IEEE 1023-2004 REDLINE
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities
04-19-2021
English
06-08-2005
Important note : All end users must be registered with an Account prior to user licenses being assigned.
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.
| 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Superseded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 |
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.
| 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 |
| 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 |
| 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 |
Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.