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About This Item

 

Full Description

N290.0-11: This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.

Scope
1.1 This Standard covers the design, qualification, installation, operation, maintenance, inspection, and documentation of the safety systems for a water-cooled nuclear power plant.

1.2 This Standard provides the general requirements for the safety systems. This Standard is a companion document of CSA N290.2 and N290.3, which outline specific requirements.

N290.1-13: This Standard has been written as a general standard for reactor shutdown systems of nuclear power plants. It establishes the design, procurement, installation, commissioning, operation, testing, and maintenance requirements of the shutdown system(s) to terminate the fission chain reaction in the event of an accident. This Standard is one of a series of standards on reactor control systems, safety systems, and instrumentation for nuclear power plants.

Scope
1.1 This Standard applies to the design, procurement, installation, commissioning, operation, testing, and maintenance requirements of reactor shutdown systems (SDSs) for existing and new water-cooled nuclear power plants (NPPs), both CANDU® and non-CANDU®.

Notes:
1) "Existing nuclear power plants" refers to those licensed for operation prior to 2013.
2) The requirements for new plants and existing plants might differ. Where requirements differ for new plants and existing plants, the differences are explicitly stated.
3) This Standard does not apply to NPPs smaller than 200 MW thermal power.

1.2 This Standard is written as a companion document to CSA N290.0, which provides general requirements for the NPP safety systems, including the reactor SDS. This Standard and its companion CSA N290.0 provide the requirements for the reactor SDS.

1.3 This Standard is written to be "technology neutral". This Standard uses the term "reactor shutdown system" (SDS), which includes the following functions: detection, actuation, and means of shutdown (MSD).

Note: In non-CANDU® plants, the "protection system" perform detection and actuation (see 10-CFR-50 Appendix A Criterion 20).
 

Document History

  1. CSA N290.0-11 (R2016)/N290.1-13 (R2018) PACKAGE

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    N290.0-11, General requirements for safety systems of nuclear power plants and N290.1-13, Requirements for the shutdown systems of nuclear power plants

    • Most Recent
  2. CAN3 N290.1-80 (R2011)


    Requirements for the Shutdown Systems of CANDU Nuclear Power Plants

    • Historical Version