[en] The aim of the publication is to provide an overview on the current knowledge, up to date best practices, experiences, benefits and challenges related to the subject approaches on instrumentation and control (I&C) systems life cycle management. This includes the coordination of life cycle management methods applied to I&C systems and those applicable to any safety systems that they might interconnect or otherwise interface with. The report is intended to be used by Member States to ensure that appropriate considerations are made to support the introduction of life cycle management approaches for all relevant stakeholders involved in the development of I&C for nuclear facilities and to discuss how these activities can support their safe, reliable and long-term operation. The publication is intended for all personnel involved in the design, development, verification and validation, manufacturing, licensing, operation and maintenance of nuclear power plant instrumentation and control systems and equipment.

[en] This Safety Guide supersedes AERB safety guide on ‘In-Service Inspection of Nuclear Power Plants,’ 2004, (AERB/NPP/SG/O-2). The structure, system and components (SSCs) of Nuclear Power plant (NPP) are subjected to influences like stress, temperature, irradiation, hydrogen absorption, corrosion and fatigue during their operating life. These influences will result in degradation of materials used in the construction of SSCs which in turn will affect their fitness for service. The components of NPPs exposed to these influences need to withstand the effects of various normal and anticipated service conditions. The synergistic effects of the operating environment on materials of construction may not be amenable for accurate prediction. Nevertheless, trending of the degradation in material/ components with time during operation of the plant is very important for ensuring integrity and safety of the SSCs and that of the NPP. An inspection programme for periodic monitoring of the SSCs to detect, assess and trend their condition is an essential aspect of the safe operation of a NPP so that appropriate timely actions are initiated to restore them to a healthy state by way of repair or replacement. This safety guide elaborates the requirements of such inspections to be carried out both prior to start of operation, viz., Pre-Service Inspection (PSI) and during reactor operation, viz., In-Service Inspections (ISI) at prescribed regular intervals

[en] 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.

[en] Romania’s energy supply is well diverse consisting of coal, hydropower, natural gas, nuclear energy and wind. Romania has deployed nuclear power since 1980’s. Currently, 2 units of Canada Deuterium Uranium 6 reactors with 1400 MW capacity in the Cernavoda site are operational. Nuclear power in Romania provides around 20% of national energy production. Cernavoda Unit 1 was completed in 1996 and produces 705.6 MW of electricity and Cernavoda Unit 2 achieved the initial criticality in 2007 and produces 706 MW of electricity. Based on the service capacity factor of both units (91.6%), Romania has a high-capacity factor of nuclear power plants worldwide according to Nuclear Engineering International. The last years of operation records demonstrated that the Cernavoda NPPs continuously advanced on the path to nuclear excellence. The National Company NUCLEARELECTRICA S.A. (SNN), a state-owned entity, is the owner/operator of Cernavoda NPPs, having experience of NPP project construction, commissioning and operation. On the same Cernavoda NPP site, there are also two other nuclear units under construction, Units 3 and 4 (C-U3/4) and the completion of this project is the subject of this case study.

[en] The French High Committee for Transparency and Information on Nuclear Safety (HCTISN) is organizing a consultation on the generic phase of the 4. periodic review of the 1300 MWe reactors of the French nuclear fleet (20 reactors operated by EDF, spread over 8 sites). Ahead of the consultation process, the HCTISN wanted to gather citizens' expectations on the safety of nuclear reactors in France. This document presents the results of this survey based on the following questions: 1 - Respondent profile (optional); 2 - Do you know your nearest nuclear power plant? (optional); 3 - How many nuclear power plants are in operation in France? (optional); 4 - What is the average age of nuclear reactors in France? (optional); 5 - Do you think there is a limit to how long a nuclear reactor can operate in France? (optional); 6 - How do you rate the safety of nuclear reactors in France?; 7 - Do you think the safety of French nuclear reactors can be improved?; 8 - What are your top 3 concerns about nuclear reactors in France? (required); 9 - On a scale of 1 to 10, do you think you have enough information about nuclear safety in France? (required); 10 - Would you be willing to give your opinion on the safety improvements proposed by EDF for its nuclear reactors in France? (compulsory); 11 - And if so, on which subjects (optional)

[en] The purpose of this publication is to provide practical and detailed information to regulatory bodies of States, particularly those embarking on a nuclear power programme, on the planning, management and conduct of regulatory review and assessment of documents and information submitted by an applicant for the licensing of a Nuclear Power Plant (NPP). This publication provides information on establishing a well-defined, well-organized and clear regulatory review and assessment process for the safety of NPPs at different licensing steps. The publication is intended for managers and staff of regulatory bodies involved in the organization, planning, management and/or conduct of regulatory review and the assessment process for the licensing of NPPs at different stages.

[en] The objective of this publication is to provide guidance on the preparation, implementation, reporting and follow-up of INSARR missions at research reactors. The guidance on the preparation of the review mission is intended for both the host organization and the review team. The guidance on the conduct of the mission is mainly directed to the review team. In principle, the guidance in this report is to be used for safety reviews of research reactors conducted by the IAEA. However, the guidelines could also be used as one source of information for periodic safety reviews conducted by the operator of the research reactor or by the regulatory body.

[en] This publication provides an analysis of results from Integrated Safety Assessment of Research Reactors (INSARR) Missions conducted at research reactors during the period from 1995 to 2021. The analysis includes an assessment of trends, common issues, and other insights that are highly beneficial to Member States operating research reactors. This publication is also useful for self-assessment of research reactor safety. This publication is intended for use by operating organizations of research reactors, regulatory bodies and other relevant organizations involved in the safety of research reactors.

[en] This publication explores the variety of contracting and ownership approaches for a nuclear power plant, illustrated with recent case studies, to assist Member States in understanding the range of options available and the associated benefits and challenges of each approach. Regardless of the approach adopted, the requirements for the safe, secure and peaceful operation of a nuclear power plant remain the same. The challenge is to make sure that these requirements are adequately considered and addressed in Member State nuclear power programmes. This publication is a revision of IAEA-TECDOC-1750, Alternative Contracting and Ownership Approaches for New Nuclear Power Plants, published in 2014, which examined build–own–operate and build–own–operate–transfer models as well as regional approaches in relation to contracting and ownership. The publication used the word ‘alternative’ to reflect that both the regional approach and build–own–operate / build–own–operate–transfer models were different from those used historically in the nuclear power industry, thus representing an alternative pathway for embarking and expanding countries at that time.

[en] This publication provides the operating experience feedback from the events reported to the IAEA's incident reporting system for research reactors (IRSRR) since its launch in 1997. The publication has a focus on the root causes, lessons learned, and corrective actions taken to prevent the occurrence of similar events. It also analyses the key lessons learned from recent events in nuclear power plants that are relevant to research reactors. Reference to other publications that cover research reactor events as well as a description of an operating experience programme are also included. This publication is intended to be used by research reactor operating organizations, regulatory bodies, and designers.