N290.0-11 - General requirements for safety systems of nuclear power plants
Preface
This is the first edition of CSA N290.0, General requirements for safety systems of nuclear power plants. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.
Scope
1.1
This Standard covers the design, qualification, installation, operation, maintenance, inspection, and documentation of the safety systems for a water-cooled nuclear power plant.
1.2
This Standard provides the general requirements for the safety systems. This Standard is a companion document of CSA N290.2 and N290.3, which outline specific requirements.
1.3
In CSA standards, shall is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the standard; should is used to express a recommendation or that which is advised but not required; and may is used to express an option or that which is permissible within the limits of the standard.
Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material.
Notes to tables and figures are considered part of the table or figure and may be written as requirements.
Annexes are designated normative (mandatory) or informative (nonmandatory) to define their application.
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N290.2-11 - Requirements for emergency core cooling systems of nuclear power plants
Preface
This is the first edition of CSA N290.2, Requirements for emergency core cooling systems of nuclear power plants. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.
Scope
1.1
This Standard covers the design, qualification, installation, operation, maintenance, inspection, and documentation of the emergency core cooling (ECC) system for a water-cooled nuclear power plant.
1.2
The ECC system's primary purpose is to transfer heat from the reactor core following a loss of reactor coolant that exceeds the makeup capability of process systems. This Standard also applies to all support systems required to ensure that the ECC system is able to maintain adequate heat transfer for as long as necessary to maintain the release of radioactive material within reference dose limits by limiting fuel failure.
1.3
This Standard was written as a companion document to CSA N290.0, which outlines general requirements for safety systems.
1.4
This Standard uses the term ECC system to refer to either a single system or multiple systems depending on the plant design.
1.5
In CSA standards, shall is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the standard; should is used to express a recommendation or that which is advised but not required; and may is used to express an option or that which is permissible within the limits of the standard.
Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material.
Notes to tables and figures are considered part of the table or figure and may be written as requirements.
Annexes are designated normative (mandatory) or informative (nonmandatory) to define their application.
