4.1 This test method is designed to provide a uniform test to assess the suitability of coatings, used in nuclear power facilities, under radiation exposure for the life of the facilities, including radiation during a DBA (Coating Service Level I areas only). Specific plant radiation exposure may exceed or be less than the amount specified in 7.2 of this standard. If required by the licensee design basis, the gamma dose used may exceed the actual anticipated plant gamma dose to account for beta dose. Coatings in Level II and III areas (outside primary containment) are expected to be exposed to lower accumulated radiation doses.1.1 This test method covers a standard procedure for evaluating the lifetime radiation tolerance of coatings to be used in nuclear power plants. This test method is applicable to Coating Service Levels I, II, and III.1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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Preface This is the second edition of the CSA N285.6 Series, Material standards for reactor components for CANDU nuclear power plants. It supersedes the first edition published in 1988. This Standard is written in SI (metric) units. N285.6.1-05 Pr

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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 specifies the requirements for the quality assurance program applicable to the design, development, maintenance, modification, and use of analytical, scientific, and design computer programs that are used in nuclear power pl

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1. Scope 1.1 This Standard provides the general requirements used in the design, construction, testing, and commissioning of concrete containment structures for CANDU nuclear power plants designated as class containment and is directed to the owners,

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1. Scope 1.1 This Standard provides the requirements for the design of concrete containment structures of a containment system, designated as "class containment" components and parts, as defined in CSA Standard N287.1.

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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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