ISA 67.01.01 : 2002
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
Hardcopy , PDF
03-01-2020
English
01-01-2002
Important note : Users cannot be edited or removed once added to your Multi user PDF.
1 Scope
2 Purpose
3 Definitions and terminology
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
Describes the installation of transducers for nuclear safety-related applications. Also establishes requirements and recommendations for the installation of transducers and auxiliary equipment for nuclear applications outside of the main reactor vessel.
| Committee |
SP67
|
| DevelopmentNote |
Supersedes and redesignates ISA 67.01 (02/2003)
|
| DocumentType |
Standard
|
| Pages |
28
|
| PublisherName |
International Society of Automation
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| ASNT SNT TC 1A : 2016 | TOPICAL OUTLINES FOR QUALIFICATION OF NONDESTRUCTIVE TESTING PERSONNEL |
| ASME B31.1 : 2016 | POWER PIPING |
| 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 |
| ISA 67.02.01 : 1999 | NUCLEAR SAFETY-RELATED INSTRUMENT SENSING LINE PIPING AND TUBING STANDARD FOR USE IN NUCLEAR POWER PLANTS |
| 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 |
| 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 |
| 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 |
| ISA 37.1 : 1975 | ELECTRICAL TRANSDUCER NOMENCLATURE AND TERMINOLOGY |
| AWS D1.1 : 2000 | STRUCTURAL WELDING CODE - STEEL |
| ISA 51.1 : 1979 | PROCESS INSTRUMENTATION TERMINOLOGY |
| IEEE 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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