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Sample records for npp control room

  1. Operation Aspect of the Main Control Room of NPP

    International Nuclear Information System (INIS)

    Sahala M Lumbanraja

    2009-01-01

    The main control room of Nuclear Power Plant (NPP) is operational centre to control all of the operation activity of NPP. NPP must be operated carefully and safely. Many aspect that contributed to operation of NPP, such as man power whose operated, technology type used, ergonomic of main control room, operational management, etc. The disturbances of communication in control room must be anticipated so the high availability of NPP can be achieved. The ergonomic of the NPP control room that will be used in Indonesia must be designed suitable to anthropometric of Indonesia society. (author)

  2. A computerized main control room for NPP: Development and investigation

    International Nuclear Information System (INIS)

    Anokhin, A. N.; Marshall, E. C.; Rakitin, I. D.; Slonimsky, V. M.

    2006-01-01

    An ergonomics assessment of the control room at Leningrad Nuclear Power Plant has been undertaken as part of an international project funded by the EU TACIS program. The project was focused on the upgrading of the existing control facilities and the installation of a validation facility to evaluate candidate refurbishment proposals before their implementation at the plant. The ergonomics methodology applied in the investigation was wide ranging and included an analysis of reported events, extensive task analysis (including novel techniques) and validation studies using experienced operators. The paper addresses the potential difficulties for the human operator associated with fully computerized interfaces and shows how the validation facility and the outcomes from ergonomics assessment will be used to minimise any adverse impact on performance that may be caused by proposed control room changes. (authors)

  3. Human error mode identification for NPP main control room operations using soft controls

    International Nuclear Information System (INIS)

    Lee, Seung Jun; Kim, Jaewhan; Jang, Seung-Cheol

    2011-01-01

    The operation environment of main control rooms (MCRs) in modern nuclear power plants (NPPs) has considerably changed over the years. Advanced MCRs, which have been designed by adapting digital and computer technologies, have simpler interfaces using large display panels, computerized displays, soft controls, computerized procedure systems, and so on. The actions for the NPP operations are performed using soft controls in advanced MCRs. Soft controls have different features from conventional controls. Operators need to navigate the screens to find indicators and controls and manipulate controls using a mouse, touch screens, and so on. Due to these different interfaces, different human errors should be considered in the human reliability analysis (HRA) for advanced MCRs. In this work, human errors that could occur during operation executions using soft controls were analyzed. This work classified the human errors in soft controls into six types, and the reasons that affect the occurrence of the human errors were also analyzed. (author)

  4. Experience in development and implementation of Control Room continuing training programme at Ignalina NPP

    International Nuclear Information System (INIS)

    Peradze, K.

    2002-01-01

    Based on the same SAT principles each NPP (or operating organisation) goes by its own way, which is defined by available resources, assistance, NPP operational conditions, including policy, economics and public opinion. There were several groups of factors, which are very important to provide quality of training- Time, Human Resources and material resources. We pay especial attention to simulator training. In different conditions personnel behaviour is defined by knowledge, rule or skills. It is very difficult to develop unknown to personnel scenarios. But sometimes- real events not described in plant procedures take place at Nuclear Power Plants. Therefore during NPP events analysis we pay a especial attention searching for situation when knowledge or rule defines personnel behaviour. To provide analysis and statistics of Control Room Personnel training at INPP simulator we developed 'INPP events computer data base'. (author)

  5. Evaluation for the habitability of the main control room and the performance of the smoke control system at NPP

    International Nuclear Information System (INIS)

    Ji, M. H.; Hong, S. R.; Sung, C. K.

    2002-01-01

    In addition to the indoor air conditioning, the habitability of the main control room for the operators at Nuclear Power Plants (NPP) has to be ensured with a strict design requirements to protect the workers from the radiation exposure, hazardous chemicals, and the smoke with toxic combustion products. With this context, the internal pressure of the control room envelope shall be sustained at slightly higher pressure than the atmospheric pressure. At this paper, the internal pressure of the control room envelope was analyzed by use of the evaluation program, CONTANW that was developed by the NIST. On the basis of design values, the performance status of the smoke control system was also checked by the program, CFAST that was released by the NIST to confirm the dynamic smoke behaviors

  6. Application of ARCON96 in NPP control room habitability assessment and its comparison with composite wake model

    International Nuclear Information System (INIS)

    Fang Sheng; Li Hong; Fang Dong

    2012-01-01

    ARCON96 is the current NRC-recommended atmospheric dispersion model that may be used to estimate atmospheric relative concentration in assessing the habitability of a NPP control room during design basis radiological events. Based on meteorological data from a NPP site in China, the atmospheric relative concentration was calculated and analyzed using ARCON96, and then compared with calculations by the composite wake model. Results demonstrated that ARCON96 is feasible for atmospheric relative concentration estimation and its estimate is more conservative than the composite wake model. (authors)

  7. Evaluation of control room habitability in case of LOCA for Maanshan NPP using codes RADTRAD, HABIT and ALOHA

    International Nuclear Information System (INIS)

    Hsu, Wen-Sheng; Wang, Jong-Rong; Chen, Hsiung-Chih; Chiang, Yu; Chen, Shao-Wen; Shih, Chunkuan

    2018-01-01

    The method for the evaluation of the control room habitability is presented in this paper with focus on Maanshan PWR nuclear power plant (NPP) using the codes RADTRAD, HABIT, and ALOHA. Therefore, this paper is divided into two parts: The first part is the evaluation of the cumulative dose at the control room, the exclusion area boundary (EAB) and the low population zone (LPZ) in case of an design basis loss of coolant accident (DBA/LOCA). For this first part, the Maanshan NPP models of the code RADTRAD/SNAP were used for the analysis. The second part is the evaluation of the control room habitability under the assumption of CO 2 storage burst. For this part, the HABIT and ALOHA codes were used. As result it was seen that the RADTRAD calculation results are below the failure criteria of standard review plan (SRP) and 10 CFR 100.11. The HABIT and ALOHA results are below the R.G. 1.78 failure criteria. These results indicate that Maanshan NPP' habitability can be maintained under the above conditions.

  8. Function analysis and function assignment of NPP advanced main control room

    International Nuclear Information System (INIS)

    Zheng Mingguang; Xu Jijun

    2001-01-01

    The author addresses the requirements of function analysis and function assignment, which should be carried out in the design of main control room in nuclear power plant according to the design research of advanced main control room, then states its contents, functions, importance and necessity as well as how to implement these requirements and how to do design verification and validation in the design of advanced main control room of nuclear power plant

  9. Assessment of control room habitability and unfiltered air inleakage test of the OPR 1000 NPP

    International Nuclear Information System (INIS)

    Song, Dong Soo; Lee, Jong Beom; Ha, Sang Jun; Huh, Seong Cheol

    2015-01-01

    The assessment of control room habitability for Hanbit unit 5 was performed based on GL 2003-01 and Regulatory Guide 1.197. The integrated control room envelope (CRE) test was performed utilizing ASTM E741. Four tests were performed using each of the control room HVAC subtrains. The control room heating, ventilating, and air conditioning (HVAC) system lineup of pressurization mode test was based upon a lineup that encompassed the design basis radiological analyses. The other control room HVAC system lineup of isolation mode test was based on an operation mode that considers toxic gas. The measured inleakage for the isolation test mode remains within the toxicity limit. Radiation effect analysis showed that the measured inleakage satisfied the regulatory criteria, and the inleakage would not result in control room operator dose exceeding 50 mSv whole body and 500 mSv thyroid except train A pressurization test mode. The thyroid dose due to maximum measured unfiltered inleakage of 8976 lpm for train A is corresponding to 700 mSv. Modifications to the CRE boundary and control room HVAC system should be done to demonstrate that the measured unfiltered inleakage for train A pressurization test mode is bounded by the regulatory criteria assumed in the design basis radiological analyses. (author)

  10. Use of the Human Centered Design concept when designing ergonomic NPP control rooms

    International Nuclear Information System (INIS)

    Skrehot, Petr A.; Houser, Frantisek; Riha, Radek; Tuma, Zdenek

    2015-01-01

    Human-Centered Design is a concept aimed at reconciling human needs on the one hand and limitations posed by the design disposition of the room being designed on the other hand. This paper describes the main aspects of application of the Human-Centered Design concept to the design of nuclear power plant control rooms. (orig.)

