{"title":"Alarm and status processing and display in the Nuplex 80+ Advanced Control Complex","authors":"D. Harmon, T. M. Starr","doi":"10.1109/HFPP.1992.283388","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283388","url":null,"abstract":"The development of a nuclear power advanced control room includes the improvement of previous generation alarm system designs. The Nuplex 80+ Advanced Control Complex alarm methodology utilizes redundant and diverse fixed-location and CRT alarms. These alarms are grouped by panels and presented on system and function display pages to support operator tasks. Plant operational mode-dependency, prioritization, signal-validation and equipment status dependency are used to improve alarm validity, and to reduce and organize alarms. Human engineered visual and audible cuing support prioritization and reduce distractions for new alarms. Critical function and success path alarms directly support operator procedures for power production and emergencies.<<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":"133386090","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}
{"title":"Getting the attention of senior management for human factors issues: quantitative survey data","authors":"H. Sarkis","doi":"10.1109/HFPP.1992.283358","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283358","url":null,"abstract":"The author describes a survey-based technique that measures and generates comparative human factors data on important organizational, work group, and job-level variables that are directly related to on-the-job accidents. As a result of an analysis of data from over 2700 employees across several industries, several key variables are determined to be significantly related to accidents in the work place. After describing a sample application of the Human Systems Reliability Survey, several proven techniques to successfully integrate human factors programs within organizations are highlighted.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"17 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":"114864643","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}
{"title":"Analyzing cognitive errors using a dynamic crew-simulation model","authors":"V. Dang, Y. Huang, N. Siu, J. Carroll","doi":"10.1109/HFPP.1992.283350","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283350","url":null,"abstract":"The analysis of human errors in a human reliability analysis requires the consideration of the context for human behavior. By simulating the evolution of the human-machine system, the crew model dynamically treats the behavior of the human operators within the context of an evolving plant response. The implemented model treats the evolution of the system of operating crew and plant in steam generator tube rupture scenarios. The treatment of cognitive errors in this implementation and in a model being developed within this simulation framework is discussed. The work in progress extends the model to generalize the response of the crews and emphasizes modeling the manner in which errors arise generally in cognitive processes rather than simulating situation-specific errors.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"27 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":"127387664","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}
{"title":"Beyond the group: enhancing team training effectiveness","authors":"A.T. Bramwell, C. A. Tolbert","doi":"10.1109/HFPP.1992.283366","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283366","url":null,"abstract":"Three organizational factors are considered that can enhance team training effectiveness: culture; leadership; and performance appraisal systems. How the content of team training is affected by changes in team membership is described. Recommendations include greater emphasis on the examination of organizational factors in needs assessments to ensure optimal training. The authors explain that organizational factors should be compatible with the team training in order to enhance its effectiveness.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"17 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":"130149615","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}
R. G. Orendi, D. Petráš, S. Prokopovich, R. R. Oft
{"title":"Outage optimization versus shutdown risk","authors":"R. G. Orendi, D. Petráš, S. Prokopovich, R. R. Oft","doi":"10.1109/HFPP.1992.283421","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283421","url":null,"abstract":"A description and results of Westinghouse evaluation of some of the key issues encountered in optimizing outage activities and in reducing shutdown risks are presented. Specific topics addressed include: the outage optimization process; the assessment and evaluation of the outage schedule; mid-loop considerations; support equipment; and human performance issues. It has been determined that cost effective plant enhancements in the form of plant/equipment modifications, changes to licensing requirements, stricter administrative controls, proper outage planning, upgraded procedures, and enhanced training can be implemented to reduce outage time, operations and maintenance costs, and man-rem exposure.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"1 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":"131246662","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}
{"title":"When technicians use computer programs: approaches to procedure writing","authors":"J. Campbell, C.M. Zimmerman","doi":"10.1109/HFPP.1992.283404","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283404","url":null,"abstract":"Conventional guidelines for maintenance procedures in the nuclear power industry need to be revised or expanded to address those situations that require the technician to interface with a computer program. As software is being used more frequently to accomplish such tasks as testing and data analysis, procedure writers find that current writer's guide to be too restrictive or not applicable to computer interface procedures. Writers must write what is in reality a software user manual using a conventional prose procedure. Methods are recommended so that a paper-based procedure clearly describes how to use a software program to accomplish a procedural task. It is suggested that writer's guides for maintenance procedures permit the use of these methods.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"391 4","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1992-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"113998339","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}
{"title":"Enhancing the training of cognitive skills for improved human reliability: lessons learned from the cognitive environment simulation project","authors":"E. Roth, R. Mumaw, H. E. Pople","doi":"10.1109/HFPP.1992.283355","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283355","url":null,"abstract":"The authors have been involved in a project to model the cognitive activities that underlie operator intention formation during complex nuclear power plant emergencies. The project has involved observation of crew performance in simulated emergencies and development of a computer simulation of operator cognitive performance on the same events. The results of the research point to a number of cognitive skills that are important in handling complex multifault events of the sort that often arise in actual incidents. These cognitive skills are summarized, and an approach to developing training scenarios to enhance these skills and improve human reliability is suggested.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"1 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":"130082482","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}
{"title":"A study of the feasibility of a human factors regulatory research facility-a status report","authors":"S. O. Parsons, J. Wachtel","doi":"10.1109/HFPP.1992.283353","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283353","url":null,"abstract":"The status of a study to investigate the feasibility of a human factors regulatory research facility for the US Nuclear Regulatory Commission (NRC) is described. The primary objectives are to examine the availability and capabilities of existing research facilities to support the current and expected human factors to research needs and to determine supplemental or new facilities which may be required. An initial literature review, list of research needs, facility listing, and subject matter panel (SMEP) meeting have been accomplished.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"13 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":"134153382","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}
{"title":"Issues in procedure development for DOE nuclear facilities","authors":"W. Reece, S. G. Hill, T. G. Ryan","doi":"10.1109/HFPP.1992.283417","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283417","url":null,"abstract":"An important element of maintaining safe and effective operations at US Department of Energy (DOE) facilities is developing good procedures. The DOE Office of Nuclear Energy has initiated a program for providing standard guidance for procedure writing practices across the complex of DOE nuclear facilities. A survey was developed and administered to collect data regarding several issues which emerged from the DOE program. The issues addressed include the definition and terminology of procedures, identification of the guidance users, and how best to gather feedback from a representative sample of the user population.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"11 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":"132232304","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}
{"title":"Progress of I&C system and control room design in TEPCO nuclear power plants","authors":"K. Iwaki","doi":"10.1109/HFPP.1992.283432","DOIUrl":"https://doi.org/10.1109/HFPP.1992.283432","url":null,"abstract":"Three generation of Tokyo Electric Power Co.'s (TEPCO's) standardized control room design, along with the I&C technologies which support the improvements among these control room designs, are discussed. The first-generation-type control room design features large size control room panels, which, after the Three Mile Island Accident, have been modified. The second-generation-type control room panels incorporate CRT-based operation and enhanced automation features. These control room design improvements were made possible through the use of powerful process computers and highly reliable digital controllers. The third-generation-type control room design, developed for application in the advanced boiling water reactor (ABWR) plants, has the goals of enhancing the reliability of the operation during emergencies and optimizing the efficiency and effectiveness of the operating crew. The development of the ABWR control room design has been guided by the operation experience of the second-generation-type control panels and analysis of the operators' workload analsis as well as the progression of state of the art technologies.<<ETX>>","PeriodicalId":150946,"journal":{"name":"Conference Record for 1992 Fifth Conference on Human Factors and Power Plants","volume":"38 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":"115018860","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}