Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283403
R. Klein, G. Klopp
Reliability centered maintenance (RCM) is a program that addresses the nuclear utility need and the regulatory pressure for improved maintenance practices. A wide variety of system inputs are required to successfully perform RCM. Expert systems are a tool to reduce workload, facilitate the process and improve the performance of an RCM program. Predictive maintenance, using data trending to monitor system performance and identify impending failures, is an alternative input to RCM. Artifical neural networks, embedded in traditional expert systems, can be used to perform predictive maintenance functions. Human factors should be included in an RCM program from the beginning. Maintainability factors related to human error should be identified and input to the RCM process to affect maintenance decisions. Human factors issues are also essential to the development and integration of an RCM expert system.<>
{"title":"The human factors impact of an expert system based reliability centered maintenance program","authors":"R. Klein, G. Klopp","doi":"10.1109/HFPP.1992.283403","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283403","url":null,"abstract":"Reliability centered maintenance (RCM) is a program that addresses the nuclear utility need and the regulatory pressure for improved maintenance practices. A wide variety of system inputs are required to successfully perform RCM. Expert systems are a tool to reduce workload, facilitate the process and improve the performance of an RCM program. Predictive maintenance, using data trending to monitor system performance and identify impending failures, is an alternative input to RCM. Artifical neural networks, embedded in traditional expert systems, can be used to perform predictive maintenance functions. Human factors should be included in an RCM program from the beginning. Maintainability factors related to human error should be identified and input to the RCM process to affect maintenance decisions. Human factors issues are also essential to the development and integration of an RCM expert system.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115184262","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283430
J. Malcolm, G.J. Hinton, J. Pauksens
The design process and features of new CANDU (Canadian Deuterium Uranium) control centres are discussed. The design process incorporates the systematic consideration of human factors (HF) issues as part of the overall systems engineering activity. This design process has been based on international standards for control center design. CANDU control centers have evolved through three generations of designs with the current advanced designs representing the fourth generation. CANDU plants have always incorporated digital technologies. Video display units (VDUs) have been present in CANDU control centers since the late 1960s. Advanced designs, such as the CANDU 3, make use of a distributed control system feeding data to a plant-wide LAN. The operator interface system is based on a set of nodes on the plant-wide LAN which then feed various VDUs in the control centers. Large-scale wall displays are also used to present operators with a plant overview. Details of the HF aspects of the control center design process and the CANDU 3 control room are discussed.<>
{"title":"Human machine interface design in new CANDU control centres","authors":"J. Malcolm, G.J. Hinton, J. Pauksens","doi":"10.1109/HFPP.1992.283430","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283430","url":null,"abstract":"The design process and features of new CANDU (Canadian Deuterium Uranium) control centres are discussed. The design process incorporates the systematic consideration of human factors (HF) issues as part of the overall systems engineering activity. This design process has been based on international standards for control center design. CANDU control centers have evolved through three generations of designs with the current advanced designs representing the fourth generation. CANDU plants have always incorporated digital technologies. Video display units (VDUs) have been present in CANDU control centers since the late 1960s. Advanced designs, such as the CANDU 3, make use of a distributed control system feeding data to a plant-wide LAN. The operator interface system is based on a set of nodes on the plant-wide LAN which then feed various VDUs in the control centers. Large-scale wall displays are also used to present operators with a plant overview. Details of the HF aspects of the control center design process and the CANDU 3 control room are discussed.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"45 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115198668","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283369
B. Hallbert
Process systems analysis and the role of human performance in achieving safe operations are discussed. Methods for conducting process systems analysis acceptance criteria are identified. In order to achieve safety in processes, clearly defined criteria must be developed regarding acceptable levels of risk, and process systems analyses must be conducted to determine compliance. An application of this principle to processes involving high consequences from risk at the Department of Energy's (DOE) Rocky Flats Plant (RFP) is offered. It is stated that the prevailing industry approach to consideration of human error places too great an emphasis upon the role of human operators within the stated confines of system objectives. This leads to the underestimation of human error in high risk processes and an over-reliance upon process hardware to meet system safety objectives. It is concluded that in order to be effective, process analyses must address a broad range of human error that acknowledges cognitive, social, management, and organizational factors.<>
{"title":"The evaluation of human reliability in process systems analysis","authors":"B. Hallbert","doi":"10.1109/HFPP.1992.283369","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283369","url":null,"abstract":"Process systems analysis and the role of human performance in achieving safe operations are discussed. Methods for conducting process systems analysis acceptance criteria are identified. In order to achieve safety in processes, clearly defined criteria must be developed regarding acceptable levels of risk, and process systems analyses must be conducted to determine compliance. An application of this principle to processes involving high consequences from risk at the Department of Energy's (DOE) Rocky Flats Plant (RFP) is offered. It is stated that the prevailing industry approach to consideration of human error places too great an emphasis upon the role of human operators within the stated confines of system objectives. This leads to the underestimation of human error in high risk processes and an over-reliance upon process hardware to meet system safety objectives. It is concluded that in order to be effective, process analyses must address a broad range of human error that acknowledges cognitive, social, management, and organizational factors.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"28 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129679788","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283385