  11. An empirical study on the basic human error probabilities for NPP advanced main control room operation using soft control

    International Nuclear Information System (INIS)

    Jang, Inseok; Kim, Ar Ryum; Harbi, Mohamed Ali Salem Al; Lee, Seung Jun; Kang, Hyun Gook; Seong, Poong Hyun

    2013-01-01

    Highlights: ► The operation environment of MCRs in NPPs has changed by adopting new HSIs. ► The operation action in NPP Advanced MCRs is performed by soft control. ► Different basic human error probabilities (BHEPs) should be considered. ► BHEPs in a soft control operation environment are investigated empirically. ► This work will be helpful to verify if soft control has positive or negative effects. -- Abstract: By adopting new human–system interfaces that are based on computer-based technologies, the operation environment of main control rooms (MCRs) in nuclear power plants (NPPs) has changed. The MCRs that include these digital and computer technologies, such as large display panels, computerized procedures, soft controls, and so on, are called Advanced MCRs. Among the many features in Advanced MCRs, soft controls are an important feature because the operation action in NPP Advanced MCRs is performed by soft control. Using soft controls such as mouse control, touch screens, and so on, operators can select a specific screen, then choose the controller, and finally manipulate the devices. However, because of the different interfaces between soft control and hardwired conventional type control, different basic human error probabilities (BHEPs) should be considered in the Human Reliability Analysis (HRA) for advanced MCRs. Although there are many HRA methods to assess human reliabilities, such as Technique for Human Error Rate Prediction (THERP), Accident Sequence Evaluation Program (ASEP), Human Error Assessment and Reduction Technique (HEART), Human Event Repository and Analysis (HERA), Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR), Cognitive Reliability and Error Analysis Method (CREAM), and so on, these methods have been applied to conventional MCRs, and they do not consider the new features of advance MCRs such as soft controls. As a result, there is an insufficient database for assessing human reliabilities in advanced

  12. Study on the task categorization of main control room in NPP

    International Nuclear Information System (INIS)

    Fang Zhou; Ma Zhicai; Ma Xusheng; Zheng Mingguang

    2005-01-01

    The paper states the importance and trendy requirements of Main Control Room (MCR) in nuclear power plant and introduces how to implement the human factor engineering principle in the design of advanced main control room. It mainly focuses on the purpose and functions, strategy and methodology, scope and contents of the MCR task categorization. The preliminary MCR task categorization is performed according to these principles. (authors)

  13. Control room habitability assessment and in-leakage test for Korean NPP - 15510

    International Nuclear Information System (INIS)

    Song, D.S.; Lee, J.B.; Ha, S.J.; Seong, J.J.

    2015-01-01

    The assessment of control room habitability for Wolsung unit 1 was performed based on GL 2003-01 and Reg. Guide 1.197. The control room habitability program including Control Room Envelope (CRE) in-leakage test procedures, self assessment guidance, CRE boundary control program, CRE maintenance/sealing program was developed for Wolsung unit 1. The integrated CRE test was performed utilizing ASTM E741. There are two operating modes of pressurization and isolation for CRE ventilation test, and four tests were performed using each of the control room HVAC sub-trains. The control room HVAC system lineup of pressurization mode test was based upon a lineup that encompassed the design basis radiological analyses. The other control room HVAC system lineup of isolation mode test was based on an operation mode that considers toxic gas. The in-leakage testing was performed in accordance with CRE in-leakage test procedures. In the pressurization mode, measured unfiltered in-leakage rates for train A and train B were 0 CFM and 405 CFM respectively. In the isolation mode, measured unfiltered in-leakage rates for train A and train B were 1,739 CFM and 1,502 CFM, respectively. Maximum concentration of ammonia at the control room HVAC intake is calculated to be 0.027 g/m 3 (39 ppm), and satisfied the toxicity limit of 300 ppm. The test result shows that the measured unfiltered in-leakage is bounded by the regulatory criteria assumed in the design basis radiological analyses. (authors)

  14. Programmes design for Bohunice NPP personnel other than control room operators

    International Nuclear Information System (INIS)

    Kalincik, L.

    2002-01-01

    This paper deals with project development of training programmes for non-licenced NPP personnel-masters, field operators, maintenance and technical supporting personnel. The programme development focuses on the part stage and on the job training at NPP. Bohunice NPP belongs to plants with higher specific number of personnel per installed power capacity. This factor also influenced the choice of programmes design. Undermentioned procedure is one of various approaches to SAT exploitation for training programmes design. (author)

  15. Human factors inspection of current control room panel in Jose Cabrera NPP

    International Nuclear Information System (INIS)

    Almeida, P.; O'Hara, J.; Higgins, J.

    2002-01-01

    Within the process of renewal of Exploitation Permit of Jose Cabrera Nuclear Power Plant, UNION FENOSA GENERACIO, S. A. (UFG) has carried out an analysis and evaluation project regarding human factors implications of current control room panel arrangement. The project has been developed in two phases. In the first phase, leaded by EPRI and carried out by experts from SAIC, an independent review from a double viewpoint of human reliability and human factors was developed. In the second phase, a multidisciplinary team (composed by human factors, risk analysis, operation, engineering, training and instrumentation and controls experts) has developed a study on human factors implications of current panel arrangement, following the methodology pointed out in NUREG-0711. The project has been developed under the direction of Brookhaven National Laboratory (BNL), organisation that has authored the aforementioned methodology, with the participation of UFG and SOLUZIONA Ingenieria. For the development of the second study the following steps were taken: Firstly, the potential effects of panel arrangement on crew performance were identified its real evidence was analysed and the goals for the improvement of control room operation were established; following NUREG-0711. After this, several design alternatives that addressed these goals were identified and were analysed along three dimensions: human factors, risk analysis and economic costs. Finally the results of these evaluations were combined using a multi-attribute decision method to arrive at a recommended alternative as he best proposal to incorporate human factors criteria and good practices in the design of control room panels. (Author)

  16. Concepts of analytical user interface evaluation method for continuous work in NPP main control room

    International Nuclear Information System (INIS)

    Lee, S. J.; Heo, G. Y.; Jang, S. H.

    2003-01-01

    This paper describes a conceptual study of analytical evaluation method for computer-based user interface in the main control room of advanced nuclear power plant. User interfaces can classify them into two groups as static interface and dynamic interface. Existing evaluation and design methods of user interface have been mainly performed for the static user interface. But, it is useful for the dynamic user interface to control the complex system, and proper evaluation method for this is seldom. Therefore an evaluation method for dynamic user interface is proper for continuous works by standards of the load of cognition and the similarity of an interface

  17. Fire environment determination in the LaSalle NPP control room

    Energy Technology Data Exchange (ETDEWEB)

    Usher, J.L.; Boccio, J.L.; Singhal, A.K.; Tam, L.T.

    1986-01-01

    One objective of NRC's Fire Protection Research Program (FPRP) is to improve the modeling of environments caused by fires in typical nuclear power plant enclosures. A three-dimensional fluid dynamics computer code (PHOENICS) has been adapted as a field-model fire code (SAFFIRE) for this purpose. The model has been applied to simulate two distinct fires in the control room of the LaSalle County power plant. The environments determined illustrate hazardous potential for both personnel and equipment.

  18. Development of contextual task analysis for NPP control room operators' work

    International Nuclear Information System (INIS)

    Hukki, K.

    1998-01-01

    The paper introduces a contextual approach to task analysis concerning control room operators' tasks and task conditions in nuclear power plants. The approach is based on the ecological concept of the situational appropriateness of activity. The task demands are dependent on the ultimate task of the operators which is to maintain the critical safety functions of the process. The context also sets boundary conditions to the fulfilment of these demands. The conceptualisation of the context affords possibilities to comprehend and make visible the core demands of the operators' work. Characteristic to the approach is that the conceptualisation is made both from the point of the operators who are making interpretations of the situation and from the point of the process to be controlled. The context is described as a world of operators' possibilities and constraints and, at the same time, in relation to the demands set by the nature of the process. The method is under development and has been applied in simulator training, in the evaluation of the control room information and in the integrated development of reliability analysis. The method emphasizes the role of explicit conceptualisation of the task situations. Explicity enhances its role as a conceptual tool and, therefore, promotes common awareness in these domains. (orig.)

  19. New generation main control room of enhanced safety NPP with MKER reactor

    International Nuclear Information System (INIS)

    Golovanev, V.E.; Gorelov, A.I.; Proshin, V.A.

    1994-01-01

    Russia is planning to begin the gradual substitution RMBK NPP units, whose resources were worked out itself, to NPP units with a 800 MW multiloop boiling water power reactor (MKER-800) enhanced safety at next ten-year period. Main drawbacks of RBMK Reactor were completely removed in design of MKER-800 reactor. Moreover some special decisions were made to give MKER-800 self-safety properties. The proposed design of the MKER-800 enhanced safety reactor is not only fully free from the drawbacks of the RBMK reactors, but also show a number of advantages of channel-type reactors. This Paper presents some preliminary proposals of MCR Design, that developed Research and Development Institute of Power Energy (RDIPE). 6 refs, 2 figs

  20. Generation IV nuclear energy systems: road map and concepts. 3. Measurement and Analysis of Conducted Noise at Main Control Room in Uljin NPP

    International Nuclear Information System (INIS)

    Goo, Cheol-Soo; Kim, Bok-Ryul; Cho, Won-Seo

    2001-01-01

    The utility has implemented digital technology into the design of the plant protection system in new nuclear power plants (NPPs) and also replaced existing analog instrumentation and control (I and C) systems with computer-based digital I and C systems as the analog systems become obsolete. Digital I and C systems, which provide more operating capabilities than analog systems, operate at conditions that are more vulnerable to EMI/RFI than existing analog systems. The purpose of the site survey is to get the actual electromagnetic measurement (EM) level in NPPs and to eliminate the need for plant-specific EM at the point of installation to demonstrate the sufficiency of equipment test levels. Actual electromagnetic environments in NPPs are major elements to decide the limit for the susceptibility of the installed equipment. The data obtained with standard methods are indispensable to make guidelines for an electromagnetic qualification test for the equipment to be installed in the NPP. We performed EM at the power ports of the Plant Control System (PCS) and the Core Protection Calculator (CPC) in Uljin to obtain the conducted noise level, which can be utilized to determine the electromagnetic environment test limit for the equipment qualification test. The continuous conducted noise and discontinuous transient or surge at the power ports of the PCS and the CPC installed at the no.3 main control room in the Uljin NPP were measured and analyzed. The measurements were continuously conducted for 2 weeks of the power-escalated phase with reactor power from 0% to full power. The measurements selected for the power leaders were the current and voltage of the power cables using a current and voltage (passive) probe, EMI test receiver, and notebook computer. The data were recorded in accordance with standard industry practices and procedures. The conducted noise current was measured over the frequency range of 30 Hz to 50 kHz, and the voltage was captured over the frequency

  1. Control rooms

    International Nuclear Information System (INIS)

    Preuss, W.

