IEEE DRAFT 497 : DE FEB 2001
Superseded
View Superseded by
DRAFT STANDARD CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR NUCLEAR POWER GENERATING STATIONS
01-12-2013
09-30-2002
1 Overview
1.1 Scope
1.2 Purpose
1.3 Application
2 References
3 Definitions
4 Selection Criteria
4.1 Type A Variables
4.2 Type B Variables
4.3 Type C Variables
4.4 Type D Variables
4.5 Type E Variables
4.6 Documentation of Selection Bases
5 Performance Criteria
5.1 Range
5.2 Accuracy
5.3 Response Time
5.4 Required Instrumentation Duration
5.5 Performance Assessment Documentation
6 Design Criteria
6.1 Single Failure
6.2 Information Ambiguity
6.3 Common Cause Failure
6.4 Independence and Separation
6.5 Power Supply
6.6 Isolation
6.7 Calibration
6.8 Testability
6.9 Direct Measurement
7 Qualification Criteria
7.1 Type A Variables
7.2 Type B Variables
7.3 Type C Variables
7.4 Type D Variables
7.5 Type E Variables
7.6 Portable Instruments
7.7 Post Event Operating Time
7.8 Documentation of Qualification Criteria
8 Display Criteria
8.1 Display Characteristics
8.2 Trend or Rate Information
8.3 Display Identification
8.4 Type of Monitoring Channel Display
8.5 Display Location
8.6 Information Ambiguity
8.7 Recording
8.8 Digital Display Signal Validation
8.9 Display Criteria Documentation
9 Quality Assurance
Figure 1: Display Channel
Figure 2: Examples of Monitoring Channel Displays
Annex A: Accident Monitoring Instrument Channel
Accuracy; Clarification and Typical Values
Annex B: Bibliography
Describes the functional and design requirements for accident monitoring instrumentation for nuclear power generating stations. It contains guidance for the selection of variables design and performance requirements.
| DocumentType |
Draft
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Superseded
|
| SupersededBy |
| IEEE 7-4.3.2-2016 | IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations |