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Abstract

1. Scope

1.1 This Standard contains the requirements for quality assurance programs applicable to the design of safety-related systems, components, and structures of a nuclear power plant, as identified by the owner.

1.2 This Standard recognizes that the extent of the application of the quality assurance requirements to a system, component, structure, or activity may vary according to its impact on the safety of the plant.

1.3 This Standard is applicable to all aspects of design work, including conceptual studies, preliminary design, detailed design, and the production of design documentation for licensing, c onstructing, installing, testing, commissioning, operating, and decommissioning activities. Note: The design process model given in Appendix A is provided to assist the reader in gaining an understanding of the basic activities of the design process and of the interrelationship of the various activities.

1.4 This Standard complements the relevant quality assurance requirements of CSA Standard CAN/CSA-N286.0 and is the governing standard for design quality assurance activities. Note: Interpretations of this Standard by the Technical Committee will be in accordance with the requirements of CSA Standard CAN/CSA-N286.0.

1.5 This Standard applies to the selection of items but not to their design when such design is defined completely by an industrial design standard.

1.6 This Standard does not apply to the design of structures and components whose design quality assurance requirements are specified in a manufacturing standard. Note: The application of this Standard may be extended, limited, or replaced by an equivalent Standard (see Clause 3.1.5). For example, the design quality requirements for pressure-retaining components are specified in CSA Standard CAN/CSA-N285.0.