ISA 67.01 : 1994
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
View Superseded by
TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
16-09-2002
01-01-1994
1 Scope
2 Purpose
3 Definitions
4 Safety classification
4.1 Code applicability
5 Equipment mounting
5.1 Mounting of in-line transducers
5.2 Mounting of off-line transducers
5.3 Mechanical protection
5.4 Auxiliary equipment
6 Location of equipment
6.1 Selecting a location
6.2 Separation of redundant transducers
6.3 Accessibility for periodic test and service
6.4 Auxiliary equipment
7 Environmental considerations
7.1 Seismic considerations
7.2 Operating vibration
7.3 Ambient operating conditions
7.4 Special operating conditions
7.5 Auxiliary equipment
8 Interface connections
8.1 Process fluid connections
8.2 Types of instrument connections
8.3 Electrical connection
9 Service, calibration, and test facilities
9.1 Calibration test connectors (input)
9.2 Vents and drains
9.3 Signal test connections (output)
9.4 Communications
9.5 Labelling
10 Quality assurance
Annex A - References and bibliography
Deals with the installation of transducers for nuclear safety-related applications.
| Committee |
SP67
|
| DevelopmentNote |
Formerly it was ISA-S67.01 (05/2001)
|
| DocumentType |
Standard
|
| PublisherName |
International Society of Automation
|
| Status |
Withdrawn
|
| SupersededBy |
| ISA 67.04.01 : 2006 | SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION |
| ASNT SNT TC 1A : 2016 | TOPICAL OUTLINES FOR QUALIFICATION OF NONDESTRUCTIVE TESTING PERSONNEL |
| ASME MFC6M : 1998 | MEASUREMENT OF FLUID FLOW IN PIPES USING VORTEX FLOW METERS |
| IEEE 383-2015 | IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities |
| IEEE 344-2013 | IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations |
| ASME PTC19.3 : 1974(R2004) | PERFORMANCE TEST CODE - PART 3: TEMPERATURE MEASUREMENT |
| ANSI N18.2 : LATEST | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| ISA S67.02 : 1983 | NUCLEAR SAFETY RELATED INSTRUMENT SENSING LINE PIPING AND TUBING STANDARDS FOR USE IN NUCLEAR POWER PLANTS |
| IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
| ASTM D 2633 : 2013-03 | TEST METHODS FOR THERMOPLASTIC INSULATIONS AND JACKETS FOR WIRE AND CABLE |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| IEEE 323-2003 | IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| ASME MFC 3M : 2004 | MEASUREMENT OF FLUID FLOW IN PIPES USING ORIFICE, NOZZLE, AND VENTURI |
| ASME B16.5 : 2017 | PIPE FLANGES AND FLANGED FITTINGS: NPS 1/2 THROUGH NPS 24 METRIC/INCH STANDARD |
| AWS D1.1 : 2000 | STRUCTURAL WELDING CODE - STEEL |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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