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[en] One of the elements essential for any organization to become a leading organization is to learn from its own and others experience. The importance of utilizing experience feedback for enhancing operational safety is highlighted in nuclear industry again and again which resulted in launching several forums nationally and internationally. In addition, IAEA action plan on nuclear safety issued after Fukushima accident further highlighted the importance of experience sharing among nuclear community to strengthen global nuclear safety regime. PNRA utilizes operating experience feedback gathered through different sources in order to improve its regulatory processes. During the review of licensing submissions, special emphasis is given to utilize the lessons learnt from experience feedback relating to nuclear industry within and outside the country. This emphasis has gradually resulted in various safety improvements at research reactors in Pakistan. Accordingly, PNRA has developed a systematic process for evaluation of international operating experience feedback with the aim to create safety conscious approach. This process includes collecting information from different international forums such as IAEA, regulatory bodies of other countries and useful feedback of past accidents followed by its screening, evaluation and suggesting recommendations both for PNRA and its licensees. As a result of this process, several improvements concerning regulatory inspection plans of PNRA as well as in regulatory decision making and operational practices of licensees have been highlighted. This paper will present PNRA process for evaluation of national and international operating experience feedback for research reactors. (author)
[en] This summary provides a view on safety and operational aspects, as addressed in the summaries of coolant characteristics (see Section 3 of this TECDOC), coolant confining structures (see Section 4 of this TECDOC) and interfaces (see Section 5 of this TECDOC), because they are key cornerstones for licensing of a nuclear facility. Growing international nuclear safety requirements for operation and additional considerations for anticipated events demand more sophisticated approaches for nuclear safety demonstration. This section is divided into two blocks: – Inventory control, accountancy and qualification procedures; – Enveloping safety analysis.
[en] As the global community strives to curb carbon emissions from the energy sector, focus has sharpened on the role nuclear energy can play in the effort throughout the 21. century. While the light water reactor fleet provides the nuclear generation backbone for meeting future capacity needs and emission goals, more than half of the world's nuclear power plants have surpassed 30 years in service. The Electric Power Research Institute (EPRI), in collaboration with research entities around the world, helps turn the world's carbon neutrality challenges into opportunities. EPRI's work delivers research to answer key questions about modernization efforts that can provide safe and cost-effective life extensions for long-term operation, increase operational flexibility to support stable power grid dynamics, reduce nuclear power plant operating costs, and the examine the latest reactor technologies for more viable new nuclear power plant construction. (authors)
[en] The in-service inspection program of the Angra 1 plant is updated every 10 years, according to applicable standards - designer (American Westinghouse project based on NRC requirements) and CNEN. NRC approves the use of ASME Section XI (In-service Inspection of Nuclear Power Plant Components). To provide this assurance for those components that are subject to the requirements of the ASME Boiler and Pressure Vessel Code presents as requirements a set of rules has been formulated to provide assurance that the functional requirements of the components are available when required. The rules have been arranged to provide appropriate levels of assurance according to the importance of the component in its relationship to plant safety. The classifications that are established during design and manufacturing have been adopted to provide the levels of importance for the components. Nuclear power plants (NPP) have operation license for 40 years. Angra 1 operation license will complete 40 years in 2024. But, according to international standard an NPP can renewal the license for more 20 years. Brazilian standard does not have requirements for license renewal. So, CNEN had prepared two technical notes for License Renewal and Long-term operation for NPP in Brazil - CNEN NTCGRC-007/18 and NT-CGRC-008/18. Angra 1 had already started the Renewal License and Long-term Operation project and ISI program will need to be on the Aging Management Program form, that require more robust trend analyzes, corrective and preventive actions and others attributes. The main purpose of this article is to show the ASME section XI subsections that are important for the License Renewal and Long-term Operation for Angra 1. (author)
Project of photovoltaic power plant at Guiscriff - SC Centrale 3 company. Construction permit application for the installation of a ground photovoltaic power plant by SC Centrale 3 company at the municipality of Guiscriff. Public inquiry from wednesday October 23, 2019 (13h30) to Friday November 29, 2019 (17h15) included
[en] This document is the construction permit application file for the installation of a 11.8 MW ground photovoltaic power plant on a 18 hectares land of the municipality of Guiscriff (Morbihan, Brittany, France). The document includes: the project owner file (presentation of the site, comprehensive impact study, answers to the remarks made by the Environmental authority), the administrative file (public inquiry and the opinions of the different commissions, civil aviation and environmental authority), the observations expressed by the public during the public inquiry, the report and conclusions of the inquiry commissioner (report, conclusion and opinion of the inquiry commissioner, answers by the project owner to the remarks expressed by the public, hydrogeologic report). The study 'photovoltaic conversion and biodiversity' is added in appendix
