Providing recommendations on the application of the concept of clearance for materials, objects and buildings that are to be released from regulatory control, this publication supports the application of the relevant requirements of IAEA Safety Standards Series No. GSR Part 3. It includes detail on the regulatory framework for clearance; the clearance process; the derivation of clearance levels; the application of clearance to solid materials, liquids and gases; generic clearance and specific clearance using activity concentration and surface contamination clearance levels. It also provides recommendations on the involvement of interested parties. Written for governmental officials, and those working for regulatory bodies and operating organizations, this publication will also be of interest to technical service providers in radiation protection. The recommendations provided are applicable to facilities that use, manufacture, process or store radioactive material, such as nuclear power plants, research reactors, other nuclear fuel cycle facilities, facilities for the management of radioactive waste, industrial plants, medical facilities, research facilities, educational facilities and accelerators. The recommendations in this publication also apply to industries processing materials containing radionuclides of natural origin and to the management of material originating from remediation activities or from post- emergency situations.

Intended for use by government officials, and those working for regulatory bodies and operating organizations, this publication will assist in the application of IAEA Safety Standards Series No. GSR Part 3 in relation to the concept of exemption of practices or sources within practices from regulatory control. It addresses the application of a graded approach to the concept of exemption through the use of generic exemption and specific exemption. It explains the concept of exclusion and its relationship to exemption and clearance. The recommendations provided in this publication are applicable to all facilities and activities that use, manufacture, process, trade or store radioactive sources or material containing either natural or artificial radionuclides. The Safety Guide primarily addresses exemption from regulatory control in planned exposure situations. Although, the concept of exemption is only applicable to planned exposure situations, guidance on the application of a screening approach for decision making in managing certain existing exposure situations is also provided.

This IAEA Safety Report describes neutron monitoring procedures and equipment that may be used for radiation protection in nuclear power production, medical and industrial applications, research institutions and civil air service. It provides guidance on measuring operational quantities of neutron radiation and practical advice for safely carrying out neutron radiation protection dosimetry, including methods for establishing traceability of those measurements to national standards. This publication is intended for designers and manufacturers of radiation monitors and personal dosimeters and radiation protection professionals who develop radiation protection standards or neutron monitoring programmes.

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.

The terms for describing advanced nuclear power plants (NPPs) need to conform to the broad, general, common understanding by the public as well as by the technical community. This publication is a revision of IAEA-TECDOC-936 incorporating developments and initiatives since 1997 in the areas of advanced, evolutionary, and innovative nuclear reactor designs, description of design development phases, inclusive of relevant safety and regulatory terminology, consistent with current IAEA safety standards and glossaries. The objective of this publication is to provide Member States with up-to-date terms for describing advanced NPPs, to draw distinctions between design phases reflecting the maturities of designs, and to clarify definitions of commonly used terms in describing advanced NPPs.

This Safety Report explains how the concepts of attribution of health effects and inference of risks can be taken into account in the application of IAEA safety standards, so as to implement them more effectively. In particular, this publication demonstrates explicitly what the relevant provisions of the safety standards are for high and moderate levels of exposure where health effects might be able to be attributed to the exposure, and for low and very low levels of exposure where risks can only be inferred. This Safety Report also aims to support more effective communication by clarifying the proper use of certain concepts detailed in the safety standards and plain language explanations of the concepts of attribution of effects and inference of risk are provided.

A periodic safety review is considered an effective way to obtain an overview of nuclear power plant safety. It is also used to determine reasonable and practicable modifications to maintain a high level of safety during continued operation, and to justify operation of a nuclear power plant beyond the original time frame. The review considers life limiting processes and features of structures, systems and components important to safety, and whether there are any foreseeable circumstances that could endanger the safe operation of the nuclear power plant. This publication addresses the scope of assessment, methods and applicable criteria within the periodic safety review and long term operation programmes framework, to support decision making for long term operation of nuclear power plants.