IEEE 352-1987
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
Available format(s)
PDF
Superseded date
09-21-2021
Superseded by
Language(s)
English
Published date
11-30-1986
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1. Overview
2. Normative references
3. Definitions, acronyms, and abbreviations
4. Objectives and methods
5. Qualitative analysis principles
6. Quantitative analysis principles
7. Guides for data acquisition and use
8. Application of reliability methods
Annex A (informative) - Bibliography
Annex B (informative) - Illustration of concepts and
methods of reliability and availability analyses
Annex C (informative) - Mean time to repair (MTTR)
process
Includes general reliability and availability analysis methods that can be applied to structures, systems, and components (SSCs) in nuclear power generating stations and other nuclear facilities.
| Committee |
Nuclear Power Engineering Committee
|
| DocumentType |
Standard
|
| Pages |
118
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE 933-2013 REDLINE | IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities |
| CEI EN 61131-6 : 2013 | PROGRAMMABLE CONTROLLERS - PART 6: FUNCTIONAL SAFETY |
| IEEE 1240-2000 | IEEE Guide for the Evaluation of the Reliability of HVDC Converter Stations |
| 08/30193509 DC : DRAFT NOV 2008 | BS EN 61508-2 - FUNCTIONAL SAFETY OF ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS - PART 2: REQUIREMENTS FOR ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS |
| I.S. EN 61508-2:2010 | FUNCTIONAL SAFETY OF ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS - PART 2: REQUIREMENTS FOR ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS |
| CEI EN 50495 : 2011 | SAFETY DEVICES REQUIRED FOR THE SAFE FUNCTIONING OF EQUIPMENT WITH RESPECT TO EXPLOSION RISKS |
| IEEE 650-2006 | IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| EN 61131-6:2012 | Programmable controllers - Part 6: Functional safety |
| EN 61508-2:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 2: Requirements for electrical/electronic/programmable electronic safety-related systems |
| EN 50495:2010 | Safety devices required for the safe functioning of equipment with respect to explosion risks |
| UNE-EN 50495:2010 | Safety devices required for the safe functioning of equipment with respect to explosion risks |
| BS EN 61131-6:2012 | Programmable controllers Functional safety |
| IEEE/ANSI N42.4-1971 | American National Standard for High Voltage Connectors for Nuclear Instruments |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEC TR 62987:2015 | Nuclear power plants - Instrumentation and control systems important to safety - Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems |
| IEEE 497-2016 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| PD IEC/TR 62987:2015 | Nuclear power plants. Instrumentation and control systems important to safety. Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems |
| IEEE DRAFT 379 : D5 2000 | DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| DIN 25424-1:1981-09 | FAULT TREE ANALYSIS; METHOD AND SYMBOLS |
| IEEE DRAFT 338 : D4 2006 | CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS |
| SAE ARP 5783 : 2012 | HEALTH AND USAGE MONITORING METRICS, MONITORING THE MONITOR |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| CEI EN 61508-2 : 2011 | FUNCTIONAL SAFETY OF ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS - PART 2: REQUIREMENTS FOR ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| BS EN 61508-2:2010 | Functional safety of electrical/electronic/ programmable electronic safety-related systems Requirements for electrical/electronic/ programmable electronic safety-related systems |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| ANS 56.3-77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
| BS EN 50495:2010 | Safety devices required for the safe functioning of equipment with respect to explosion risks |
| IEEE 1205-2014 | IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| IEEE 1819-2016 | IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEC 61131-6:2012 | Programmable controllers - Part 6: Functional safety |
| IEC 61508-2:2010 | Functional safety of electrical/electronic/programmable electronic safety-related systems - Part 2: Requirements for electrical/electronic/programmable electronic safety-related systems (see Functional Safety and IEC 61508) |
| BS IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| BS IEC 61508-2 : 2000 AMD 13780 | FUNCTIONAL SAFETY OF ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS - PART 2: REQUIREMENTS FOR ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| 05/30143456 DC : DRAFT DEC 2005 | IEC 61508-2 - FUNCTIONAL SAFETY OF ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY - PART 2: REQUIREMENTS FOR ELECTRICAL/ELECTRONIC/PROGRAMMABLE ELECTRONIC/PROGRAMMABLE ELECTRONIC SAFETY-RELATED SYSTEMS |
| I.S. EN 61131-6:2012 | PROGRAMMABLE CONTROLLERS - PART 6: FUNCTIONAL SAFETY (IEC 61131-6:2012 (EQV)) |
| UNE-EN 61508-2:2011 | Functional safety of electrical/electronic/programmable electronic safety-related systems -- Part 2: Requirements for electrical/electronic/programmable electronic safety-related systems |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| I.S. EN 50495:2010 | SAFETY DEVICES REQUIRED FOR THE SAFE FUNCTIONING OF EQUIPMENT WITH RESPECT TO EXPLOSION RISKS |
| CAN/CSA-C22.2 NO. 61508-2:17 | Functional safety of electrical/electronic/programmable electronic safety-related systems — Part 2: Requirements for electrical/electronic/programmable electronic safety-related systems (Adopted IEC 61508-2:2010, second edition, 2010-04, with Canadian deviations) | Sécurité fonctionnelle des systèmes électriques/électroniques/électroniques programmables relatifs à la sécurité — Partie 2 : Exigences pour les systèmes électriques/électroniques/électroniques programmables relatifs à la sécurité (norme IEC 61508-2:2010 adoptee, deuxième édition, 2010-04, avec exigences propres au Canada) |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| IEEE 1682-2011 | IEEE Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Nuclear Power Generating Stations |
| IEEE 379-2000 | IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEEE 379-1988 | IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| IEEE 577-1976 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| IEEE 1082-1997 | IEEE Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating Stations |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| MIL-STD-1629 Revision A:1980 | PROCEDURES FOR PERFORMING A FAILURE MODE, EFFECTS AND CRITICALITY ANALYSIS |
| IEEE 500-1984 | IEEE Guide To The Collection And Presentation Of Electrical, Electronic, Sensing Component, And Mechanical Equipment Reliability Data for Nuclear-Power Generating Stations |
| IEEE 603-1980 | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Systems |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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