W. McGee
One method of measuring the effectiveness of training programs combines selected objective and subjective inputs into a single performance factor. This factor has been used for a variety of programs at a nuclear generating station. This method has been applied to the task of evaluating training program effectiveness. The measurement program is known as the Windows Program. The data in the Windows Program is displayed in a number of ways to allow data analysis and comparison among stations. The easy-to-read, concise, data displays permits clear communication of programmatic strengths and weaknesses. This information is shared with all levels of station management and corporate management.<>
{"title":"The training window: viewing training programs' effectiveness","authors":"W. McGee","doi":"10.1109/HFPP.1992.283385","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283385","url":null,"abstract":"One method of measuring the effectiveness of training programs combines selected objective and subjective inputs into a single performance factor. This factor has been used for a variety of programs at a nuclear generating station. This method has been applied to the task of evaluating training program effectiveness. The measurement program is known as the Windows Program. The data in the Windows Program is displayed in a number of ways to allow data analysis and comparison among stations. The easy-to-read, concise, data displays permits clear communication of programmatic strengths and weaknesses. This information is shared with all levels of station management and corporate management.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"23 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125843505","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283442
R. J. Eckenrode, W.H. Swenson
The authors report on a program to evalute the human factors portions of the GE Advanced Boiling Water Reactor (ABWR), CE System 80+, and Westinghouse AP-600 advanced reactor designs. These reviews are being conducted to ensure that the man-machine interfaces for advanced reactor control facilities are consistent with accepted human factors principles and practices, and that the design features will meet regulatory requirements for design certification. These reviews are conducted using existing guidance and review criteria under development for application to emerging technologies such as the use of electroluminescent displays and on-screen controls. As part of the review and the vendor's design, inspections, tests, and analyses are being developed to ensure that the resulting control facilities are built to adequately support operator performance under all plant conditions.<>
作者报告了一个评估GE先进沸水反应堆(ABWR)、CE System 80+和西屋AP-600先进反应堆设计的人为因素部分的程序。正在进行这些审查，以确保先进反应堆控制设施的人机界面符合公认的人为因素原则和做法，并且设计特征将满足设计认证的监管要求。这些审查是根据现有的指导和正在制定的审查标准进行的，这些标准适用于新兴技术，如使用电致发光显示器和屏幕控制。作为审查和供应商设计的一部分，正在开发检查，测试和分析，以确保最终的控制设施能够在所有工厂条件下充分支持操作员的性能。
{"title":"NRC Office of Nuclear Regulation human factors programs in nuclear power","authors":"R. J. Eckenrode, W.H. Swenson","doi":"10.1109/HFPP.1992.283442","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283442","url":null,"abstract":"The authors report on a program to evalute the human factors portions of the GE Advanced Boiling Water Reactor (ABWR), CE System 80+, and Westinghouse AP-600 advanced reactor designs. These reviews are being conducted to ensure that the man-machine interfaces for advanced reactor control facilities are consistent with accepted human factors principles and practices, and that the design features will meet regulatory requirements for design certification. These reviews are conducted using existing guidance and review criteria under development for application to emerging technologies such as the use of electroluminescent displays and on-screen controls. As part of the review and the vendor's design, inspections, tests, and analyses are being developed to ensure that the resulting control facilities are built to adequately support operator performance under all plant conditions.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"1972 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129979760","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283405
A. Spiker, W. F. Walls, J. L. Campbell
Work in progress to develop job cards for mechanical maintenance personnel in nuclear power plants is described. Job cards are laminated 5 in.*7 in. cards containing a mix of informational graphics and text for important tasks involving mechanical maintenance equipment. They are organized by functional category, including general maintenance, pumps, valves, rigging, troubleshooting, alignment, V-belts and sheaves, documents, and system information. Card content is carefully developed to ensure that there are no conflicts with any controlled plant documents concerning the task. The job cards are in trial-use at two US power plants. The users include mechanics, trainees, job planners, and contractors. The authors summarize the methods used to identify the user and plant requirements for the job cards; the procedures adopted to specify content and packaging of the cards; the preliminary data documenting the job cards' acceptance, usability, and usefulness within the nuclear power plant environment.<>
{"title":"Development of job cards for mechanical maintenance","authors":"A. Spiker, W. F. Walls, J. L. Campbell","doi":"10.1109/HFPP.1992.283405","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283405","url":null,"abstract":"Work in progress to develop job cards for mechanical maintenance personnel in nuclear power plants is described. Job cards are laminated 5 in.*7 in. cards containing a mix of informational graphics and text for important tasks involving mechanical maintenance equipment. They are organized by functional category, including general maintenance, pumps, valves, rigging, troubleshooting, alignment, V-belts and sheaves, documents, and system information. Card content is carefully developed to ensure that there are no conflicts with any controlled plant documents concerning the task. The job cards are in trial-use at two US power plants. The users include mechanics, trainees, job planners, and contractors. The authors summarize the methods used to identify the user and plant requirements for the job cards; the procedures adopted to specify content and packaging of the cards; the preliminary data documenting the job cards' acceptance, usability, and usefulness within the nuclear power plant environment.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132681297","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283348
