Human Factors and Power Plants, 1997. Global Perspectives of Human Factors in Power Generation., Proceedings of the 1997 IEEE Sixth Conference on

8-13 June 1997

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  • Global Perpectives of Human Factors in Power Generation. Proceeding of the 1997 IEEE Sixth Conference on Human Factors and Power Plants

    Publication Year: 1997
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  • A frequency-domain stochastic stability criterion for human-controlled nonlinear systems [nuclear power plant control]

    Publication Year: 1997, Page(s):1/1 - 112
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (1495 KB)

    A class of human controlled systems is modelled as randomly-sampled nonlinear control systems. The transfer function of human controlled systems is defined and used to derive a criterion for the stability with probability 1' which can be considered as a stochastic analogue of the well-known circle criterion available for related classical deterministic feedback systems. In order to demonstrate the... View full abstract»

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  • Quality upsizing-a concept whose time is here

    Publication Year: 1997, Page(s):1/14 - 1/15
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (279 KB)

    The quality movement has significant lessons. The issue now is to apply our learning from these lessons to a recovery from downsizing and rightsizing. A concept called quality upsizing is suggested. Upsizing is more than the opposite of downsizing. What business/industry needs is to position itself for the future. In a global economy with deregulation facing many industries, re-engineering and dow... View full abstract»

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  • The development of K-HPES: a Korean-version human performance enhancement system [for nuclear power plant control]

    Publication Year: 1997, Page(s):1/16 - 1/20
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (933 KB)

    K-HPES is a Korean-version HPES (human performance enhancement system) developed on the basis of INPO-HPES in 1993. The development of K-HPES was an effort of KEPRI (Korea Electric Power Research Institute) to reduce human errors and to enhance human performance in nuclear power plants (NPPs), and the program is currently being operated at all NPPs in Korea. KEPRI is now developing a computerized ... View full abstract»

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  • Criteria for review of root-cause analysis programs

    Publication Year: 1997, Page(s):2/1 - 2/6
    Cited by:  Papers (1)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (601 KB)

    This pager describes the US Nuclear Regulatory Commission's (NRC's) criteria for reviewing licensee root-cause analysis programs, as well as corrective action plans, and the methods that NRC inspectors can use to determine the adequacy of the programs. The specific criteria to be used for evaluating the licensee's root-cause analyses, corrective actions and corrective action implementation plans a... View full abstract»

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  • Human factors experience in designing a modern control room for a VVER-1000 nuclear plant

    Publication Year: 1997, Page(s):2/7 - 212
    Cited by:  Papers (1)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (736 KB)

    The original I&C system at the Temelin nuclear plant (Czech Republic) consisted of a number of near-stand-alone systems, each designed to perform a single function (i.e., reactor protection, turbine control, etc.). While such systems were coordinated to the degree necessary to perform their intended functions, the information describing the status or behavior characteristics of the systems was... View full abstract»

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  • Development and validation of the automatic control rods operation system for ABWR

    Publication Year: 1997, Page(s):2/13 - 2/17
    Cited by:  Papers (1)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (510 KB)

    TOSHIBA has introduced the first automatic control rods operation system for the first ABWR (advanced BWR) in the world. The automatic control rods operation system, which is named APR (Automatic Power Regulator), has core critical approach control, pressurization control and power control function and covers the operation from reactor startup to about 70% electrical power. APR calculates the mani... View full abstract»

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  • Current human factors standards development efforts within IEEE

    Publication Year: 1997, Page(s):3/1 - 3/6
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (530 KB)

    Since 1980, the Institute of Electrical and Electronics Engineers (IEEE) has supported the development of human factors standards. Within the IEEE, Subcommittee 7 (SC-7) of the Nuclear Power Engineering Committee (NPEC) develops and maintains human factors standards. Members of SC-7, Human Factors and Control Facilities, have extensive expertise in the human factors of nuclear generating facilitie... View full abstract»

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  • Procedures, quality, standards, and the role of human factors and computerized tools [in power plant control]