    1990-01-01

    The current state of knowledge about screen systems for application in traffic (e.g., flight control), process control, and production is presented. The 29 lectures, 5 of which relate to aviation, deal with the optimization of the man-machine interface with respect to unusual operating situations and adequate presentation and action methods on the basis of taks and event analyses integrating the users. (DG) [de

  2. HAMMLAB 1999 experimental control room: design - design rationale - experiences

    International Nuclear Information System (INIS)

    Foerdestroemmen, N. T.; Meyer, B. D.; Saarni, R.

    1999-01-01

    A presentation of HAMMLAB 1999 experimental control room, and the accumulated experiences gathered in the areas of design and design rationale as well as user experiences. It is concluded that HAMMLAB 1999 experimental control room is a realistic, compact and efficient control room well suited as an Advanced NPP Control Room (ml)

  3. Display systems for NPP control

    International Nuclear Information System (INIS)

    Rozov, S.S.

    1988-01-01

    Main trends in development of display systems used as the means for image displaying in NPP control systems are considered. It is shown that colour display devices appear to be the most universal means for concentrated data presentation. Along with digital means the display systems provide for high-speed response, sufficient for operative control of executive mechanisms. A conclusion is drawn that further development of display systems will move towards creation of large colour fields (on reflection base or with multicolour gas-discharge elements)

  4. Applying human factors engineering program to the modernization project of NPP Control Room in accordance with U.S.NRC and KTA regulations

    International Nuclear Information System (INIS)

    Avellar, Renato Koga de; Schirru, Roberto

    2017-01-01

    Application of Human Factors Engineering (HFE) in the design and implementation of such a project is essential to ensure that the new man-machine interface outcoming from the modernization does not have any negative impacts on human performance and plant safety. This paper analyzes the applicability of the Human Factors Engineering Program in the licensing and certification of Konvoi Nucleoelectric Power Plant Control Room Modernization Project using digital instrumentation and control in accordance with U.S.NRC and KTA regulations. The results of the analyses show that although regulatory bodies adopt different methodology in the process of licensing the modernization of control rooms, the engineering aspects are being developed based on the principles of engineering. (author)

  5. Applying human factors engineering program to the modernization project of NPP Control Room in accordance with U.S.NRC and KTA regulations

    Energy Technology Data Exchange (ETDEWEB)

    Avellar, Renato Koga de, E-mail: rkoga@eletronuclear.gov.br [Eletrobrás Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil). Assessoria de Licenciamento Nuclear e Ambiental; Schirru, Roberto, E-mail: schirru@lmp.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2017-07-01

    Application of Human Factors Engineering (HFE) in the design and implementation of such a project is essential to ensure that the new man-machine interface outcoming from the modernization does not have any negative impacts on human performance and plant safety. This paper analyzes the applicability of the Human Factors Engineering Program in the licensing and certification of Konvoi Nucleoelectric Power Plant Control Room Modernization Project using digital instrumentation and control in accordance with U.S.NRC and KTA regulations. The results of the analyses show that although regulatory bodies adopt different methodology in the process of licensing the modernization of control rooms, the engineering aspects are being developed based on the principles of engineering. (author)

  6. Cuba: Juragua NPP. Project Control. Annex 5

    International Nuclear Information System (INIS)

    Serradet, M.A.

    1999-01-01

    This annex deals with project control. The long suspension of Juragua NPP has affected personnel, equipment and site structures. Efforts are being made to revive the plant and to protect existing resources (assets). An action plan has been prepared. (author)

  7. Automatic control system at the ''Loviisa'' NPP

    International Nuclear Information System (INIS)

    Kukhtevich, I.V.; Mal'tsev, B.K.; Sergievskaya, E.N.

    1980-01-01

    Automatic control system of the Loviisa-1 NPP (Finland) is described. According to operation conditions of Finland power system the Loviisa-1 NPP must operate in the mode of week and day control of loading schedule and participate in current control of power system frequency and capacity. With provision for these requirements NPP is equipped with the all-regime system for automatic control functioning during reactor start-up, shut-down, in normal and transient regimes and in emergency situations. The automatic control system includes: a data subsystem, an automatic control subsystem, a discrete control subsystem including remote, a subsystem for reactor control and protection and overall station system of protections: control and dosimetry inside the reactor. Structures of a data-computer complex, discrete control subsystems, reactor control and protection systems, neutron flux control system, inside-reactor control system, station protection system and system for control of fuel element tightness are presented in short. Two-year experience of the NPP operation confirmed advisability of the chosen volume of automatization. The Loviisa-1 NPP operates successfully in the mode of the week and day control of supervisor schedule and current control of frequency (short-term control)

  8. New Emergency control center of Slovenske Elektrarne Bohunice NPP

    International Nuclear Information System (INIS)

    Pecko, E.

    2012-01-01

    Emergency preparedness of nuclear power plant and operation assurance in case of a possible emergency calls to have devices for emergency response with equipment for rapid detection and continuous evaluation of anticipated events. Chief executive body designated to manage a nuclear power plant during major events is the emergency committee (EC). Emergency Committee is a part of the Emergency Response Organization (ERO). The following centers are on alert to ensure the activities of the ERO - Emergency Response office: - control room (CR) and emergency control room (ECR); - emergency management center (EMC); - Monitoring Centre (MC); - emergency backup control center (EBCC); - congregations of civil protection (CP) and CP shelters; - communications with warning and notification system (VARVYR). From a historical and practical point of view in the vicinity of Jaslovske Bohunice has been set up a joint emergency control center. The center was located on the territory of the former already inoperative V1 NPP. V1 NPP is currently integrated into the organizational structure of JAVYS. Operating Bohunice V2 NPP plant is a designated part of the Slovenske Elektrarne, a. s., whose majority owner is an Italian operator ENEL. In terms of various relevant factors, it was decided to build a new emergency management center on the territory of operating V2 NPP, meet the current standards.

  9. Perception of tomorrow's nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Meyer, O.R.

    1986-01-01

    Major development programs are upgrading today's light water reactor nuclear power plant (NPP) control rooms. These programs involve displays, control panel architecture, procedures, staffing, and training, and are supported by analytical efforts to refine the definitions of the dynamics and the functional requirements of NPP operation. These programs demonstrate that the NPP control room is the visible command/control/communications center of the complex man/machine system that operates the plant. These development programs are primarily plant specific, although the owners' groups and the Institute of Nuclear Power Operations (INPO) do provide some standardization. The Idaho National Engineering Laboratory recently completed a project to categorize control room changes and estimate the degree of change. That project, plus related studies, provides the basis for this image of the next generation of NPP control rooms. The next generation of NPP control rooms is envisioned as being dominated by three current trends: (1) application of state-of-the-art computer hardware and software; (2) use of NPP dynamic analyses to provide the basis for the control room man/machine system design; and (3) application of empirical principles of human performance

  10. New trends in designing NPP control boards

    International Nuclear Information System (INIS)

    Kondrat'ev, V.V.

    1981-01-01

    A short analytical summary of the latest developments and future trends in designing NPP control boards is given. The designs of the Westinghause and the Hynkley-Point NPP control boards are described in detail. The essence of the advanced control board concept consists , firstly, in expanded use of computer-controlled displays for the sake of reducing the content of unimportant information presented to an operator, and, secondary, in better account of human possibilities to convert the NPP operation information into a more suitable form. An enlarged use of the direct digital reactor control utilizing microprocessors is expected. Besides, the employment of full-scale control board mock-ups and information desks as well as testing newly-developed control boards at computer reactor simulators are concluded to be used at all-growing rate [ru

  11. Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

    International Nuclear Information System (INIS)

    Egorov, Yu.A.

    1987-01-01

    Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

  12. A methodology of selection of exercises for operator training on a control room simulator and its application to the data bank of exercises at the Dukovany NPP

    International Nuclear Information System (INIS)

    Holy, J.

    2005-07-01

    The report describes the preparation of methodology for the selection of scenarios to be used during operator training on a full-scope simulator. The scenarios are selected from a data bank of scenarios, which is under preparation based on feedback from the operational history and theoretical analyses. The new methodology takes into account 3 basic attributes defining the priority for use within the training programme: frequency of occurrence, safety-related significance, and difficulty. The attributes are scored and based on a joint score, the importance of inclusion of the scenario in the training programme is also scored. The methodology was applied to the data bank of scenarios for simulation of abnormal states and incidents trained on the up-to-date simulator of the Dukovany NPP, and the results of this pilot application were made available to Dukovany operator training staff as a tool for the preparation of training plans for the years to come. The results of a PSA study are used for a non-trivial selection of the scenarios

  13. Development and quantitative effect estimation of an integrated decision support system to aid operator's cognitive activities for NPP advanced main control rooms

    International Nuclear Information System (INIS)

    Lee, Seung Jun

    2007-02-01

    As digital and computer technologies have grown, human-machine interfaces (HMIs) have evolved. In safety critical systems, especially in nuclear power plants (NPPs), HMIs are important for reducing operational costs, for reducing the number of necessary operators, and for reducing the probability of accident occurrence. Efforts have been made to improve main control room (MCR) interface design and to develop automation or support systems to ensure convenient operation and maintenance. In this paper, an integrated decision support system to aid the cognitive activities of operators is proposed for advanced MCRs in future NPPs. The proposed system supports not merely a particular task, but also the entire operation process based on a human cognitive process model. It supports the operator's entire cognitive process by integrating decision support systems that support each cognitive activity. In this paper, the operator's operation processes are analyzed based on a human cognitive process model and appropriate support systems that support each activity of the human cognitive process are suggested. Two decision support systems were developed in this paper. The first one is the fault diagnosis advisory system (FDAS) which detects faults and diagnoses them. The FDAS provides a list of possible faults and expected causes to operators. It was implemented using two kinds of neural networks for more reliable diagnosis results. The second system is the multifunctional operator support system for operation guidance, which includes the FDAS and the operation guidance system. The operation guidance system is to prevent operator's commission errors and omission errors. Furthermore, the effect of the proposed system was estimated because to evaluate decision support systems in order to validate their efficiency is as important as to design highly reliable decision support systems. The effect estimations were performed theoretically and experimentally. The Bayesian

  14. Slovakia: Mochovce NPP. Project control. Annex 10

    International Nuclear Information System (INIS)

    Bodorik, K.

