land-based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications. This publication is intended for organizations responsible for designing, manufacturing, and constructing nuclear power plants, operating organizations and contractors, including plant operators who are involved in planning, managing and implementing the design and design modification of nuclear power plants, and regulatory bodies and technical support organizations.

This Safety Guide provides recommendations on the safe disposal of disused sealed radioactive sources in borehole disposal facilities. Sealed radioactive sources are used all over the world for a wide range of purposes, in areas such as health, industry, research and agriculture. These sources are usually managed safely while in use, but States often experience challenges in their management once the sources reach the end of their useful lives. Even though they may no longer emit sufficient radiation for their intended purpose, disused sources are radioactive and potentially hazardous, and they need to be managed as radioactive waste. Written for regulators and others involved in the development and management of borehole disposal facilities, the objective of this Safety Guide is to provide recommendations on the commissioning, operation, closure, institutional control and regulation of borehole disposal facilities for disused sealed radioactive sources, and small volumes of low and intermediate level secondary waste generated during the management of these sources. This Safety Guide can also be used as a basis for reassessing and, where appropriate, upgrading the safety of existing borehole disposal facilities.

The objective of this Safety Guide is to provide recommendations for meeting the requirements of GSR Part 4 (Rev. 1) in the development and application of Level 1 Probabilistic Safety Assessments (PSAs) for nuclear power plants (NPPs). The recommendations provided in this publication promoting technical consistency among Level 1 PSA studies, in order to provide reliable support for applications of PSAs and risk informed decision making, particularly to support the design of NPPs and decision making during plant commissioning and operation. The revised Safety Guide's scope encompasses the main methodological aspects of PSA and in particular has been updated to reflect developments in specific areas, such as passive systems reliability, computer based systems reliability, combinations of hazards, human reliability analysis and to expand the scope of PSA to include site level risk considerations such as multi-unit and spent fuel pool PSA.

Radiation sources used in research and education include particle accelerators, sealed radioactive sources, such as low activity check sources and high activity sealed radioactive sources in irradiators; unsealed radioactive sources that are used as tracers in field work and in laboratory work; naturally occurring radioactive material and X ray generators such as diffraction apparatus and fluorescence analysers. This Safety Guide provides recommendations on how to meet the relevant requirements of IAEA Safety Standards Series No. GSR Part 3 in the use of radiation sources in research and education. It provides guidance on the control of occupational exposure and of public exposure, for planned exposure situations and, where appropriate, emergency exposure situations and on the safety measures specific to this practice. The recommendations in this publication are aimed primarily at operating organizations such as educational and research establishments including schools, colleges, universities and technical institutes that are authorized to use radiation sources in academic programmes, as well as their employees, students, teachers and radiation protection officers. The guidance will also be of interest to individuals working for regulatory bodies and other relevant organizations involved in design, manufacture, supply and service of radiation sources and associated equipment for research and education.

This Safety Guide provides recommendations on the seismic safety evaluation of nuclear installations. It addresses all types of new and existing nuclear installations. This Safety Guide presents three assessment methodologies: the deterministic approach, generally known as seismic margin assessment (SMA), seismic probabilistic safety assessment (SPSA), and a combination of SMA and SPSA known as ‘probabilistic safety assessment (PSA) based SMA. This Safety Guide provides specific recommendations on applying a performance-based graded approach to the seismic safety evaluation of nuclear installations other than nuclear power plants. It also covers the relation between seismic safety margins and defense-in-depth (DiD) level 3 and level 4. For new nuclear installations, this Safety Guide provides recommendations to assess adequacy of seismic margin to avoid cliff edge effects considering DiD level 3 and level 4. This publication is intended for use by regulatory bodies, operating organisations, and designers of nuclear installations.

The objective of this Safety Guide is to provide recommendations for the design of new nuclear power plants related to defence in depth and the practical elimination of plant event sequences that could lead to an early radioactive release or a large radioactive release. It also provides recommendations in relation to design aspects of defence in depth, in particular on those aspects associated with design extension conditions.??Since the introduction of the term "practical elimination" in the early 90's and the recognition that accident conditions could include design extension conditions without significant fuel degradation and design extension conditions with core melting, those topics have been the subject of extensive discussions and several publications. The purpose of this publication is to facilitate international consensus on the understanding of those topics among regulators and designers and to provide recommendations for their consistent implementation in relevant nuclear power plant designs. In particular, this Specific Safety Guide gives recommendations related to the demonstration of the implementation of the practical elimination concept for those plant event sequences that could lead to an early radioactive release or a large radioactive release, which relies on the physical impossibility or on the high-level confidence that they are extremely unlikely to arise.

This Safety Guide provides recommendations on meeting the requirements established in IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material, 2018 Edition, for a radiation protection programme for the transport of radioactive material. The objectives of a radiation protection programme for the transport of radioactive material are to provide for adequate consideration of radiation protection measures in transport; to ensure that the system of radiological protection is adequately applied; to enhance a safety culture in the transport of radioactive material; and to provide practical measures to meet these objectives. The recommendations provided in this Safety Guide are applicable to the transport of radioactive material by all modes on land, water, or in the air, including transport that is incidental to the use of the radioactive material. The intended audience for this Safety Guide includes competent authorities, consignors, carriers, consignees, and operators of ports (e.g. harbours, seaports and airports). It will also be of interest to the employees of public authorities (customs authorities, harbour authorities, port authorities) concerning activities associated with the transport of radioactive material that involve radiation exposure.

This publication provides specific recommendations on research reactor instrumentation and control systems and software important to safety, including instrumentation and control system architecture and associated components, from sensors to actuators, operator interfaces and auxiliary equipment, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations and guidance apply to both the design and configuration management of instrumentation and control systems for new research reactors and the modernization of the instrumentation and control systems at existing research reactor facilities. In addition, this Safety Guide provides recommendations and guidance on human factors engineering and human-machine interfaces, and for computer based systems and software for use in instrumentation and control systems important to safety. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-37, which it supersedes.

This Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.

This Safety Guide provides recommendations on radiation protection and radioactive waste management in the design and operation of research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It identifies important components that should be considered at the design stage with regard to facilitating radiation protection and radioactive waste management. It also recommends good practices in implementing operational radiation protection and radioactive waste management programmes, and in their optimization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.6, which it supersedes.

The transport of radioactive material is an essential activity worldwide. To ensure the protection and safety of people, property and the environment, appropriate regulations for the safe transport of radioactive material, both at the national level and at the international level, are necessary. Competent authorities regulate the transport of radioactive material through the application of national regulations, which should be consistent with relevant international regulations. This Safety Guide provides recommendations on actions that competent authorities should take to ensure compliance with the applicable regulations for the safe transport of radioactive material.

This Safety Guide provides recommendations on the operating organization and on personnel for research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.5, which it supersedes