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IEEE 1023-2004 REDLINE

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities
Available format(s)

PDF

Superseded date

04-19-2021

Language(s)

English

Published date

06-08-2005

Publisher

Institute of Electrical & Electronics Engineers

1 Overview
  1.1 Scope
  1.2 Purpose
2 Normative references
3 Definitions
4 Systematic application of human factors engineering
5 Basic considerations of human factors engineering
  5.1 Task considerations
  5.2 Environmental considerations
  5.3 Equipment considerations
  5.4 Personnel considerations
  5.5 Organization and support considerations
6 Implementation of human factors engineering activities
  6.1 Engineering process model
  6.2 Planning
  6.3 Analysis
  6.4 Specification
  6.5 Testing and evaluation
  6.6 Operations and maintenance
Annex A (informative) Bibliography
Annex B (informative) Sample implementations of HFE activities
        per the Star Model
Annex C (informative) Screening checklist
      C.1 Task requirements
      C.2 Control board, panel or rack modification
      C.3 Component replacements
Annex D (informative) Design review checklist

Presents recommended practices for applying human factors engineering (HFE) to systems and equipment that have significant human interfaces in nuclear power generating stations and other nuclear facilities.

This document provides recommended practices for applying human factors engineering (HFE) to systems and equipment that have significant human interfaces in nuclear power generating stations and other nuclear facilities.

Committee
Nuclear Power Engineering Committee
DocumentType
Standard
ISBN
978-0-7381-4644-7
Pages
70
ProductNote
This standard also refers to - IEEE P1586™ (D1.0)
PublisherName
Institute of Electrical & Electronics Engineers
Status
Superseded
SupersededBy
Supersedes

DIN EN ISO 11064-7 E : 2006 ERGONOMIC DESIGN OF CONTROL CENTRES - PART 7: PRINCIPLES FOR THE EVALUATION OF CONTROL CENTRES
IEEE DRAFT 1289 : D13 FEB 96 GUIDE FOR THE APPLICATION OF HUMAN FACTORS ENGINEERING IN THE DESIGN OF COMPUTER-BASED MONITORING AND CONTROL DISPLAYS FOR NUCLEAR POWER GENERATING STATIONS
04/19979705 DC : DRAFT SEP 2004 BS EN ISO 11064-7 - ERGONOMIC DESIGN OF CONTROL CENTRES - PART 7: PRINCIPLES FOR THE EVALUATION OF CONTROL CENTRES
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
IEEE 692-2013 REDLINE IEEE Standard for Criteria for Security Systems for Nuclear Power Generating Stations
IEEE 1786-2011 IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities
ISO 11064-7:2006 Ergonomic design of control centres Part 7: Principles for the evaluation of control centres
BS EN ISO 11064-7:2006 Ergonomic design of control centres Principles for the evaluation of control centres
DIN EN ISO 11064-7:2006-08 Ergonomic design of control centres - Part 7: Principles for the evaluation of control centres (ISO 11064-7:2006)
EN ISO 11064-7:2006 Ergonomic design of control centres - Part 7: Principles for the evaluation of control centres (ISO 11064-7:2006)
IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
IEEE 1289 : 1998 APPLICATION OF HUMAN FACTORS ENGINEERING IN THE DESIGN OF COMPUTER-BASED MONITORING AND CONTROL DISPLAYS FOR NUCLEAR POWER GENERATING STATIONS
IEEE 420-2013 REDLINE IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations
IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
ANS 10.5 : 2006(R2011) ACCOMMODATING USER NEEDS IN SCIENTIFIC AND ENGINEERING COMPUTER SOFTWARE DEVELOPMENT
IEEE 497-2002 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
ANS 58.8 : 1994(R2017) TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
IEEE 1082-1997 IEEE Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating Stations
AIAA G 035 : 2000 GUIDE FOR HUMAN PERFORMANCE MEASUREMENTS
ANS 3.1 : 2014 SELECTION, QUALIFICATION, AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS
ANS 3.5 : 2009 NUCLEAR POWER PLANT SIMULATORS FOR USE IN OPERATOR TRAINING AND EXAMINATION
IEEE 1220-2005 IEEE Standard for Application and Management of the Systems Engineering Process
IEEE 1289 : 1998 APPLICATION OF HUMAN FACTORS ENGINEERING IN THE DESIGN OF COMPUTER-BASED MONITORING AND CONTROL DISPLAYS FOR NUCLEAR POWER GENERATING STATIONS
ANS 3.2 : 2012(R2017) MANAGERIAL, ADMINISTRATIVE, AND QUALITY ASSURANCE CONTROLS FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS
IEEE 603-1998 IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
IEEE 845-1999 IEEE Guide for the Evaluation of Human-System Performance in Nuclear Power Generating Stations
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations

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