    1999-01-01

    This annex deals with project control. Mochovce NPP suffered considerable delay primarily due to lack of money. This situation was corrected and construction resumed in 1996. Throughout the 'dormant' period the plant received considerable support from the major contractors, who maintained skeleton staff at site. Significant safety and managerial improvements are being introduced and a strategic plan for the plant has been developed. (author)

  15. Control room design

    International Nuclear Information System (INIS)

    Zinke, H.

    1980-01-01

    To control a 1300 megawatt nuclear power plant, about 15000 plant parameters must be collected together to control and operate the plant. The control room design therefore is of particular importance. The main design criteria are: Required functions of the power plant process - Level of Automation - Ergonomics - Available Technology. Extensive analysis has resulted in a control room design method. This ensures that an objective solution will be reached. Resulting from this methodical approach are: 1. Scope, position and appearance of the instrumentation. 2. Scope, position and appearance of the operator controls. Process analysis dictates what instrumentation and operator controls are needed. The priority and importance of the control and instrumentation (this we define as the utilisation areas), dictates the rough layout of the control room. (orig./RW)

  16. Guidelines for control room systems design. Working material. Report

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains comprehensive technical and methodological information and recommendations for the benefit of Member States for advice and assistance in ''NPP control room systems'' design backfitting existing nuclear power plants and design for future stations. The term ''Control Room Systems'' refers to the entire human/machine interface for the nuclear stations - including the main control room, back-ups control room and the emergency control rooms, local panels, technical support centres, operating staff, operating procedures, operating training programs, communications, etc. Refs, figs and tabs

  17. PS Control Room

    CERN Multimedia

    CERN PhotoLab

    1963-01-01

    The good old PS Control Room, all manual. For each parameter, a knob or a button to control it; for each, a light or meter or oscilloscope to monitor it; carefully written pages serve as the data bank; phones and intercom for communication. D.Dekkers is at the microphone, M.Valvini sits in front.

  18. Crack resistance increasing in epoxide-rubber coatings of NPP room floors

    International Nuclear Information System (INIS)

    Khorenzhenko, V.I.

    1986-01-01

    Problems of crack resistance increasing in epoxide-rubber coatings for the floors are considered. Exploitation experience of the floors in the special rooms of NPP is given. Perspectivity of application of the compositions described as the building materials for nuclear power stations is pointed out

  19. CFD analysis of the temperature field in emergency pump room in Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Rämä, Tommi, E-mail: tommi.rama@fortum.com [Fortum Power and Heat, P.O.B. 100, FI-00048 Fortum (Finland); Toppila, Timo, E-mail: timo.toppila@fortum.com [Fortum Power and Heat, P.O.B. 100, FI-00048 Fortum (Finland); Kelavirta, Teemu, E-mail: teemu.kelavirta@fortum.com [Fortum Power and Heat, Loviisa Power Plant, P.O.B. 23, FI-07901 Loviisa (Finland); Martin, Pasi, E-mail: pasi.martin@fortum.com [Fortum Power and Heat, Loviisa Power Plant, P.O.B. 23, FI-07901 Loviisa (Finland)

    2014-11-15

    Highlights: • Laser scanned room geometry from Loviisa NPP was utilized for CFD simulation. • Uncertainty of CFD simulation was estimated using the Grid Convergence Index. • Measured temperature field of pump room was reproduced with CFD simulation. - Abstract: In the Loviisa Nuclear Power Plant (NPP) six emergency pumps belonging to the same redundancy are located in the same room. During a postulated accident the cooling of the room is needed as the engines of the emergency pumps generate heat. Cooling is performed with fans blowing air to the upper part of the room. Temperature limits have been given to the operating conditions of the main components in order to ensure their reliable operation. Therefore the temperature field of the room is important to know. Temperature measurements were made close to the most important components of the pump room to get a better understanding of the temperature field. For these measurements emergency pumps and cooling fan units were activated. To simulate conditions during a postulated accident additional warm-air heaters were used. Computational fluid dynamic (CFD) simulations were made to support plant measurements. For the CFD study one of the pump rooms of Loviisa NPP was scanned with a laser and this data converted to detailed 3-D geometry. Tetrahedral computation grid was created inside the geometry. Grid sensitivity studies were made, and the model was then validated against the power plant tests. With CFD the detailed temperature and flow fields of the whole room were produced. The used CFD model was able to reproduce the temperature field of the measurements. Two postulated accident cases were simulated. In the cases the operating cooling units were varied. The temperature profile of the room changes significantly depending on which units are cooling and which only circulating the air. The room average temperature stays approximately the same. The simulation results were used to ensure the acceptable operating

  20. Local control room

    CERN Multimedia

    CERN PhotoLab

    1972-01-01

    Local control room in the ejection building : all electronics pertaining to proton distribution and concomitants such as beam gymnastics and diagnostics at high energies will eventually be gathered here. Shown is the first of two rows of fast ejection electronic racks. It includes only what is necessary for operation.

  1. Qualified operator training in the simulated control room environment

    International Nuclear Information System (INIS)

    Ionescu, Teodor; Studineanu, Emil; Radulescu, Catalina; Bolocan, Gabriel

    2005-01-01

    Full text: Mainly designed for the training of the Cernavoda NPP Unit 2 operators, the virtual simulated environment allows the training of the already qualified operators for Cernavoda NPP Unit 1, adding to the already trained knowledge, the differences which has occurred in the Unit 2 design. Using state-of-the-art computers and displays and qualified software, the virtual simulated panels could offer a viable alternative to classic hardware-based training. This approach allows quick training of the new procedures required by the new configuration of the re-designed operator panels in the main control room of Cernavoda NPP Unit 2. (authors)

  2. Qualified operator training in the simulated control room environment

    International Nuclear Information System (INIS)

    Ionescu, Teodor; Studineanu, Emil; Radulescu, Catalina; Bolocan, Gabriel

    2005-01-01

    Mainly designed for the training of the Cernavoda NPP Unit 2 operators, the virtual simulated environment allows the training of the already qualified operators for Cernavoda NPP Unit 1, adding to the already trained knowledge, the differences which have occurred in the Unit 2 design. Using state-of-the-art computers and displays and qualified software, the virtual simulated panels could offer a viable alternative to classic hardware-based training. This approach allows quick training of the new procedures required by the new configuration of the re-designed operator panels in the main control room of Cernavoda NPP Unit 2. (authors)

  3. Review of Methods Related to Assessing Human Performance in Nuclear Power Plant Control Room Simulations

    Energy Technology Data Exchange (ETDEWEB)

    Katya L Le Blanc; Ronald L Boring; David I Gertman

    2001-11-01

    With the increased use of digital systems in Nuclear Power Plant (NPP) control rooms comes a need to thoroughly understand the human performance issues associated with digital systems. A common way to evaluate human performance is to test operators and crews in NPP control room simulators. However, it is often challenging to characterize human performance in meaningful ways when measuring performance in NPP control room simulations. A review of the literature in NPP simulator studies reveals a variety of ways to measure human performance in NPP control room simulations including direct observation, automated computer logging, recordings from physiological equipment, self-report techniques, protocol analysis and structured debriefs, and application of model-based evaluation. These methods and the particular measures used are summarized and evaluated.

  4. Occurrences in control room equipment, procedures and personnel performances: IRS control room events

    International Nuclear Information System (INIS)

    Tolstykh, V.

    1994-01-01

    The IAEA/NEA Incident Reporting System (IRS) was established in the early 1980, its objective being to gain from operating experience achieved in countries with nuclear power programmes by means of exchanging information on events relevant to safety. Among the 2171 events in the database, 175 events (i.e. 8%) were identified as ''control room events''. It was decided to group these into three sets for further study: 65 events with common mode/cause failures (CCFs), 22 events with cognitive errors and 30 events with unforeseen interaction between NPP systems. It is expected that the pitfalls experienced in the IRS and the questions derived from this study will help to gain a better understanding of the needs and interests of specialists in advanced information methods and artificial intelligence in NPP control rooms. (author)

  5. Contamination control by laundry monitor at NPP

    International Nuclear Information System (INIS)

    Singh, Vishwanath P.; Rana, P.K.; Lokeshwar Rao, S.; Managanvi, S.S.

    2010-01-01

    The operation of nuclear power reactor produces electricity as well as small quantity of radioactive waste as gaseous, liquid and solid. The waste contains radionuclides produced by fission and activation in reactor systems with wide spectrum of energy and half life. The long-lived nuclides Sr, Cs, Ba, Iodine and Co etc compared to short-lived are important in view of radiation protection. The radioactive contamination on the materials, human body or other places where it is undesirable is enormously harmful to workers at Nuclear Power Plant (NPP). The spread of radioactive from controlled areas is very complex problem for power reactor plant management

  6. Hybrid control rooms: the effects of introducing new technology into existing control rooms

    International Nuclear Information System (INIS)

    Morisseau, Dolores S.

