This Safety Guide considers the application of a graded approach throughout the lifetime of a research reactor (site evaluation, design, construction, commissioning, operation and preparation for decommissioning), including utilization and experiments that are specific features of research reactor operation. A major aspect of this Safety Guide involves the use of a graded approach in the application of the safety requirements for the design and operation of research reactors, so that the fundamental safety objective to protect people and the environment from harmful effects of ionizing radiation is achieved. It is intended for use by operating organizations, regulatory bodies and other organizations involved in the design, construction and operation of research reactors. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-22, which it supersedes.

With rapidly advancing digital technologies, smart devices are increasingly used in nuclear power plants. These smart devices can be implemented as separate or standalone field components or embedded as components in other equipment or systems and can be used to increase plant reliability, enhance safe operation and improve testing and monitoring functions. However, the use of smart devices may potentially introduce new hazards, vulnerabilities and failure modes. The safety aspects and design criteria associated with the safe use of industrial commercial smart devices in systems important to safety considered in this publication include: functional suitability and the evidence required to demonstrate this suitability, quality, qualification, the consideration of certification by non-nuclear organizations using non-nuclear standards, and aspects affecting integration of the smart device into existing systems in order to ensure that the smart device will retain its suitability for the required lifetime.

In recent decades, the number of IAEA Member States planning to extend the operation of their nuclear power plants (NPPs) beyond the time frame originally anticipated has steadily increased. These decisions have been influenced by the significant economic advantages offered by the long term operation (LTO) of existing NPPs. This Safety Report complements IAEA Safety Standards Series Nos SSR?2/2 (Rev. 1), Safety of Nuclear Power Plants: Commissioning and Operation, and SSG?48, Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants. It provides information on selected topics from the latter, and specifically, it addresses data collection and record keeping, scope setting for structures, systems and components, plant programmes, corrective action programmes, and documentation of ageing management and LTO assessment. The publication focuses on NPPs throughout their lifetime, including operation beyond the time frame originally established for their operation and decommissioning, while considering the different reactor designs that exist around the world. It is also relevant for facilities for spent fuel storage and radioactive waste management at NPPs. It may also be used as a basis for managing the ageing of other nuclear installations and for radioactive waste 2 management facilities. This Safety Report is intended to provide information for operating organizations but may be also used by regulatory bodies.

On request, the IAEA performs comprehensive audits of radiotherapy programmes to assess the whole process, including aspects such as organization, infrastructure and clinical and medical physics components. The objective of a comprehensive clinical audit is to review and evaluate the quality of all components of the practice of radiotherapy at the institution, including its professional competence, with a view to quality improvement. A multidisciplinary team, known as Quality Assurance Team in Radiation Oncology (QUATRO), comprising a radiation oncologist, a medical physicist and a radiation therapist, are required to carry out the audit. The present publication provides revisions of the QUATRO guidelines published in 2007, by incorporating new procedures relevant to newer technologies and modalities that have become routinely used in radiotherapy centres in the interim period.

This Safety Report provides practical guidance to governments, regulatory bodies, other relevant competent authorities, and building and construction material industries on setting up arrangements for regulatory control relevant to building and construction materials that give rise to radiation exposures at any step in their life cycle. These steps would include raw material production, manufacturing, supply and end use. It also considers the responsibilities of the suppliers of raw, waste or recycled materials for incorporation into building or construction materials, and it covers verification programmes for building and construction materials prior to their use as well as in completed construction projects.

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This Safety Guide identifies the main objectives and responsibilities of the operating organization for the recruitment, qualification and training of personnel for new and existing nuclear power plants to establish and maintain a high level of competence of personnel and to ensure safe operation of the nuclear power plant. This publication can also be used as a guide for the recruitment, training and qualification of personnel for nuclear installations other than nuclear power plants.

The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.

Aimed primarily at operating organizations of nuclear power plants (NPPs) and regulatory bodies, this Safety Guide provides specific recommendations to ensure that operations in NPPs are conducted in a safe, effective, thorough and professional manner. It identifies the main responsibilities and operating practices in relation to such safe operation. The structure of the operations department, which is the part of the operating organization responsible for the conduct of operations of an NPP is addressed. Also addressed are the setting of high standards of performance and making safety related decisions in an effective manner, conducting control room activities in a thorough and professional manner and maintaining a nuclear power plant within the established operational limits and conditions.