J. D. Beattie
An overview of the history, current activities, and future directions of human factors in Canada's nuclear power industry is given. A brief profile of the operating nuclear power plants in Canada and their basic characteristics is provided. The history of human factors participation in the nuclear power industry is outlined, and some of the activities and ongoing developments that are most significant are described. Human factors is acquiring increased importance and a wider recognition of its role in the design, licensing, and operation of nuclear plants.<>
{"title":"Human factors in the Canadian nuclear industry-application and research","authors":"J. D. Beattie","doi":"10.1109/HFPP.1992.283348","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283348","url":null,"abstract":"An overview of the history, current activities, and future directions of human factors in Canada's nuclear power industry is given. A brief profile of the operating nuclear power plants in Canada and their basic characteristics is provided. The history of human factors participation in the nuclear power industry is outlined, and some of the activities and ongoing developments that are most significant are described. Human factors is acquiring increased importance and a wider recognition of its role in the design, licensing, and operation of nuclear plants.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"103 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115362195","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283389
R. Fink, A. Zarechnak, R. Williges, J. F. O'brien
The Electric Power Research Institute (EPRI) has carried out a program of research over the last ten years on the improvement of nuclear plant control room alarm systems. Newer technologies have become available including microprocessor-based annunciators that offer new possibilities for upgrading control room alarm systems. The results of a formal test program that evaluated alternate alarm systems with both conventional and computer-driven displays are summarized, and the implications of the results with respect to choices in a system upgrade are discussed. The promises and problems of newer systems are also discussed, and future directions for the alarm research program are described.<>
{"title":"Appropriate choice of alarm system technologies: EPRI research","authors":"R. Fink, A. Zarechnak, R. Williges, J. F. O'brien","doi":"10.1109/HFPP.1992.283389","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283389","url":null,"abstract":"The Electric Power Research Institute (EPRI) has carried out a program of research over the last ten years on the improvement of nuclear plant control room alarm systems. Newer technologies have become available including microprocessor-based annunciators that offer new possibilities for upgrading control room alarm systems. The results of a formal test program that evaluated alternate alarm systems with both conventional and computer-driven displays are summarized, and the implications of the results with respect to choices in a system upgrade are discussed. The promises and problems of newer systems are also discussed, and future directions for the alarm research program are described.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"137 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116900175","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283443
J. Persensky
A human factors research program was established by the Nuclear Regulatory Commission (NRC) to broaden the NRC's understanding of human performance and to identify causes of human error, to accurately measure human performance so as to enhance operation safety and preclude critical errors, and to develop the technical basis for requirements, recommendations, and guidance related to human performance. Some of the research that the Nuclear Regulatory Research (RES) Human Factors Branch (HFB) is pursuing in support of these objectives is summarized.<>
{"title":"USNRC office of Nuclear Regulatory Research Human Factors Branch","authors":"J. Persensky","doi":"10.1109/HFPP.1992.283443","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283443","url":null,"abstract":"A human factors research program was established by the Nuclear Regulatory Commission (NRC) to broaden the NRC's understanding of human performance and to identify causes of human error, to accurately measure human performance so as to enhance operation safety and preclude critical errors, and to develop the technical basis for requirements, recommendations, and guidance related to human performance. Some of the research that the Nuclear Regulatory Research (RES) Human Factors Branch (HFB) is pursuing in support of these objectives is summarized.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"37 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117026389","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1992-06-07DOI: 10.1109/HFPP.1992.283427
D. A. Ward
The following topics are discussed: challenges faced by the Nuclear Regulatory Commission (NRC) during the decade of the 1980s; the activities of the Advisory Committee on Reactor Safeguards (ACRS) of the NRC; the Systematic Assessment of Licensee Performance (SALP) which attempts to gauge how well a utility is operating a plant; the Institute of Nuclear Power Operations (INPO), which developed following the accident at Three-Mile Island; and the question of how nuclear power plants should organize and manage their human and technological resources to maximize their safe and efficient operation.<>
{"title":"Do we need advanced humans?","authors":"D. A. Ward","doi":"10.1109/HFPP.1992.283427","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283427","url":null,"abstract":"The following topics are discussed: challenges faced by the Nuclear Regulatory Commission (NRC) during the decade of the 1980s; the activities of the Advisory Committee on Reactor Safeguards (ACRS) of the NRC; the Systematic Assessment of Licensee Performance (SALP) which attempts to gauge how well a utility is operating a plant; the Institute of Nuclear Power Operations (INPO), which developed following the accident at Three-Mile Island; and the question of how nuclear power plants should organize and manage their human and technological resources to maximize their safe and efficient operation.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"43 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121978532","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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