IEEE 497-2010
Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by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 Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
Available format(s)
PDF
Superseded date
29-07-2016
Superseded by
Language(s)
English
Published date
10-11-2010
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1. Overview
2. Normative references
3. Definitions
4. Selection criteria
5. Performance criteria
6. Design criteria
7. Qualification criteria
8. Display criteria
9. Quality assurance
Annex A (informative) - Accident monitoring instrument
channel accuracy
Annex B (informative) - Examples of monitoring channel
displays
Annex C (informative) - Operational state diagram
Annex D (informative) - Bibliography
This standard contains the functional and design criteria for accident monitoring instrumentation for nuclear power generating stations.
| Committee |
Nuclear Power Engineering Committee
|
| DevelopmentNote |
Supersedes IEEE DRAFT 497. (02/2005) Also numbered as IEC 63147. (12/2017)
|
| DocumentType |
Standard
|
| ISBN |
978-0-7381-6937-8
|
| Pages |
34
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE 1023-2004 REDLINE | IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| ANS 59.2-1985 | NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR, |
| IEC TR 63123:2017 | Nuclear power plants - Instrumentation, control and electrical power systems - Guidance for the application of IEC 63147:2017/IEEE Std 497™ -2016 in the IAEA / IEC framework |
| 18/30376682 DC : DRAFT APR 2018 | BS IEC/IEEE 63113 - NUCLEAR FACILITIES - INSTRUMENTATION IMPORTANT TO SAFETY - SPENT FUEL POOL INSTRUMENTATION |
| 17/30357475 DC : 0 | BS IEC/IEEE 63113 - NUCLEAR FACILITIES - INSTRUMENTATION IMPORTANT TO SAFETY - SPENT FUEL POOL INSTRUMENTATION |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| BS IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEEE 627-2010 | IEEE Standard for Qualification of Equipment Used in Nuclear Facilities |
| ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
| IEEE 577-2012 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations |
| ASME PV CODE 3 NCA DIV 1&2 : 2017 | BPVC Section III-Rules for Constructions of Nuclear Facility Components BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - GENERAL REQUIREMENTS FOR DIVISION 1 AND DIVISION 2 |
| IEC 60812:2006 | Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA) |
| IEEE 379-2014 | IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEC 62340:2007 | Nuclear power plants - Instrumentation and control systems important to safety - Requirements for coping with common cause failure (CCF) |
| ANS 4.5-80(R1986) | ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR |
| IEEE 7-4.3.2-2010 REDLINE | IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
| IEC 60980:1989 | Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEEE 308-2001 | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEC 60880:2006 | Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions |
| IEEE 344-2004 | IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| IEEE 379-2000 | IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| IEC 60780:1998 | Nuclear power plants - Electrical equipment of the safety system - Qualification |
| IEC 61225:2005 | Nuclear power plants - Instrumentation and control systems important to safety - Requirements for electrical supplies |
| ISA 67.01.01 : 2002 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| IEC 60709:2004 | Nuclear power plants - Instrumentation and control systems important to safety - Separation |
| IEEE 1023-2004 REDLINE | IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
| IEEE 577-2004 | IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities |
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