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  • ISA 67.01 : 1994

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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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    TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS

    Available format(s):  Hardcopy

    Superseded date:  16-09-2002

    Language(s):  English

    Published date:  01-01-1994

    Publisher:  International Society of Automation

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    Table of Contents - (Show below) - (Hide below)

    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

    Abstract - (Show below) - (Hide below)

    Deals with the installation of transducers for nuclear safety-related applications.

    General Product Information - (Show below) - (Hide below)

    Committee SP67
    Development Note Formerly it was ISA-S67.01 (05/2001)
    Document Type Standard
    Publisher International Society of Automation
    Status Superseded
    Superseded By

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    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
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    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
    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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