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Superseded
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by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Superseded date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Superseded by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
Important note : Users cannot be edited or removed once added to your Multi user PDF.
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Superseded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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