    2001-02-01

    The goal of this part of the Hybrid Control Room Project is to gain a perspective on the issues and problems that are an integral part of introducing new technology, automated systems, or support systems into nuclear power plant (NPP) control rooms, particularly when they are introduced on a system-by-system basis. For purposes of this project, hybrid control rooms are defined as those into which new technology, such as digital and computer-based controls are gradually incorporated as opposed to those that are completely, or nearly completely, refitted with new technology. Although the focus of this project is the introduction of computer based, digital systems into NPP control rooms, it is not possible to exclude the effects throughout the process that are inevitable when new technology is introduced anywhere in complex process control systems. Thus, this document examines the effects of such changes within the context of the organisation in which they occur, including the management of change, work procedures and work methods, communications and crew interaction, training, and the interdependent functions in the operational context. (Author)

  7. Control system for NPP powerfull turbines

    International Nuclear Information System (INIS)

    Osipenko, V.D.; Rozhanskij, V.E.; Rokhlenko, V.Yu.

    1985-01-01

    A control system for NPP 1000 MW turbines safety is described. The turbine safety system has a hydraulic drive to actuate in case of increasipg of rotational speed of a turbine rotor and an electrohydraulic drce to operate in case of pressure reduction in the lubrication system, axial displacement deviation, etc. The system is highly reliable due to application of a safety system without slide valves and long-term operation of hydraulic controls in guarding conditions; the system epsures multifunctional control with high accuracy and speed due to application of the intricate electronic part, high speed of response with a limited use of high pressure oil due to application of two-pressure pumps, pneumohydraulic accumulators and oil discharge valves. Steady-state serviceability of the system is maintained by devices for valve cooling dawn. A shockless change from electrohydraulic to hydraulic control channels is provided

  8. Replacement of the computerized control system at NPP under operation

    International Nuclear Information System (INIS)

    Ermolaev, A.D.; Rakitin, I.D.

    1985-01-01

    Reasons and preconditions for replacement of the computerized control systems (CCS) at NPP under operation are consi-- dered. Problems dealing with management of CCS replacement, maintenance of a new CCS as well as NPP personnel training for the new system maintenance are discussed. A necessity of NPP personnel participation in these works in order to adapt CCS to requirements of NPP operation personnel and to initiate the training process is underlined. Replacement of CCS at NPP under operation is associated, as a rule, with obsolescence of old systems not ensuring growing requirements to NPP workability and safety. Principles observed at CCS replacement are reduced, mainly, to the following; maximum utilizatian of existing equipment, metal strUctures, cables, instruments, power supplies, ventilation system minimum of construction works and new communications; the least change of acting panels and boxes; changes in control desks should be introduced on the basis of the analysis of operator actions '

  9. CEBAF Control Room Renovation

    International Nuclear Information System (INIS)

    Michael Spata; Thomas Oren

    2005-01-01

    The Machine Control Center (MCC) at Jefferson Lab's Continuous Electron Beam Accelerator Facility (CEBAF) was initially constructed in the early 1990s and based on proven technology of that era. Through our experience over the last 15 years and in our planning for the facility's 12 GeV upgrade we reevaluated the control room environment to capitalize on emerging visualization and display technologies and improve workflow processes and ergonomic attributes. This effort also sets the foundation for the redevelopment of the accelerator's control system to deliver high reliability performance with improvements in beam specifications management and information flow. The complete renovation was performed over a three-week maintenance period with no interruption to beam operations. We present the results of this effort

  10. CEBAF Control Room Renovation

    International Nuclear Information System (INIS)

    Michael Spata; Thomas Oren

    2005-01-01

    The Machine Control Center at Jefferson Lab's Continuous Electron Beam Accelerator Facility was initially constructed in the early 1990s and based on proven technology of that era. Through our experience over the last 15 years and in our planning for the facilities 12 GeV upgrade we reevaluated the control room environment to capitalize on emerging visualization and display technologies and improve on workflow processes and ergonomic attributes. This effort also sets the foundation for the redevelopment of the accelerator's control system to deliver high reliability performance with improvements in beam specifications management and information flow. The complete renovation was performed over a three-week period with no interruption to beam operations. We present the results of this effort

  11. On psichological problem of NPP operation and control

    International Nuclear Information System (INIS)

    Mashin, V.A.

    1994-01-01

    The role of psichological factor as a reserve for increasing NPP safety connected with human factor is discussed. It is emphasized that the process of NPP personnel professional training should not be restricted by formation of a certain set of knowledge, skills and experience. It is necessary to initiate ability for constant self-developing. Control for assurance of effective interaction of the whole NPP personnel is an important problem

  12. CEBAF Control Room Renovation

    International Nuclear Information System (INIS)

    Michael Spata; Anthony Cuffe; Thomas Oren

    2005-01-01

    The Machine Control Center (MCC) at Jefferson Lab's Continuous Electron Beam Accelerator Facility (CEBAF) was constructed in the early 1990s and based on proven technology of that era. Through our experience over the last 15 years and in our planning for the facilities 12 GeV upgrade we reevaluated the control room environment to capitalize on emerging visualization and display technologies and improve on work-flow processes and ergonomic attributes. The renovation was performed in two phases during the summer of 2004, with one phase occurring during machine operations and the latter, more extensive phase, occurring during our semi-annual shutdown period. The new facility takes advantage of advances in display technology, analog and video signal management, server technology, ergonomic workspace design, lighting engineering, acoustic ceilings and raised flooring solutions to provide a marked improvement in the overall environment of machine operations

  13. Controlling the clean room atmosphere

    International Nuclear Information System (INIS)

    Meeks, R.F.

    1979-01-01

    Several types of clean rooms are commonly in use. They include the conventional clean room, the horizontal laminar flow clean room, the vertical laminar flow clean room and a fourth type that incorporates ideas from the previous types and is known as a clean air bench or hood. These clean rooms are briefly described. The origin of contamination and methods for controlling the contamination are discussed

  14. Electrohydraulic system to control NPP turbines

    International Nuclear Information System (INIS)

    Kosyak, Yu.F.; Virchenko, M.A.; Rozhanskij, V.E.; Rokhlenko, V.Yu.; Gapunin, A.Ya.; Zhornitskaya, T.Ya.; Rasskazov, I.Eh.; Butsenko, V.N.; Brajnin, L.S.; Makarenko, N.I.

    1985-01-01

    Operation regimes of electrohydraulic regulation system (EHRS) of NPP turbines, designed to control the turbine in start-up and working conditions, have been decribed. In start-up regimes EHRS ensures the testing of control valves of the turbine, the turn of the turbine from zero to the nominal rotation frequency (automatic, semiautomatic and manual regulation), turbine acceleration to test safety automatic systems, gradual change in rotation frequency during generator synchronization with circuit. Under working conditions EHRS ensures the maintenance of frequency, power and vapour pressure before the turbine. A block diagram of EHRS is presented. Sensors and electronic part of EHRS are supplied with triple reservation, which ensures a high relaibility of the system

  15. Nuclear power plant control room operator control and monitoring tasks

    International Nuclear Information System (INIS)

    Bovell, C.R.; Beck, M.G.; Carter, R.J.

    1998-01-01

    Oak Ridge National Laboratory is conducting a research project the purpose of which is to develop the technical bases for regulatory review criteria for use in evaluating the safety implications of human factors associated with the use of artificial intelligence and expert systems, and with advanced instrumentation and control (I and C) systems in nuclear power plants (NPP). This report documents the results from Task 8 of that project. The primary objectives of the task was to identify the scope and type of control and monitoring tasks now performed by control-room operators. Another purpose was to address the types of controls and safety systems needed to operate the nuclear plant. The final objective of Task 8 was to identify and categorize the type of information and displays/indicators required to monitor the performance of the control and safety systems. This report also discusses state-of-the-art controls and advanced display devices which will be available for use in control-room retrofits and in control room of future plants. The fundamental types of control and monitoring tasks currently conducted by operators can be divided into four classifications: function monitoring tasks, control manipulation tasks, fault diagnostic tasks, and administrative tasks. There are three general types of controls used in today's NPPs, switches, pushbuttons, and analog controllers. Plant I and C systems include components to achieve a number of safety-related functions: measuring critical plant parameters, controlling critical plant parameters within safety limits, and automatically actuating protective devices if safe limits are exceeded. The types of information monitored by the control-room operators consist of the following parameters: pressure, fluid flow and level, neutron flux, temperature, component status, water chemistry, electrical, and process and area radiation. The basic types of monitoring devices common to nearly all NPP control rooms include: analog meters

  16. Training change control process at Cernavoda NPP

    International Nuclear Information System (INIS)

    Valache, Cornelia Mariana

    2005-01-01

    The paper presents the process of 'Training Change Control' at Cernavoda NPP. This process is a systematic approach that allows determination of the most effective training and/or non-training solutions for challenges that may influence the content and conditions for a training program or course. Changes may be the result of: - response to station systems or equipment modifications; - new or revised procedures; - regulatory requirements; - external organizations requirements; - internal evaluations meaning feedback from trainees, trainers, management or post-training evaluations; - self-assessments; - station condition reports; - operating experience (OPEX); - modifications of job scope; - management input. The Training Change Control Process at Cernavoda NPP includes the following aspects. The first step is the identification of all the initiating factors for a potential training change. Then, retain only those, which could have an impact on training and classify them in two categories: as deficiencies or as enhancement suggestions. The process is different for the two categories. The deficiency category supposes the application of the Training Needs Analysis (TNA) process. This is a performance-oriented process, resulting in more competent employees, solving existing and potential performance problems. By using needs analysis to systematically determine what people or courses and programs are expected to do and gathering data to reveal what they are really doing, we can receive a clear picture of the problem and then we can establish corrective action plans to fix it. The process is supported by plant subjects matter and by training specialists. On the other hand, enhancements suggestions are assessed by designated experienced persons and then are implemented in the training process. Regarding these two types of initiating factors for the training change control process, the final result consists of a training improvement, raising the effectiveness, efficiency or

  17. Dissemination of Knowledge about NPP Instrumentation and Control Systems

    International Nuclear Information System (INIS)

    Yastrebenetsky, M.

