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Operational Limits and Conditions and Operating Procedures for Research Reactors

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.

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Core Management and Fuel Handling for Research Reactors

This Safety Guide provides specific recommendations on core management and fuel handling for research reactors, including handling and storage of fresh fuel, irradiated fuel, core components and neutron sources, 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. This Safety Guide is a revision of lAEA Safety Standards Series No. NS-G-4.3, which it supersedes.

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Maintenance, Periodic Testing and Inspection of Research Reactors

This Safety Guide provides specific recommendations on the maintenance, periodic testing and inspection of research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It provides guidance on design considerations and recommends good practices in implementing the programme and establishing the organization and responsibilities for maintenance, periodic testing and inspection as well as for the selection, training and qualification of personnel. Procedures, administrative controls and maintenance facilities are also covered as well as procurement and storage of spare parts and components, and testing and inspection methods and techniques used for maintenance, periodic testing and inspection. The recommendations provided in this Safety Guide are aimed at operating organizations of research reactors, regulatory bodies and other organizations involved in a research reactor project. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.2, which it supersedes.

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Commissioning of Research Reactors

This Safety Guide provides specific recommendations on establishing a programme and organization for commissioning of research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It covers the commissioning stages, procedures, reports and documentation and provides guidance for commissioning of new experimental devices and modifications. 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. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.1, which it supersedes.

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Safety of Conversion Facilities and Uranium Enrichment Facilities

This Safety Guide, a revision of IAEA Safety Standards Series No. SSG-5, was initiated to provide recommendations on site evaluation, design, construction, commissioning, operation and preparation for decommissioning of conversion facilities and uranium enrichment facilities to meet the applicable requirements established in IAEA Safety Standards No. SSR-4, Safety of Nuclear Fuel Cycle Facilities, which incorporates the lessons learned from the accident at the Fukushima Daiichi nuclear power plant. The revised Safety Guide also reflects current operational practices at conversion facilities and uranium enrichment facilities. The recommendations in this publication are aimed primarily at operating organizations of conversion facilities and uranium enrichment facilities, regulatory bodies and designers.

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Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities

This Safety Guide provides specific recommendations on the safety of uranium and plutonium mixed oxide (MOX) fuel fabrication facilities. The potential hazards of a MOX fuel fabrication facility are release of actinides, increased radiotoxicity due to trans-uranium actinides, and nuclear criticality. The toxicity of plutonium is high and therefore it is important that best practices be employed at all stages of the fabrication of MOX fuel, and that plutonium be handled, processed, treated and stored safely. The revised Safety Guide reflects current operational practices at MOX fuel fabrication facilities. The recommendations in this publication are aimed primarily at the operating organizations of fuel fabrication facilities, regulatory bodies and designers.

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Safety of Uranium Fuel Fabrication Facilities

This Safety Guide provides specific recommendations on the safety of uranium fuel fabrication facilities and describes the actions, conditions and procedures for meeting safety requirements. It deals specifically with the handling, processing and storage of low enriched uranium that has a uranium 235 concentration of no more than 6%, derived from natural, highly enriched or reprocessed uranium. This publication is a revision by amendment of IAEA Safety Standards Series No. SSG-6. It addresses the new safety requirements established by IAEA Safety Standards SSR-4, Safety of Nuclear Fuel Cycle Facilities, which incorporates the lessons learned from the accident at the Fukushima Daiichi nuclear power plant.

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Use of a Graded Approach in the Application of the Safety Requirements for Research Reactors

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.

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Hazards Associated with Human Induced External Events in Site Evaluation for Nuclear Installations

Hazards associated with human induced external events (HIEEs) need to be considered in the evaluation of sites for nuclear installations, in the design of new nuclear installations and in the operation of existing nuclear installations. This Safety Guide provides recommendations on the evaluation of these hazards in order to meet the requirements set out in IAEA Safety Standards Series No. SSR-1, Site Evaluation for Nuclear Installations. It provides a process for identification of source of HIEEs, screening of hazards using distance and probability, and detailed evaluation to establish hazard and load characterization parameters. This publication is intended for use by organizations involved in the identification, screening, analysis, evaluation and review of hazards associated with HIEEs, and the provision of technical support, as well as regulatory bodies.

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Maintenance, Testing, Surveillance and Inspection in Nuclear Power Plants

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.

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Conduct of Operations at Nuclear Power Plants

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.

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Recruitment, Qualification and Training of Personnel for Nuclear Power Plants

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.

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