This PDF includes GI 2. 1. Scope 1.1 This Standard applies to pressure-retaining components and their supports of CANDU nuclear power plants that have a Code Classification of Class 1C, 2C, or 3C as defined by CSA Standard N285.0. 1.2 This Stand

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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 General This Standard applies to airborne and liquid effluents associated with the normal operation of CANDU Nuclear Power Plants. It provides guidelines and a methodology for calculating the upper limits (the Derived Release Limits)

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1. Scope 1.1 General 1.1.1 This Standard provides guidelines and a methodology for calculating effective doses and thyroid doses to people (either individually or collectively) in the path of airborne radioactive material released from a nuclear f

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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 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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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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1. Scope 1.1 General This Standard covers once-through high efficiency air-cleaning assemblies for maintaining radioactive particulate and radioiodine releases below licenced limits in nuclear power plants. The Standard identifies and establishes mi

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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 describes the investigations required to obtain the seismological and geological information necessary to determine, for a proposed CANDU nuclear power plant site, the seismic ground motion that will be utilized in seismic qu

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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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