    2016-01-01

    Full text: Instrumentation and control (I&C) systems are the most variable part in the nuclear power plants (NPP) comparatively with any other NPP systems. This statement is connected with the wide use of computers, rapid changes in information technologies, with the appearance of new computer complex electronic components, e.g., field programmable gate arrays (FPGA) and with appropriate point of their insertion into NPP I&C life cycle. The changes in NPP I&C systems require the dissemination of the knowledge about these systems. Lessons after Fukushima accident increase necessity of these actions. The elaboration and following dissemination of this knowledge took place in different directions: • Writing and issue of three new books about NPP I&C systems for specialists and for students which were issued in Ukrainian and USA public houses (the last book was issued in 2014); • Organization of five international scientific technical conferences, devoted to NPP I&C safety problems; • Elaboration of national (Ukrainian) standards and regulations pertaining to safety important NPP I&C systems (the last standard was issued in 2015) and participation in elaboration of international standards; • Lecturing for university students, NPP specialists and I&C designers. These actions in all directions are added to IAEA activity in the area NPP I&C systems (e.g., IAEA NP-T-3.12 “Core Knowledge on I&C systems in NPP”). (author

  18. Using the digital reactor control systems at NPP

    International Nuclear Information System (INIS)

    Schirl, G.; Hertel, J.

    2006-01-01

    A conception of application of the digital reactor control systems (RCS) at NPP is presented. The digital RCS architecture and safety ensuring are considered. The strategy and algorithm of the operating NPP equipping with the new digital RCS are given too [ru

  19. Baseline Study Methodology for Future Phases of Research on Nuclear Power Plant Control Room Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Le Blanc, Katya Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bower, Gordon Ross [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hill, Rachael Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary Alexander [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-07-01

    In order to provide a basis for industry adoption of advanced technologies, the Control Room Upgrades Benefits Research Project will investigate the benefits of including advanced technologies as part of control room modernization This report describes the background, methodology, and research plan for the first in a series of full-scale studies to test the effects of advanced technology in NPP control rooms. This study will test the effect of Advanced Overview Displays in the partner Utility’s control room simulator

  20. Leadership in the control room

    International Nuclear Information System (INIS)

    McDougall, S.J.

    2006-01-01

    This paper discusses the importance of leadership within the control rooms at nuclear power facilities. the leadership capability of control room staff has a significant influence over the improvement of human performance and the development of an 'event free' culture within the business. The development of leadership competency in the control room must be an important part of any nuclear power utility business improvement plan. (author)

  1. Leadership in the control room

    Energy Technology Data Exchange (ETDEWEB)

    McDougall, S.J. [Bruce Power, Bruce B Operations Div., Tiverton, Ontario (Canada)

    2006-07-01

    This paper discusses the importance of leadership within the control rooms at nuclear power facilities. the leadership capability of control room staff has a significant influence over the improvement of human performance and the development of an 'event free' culture within the business. The development of leadership competency in the control room must be an important part of any nuclear power utility business improvement plan. (author)

  2. Modern control room for AHWR

    International Nuclear Information System (INIS)

    Verghese, Clement C.; Joseph, Jose; Biswas, B.B.; Patil, R.K.

    2005-01-01

    Advanced Heavy Water Reactor (AHWR) is a next generation nuclear power plant being developed by Bhabha Atomic Research Centre. A modern control room has been conceived for operation and monitoring of the plant in tune with the advanced features of the reactor. A state of the art C and I architecture based on extensive use of computers and networking has been conceived for this plant. This architecture enables the implementation of a fully computerised operator friendly control room with soft HMIs. Features of the modern control room and control room and concept of soft HMI based operator interfaces have been described in the paper. (author)

  3. A control room lighting study

    International Nuclear Information System (INIS)

    Vaidya, V.V.; Iwasa-Madge, K.M.; Howard, B.; Willson, R.B.

    1984-01-01

    Operators at a Heavy Water Plant in Ontario, Canada complained about lighting-related difficulties in the control room. The Human Factors Engineering Unit was requested to perform a lighting survey and make recommendations to improve the control centre lighting conditions. This paper describes the control room, the operator tasks, the procedures used for the lighting survey, the findings, and the changes recommended

  4. Control room lay-out

    International Nuclear Information System (INIS)

    Toma, Violeta

    2004-01-01

    TRIUMF (Tri-University Meson Facility) is Canada's national laboratory for particle and nuclear physics. There are 6 accelerators and 3 Control Rooms at TRIUMF. The main control room serves the big cyclotron, the 500 MeV, and the adjacent experiment. The 42 MeV and two 32 MeV ones are production dedicated. These cyclotrons belong to a private company but are operated by TRIUMF staff from ATG (Applied Technology Group) Control Room. The last is ISAC (Isotope Acceleration and Separation) Control Room, from which the LINAC is controlled. Research areas cover theoretical (2 subjects), pure (5 subjects) and applied (8 subjects) physics. In the early '70s, as the 500 MeV was being completed, the first Control Room was built in the main accelerator building. The recent topics covered by this paper are proton and pion therapy, what are the operator's duties?, the CP42, TR30 and TR13 cyclotron control rooms, the ISAC control systems including control room modification. Due to the nature of an operator's job, the Control Room layout is pretty important. This is true for any work environment, but when working shifts it becomes essential. Lots of time and effort, not to mention money, were spent to figure out the optimum configuration. It seems to me that the key factor in the control room layout is versatility, and this is because it has to keep happy a group of people with different inclinations, which have a tendency to become quite moody after the second night shift. No matter what, there will still be unhappy people, but we are trying our best. (Y. Tanaka)

  5. In the LEAR control room

    CERN Multimedia

    CERN PhotoLab

    1983-01-01

    View into the control room of the Low Energy Antiproton Ring (LEAR). Edgar Asseo (sitting) and Dieter Möhl and Georges Carron reflecting upon some beam dynamics (or hardware?) problem. Vassilis Agoritsas, in the background, leaning over a plan or a keyboard. LEAR in its early years (1982 to about 1990) was run from this local control room in building 363 close to the end of the PS South Hall, where the ring was installed. Later-on the operation was surveyed from the PS main control room.

  6. NPP Temelin instrumentation and control system upgrade and verification

    International Nuclear Information System (INIS)

    Ubra, O.; Petrlik, J.

    1998-01-01

    Two units of Ver 1000 type of the Czech nuclear power plant Temelin, which are under construction are being upgraded with the latest instrumentation and control system delivered by WEC. To confirm that the functional design of the new Reactor Control and Limitation System, Turbine Control System and Plant Control System are in compliance with the Czech customer requirements and that these requirements are compatible with NPP Temelin upgraded technology, the verification of the control systems has been performed. The method of transient analysis has been applied. Some details of the NPP Temelin Reactor Control and Limitation System verification are presented.(author)

  7. Electromagnetic compatibility of tools and automated process control systems of NPP units

    International Nuclear Information System (INIS)

    Alpeev, A.S.

    1994-01-01

    Problems of electromagnetic compatibility of automated process control subsystems in NPP units are discussed. It is emphasized, that at the stage of development of request for proposal for each APC subsystem special attention should be paid to electromagnetic situation in specific room and requirements to the quality of functions performed by the system. Besides, requirements to electromagnetic compatibility tests at the work stations should be formulated, and mock-ups of the subsystems should be tested

  8. Control room philosophy: Principles of control room design and control room work

    International Nuclear Information System (INIS)

    Skriver, Jan; Ramberg, Jasmine; Allwin, Pernilla

    2006-01-01

    In order to provide insights for improvement of work in control rooms several factors have to be considered. Knowledge of principles including control room philosophies will guide the recommended improvements. In addition to knowledge about specific principles an advantage for an organization can be an understanding of similarities and policies used in other high risk industry. The report has been developed on the basis of a document analysis of international standards and other guiding documents. (NUREG 0711, ISO 11064, ISO 6385, IEC 60964). In addition to the document analysis which has strived to compare the documents to see similarities in important principals, experience from working with control room design, modifications and evaluations in other high risk industries has pervaded the report. Important principles have been identified which are recommended to be included in a control room philosophy. Many of these are similar to the principles identified in the international standards. An additional principal which is regarded as important is the utilization of Key Performance Indicators (KPI) which can be used as a measure to target preventative means. Further more it is critical that the control room philosophy is easy to access and comprehend for all users. One of the challenges that remain after having developed a control room philosophy is how to utilize it in the daily work situation. It is vital that the document remains as a living document, guiding the continual improvement of the control room in the various life cycle stages

  9. The conference hybrid control room

    International Nuclear Information System (INIS)

    Gieci, A.; Caucik, J.; Macko, J.