[en] The Canadian Nuclear Safety Commission (CNSC) is responsible for regulating the use of nuclear energy and materials. The CNSC permits nuclear power utilities to operate nuclear power plants (NPPs) in Canada under a power reactor operating licence (PROL). A PROL specifies applicable standards for operation. Canadian nuclear power utilities are licensed in accordance with applicable standards in their PROL. The CNSC’s licensing regime includes the licence conditions handbook (LCH), which is a companion piece to interpret a licence. The general purpose of the LCH is, for each licence condition, to clarify the regulatory requirements and other relevant parts of the licensing basis. The LCH requires the licensee to ensure that the instrumentation and control (I&C) system is designed to satisfy requirements of the plant level system classification, ensure that system safety features for enhancing system reliability and integrity are identified and implemented in the design, and ensure that the system is not vulnerable to common cause failure (CCF). In particular, the LCH references CSA standard N290.14-07, Qualification of Pre-Developed Software for Use in Safety-Related Instrumentation and Control Applications in Nuclear Power Plants, for justification in using digital predevelopment software. This is the standard used by licensed utilities in Canada to qualify commercial grade software for use in safety related applications. This standard was written by the CSA Group through a consensus standards development process approved by the Standards Council of Canada. This process brings together volunteers representing varied viewpoints and interests to achieve alignment and balance between stakeholders. N290.14-15, Qualification of Digital Hardware and Software for Use in Instrumentation and Control Applications for Nuclear Power Plants, is the second edition of the standard, which has been or will be considered for adoption by licensees (when those utilities apply for re-licensing). This second edition has been greatly expanded, to include hardware qualification requirements and an expanded scope of software. This standard also references several other publications, including, but not limited to those by the Electric Power Research Institute (EPRI), International Electrotechnical Commission (IEC), Institute of Electrical and Electronics Engineers (IEEE) and the International Organization for Standardization (ISO). It was developed by the Canadian Standards Association (operating as ‘CSA Group’) and provides an interlinked set of requirements for the management of nuclear facilities and activities.
[en] Advanced reactors have promise as the future of United States nuclear energy infrastructure. However, licensing these reactors presents many new questions for the nuclear community, particularly around developing a 'technology-neutral' framework capable of handling a staggering amount of diversity in technologies and operating models. Congress's enactment of the Nuclear Energy Innovation and Modernization Act (NEIMA) in early 2019 enables the United States Nuclear Regulatory Commission (NRC) to devote substantial resources to developing such a framework. Congress draws a distinction between the existing licensing framework that is focused on light water reactors (LWRs) and the technology-neutral framework that it directs the NRC to establish. However, to aid in the eventual development of a 'technology-neutral' reactor licensing framework, it is important to conceptually understand the history and context of the current licensing framework for commercial nuclear power plants (NPPs). To that end, this study analyses whether the existing licensing framework was ever intended to be fully applicable to advanced reactors. The study reveals that, while the existing framework did not ignore advanced reactors and is capable of accomplishing the review and licensing of such reactors, the current NRC regulatory framework ultimately was designed primarily for licensing traditional LWRs. This conclusion is reached through a review of regulatory history documents and policy statements of the time and illustrates how the existing framework was not specifically intended to provide a technology-neutral framework. Thus, significant gains may be possible by learning from past experience when exploring a new licensing framework that more substantially addresses technology-neutral licensing concepts
[en] The Nuclear Regulatory Authority (ARN) was established as an autonomous body reporting to the President of Argentina by Act 24,804 known as the Nuclear Activity National Act, which came into force on April 25, 1997, and is empowered to regulate and control the nuclear activity with regard to radiation and nuclear safety, physical protection and nuclear non-proliferation issues. It must also advise the Executive on issues under its purview. The objective of the Nuclear Regulatory Authority is to establish, develop and enforce a regulatory system applicable to all nuclear activities performed in Argentina. The construction, commissioning, operation and decommissioning, as well as important modifications of nuclear reactors, shall be previously authorized and licensed by the ARN. The ARN controls seven research reactors: three research reactors in operation, one under construction, two critical facilities in operation, and one critical facility under decommission. The operation licenses for research reactors and critical facilities, issued by the ARN, have a fixed validity. As a condition to renew the operation license, the regulatory authority requires the operating organization to perform a comprehensive safety review. This review process shall be done in accordance with a specific guide, prepared by the ARN. This requirement was established for the first time in a in a staggered way, selecting the research reactor RA0 as the first step. This document describes in general terms the guide for the safety review, and presents the most relevant results arising from its application to the case of the RA-0 research reactor. (author)
[en] Regulators in the United Kingdom require that nuclear licence holders maintain a ‘nuclear baseline’, which defines the roles and capabilities required to ensure safety and competency to act as a licensee. The nuclear baseline is agreed with the nuclear regulator, and an essential part is the intelligent customer capability. This capability ensures that licensees are able to engage contractors to perform safety related work packages and that they maintain an understanding, knowledge and ownership of contractors’ work that could potentially affect nuclear safety, industrial safety, health and environment management. Key activities in maintaining intelligent customer capability include: — Annual review of intelligent customer skills to ensure relevance; — Appointment of staff to intelligent customer roles; — Forecasts of the demand for intelligent customer capability; — Maintenance of a minimum intelligent customer capability regardless of workload; — Confirmation that staff in intelligent customer roles remain suitably qualified and experienced; — Chief engineer approval prior to changes to intelligent customer appointments.