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ISA 67.04.01

Setpoints for Nuclear Safety-Related Instrumentation

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Organization: ISA
Publication Date: 8 December 2018
Status: active
Page Count: 30
scope:

This standard defines the requirements for assessing, establishing, and maintaining nuclear safety-related and other important instrument setpoints associated with nuclear power plants or nuclear reactor facilities. The scope includes instrumentation-based setpoints that assure compliance to one or more safety or design limits.

Purpose

The purpose of this standard is to define the bases for establishing safety-related and other important instrument setpoints associated with nuclear power plants and nuclear reactor facilities.

 

Document History

ISA 67.04.01
December 8, 2018
Setpoints for Nuclear Safety-Related Instrumentation
This standard defines the requirements for assessing, establishing, and maintaining nuclear safety-related and other important instrument setpoints associated with nuclear power plants or nuclear...
ISA 67.04.01
May 16, 2006
Setpoints for Nuclear Safety-Related Instrumentation
This standard defines the requirements for assessing, establishing, and maintaining nuclear safety-related and other important instrument setpoints associated with nuclear power plants or nuclear...
ISA 67.04.01
May 16, 2006
Setpoints for Nuclear Safety-Related Instrumentation
This standard defines the requirements for assessing, establishing, and maintaining nuclear safety-related and other important instrument setpoints associated with nuclear power plants or nuclear...
ISA 67.04.01
February 29, 2000
Setpoints for Nuclear Safety-Related Instrumentation
A description is not available for this item.
ISA S67.04 P1
January 1, 1994
Setpoints for Nuclear Safety-Related Instrumentation
A description is not available for this item.

References

This document references:
IEEE 338 - Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems
Published by IEEE on February 6, 2012
The standard provides criteria for the performance of periodic testing of nuclear power generating station safety systems. The scope of periodic testing consists of functional tests and checks,...
This document references:
ASME NQA-1 - Quality Assurance Requirements for Nuclear Facility Applications
Published by ASME on December 31, 2019
PURPOSE Part I — this Part — establishes requirements for the development and implementation of a Quality Assurance Program (QAP) for nuclear facility applications. It is arranged by Requirements 1...
This document references:
IEEE 338 - Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems
Published by IEEE on February 6, 2012
The standard provides criteria for the performance of periodic testing of nuclear power generating station safety systems. The scope of periodic testing consists of functional tests and checks,...
This document references:
IEEE 352 - Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities
Published by IEEE on December 7, 2016
This guide contains general reliability and availability analysis methods that can be applied to structures, systems, and components (SSCs) in nuclear power generating stations and other nuclear...
This document references:
ISA 51.1 - Process Instrumentation Terminology
Published by ISA on January 1, 1979
This Process Instrumentation Terminology Standard is intended to include many specialized terms used in the industrial process industries, to describe the use, performance, operating influences,...
This document references:
67.02.01 - Nuclear Safety-Related Instrument-Sensing Line Piping and Tubing Standard for Use in Nuclear Power Plants
Published by ISA on November 29, 2021
This standard covers design, protection, and installation of nuclear safety-related instrument-sensing lines and sampling lines for nuclear power plants. The standard covers the pressure boundary...
This document is referenced by:
CSA N290.15 - Requirements for the safe operating envelope of nuclear power plants
Published by CSA on January 1, 2019
This Standard outlines a consensus approach to defining, implementing, and maintaining the SOE at NPPs. Additional guidance is provided in Annex A for operating CANDU® NPPs. In this Standard, “shall”...
This document is referenced by:
AG-1 - Code on Nuclear Air and Gas Treatment
Published by ASME on October 13, 2023
This Code provides requirements for the performance, design, fabrication, installation, inspection, acceptance testing, and quality assurance of equipment used in air and gas treatment systems in...
This document is referenced by:
ANS 51.10 - Auxiliary Feedwater System for Pressurized Water Reactors
Published by ANS on January 1, 2020
This standard1) sets forth the safety-related functional requirements, performance requirements, design criteria, design requirements for testing and maintenance, and interfaces for the...
This document is referenced by:
741 - Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
Published by IEEE on March 24, 2022
This standard provides the principal design criteria, design features, and testing requirements for the protection of Class 1E power systems and equipment supplied from those systems. It identifies...
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