CSA N290.8 : 2015
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
TECHNICAL SPECIFICATION REQUIREMENTS FOR NUCLEAR POWER PLANT COMPONENTS
Hardcopy , PDF
02-11-2020
French, English
01-01-2015
Important note : Users cannot be edited or removed once added to your Multi user PDF.
Preface
1 Scope
2 Reference publications
3 Definitions and abbreviations
4 Preparation of technical specifications
5 Instrumentation and control components
6 Mechanical components
7 Electrical components
Annex A (informative) - Data sheet contents
Annex B (informative) - National and international Standards
bodies
Annex C (informative) - I&C safety categories
Annex D (Informative) - Commercial guidance
Specifies a consistent approach across the industry to produce specifications for components used in normal operation, anticipated operational occurrences (AOOs), and design basis accidents (DBAs).
| DevelopmentNote |
French Edition issued on 01-05-2016. (06/2016) ERRATA 2016 only available in French Version. (07/2016)
|
| DocumentType |
Standard
|
| Pages |
55
|
| PublisherName |
Canadian Standards Association
|
| Status |
Superseded
|
| N290.5-16 | Requirements for electrical power and instrument air systems of CANDU nuclear power plants |
| N290.18-17 | Periodic safety review for nuclear power plants |
| N290.6-16 | Requirements for monitoring and display of nuclear power plant safety functions in the event of an accident |
| CSA N290.14 : 2015 | QUALIFICATION OF DIGITAL HARDWARE AND SOFTWARE FOR USE IN INSTRUMENTATION AND CONTROL APPLICATIONS FOR NUCLEAR POWER PLANTS |
| CSA N290.0 & N290.2 PACKAGE : 2017 | CONSISTS OF N290.0-17, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.2-17, REQUIREMENTS FOR EMERGENCY CORE COOLING SYSTEMS OF NUCLEAR POWER PLANTS |
| IEEE 382-2006 | IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations |
| CSA N285.0 : 2006 | GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS |
| NEMA MG 1 : 2016 | MOTORS AND GENERATORS |
| ASME B31.1 : 2016 | POWER PIPING |
| IEEE 610 : 1991 | COMPUTER DICTIONARY - A COMPILATION OF IEEE STANDARD COMPUTER GLOSSARIES |
| IEC 61226:2009 | Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions |
| CSA B51 : 2014 | BOILER, PRESSURE VESSEL, AND PRESSURE PIPING CODE |
| API 520-1 : 2014 | SIZING, SELECTION, AND INSTALLATION OF PRESSURE-RELIEVING DEVICES - PART 1: SIZING AND SELECTION |
| ASME QME 1 : 2012 | QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES |
| CSA N290.12 : 2014 | HUMAN FACTORS IN DESIGN FOR NUCLEAR POWER PLANTS |
| IEC 62003:2009 | Nuclear power plants - Instrumentation and control important to safety - Requirements for electromagnetic compatibility testing |
| IEC 61508-5:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 5: Examples of methods for the determination of safety integrity levels (see Functional Safety and IEC 61508) |
| MSS SP 67 : 2017 | BUTTERFLY VALVES |
| CSA N293 : 2012 | FIRE PROTECTION FOR NUCLEAR POWER PLANTS |
| IPC A 610 : F | ACCEPTABILITY OF ELECTRONIC ASSEMBLIES |
| CSA Z299.0 : 1986 | GUIDE FOR SELECTING AND IMPLEMENTING THE CAN3-Z299-85 QUALITY ASSURANCE PROGRAM STANDARDS |
| IEEE 142 : 2007 | GROUNDING OF INDUSTRIAL AND COMMERCIAL POWER SYSTEMS |
| MSS SP 61 : 2013 | PRESSURE TESTING OF VALVES |
| ISO 9001:2015 | Quality management systems — Requirements |
| CSA Z299.4 : 1985 | QUALITY ASSURANCE PROGRAM - CATEGORY 4 |
| IEEE 1184-2006 | IEEE Guide for Batteries for Uninterruptible Power Supply Systems |
| API 610 : 2010 | CENTRIFUGAL PUMPS FOR PETROLEUM, PETROCHEMICAL AND NATURAL GAS INDUSTRIES |
| ASME B16.34 : 2017 | VALVES - FLANGED, THREADED, AND WELDING END |
| IEC 61513:2011 | Nuclear power plants - Instrumentation and control important to safety - General requirements for systems |
| CSA Z299.2 : 1985 | QUALITY ASSURANCE PROGRAM - CATEGORY 2 |
| MIL-HDBK-470 Revision A:1997 | Designing and Developing Maintainable Products and Systems, Volume I |
| CSA N290.7 : 2014 | CYBER SECURITY FOR NUCLEAR POWER PLANTS AND SMALL REACTOR FACILITIES |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| CSA N290.14 : 2015 | QUALIFICATION OF DIGITAL HARDWARE AND SOFTWARE FOR USE IN INSTRUMENTATION AND CONTROL APPLICATIONS FOR NUCLEAR POWER PLANTS |
| MSS SP 88 : 2015 | DIAPHRAGM VALVES |
| IEEE 946-2004 | IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems |
| IEC 60534-7:2010 | Industrial-process control valves - Part 7: Control valve data sheet |
| ASME PV CODE 11 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS |
| IEEE 1115-2014 | IEEE Recommended Practice for Sizing Nickel-Cadmium Batteries for Stationary Applications |
| IEEE 485-2010 | IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications |
| API 520-2 : 2015 | SIZING, SELECTION, AND INSTALLATION OF PRESSURE-RELIEVING DEVICES - PART 2: INSTALLATION |
| CSA Z299.3 : 1985 | QUALITY ASSURANCE PROGRAM - CATEGORY 3 |
| CSA Z299.1 : 1985 | QUALITY ASSURANCE PROGRAM - CATEGORY 1 |
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