I.S. EN 60987:2015
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - HARDWARE DESIGN REQUIREMENTS FOR COMPUTER-BASED SYSTEMS
Hardcopy , PDF
10-09-2021
English
01-01-2015
For Harmonized Standards, check the EU site to confirm that the Standard is cited in the Official Journal.
Only cited Standards give presumption of conformance to New Approach Directives/Regulations.
FOREWORD
INTRODUCTION
1 Scope
2 Normative references
3 Terms and definitions
4 Project structure
5 Hardware requirements
6 Design and development
7 Verification and validation
8 Qualification
9 Manufacture
10 Installation and commissioning
11 Maintenance
12 Modification
13 Operation
Annex A (informative) - Overview of system life cycle
Annex B (informative) - Outline of qualification
Annex C (informative) - Example of maintenance procedure
Bibliography
Annex ZA (normative) - Normative references to international
publications with their corresponding European
publications
Covers NPP computer-system hardware for systems of Class 1 and 2.
DevelopmentNote |
For CENELEC adoptions of IEC publications, please check www.iec.ch to be sure that you have any corrigenda that may apply. (01/2017)
|
DocumentType |
Standard
|
Pages |
86
|
PublisherName |
National Standards Authority of Ireland
|
Status |
Superseded
|
SupersededBy |
Standards | Relationship |
EN 60987:2015 | Identical |
IEC 61025:2006 | Fault tree analysis (FTA) |
EN 60812:2006 | Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA) |
ISO 3951-1:2013 | Sampling procedures for inspection by variables — Part 1: Specification for single sampling plans indexed by acceptance quality limit (AQL) for lot-by-lot inspection for a single quality characteristic and a single AQL |
EN 22768-2:1993 | General tolerances - Part 2: Geometrical tolerances for features without individual tolerance indications (ISO 2768-2:1989) |
IEC 61226:2009 | Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions |
IEC 60812:2006 | Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA) |
IEC 62138:2004 | Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions |
EN 62138:2009 | NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT FOR SAFETY - SOFTWARE ASPECTS FOR COMPUTER-BASED SYSTEMS PERFORMING CATEGORY B OR C FUNCTIONS |
EN 60880:2009 | NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL SYSTEMS IMPORTANT TO SAFETY - SOFTWARE ASPECTS FOR COMPUTER-BASED SYSTEMS PERFORMING CATEGORY A FUNCTIONS |
EN ISO 9001:2015 | Quality management systems - Requirements (ISO 9001:2015) |
ISO 2768-2:1989 | GENERAL TOLERANCES - PART 2: GEOMETRICAL TOLERANCES FOR FEATURES WITHOUT INDIVIDUAL TOLERANCE INDICATIONS |
ISO/IEC 12207:2008 | Systems and software engineering — Software life cycle processes |
EN 22768-1:1993 | General tolerances - Part 1: Tolerances for linear and angular dimensions without individual tolerance indications (ISO 2768-1:1989) |
EN 61025:2007 | Fault tree analysis (FTA) |
IEC 60880:2006 | Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions |
ISO 9001:2015 | Quality management systems — Requirements |
IEC 60780:1998 | Nuclear power plants - Electrical equipment of the safety system - Qualification |
IEC 61513:2011 | Nuclear power plants - Instrumentation and control important to safety - General requirements for systems |
ISO 3951-2:2013 | Sampling procedures for inspection by variables — Part 2: General specification for single sampling plans indexed by acceptance quality limit (AQL) for lot-by-lot inspection of independent quality characteristics |
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