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This PDF includes GI #2. 1. Scope This Standard provides requirements and guidelines for protection against fires in CANDU nuclear power plants. It applies to the design, construction, commissioning, all operational phases, and decommissioning of the

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Preface This is the first edition of CSA N286, Management system requirements for nuclear power plants. It replaces CSA N286.0, published in 1992, 1982, and 1978 under the title Overall Quality Assurance Program Requirements for Nuclear Power Plants. T

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1. Scope 1.1 This Standard outlines the requirements for seismic instrumentation systems for nuclear power plants where site- specific seismic responses are required to be determined and recorded.

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1. Scope 1.1 This Standard specifies the requirements and establishes the rules for design, fabrication, and installation of pressure- retaining containment system components. In this Standard the term "components" includes nonregistered items. 1.2

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1. Scope 1.1 This Standard specifies the requirements for periodic inspection of containment system components in CANDU nuclear power plants. 1.2 This Standard provides the inspection requirements for assurance of the structural integrity of metal

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1. Scope 1.1 This Standard covers the design, fabrication, qualification, installation, and inspection of CANDU nuclear power plant electrical and instrument air support power systems. These support power systems are part of the category of systems ca

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1. Scope 1.1 General This Standard sets forth the general requirements for seismic qualification of CANDU Nuclear Power Plants. It applies to all structures and systems of the CANDU Nuclear Power Plant that require seismic qualification based on

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1. Scope 1.1 This Standard applies to those structures and components in CANDU nuclear power plants which require seismic qualification by analytical methods (see CSA Standard CAN3-N289.1, General Requirements for Seismic Qualification of CANDU Nuclea

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1. Scope 1.1 This Standard defines the consideration and requirements for performing an acceptable seismic qualification test and presents the different test methods that may be used. Note: Selected safety related systems are required to be seismical

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1. Scope 1.1 The Standard is concerned with two aspects of the reactor regulating system. The first relates to reactor safety; the second is concerned with effective control of the reactor. These two aspects are not separate. This Standard, therefore,

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