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Full Description

This is the fifth edition of CSA N287.7, In-service examination and testing requirements for concrete containment structures for nuclear power plants. This Standard provides uniform rules whereby, through systematic and periodic examination, the structural and leak-tight integrity of concrete containment structures can be assessed. This Standard is part of the N287 series of Standards, which provides the requirements for concrete containment structures for nuclear power plants. These Standards were initiated in response to the recognition by the utilities and industries concerned with nuclear structures in Canada of a need for Standards applicable to the design, construction, and testing of concrete containment structures for nuclear power plants.

The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.

Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and Regulations. Requirements additional to those specified in this Standard could be imposed by the Canadian Nuclear Safety Commission.

This Standard provides requirements for in-service examinations of concrete containment structure which includes, but is not limited to the following structural and non-structural elements:
a) concrete;
b) reinforcement (pre-stressed and non-pre-stressed);
c) steel (e.g., liner, embedded parts, anchors);
d) non-metallic liners and coating systems;
e) joint sealants; and
f) elements necessary to support containment structure (e.g. foundations).

This Standard also provides requirements for integrated leakage rate testing (ILRT) of the containment boundary. In-service examination of containment system components designed in accordance with the CSA N285 series of Standards are beyond the scope of this Standard.
 

Document History

  1. CSA N287.7-17 (R2022)

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    In-Service Examination and Testing Requirements for Concrete Containment Structures for Nuclear Power Plants, Includes Errata (2018) and Errata (2022)

    • Most Recent
  2. CSA N287.7-08 (R2013)


    In-Service Examination and Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants, Includes Update No. 1 (2010)

    • Historical Version
  3. CAN/CSA N287.7-96 (R2005)


    In-Service Examination and Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants

    • Historical Version