IEC 63147:2017
Current
The latest, up-to-date edition.
Criteria for accident monitoring instrumentation for nuclear power generating stations
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English
14-12-2017
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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
Annex E (informative) - IEEE list of participants
IEC 63147:2017(E) contains the functional and design criteria for accident monitoring instrumentation for new plant designs and nuclear power generating stations desiring to perform design modifications. The purpose of this standard is to establish selection, design, performance, qualification, and display criteria for accident monitoring instrumentation for anticipated operational occurrences, design basis events, and severe accidents.
This standard applies to accident monitoring instrumentation intended for use during the following operations:
- As required for planned operator action related to accident mitigation,
- For assessing plant conditions, safety system performance, and making decisions related to plant response to abnormal events,
- For achieving and maintaining safe shutdown following an accident
This standard does not apply to the following:
- Accident monitoring instrumentation that is intended solely for historical recording or solely for maintenance purposes
- Other instrumentation that may be available during accident conditions.
This standard is an adoption of IEEE 497-2016 by IEC.
When applied in an IAEA / IEC environment this standard is to be used in conjunction with IEC TR 63123.
| Committee |
TC 45/SC 45A
|
| DevelopmentNote |
Also numbered as IEEE 497. To be read in conjunction with IEC TR 63123. Stability Date: 2020. (12/2017)
|
| DocumentType |
Standard
|
| Pages |
26
|
| PublisherName |
International Electrotechnical Committee
|
| Status |
Current
|
| Standards | Relationship |
| DIN IEC 63147:2022-03 | Identical |
| VDE 0491-4-3:2022-03 | Identical |
| BS IEC 63147:2017 | Identical |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| 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 |
| 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 |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| IEC 60880:2006 | Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| 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 |
| 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 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 |
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