IEEE 7 4.3.2 1994
$52.00
IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
| Published By | Publication Date | Number of Pages |
| IEEE | 1994 | 47 |
Revision Standard – Inactive – Superseded. Additional computer specific requirements to supplement the criteria and requirements of IEEE Std 603-1991 are specified. Within the context of this standard, the term computer is a system that includes computer hardware, software, firmware, and interfaces. The criteria contained herein, in conjunction with criteria in IEEE Std 603-1991, establish minimum functional and design requirements for computers used as components of a safety system.
PDF Catalog
| PDF Pages | PDF Title |
|---|---|
| 1 | Title Page |
| 3 | Introduction |
| 6 | Participants |
| 8 | CONTENTS |
| 9 | 1. Scope 2. References |
| 10 | 3. Definitions and abbreviations 3.1 Definitions 3.2 Abbreviations |
| 11 | 4. Safety system design basis 5. Safety system criteria 5.1 Single-failure 5.2 Completion of protective action 5.3 Quality |
| 13 | 5.4 Equipment qualification 5.5 System integrity |
| 14 | 5.6 Independence 5.7 Capability for test and calibration 5.8 Information displays 5.9 Control of access |
| 15 | 5.10 Repair 5.11 Identification 5.12 Auxiliary features 5.13 Multi-unit stations 5.14 Human factor considerations 5.15 Reliability 6. Sense and command features—Functional and design requirements 7. Execute features—Functional and design requirements 8. Power source requirements |
| 16 | Annex A— Relationship of this standard to IEEE Std 603-1991 |
| 18 | Annex B— Diversity needs determination |
| 19 | Annex C—Electromagnetic compatibility |
| 22 | Annex D— Qualification of existing commercial computers |
| 25 | Annex E—Verification and validation |
| 34 | Annex F— Identification and resolution of abnormal conditions and events |
| 40 | Annex G— Communication independence |
| 43 | Annex H— Computer reliability |
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