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ISA 67.01.01 : 2002

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by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

Available format(s)

Hardcopy , PDF

Superseded date

03-01-2020

Superseded by

ANSI/ISA-67.01.01-2019

Language(s)

English

Published date

01-01-2002

€113.06
Excluding VAT

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Superseded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

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IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
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
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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