    2008-01-01

    An original concept of a hybrid control room was developed for the Mochovce-3 and Mochovce-4 reactor units which are under construction. The basic idea underlying the concept is that the control room should be a main working place for the operators (reactor operator and turbine operator) and for the shift supervisor, designed as a comprehensive unit desk shaped so that all members of the control room crew are in a face-to-face contact constantly. The main desk consists of three clearly identified areas serving the operators and the unit supervisor as their main working places. A soft control system is installed at the main working places. A separate safety-related working place, designed as a panel with classical instrumentations at the conference hybrid control room, is provided in case of abnormal conditions or emergency situation. Principles of ergonomics and cognitive engineering were taken into account when designing the new conference hybrid control room for the Mochovce-3 and -4 reactor units. The sizes, propositions, shapes and disposition of the equipment at the control room have been created and verified by using virtual reality tools. (orig.)

  10. Nuclear reactor control room construction

    International Nuclear Information System (INIS)

    Lamuro, R.C.; Orr, R.

    1993-01-01

    A control room for a nuclear plant is disclosed. In the control room, objects labelled 12, 20, 22, 26, 30 in the drawing are no less than four inches from walls labelled 10.2. A ceiling contains cooling fins that extend downwards toward the floor from metal plates. A concrete slab is poured over the plates. Studs are welded to the plates and are encased in the concrete. 6 figures

  11. Future control room design (modernization of control room systems)

    International Nuclear Information System (INIS)

    Reischl, Ludwig; Freitag, Timo; Dergel, Rene

    2009-01-01

    In the frame of lifetime extension for nuclear power plants the modernization of the complete safety and operational control technology will be digitalized. It is also recommended to modernize the operator facilities, monitoring systems in the control room, the back-up shut-down center and the local control stations. The authors summarize the reasons for the modernization recommendations and discuss possible solutions for display-oriented control rooms. A concept for control room backfitting includes generic requirements, requirements of the local authorities, ergonomic principles information content and information density, and the design process. The backfitting strategy should include a cooperation with the operational personnel, The quality assurance and training via simulator needs sufficient timing during the implementation of the backfitting.

  12. Control room and ergonomic design

    International Nuclear Information System (INIS)

    Hinz, W.

    1984-01-01

    The important basis for the configuration of the control room of a nuclear power station is the concept for controlling a fault and that for controlling normal operation. The tasks resulting from this for the control room personnel are decided by the control room concept. In this configuration process (from the division of process control tasks between the system components operators and control technology to the configuration of individual means of operation) the characteristics and capabilities of the personnel, which are subject to special requirements as regards their qualifications, are observed. New concepts which are only now technically feasible are therefore being developed for information processing and display, in order to give the personnel a better oversight of the state and trends of the plant. (orig./DG) [de

  13. Review of international standards related to the design for control rooms on nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, Masashi; Yoshikawa, Hidekazu; Fujita, Yushi

    2005-01-01

    The improvement of Human-Machine Interface (HMI) design for control rooms on nuclear power plants (NPP) has been accomplished world wide, especially after the TMI-2 accident. The design process and guidelines are standardized in IEC60964 and supplemental standards as international standard. However, technological update is required due to the increased use of computerized control and monitoring equipment and systems in control rooms on NPP in recent years. Standards are becoming more important for computerized control rooms because there is more freedom to design than conventional hardware based system. For computerized control rooms, standards for hardware and software of HMI systems should be also considered. Standards and guidelines for computerized control rooms on NPP have been developed recently in each body such as IEC, ISO, and IEEE etc. Therefore, reviewing these standards and guidelines related to control rooms design of NPP can be useful not only for revision of the international standards such as IEC60964, but also for users of the standards and guidelines. In this paper, we reviewed the international standards related to the design for control rooms, in the two aspects of HMI design and hardware and software design, considering the undergoing revision work and their application. (author)

  14. NPP capital equipment life control facilities and tools

    International Nuclear Information System (INIS)

    Nekrasov, A.V.; Proskuryakov, K.N.

    2009-01-01

    Algorithms and simulation package for calculation of eigen modes of coolant pressure oscillations in equipment of primary coolant circuit of WWER-1000 NPP, tuned-circuit Q-factor of an oscillating contour of the coolant, fluctuation frequencies pass band and attenuation factors of were developed. Calculation results for cases of presence and absence of gaseous state radiolysis products in the coolant were obtained. Results analysis makes it possible to disclose operating conditions which result in raised vibrations, and to develop control response in NPP industrial control system for their prevention [ru

  15. Computer Security of NPP Instrumentation and Control Systems: Cyber Threats

    International Nuclear Information System (INIS)

    Klevtsov, A.L.; Trubchaninov, S.A.

    2015-01-01

    The paper is devoted to cyber threats, as one of the aspects in computer security of instrumentation and control systems for nuclear power plants (NPP). The basic concepts, terms and definitions are shortly addressed. The paper presents a detailed analysis of potential cyber threats during the design and operation of NPP instrumentation and control systems. Eleven major types of threats are considered, including: the malicious software and hardware Trojans (in particular, in commercial-off-the-shelf software and hardware), computer attacks through data networks and intrusion of malicious software from an external storage media and portable devices. Particular attention is paid to the potential use of lower safety class software as a way of harmful effects (including the intrusion of malicious fragments of code) on higher safety class software. The examples of actual incidents at various nuclear facilities caused by intentional cyber attacks or unintentional computer errors during the operation of software of systems important to NPP safety.

  16. Methods and means for improving the man-machine systems for NPP control

    International Nuclear Information System (INIS)

    Konstantinov, L.V.; Rakitin, I.D.

    1984-01-01

    Consideration is being given to the role of ''human factors'' and the ways of improving the man-machine interaction in NPP control and safety systems (CSS). Simulators and tAaining equipment on the basis of dynamic power unit models used for training and improving skill of NPP operatoAs, as well as for mastering collective actions of personnel under accidental conditions are considered in detail. The most perfect program complexes for fast NPP diagnostics and theiA pealization in the Federal Republic of Germany, Japan, Canada, the USA and other countries are described. A special attention is paid to the means and methods of videoterminal dialogue operator interaction with an object both in normal and extreme situations. It is noted that the problems of the man-machine interaction have become the subject of study only in the end of 70s after analyzing the causes of the Three-Mile-Island accident (USA). Publications dealing with the development of perspective control rooms for NPP were analyzed. It was concluded that radical changes both in equipment and principles of organizing the personnel activity will take place in the nearest future. They will be based on the progress in creating dialogue means and computers of the fourth and fifth generations as well as on engineering and psychological and technical aspects of designing

  17. Improvement of waste release control in French NPP

    International Nuclear Information System (INIS)

    Samson, T.; Lucquin, E.; Dupin, M.; Florence, D.; Grisot, M.

    2002-01-01

    The new waste release control in French NPP is more restrictive than the old one and needs heavy investment to bring plants to compliance with it. The great evolutions are a chemical follow up on more chemicals with a higher measurement frequency and with lower maximum concentrations and a specific measurement of carbon 14. Regarding radioactive releases, a new counting has been settled and activity of carbon 14 release is now measured and no longer calculated. The evolution of the French regulation leads to develop specific procedures and analytical techniques in chemistry and in radiochemistry (UV spectrometric methods, carbon 14 measurements,..) EDF NPP operators have launched a voluntarist process to reduce their releases since the beginning and before the evolution of the regulation. EDF priorities in terms of environment care lead henceforth to implement a global optimisation of the impact for a better control of releases. The new regulation will help EDF to reach its goals because it covers all the aspects in one administrative document: it is seen as a real simplification and a clarification towards public. In addition, this new regulation fits in with international practices which will allow an easier comparison of results between EDF and foreign NPP. These big environmental concerns lead EDF to create a national dedicated laboratory (LAMEN) in charge of developing specific measurement procedures to be implemented either by NPP or by sub-contractor laboratories. (authors)

  18. Improvement of waste release control in French NPP

    Energy Technology Data Exchange (ETDEWEB)

    Samson, T.; Lucquin, E.; Dupin, M. [EDF/GDL (France); Florence, D. [EDF/GENV (France); Grisot, M. [EDF/CNPE Saint Laurent (France)

    2002-07-01

    The new waste release control in French NPP is more restrictive than the old one and needs heavy investment to bring plants to compliance with it. The great evolutions are a chemical follow up on more chemicals with a higher measurement frequency and with lower maximum concentrations and a specific measurement of carbon 14. Regarding radioactive releases, a new counting has been settled and activity of carbon 14 release is now measured and no longer calculated. The evolution of the French regulation leads to develop specific procedures and analytical techniques in chemistry and in radiochemistry (UV spectrometric methods, carbon 14 measurements,..) EDF NPP operators have launched a voluntarist process to reduce their releases since the beginning and before the evolution of the regulation. EDF priorities in terms of environment care lead henceforth to implement a global optimisation of the impact for a better control of releases. The new regulation will help EDF to reach its goals because it covers all the aspects in one administrative document: it is seen as a real simplification and a clarification towards public. In addition, this new regulation fits in with international practices which will allow an easier comparison of results between EDF and foreign NPP. These big environmental concerns lead EDF to create a national dedicated laboratory (LAMEN) in charge of developing specific measurement procedures to be implemented either by NPP or by sub-contractor laboratories. (authors)

  19. Safety review for human factors engineering and control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Yang Mengzhuo

    1998-01-01

    Safety review for human factors engineering and control rooms of nuclear power plants (NPP) is in a forward position of science and technology, which began at American TMI severe accident and had been implemented in China. The importance and the significance of the safety review are expounded, the requirements of its scope and profundity are explained in detail. In addition, the situation of the technical document system for nuclear safety regulation on human factors engineering and control rooms of NPP in China is introduced briefly, on which the safety review is based

  20. At ISR Main Control Room

    CERN Multimedia

    1983-01-01

    After 13 years the exploitation of the Intersecting Storage Rings as a beam-beam collider went to an end. In this last year the demands were very exacting, both in terms of operating time and diversified running conditions (Annual Report 1983 p. 123). Before dismantelement the photographer made a last tour, see photos 8310889X --> 8310667X. This photo shows the Main Control Room.