    Publication Year: 1997, Page(s):3/7 - 312
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (412 KB)

    This paper deals with the role that human-factors can play with respect to some basic factor related to power plant procedure management. It highlights the existence of a contradiction to principles when, to better understand procedures, a standard for procedure extension is defined and followed: this generates an extra mental activity for the procedure writer, against a basic human factor princip... View full abstract»

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  • The application of advanced visualisation and simulation techniques in control room design and operator training [nuclear power plants]

    Publication Year: 1997, Page(s):3/13 - 3/18
    Cited by:  Papers (1)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (515 KB)

    The importance of human factors in nuclear power plant central control room (CCR) design is well recognised. British Nuclear Fuels (BNFL) has gone beyond the now 'normal' design process incorporating human factors, and has invested in the development and application of virtual reality (VR). The focus of this paper is the design of the Sellafield Mox Plant (SMP) CCR, from the design phase through t... View full abstract»

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  • Panel discussion: detailed control room design reviews: were they worth the effort

    Publication Year: 1997, Page(s):3/19 - 3/21
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (206 KB)

    On March 28, 1979, the accident at Three Mile Island, Unit 2 (TMI-2) which was initiated by mechanical malfunctions was exacerbated by a combination of human errors that occurred while responding to the malfunctions. The TMI-2 control room exhibited many of the design weaknesses of the nuclear power plants at that time, including displays that were difficult to read and that did not distinguish be... View full abstract»

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  • Detailed Control Room Design Reviews-were they worth the effort?

    Publication Year: 1997, Page(s):3/22 - 3/26
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (402 KB)

    In order to consider the issue of the Detailed Control Room Design Review (DCRDR) it is appropriate to pose a series of questions to provide context and a framework to the discussion: What was the nature of experience with DCRDRs? What was the general approach taken to perform the work? What were the findings from the work? What resulted from the findings? Was the DCRDR a useful tool? What were th... View full abstract»

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  • Duke Power Company's detailed control room design review

    Publication Year: 1997, Page(s):3/27 - 3/28
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (171 KB)

    Duke Power Company has been unique among utilities in that, until the early 1990s, it has had its own design engineering and construction departments which designed and built the company's power plants. To conduct its Detailed Control Room Design Review (DCRDR), Duke relied heavily on these resources. To address the Control Room Design issues in NUREG-0737, Duke Power put together a Control Room R... View full abstract»

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  • Been there, done that [Detailed Control Room Design Review]

    Publication Year: 1997, Page(s):3/29 - 3/32
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (396 KB)

    The author describes his work in Detailed Control Room Design Reviews with reference to NUREG 0700 guidelines. The work relates to human factors aspects in Commonwealth Edison Company's nuclear power stations' control rooms. View full abstract»

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  • Were the control room design reviews worth it?

    Publication Year: 1997, Page(s):3/33 - 3/34
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (216 KB)

    The author discusses his work in human factors aspects of nuclear power station control rooms design. He briefly outlines his work for BioTech on the preparation of the NUREG 0700 guidelines and on a contract with Duke Power Company as well as other experiences. View full abstract»

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  • Safety issues for digital upgrades in operating NPPs

    Publication Year: 1997, Page(s):4/1 - 4/6
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (573 KB)

    The objective of this paper is to address safety and licensing issues connected with the replacement of the existing analog protection and control systems in nuclear power plants with the new, digital equipment. While digital systems have characteristics that are potentially beneficial to overall plant operation and maintenance, they also have the potential to jeopardize nuclear safety, if the upg... View full abstract»

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  • Human factors considerations in control room modernization: trends and personnel performance issues

    Publication Year: 1997, Page(s):4/7 - 410
    Cited by:  Papers (1)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (518 KB)

    Advanced human-system interface (HSI) technology is being integrated into existing nuclear plants as part of plant modifications and upgrades. The result of this trend is that hybrid HSIs are created, i.e., HSIs containing a mixture of conventional (analog) and advanced (digital) technology. The purpose of the present research is to define the potential effects of hybrid HSIs on personnel performa... View full abstract»

