In-Service Testing and Examination Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants
View Access for this document is only available for viewers in Canada
Development of this Standard began in 1973 under the sponsorship of the Canadian Nuclear Association's Codes, Standards, and Practices Committee. In 1974 the decision was made to promulgate this document as a CSA Standard.
Standards in this series were initiated in response to a recognition by the utilities and industries concerned with nuclear structures in Canada, of a need for the documentation of Standards applicable to the design, construction, and testing of concrete containment structures incorporated as components of a CANDU nuclear power plant.
The purpose of this Standard, is to provide uniform rules whereby, through systematic and periodic inspections of the concrete containment structure, the Structural and leak—tight integrity may be assessed, thereby reaffirming the established function of the structures.
This Standard is one in a series of Standards, which together, form a code. The Code will comprise of the Standards listed below, and such additional ones as may be required from time to time:
N287.l, General Requirements;
N287.2, Material Requirements;
N287.3, Design Requirements;
N287.4, Construction, Fabrication and Installation Requirements:
N287.5, Testing and Examination Requirements;
N287;6, Pre&0perational Proof and Leakage Rate Testing Requirements.
In preparation of this and the above Standards, it was the decision of the Committee to make use of existing Standards, Codes, and other reference material wherever possible, noting only the exceptions applicable to concrete containment structures. Such material is listed in the reference publications.
This Standard was prepared by the Committee on Concrete Containment Structures for Nuclear Power Plants under the jurisdiction of the Sectional Committee for Nuclear Standards.
This Standard covers the requirements for the periodic in—service tests and examination of concrete containment structures of a containment system, designed as Class Containment components.
NOTE: The requirements for the periodic testing and inspection of other components and appurtenances of the containment system designed in accordance with CSA Standard N285.1, General and Design Requirements for CANDU Nuclear Power Plant Components are beyond the scope of this Standard and the user is referred to CSA Standard N285.4, Periodic Inspection of CANDU Nuclear Power Plant Components, for their requirements.