ISA RP67.04.02 : 2000
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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METHODOLOGIES FOR THE DETERMINATION OF SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
Hardcopy , PDF
19-03-2021
English
01-01-2000
Introduction
1 Scope
2 Purpose
3 Definitions
4 Using this recommended practice
5 Preparation for determining instrument channel setpoints
6 Calculating instrument channel uncertainties
7 Establishment of setpoints
8 Performance test
9 Interfaces
10 Documentation
11 References
Annex A - Glossary
Annex B - Vessel and reference leg temperature effects on
differential pressure transmitters used for level
measurement
Annex C - Effects on flow measurement accuracy
Annex D - Insulation resistance effects
Annex E - As-found and as-left data - collection and
interpretation
Annex F - Line pressure loss/head pressure effects
Annex G - RTD accuracy confirmation
Annex H - Uncertainties associated with digital signal
processing
Annex I - Recommendations for inclusion of instrument
uncertainties during normal operation in the
as-found tolerance determination
Annex J - Discussions concerning statistical analysis
Annex K - Propagation of uncertainty through
signal-conditioning modules
Annex L - Example uncertainty/setpoint calculations
Specifies guidelines and examples of methods for the implementation of ANSI/ISA-67.04.01-2006 in order to facilitate the performance of instrument uncertainty calculations and setpoint determination for safety-related instrument setpoints in nuclear power plants.
DevelopmentNote |
Supersedes ISA RP67.04 PT2 (05/2001)
|
DocumentType |
Standard
|
Pages |
156
|
PublisherName |
International Society of Automation
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
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 |
ASME OM : 2017 | OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS |
CSA N290.15 : 2010 : INC : UPD 1 : 2016 : R201500 | REQUIREMENTS FOR THE SAFE OPERATING ENVELOPE OF NUCLEAR POWER PLANTS |
14/30258869 DC : 0 | BS IEC 62765-1 ED 1.0 - NUCLEAR POWER PLANTS - INSTRUMENTATION AND CONTROL IMPORTANT TO SAFETY - MANAGEMENT OF AGEING OF SENSORS AND TRANSMITTERS - PART 1: PRESSURE TRANSMITTERS |
CSA N290.15 : 2010 | REQUIREMENTS FOR THE SAFE OPERATING ENVELOPE OF NUCLEAR POWER PLANTS |
CSA N290.15 : 2010 : FR | REQUIREMENTS FOR THE SAFE OPERATING ENVELOPE OF NUCLEAR POWER PLANTS |
ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
IEC 62765-1:2015 | Nuclear powers plants - Instrumentation and control important to safety - Management of ageing of sensors and transmitters - Part 1: Pressure transmitters |
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