CSA Group Contient N290.0-11, Exigences générales applicables aux systèmes de sûretédes centrales nucléaires et N290.2-11, Exigences applicables aux circuits de refroidissement d'urgence du coeur des centrales nucléaires

Preface This document is the first edition of CSA N290.0, General Requirements for Safety Systems of Nuclear Power Plants. This document is one of a series of standards for reactor control systems, safety systems and instrumentation for nuclear power plants. Scope 1.1 This standard applies to the design, qualification, installation, operation, maintenance, inspection and documentation of safety systems for nuclear power plants that are cooled to 'water. 1.2 This Standard sets out general requirements applicable to security systems. It accompanies the CSA N290.2 and N290.3 standards which set out specific requirements. 1.3 In this standard, the word "must" indicates a requirement, that is, a requirement that the user must meet to ensure compliance with the standard; "Should" indicates a recommendation or what it is advised but not required to do; and "may" indicates a possibility or what is permitted. The notes accompanying the articles do not include prescriptions or recommendations. They serve to separate from the text explanations or information that is not properly part of the norm. The notes at the bottom of the figures and tables are part of these and may be written as prescriptions. The annexes are qualified as normative (mandatory) or informative (optional) to specify its application. ---------------------------- N290.2-11 Requirements for emergency cooling circuits in the core of nuclear power plants Preface Ce This document is the first edition of CSA N290.2, Requirements for Emergency Cooling Circuits in the Core of Nuclear Power Plants. This document is one of a series of standards for reactor control systems, safety systems and instrumentation for nuclear power plants. Field of application 1.1 This standard applies to the design, qualification, installation, operation, maintenance, inspection and documentation of the emergency cooling circuits of nuclear power plants. 'water. 1.2 The primary function of a RUC system is to transfer heat from the fuel into the reactor core resulting from a loss of coolant that is greater than the process capacity of the process systems. This standard also applies to all support systems required to ensure that the RUC system is capable of maintaining adequate heat transfer for as long as necessary to keep the release of radioactive material within limits by reducing clad fractures. 1.3 This standard accompanies CSA N290.0, which sets out the general requirements applicable to nuclear plant safety systems.  1.4 In this standard, the abbreviation "RUC circuit" refers to both a single circuit and a set of circuits, depending on the plant. 1.5 In this standard, the word "must" indicates a requirement, that is, a requirement that the user must meet to ensure compliance with the standard; "Should" indicates a recommendation or what it is advised but not required to do; and "may" indicates a possibility or what is permitted. The notes accompanying the articles do not include prescriptions or recommendations. They serve to separate from the text explanations or information that is not properly part of the norm. The notes at the bottom of the figures and tables are part of these and may be written as prescriptions. The annexes are qualified as normative (mandatory) or informative (optional) to specify its application.