ISA 67.04.01 : 2006
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
Hardcopy , PDF
English
01-01-2006
19-03-2021
1 Purpose
2 Scope
3 Definitions
4 Establishment of Setpoints
4.1 Safety Limits
4.2 Analytical Limits
4.3 Trip Setpoints
4.4 Choosing Trip Setpoints
4.5 Combination of Uncertainties
4.6 Performance Test Acceptance Criteria
5 Documentation
6 Maintenance of safety-related setpoints
6.1 Testing
6.2 Replacement
7 References
8 Informative References
Specifies the requirements for assessing, establishing, and maintaining nuclear safety-related and other important instrument setpoints associated with nuclear power plants or nuclear reactor facilities.
| Committee |
SP67
|
| DocumentType |
Standard
|
| Pages |
22
|
| PublisherName |
International Society of Automation
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE 741-2007 | IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations |
| ISA TR67.04.08 : 1996 | SETPOINTS FOR SEQUENCED ACTIONS |
| ISA 67.06.01 : 2002 | PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| ISA TR67.04.09 : 2005 | GRADED APPROACHES TO SETPOINT DETERMINATION |
| CSA N290.0 & N290.1 PACKAGE : 2013 | CONSISTS OF N290.0-11, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.1-13, REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF NUCLEAR POWER PLANTS |
| IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for 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 |
| BS IEC 63147:2017 | Criteria for accident monitoring instrumentation for nuclear power generating stations |
| ISA 67.06 : 1984 | RESPONSE TIME TESTING OF NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE DRAFT 741 : D1 2006 | CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS |
| ISA 67.01 : 1994 | TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS |
| ISA 67.06.01 : 2002 | PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS |
| ISA 67.02.01 : 1999 | NUCLEAR SAFETY-RELATED INSTRUMENT SENSING LINE PIPING AND TUBING STANDARD FOR USE IN NUCLEAR POWER PLANTS |
| ASME NQA 1 : 2015 | Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015) |
| ISA RP67.04.02 : 2000 | METHODOLOGIES FOR THE DETERMINATION OF SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| ISA 51.1 : 1979 | PROCESS INSTRUMENTATION TERMINOLOGY |
| IEEE 338-2012 | IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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