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CSAN290.4 : 2011

CSAN290.4 : 2011

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

REQUIREMENTS FOR REACTOR CONTROL SYSTEMS OF NUCLEAR POWER PLANTS

Available format(s)

Hardcopy , PDF

Superseded date

12-10-2020

Language(s)

English, French

Published date

01-01-2016

Publisher

Canadian Standards Association

Preface
1 Scope
2 Reference publications
3 Definitions
4 Functional requirements
5 Requirements
6 Quality management
Annexes
A (informative) - Guidance on control logic implementation

Describes provisions for safe and effective control of reactor power. Applies to all components of the system, including mechanical, process, software, electrical, and instrumentation and control design used for the control of the neutron flux and the thermal output of the reactor.

DevelopmentNote
French Edition issued on 01/12/2012. (04/2013)
DocumentType
Standard
Pages
26
ProductNote
Reconfirmed EN
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy
Supersedes

CSA N286.2 : 0 DESIGN QUALITY ASSURANCE FOR NUCLEAR POWER PLANTS
CSA N286.0 : 0 OVERALL QUALITY ASSURANCE PROGRAM REQUIREMENTS FOR NUCLEAR POWER PLANTS
CSA N286.1 : 0 PROCUREMENT QUALITY ASSURANCE FOR NUCLEAR POWER PLANTS
N285.0-12/N285.6 SERIES-12 General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants
CSA N286.3 : 0 CONSTRUCTION QUALITY ASSURANCE FOR NUCLEAR POWER PLANTS
N285.4-14 Periodic inspection of CANDU nuclear power plant components
CSA N286.5 : 0 OPERATIONS QUALITY ASSURANCE FOR NUCLEAR POWER PLANTS
CSA N290.1 : 2013 REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF CANDU NUCLEAR POWER PLANTS
CSA N290.14 : 2015 QUALIFICATION OF DIGITAL HARDWARE AND SOFTWARE FOR USE IN INSTRUMENTATION AND CONTROL APPLICATIONS FOR NUCLEAR POWER PLANTS
IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations

View more information
Hardcopy - English
PDF - English
Hardcopy - French
PDF - French

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