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  • Implementation of a Safety Parameter Display System in a Windows/sup TM/ environment

    Publication Year: 1997, Page(s):4/11 - 4/15
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (501 KB)

    In early 1997, Millstone Nuclear Power Plant-Unit 2 installed a new Safety Parameter Display System (SPDS) using a new PC Windows/sup TM/, based man-machine-interface. This paper presents a description of why the change was made, the process by which the change occurred, and lists the lessons learned in accomplishing this task. The lessons learned identify some of the important items to be conside... View full abstract»

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  • Human factors aspects of the major upgrade to the control systems at the LANL Plutonium Facility

    Publication Year: 1997, Page(s):4/16 - 4/20
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (605 KB)

    The Plutonium Facility (TA-55) at Los Alamos National Laboratory (LANL) has been in operation for almost 20 years. The Operations Center of TA-55 is the nerve center of the facility where operators are on duty around the clock and monitor several thousand data points using the Facility Control System (FCS). The FCS monitors, displays, alarms, and provides some limited control of several systems, i... View full abstract»

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  • A human factors design process to integrate CANDU 9 control centre features

    Publication Year: 1997, Page(s):5/1 - 5/6
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (788 KB)

    The next generation CANDU control centre is being designed for the 900 MWe CANDU 9 station. The design is based upon the Darlington CANDU station which is among the world leaders in capacity factor with low operation, maintenance and administration (OM&A) costs. This evolutionary design includes the enhanced functionality of existing CANDU control centres, advanced features made possible by ne... View full abstract»

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  • The effects or advanced plant design features and control room staffing on operator and plant performance

    Publication Year: 1997, Page(s):5 - 7
    Cited by:  Papers (3)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (712 KB)

    This report documents the results of an empirical study of operator and plant performance in simulator based settings for nuclear power plants. The simulator settings were made representative of conventional and advanced plants that employ passive system designs. The control room architectures were also made representative of both plant types. Two control room staffing sizes were employed in each ... View full abstract»

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  • Control room modernization from the Swedish regulatory perspective

    Publication Year: 1997, Page(s):6/1 - 6/2
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (194 KB)

    Most Swedish nuclear power plants are modernizing the instrumentation and control systems (I&C systems) including the control room. They have taken a proactive top-down approach starting the programs with analysis and decisions on the requirements and implementation strategy controlling the future single projects of the programs. The Inspectorate has been involved from an early stage and asked... View full abstract»

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  • The computerised procedures for the French N4 series

    Publication Year: 1997, Page(s):6/3 - 6/9
    Cited by:  Papers (1)
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (515 KB)

    After a brief presentation of the main characteristics an efficient operating system should have, a presentation of the N4 PWR nuclear power plant operating system processing, allowing benefits in terms of quality of the operation, reduction in alarm occurrence and operator presentation, is given. The paper emphasises the N4 computerised procedures. The operator presentation and the processing are... View full abstract»

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  • Upgrading of control room in Oskarshamn

    Publication Year: 1997, Page(s):6/10 - 6/13
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (312 KB)

    The second largest utility in Sweden, Sydkraft, initiated a pre-study in 1994 with the aim to develop a control room philosophy as a basis for development and design of upgrading of control rooms for six differ Units. There are five nuclear power reactors and one central interim storage facility for spent nuclear fuel (CLAB) at the site of Oskarshamn Nuclear Power Plant (OKG AB) and Barseback Nucl... View full abstract»

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  • ACOT-guideline for self-assessment of safety culture

    Publication Year: 1997, Page(s):6 - 14
    Request permission for reuse | Click to expandAbstract | PDF file iconPDF (413 KB)

    In 1991 an IAEA safety series document on safety culture was published as 75-INSAG-4. Very soon after its publication, interest was expressed on whether it was possible to make an assessment of safety culture in a particular organisation. In order to properly address safety culture it is necessary to consider the contribution of all organisations which have an impact on it. Therefore, while assess... View full abstract»

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