Written for use by operating organizations of nuclear power plants and regulatory bodies, this Safety Guide provides specific recommendations on maintenance, testing, surveillance and inspection to ensure that the levels of reliability and availability of all structures, systems and components important to safety remain in accordance with the assumptions and intent of the design, and also that the safety of the plant is not adversely affected after the commencement of operation. The publication covers the establishment and implementation of preventive and corrective maintenance programmes; testing surveillance and inspection; the repair of defective plant equipment; the provision of related facilities and equipment; procurement; and generating and retaining records of maintenance activities.

This Safety Guide provides recommendations on the safety assessment for research reactors in the authorization process, and on performance of safety analysis and preparation of the safety analysis report. It also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates guidance on interfaces between nuclear safety and nuclear security. The recommendations in this Safety Guide are intended for operating organizations of research reactors; it can also be used by designers performing a safety assessment for a research reactor. Furthermore, this guide provides useful guidance for regulatory bodies performing a review and assessment of submitted safety analysis reports as an important document within authorization process. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-20, which it supersedes.

Written for use by regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide addresses the commissioning, operation and preparation for decommissioning stages for a nuclear power plant. The role of the operating organization in the siting, design, manufacturing and construction of a nuclear power plant is outside the scope. In most States, the operating organization is the legal entity responsible for safety, financial and commercial obligations, as well as other obligations that are connected with the operation of a nuclear power plant. This Safety Guide is solely concerned with those responsibilities and obligations that are necessary to ensure the safe operation of the nuclear power plant(s) under the control of the operating organization.

This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.4, which it supersedes. The revised version provides specific recommendations on developing, formulating and presenting the operational limits and conditions as well as the operating procedures for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations in this publication are intended for use by operating organizations of research reactors, regulatory bodies and other relevant organizations involved in a research reactor project.

In the context of the safe management of disused sealed radioactive sources, an important and emerging issue of immediate concern is the management of depleted uranium (DU) contained in radiation shielding materials, as potential radioactive waste. This publication presents relevant information on technical issues and factors, as well as specific Member State experiences leading to the identification of potential options for the management of DU shields. Various options for safe, secure and cost-effective solutions have been explored, ranging from returning to manufacturer, including reuse, recycling, storage and disposal in licensed facilities.

This publication gives practical information and examples on safety analysis principles and methods as well as the contents of licensing documentation needed to support application of IAEA safety standards to nuclear fuel cycle facilities. A systematic methodology is presented, covering the establishment of acceptance criteria, hazard evaluation, identification of postulated initiating events, analysis of accident sequences and consequences. Information is also provided on application of the results of the safety analysis in the design and operational phases, and on appropriate management system processes. The publication applies to all lifetime stages of relevant facilities and for modifications and upgrades. The information presented may be used for periodic safety reviews and consideration of extended lifetime of facilities. With respect to licensing documentation, the publication provides indicative contents and format of the safety analysis report as a higher level document that incorporates the information required at various steps in the licensing and re-licensing process.

This Safety Guide provides recommendations on the structure and content of the safety analysis report to be submitted by the operating organization to the regulatory body for authorization of the siting, construction, commissioning, operation and decommissioning of a nuclear power plant. It is intended to facilitate both the development of the safety analysis report by the operating organization and the checking of its completeness and adequacy by the regulatory body. The publication is a revision of IAEA Safety Standards Series No. GS?G?4.1, Format and Content of the Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi accident and the subsequent stress tests performed. It also describes good practices and experience from the use of safety analysis reports for newly built nuclear power plants in different States and informs on recent progress made in approaches to safety assessment.

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 publication has been developed to assist IAEA Member States in establishing and maintaining regulatory control through notification, authorization, inspection and enforcement in relation to facilities and activities with radiation sources, in order to achieve the fundamental safety and security objectives. The publication addresses the implementation of the requirements for safety and security in a harmonized way, taking into account differences in the requirements as well as differences in States' regulatory infrastructures. For example, in some States the same regulatory body is responsible for the control of safety and security, while in others, safety and security are controlled by separate regulatory bodies. A harmonized approach for notification, authorization, inspection and enforcement is intended to improve the efficiency and effectiveness of regulatory control through concurrent inspection for safety and security.

