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CAN/CSA-N286.4-M86 (R2000)
Commissioning Quality Assurance for Nuclear Power Plants
SKU: 2703097
Published by CSA Group
Publication Year 1986
Reaffirmed in 2000
Withdrawn
Product Details
Scope
1.1 This Standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant.
1.2 This Standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements.
1.3 This Standard is addressed to the owner and is applicable to commissioning activities carried out by both the owner and participants designated by the owner.
1.4 This Standard applies to the commissioning of safety- related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner.
1.5 This Standard recognizes that the extent of the application of the quality assurance requirements to the particular equipment, system, structure, or activity can vary according to the potential impact on the safety of the plant.
Notes:
(1) Interpretation of this Standard by the Technical Committee will be in accordance with the intent expressed in Standard CAN3-N286.0.
(2) The application of the term safety-related will be defined in an application guideline that is to be included in a future edition of CAN3-N286.0.
1.1 This Standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant.
1.2 This Standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements.
1.3 This Standard is addressed to the owner and is applicable to commissioning activities carried out by both the owner and participants designated by the owner.
1.4 This Standard applies to the commissioning of safety- related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner.
1.5 This Standard recognizes that the extent of the application of the quality assurance requirements to the particular equipment, system, structure, or activity can vary according to the potential impact on the safety of the plant.
Notes:
(1) Interpretation of this Standard by the Technical Committee will be in accordance with the intent expressed in Standard CAN3-N286.0.
(2) The application of the term safety-related will be defined in an application guideline that is to be included in a future edition of CAN3-N286.0.
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CAN/CSA-N286.4-FM86 (C2000)
Assurance de la qualité de la mise en service des centrales nucléaires
Withdrawn
French
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