CSAN290.4 : 2011
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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
Hardcopy , PDF
12-10-2020
English, French
01-01-2016
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Superseded
|
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 |
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 |
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