This Safety Guide provides recommendations on the establishment of a framework for safety in accordance with the IAEA safety standards for States deciding on and preparing to embark on a nuclear power programme. In this regard, it proposes 197 safety related actions to be taken in the first three phases of the development of the nuclear power programme, to achieve the foundation for a high level of safety throughout the entire lifetime of the nuclear power plant (NPP). This includes safety in the construction, commissioning, and operation of the NPP and the associated management of radioactive waste and spent fuel, and safety in decommissioning. Thus, it contributes to the building of leadership and management for safety and of an effective safety culture and serves as guidance for self-assessment by all organizations involved in the development of a safety infrastructure.

This publication provides Member States with a structured approach to developing an effective human resource management (HRM) strategy, which can be adapted to suit the nature and scope of the national nuclear power programme. It identifies the four components of an integrated HRM strategy particularly relevant for countries developing a nuclear power programme for the first time and examines these issues in the context of each phase of the Milestones Approach. In each phase the publication identifies the required actions related to these issues, and presents observations and lessons learned from Member States.

It was formerly hypothesized that placing a radioactive source near the end of a lightning conductor would improve the likelihood that lightning would strike the conductor. It is estimated that hundreds of thousands of these radioactive lightning conductors (RLCs) were installed worldwide. However, no convincing scientific evidence has been produced to demonstrate increased efficacy and the use of RLCs does not comply with the justification principle established in the International Basic Safety Standards. Therefore, most countries have recognized the need to stop installing RLCs and to remove existing devices from the public domain. This publication summarizes all technical and organizational aspects related to the recovery and dismantling of RLCs as well as the safe management of the associated disused radioactive sources. The report describes the general arrangement, highlights the quality management components, identifies the staffing requirements and covers certain areas vital for the preparation for dismantling and source conditioning operations. Relevant information is provided on the various models of radioactive lightning conductors and how their design features influence the dismantling and source recovery operations. The publication also incorporates the most recent experience on various concluded projects in several Member States and captures the lessons learned.

Security management for radioactive material in use, storage and associated facilities includes the establishment and implementation of policies, plans, procedures and processes for the security of radioactive material. Security management assists to ensure that the security systems are effective, reliably operated and maintained with the necessary resources. Based on extensive input from technical and legal experts, this publication sets forth security management as an essential tool to verify that personnel, procedures and equipment operate interdependently and in an integrated manner, and that the leadership and personnel responsible for security demonstrate the highest commitment towards promoting a robust nuclear security culture within the organization. This Technical Guidance references and takes into account other IAEA Nuclear Security Series publications that provide guidance relating to security management. The document further provides guidance , including on the development of a security plan for radioactive material in use and in storage and for associated facilities. The Security Plan is an essential component of an operators licensing submission package. This Technical Guidance takes into account other IAEA Nuclear Security Series publications that provide guidance relating to security management and relating to security plans.

Probabilistic fault displacement hazard analysis (PFDHA) is a relatively new methodology, and actual examples of applications are quite limited. The current publication provides an introduction to probabilistic approaches to fault displacement hazard assessment with reference to relevant IAEA safety standards. It delineates the most important aspects of PFDHA (including up to date practices, open problems, and challenging issues) within a coherent framework. The information provided will be valuable not only for Member States when applying PFDHA to the site safety assessment of existing installations, but also for nuclear power plant operating organizations, regulatory bodies, vendors, technical support organizations and researchers working in the area of seismic hazard assessmen

Neutron Activation Analysis (NAA) is the most common technique used in research reactors worldwide. The IAEA aims to enhance quality assurance in NAA laboratories by supporting annual proficiency testing, by developing and offering relevant e?learning as well as specialized publications. This publication, which is based on the most up to date relevant ISO guides and international practices, provides practical guidance on quality assurance (QA) and quality control (QC) in NAA laboratories. It is intended to be used in the day?to?day work of NAA at research reactors. Potential sources of errors and associated QA/QC actions are detailed for all main areas of NAA practice. Easy to use tables are provided, intended for direct reference in the laboratory.