  1. Control room MMI 2000 for NORS simulator in HAMMLAB

    International Nuclear Information System (INIS)

    Saarni, R.; Foerdestroemmen, N.T.; Meyer, B.D.; Skjerve, A.B.M.

    2001-03-01

    The report presents the control room MMI as of year 2000 for the NORS simulator in HAMMLAB. It consists of two main parts: NORS Reference Control Room MMI and NORS Experimental Control Room MMI. They are both utilised in human factors experiments in HAMMLAB. The HAMMLAB Experimental Control Room 2000 is presented together with the NORS Reference CR MMI, which includes the following display types: Overview displays, process and control displays, trend displays, supplementary alarm displays and logic displays for the protection system and other automatic control systems. User experiences based on feedback from professional Loviisa NPP operators are also given. For the Experimental Control Room MMI, main emphasis is on presenting the design of a new large screen overview display called; experimental Automatic Information Presentation (AIP) display. It was used for the first time last year in the HCA-2000 experiment in HAMMLAB. The design is quite different from previous overview displays being developed and used in HAMMLAB. The display presents the overall dynamic status of both the process and the automatic systems. The plans for the future include to develop and user test an upgraded AIP overview display, and to enhance and user test a limited set of task-based display prototypes. (Author)

  2. The influence and evaluation of different virtual reality presentations for the main control room of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Rouwen; Lin Chiuhsiang Joe; Lin Shiaufeng; Yang Chihwei; Cheng Tsungchieh; Yang Lichen

    2011-01-01

    Certainly, a nuclear power plant (NPP) is a complex system and requires high reliability. Engineering technology plays an important role in NPP that requires complex technical equipment and interfaces in order to achieve public security and working safety. Through training, operators can understand the nuclear power system and further establish the fit between human operators and the system, in order to reduce human errors and to ensure the working safety of the control room of NPP. However, the operator trainings for the control room of NPP are difficult and time-consuming. Virtual control room is thus developed using the virtual reality (VR) technology to help the training process. Presently several researches have developed virtual system for NPP for the purpose of training. However, whether the virtual training system for the control room of NPP can give users realistic immersive context as in the real environment is unknown. Whether these virtual systems are helpful in training performance are yet to be confirmed. For this reason, the control room of Lung-Men NPP of Taiwan was constructed with VR technology in this study in order to compare the performances of two VR representation methods (Desktop VR and Project VR). A searching task was planned in which the operators have to find out the objects appointed by the experimenter in the virtual interface of the main control room. The time to complete the task was collected as dependent variables in this experiment. The subjects have to complete the questionnaire that was developed for evaluating the usability of the virtual interface of MRC after finishing the experiment. The result showed that the performance of the virtual interface of NPP presented by the VR projector was better than the desktop. (author)

  3. Strengthening the control on radioactive sources - Cernavoda NPP operating experience

    International Nuclear Information System (INIS)

    Daian, I.; Simionov, V.

    2005-01-01

    This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant, including decommissioning. (authors)

  4. Strengthening the control on radioactive sources - Cernavoda NPP operating experience

    International Nuclear Information System (INIS)

    Daian, I.; Simionov, V.

    2005-01-01

    Full text: This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant. (authors)

  5. Plant level of automated control system at a NPP with RBMK reactor

    International Nuclear Information System (INIS)

    Vorob'ev, V.P.; Gorbunov, V.P.; Dmitriev, V.M.; Litvin, A.S.

    1987-01-01

    The functional structure of plant level automated control system (ACS) at NPP with RBMK-1000 reactors, its binding with the on-line control system of higher and lower levels, as well as engineering requirements to software and recommendations on composition of hardware components, are considered. NPP ACS is an organizational-engineering system consisting of computer facilities and binding aimed at solving management, economical, organizational and physical-engineering problems to control NPP more effectively. The system carries out data acquisition, preliminary processing, analysis, transmission and representation for users to accept solutions for NPP operation by operative and management personnel. The main aim of integrated NPP ACS is the control development and increase of NPP economical efficiency, the increase of electric and heat energy production, the optimization of the production distribution between units, the development of production and economic NPP control

  6. Ergonomics and control room design

    International Nuclear Information System (INIS)

    Williams, J.C.; Story, D.T.

    1987-01-01

    The application of ergonomic principles to the design process and some aspects of the Sizewell B control room is discussed. Also outlined is the management process which ensures that these principles are applied systematically throughout the design development activity and highlights the functional requirements which must also be met in the creation of a total man-machine system package which meets all the technical design criteria. The ergonomics requirements are part of this process and extend into all aspects of design ranging from such matters as workplace organization to environmental factors, social engineering, communications and aesthetics. (author)

  7. Computer security of NPP instrumentation and control systems: categorization

    International Nuclear Information System (INIS)

    Klevtsov, A.L.; Simonov, A.A.; Trubchaninov, S.A.

    2016-01-01

    The paper is devoted to studying categorization of NPP instrumentation and control (I&C) systems from the point of view of computer security and to consideration of the computer security levels and zones used by the International Atomic Energy Agency (IAEA). The paper also describes the computer security degrees and zones regulated by the International Electrotechnical Commission (IEC) standard. The computer security categorization of the systems used by the U.S. Nuclear Regulatory Commission (NRC) is presented. The experts analyzed the main differences in I&C systems computer security categorization accepted by the IAEA, IEC and U.S. NRC. The approaches to categorization that should be advisably used in Ukraine during the development of regulation on NPP I&C systems computer security are proposed in the paper

  8. Guidelines for control room design reviews

    International Nuclear Information System (INIS)

    1981-09-01

    The control room design review is part of a broad program being undertaken by the nuclear industry and the government to ensure consideration of human factors in nuclear power plant design and operation. The purpose of the control room design review described by these guidelines is to (1) review and evaluate the control room workspace, instrumentation, controls, and other equipment from a human factors engineering point of view that takes into account both system demands and operator capabilities; and (2) to identify, assess, and implement control room design modifications that correct inadequate or unsuitable items. The scope of the control room design review described by these guidelines covers the human engineering review of completed control rooms; i.e., operational control rooms or those at that stage of the licensing process where control room design and equipment selection are committed. These guidelines should also be of use during the design process for new control rooms. However, additional analyses to optimize the allocation of functions to man and machine, and further examination of advanced control system technology, are recommended for new control rooms. Guidelines and references for comprehensive system analyses designed to incorporate human factors considerations into the design and development of new control rooms are presented in Appendix B. Where possible, a generic approach to the control room design review process is encouraged; for example, when control room designs are replicated wholly or in part in two or more units. Even when designs are not replicated exactly, generic reviews which can be modified to account for specific differences in particular control rooms should be considered. Industry organizations and owners groups are encouraged to coordinate joint efforts and share data to develop generic approaches to the design review process. The control room design review should accomplish the following specific objectives. To determine

  9. Diagnostic system for process control at NPP Dukovany load follow

    International Nuclear Information System (INIS)

    Rubek, J.; Petruzela, I.

    1998-01-01

    The NPP Dukovany is being operated in the frequency control since 1996. In last year a project for the plant load follow has been developed. One part of the project is to install a diagnostic system for process control. At present the main control loops of the plant control system are regular tested after unit refuelling only. The functionality and control system parameter adjusting is tested by certificated procedures. This state is unsuitable in view of the plan load follow operation. The relevant operational modes are based on minimisation of influence on plant component life time and on achievement of planned unit parameters. Therefore it is necessary to provide testing of main control system parts in shorter time period. Mainly at time when the unit is really in load follow operation. The paper describes the diagnostic system for process control which will be at NPP Dukovany implemented. The principal of the system will be evaluation of real and expected changes of technological variables. The system utilises thermohydraulic relation among main technological variables and relation among controlled and manipulated variables. Outputs of the system will be used to operational staff support at the plant operation. It enables: determination of control system state, estimation and check of future control system state, early indication of the deviation of process from normal conditions, check of efficiency of operational staff intervention into plant control. The system gives the plant operator new information for the plant process control. Simultaneously the coupling of new system outputs on existing signalisation is solved. (author)

  10. Improvement of main control room

    International Nuclear Information System (INIS)

    Chae, Sung Ki; Ham, Chang Sik; Kwon, Ki Chun

    1991-07-01

    Information display system, advanced alarm system and fiber optical communication system were developed to improve the main control room in nuclear power plant. Establishing the new hierachical information structure of plant operation data, plant overview status board(POSB) and digital indicator(DI) were designed and manufactured. The prototype advanced alarm system which employed the new alarm logics and algorithm compared with the conventional alarm system were developed and its effectiveness was proved. Optical communication system which has multi-drop feature and capability of upgrading to large-scale system by using BITBUS communication protocol which is proven technology, were developed. Reliability of that system was enhanced by using distributed control. (Author)

  11. Bulgaria: Belene NPP. Project Control. Annex 3

    International Nuclear Information System (INIS)

    Nabatov, N.

    1999-01-01

    This annex deals with project control. The Belene project has been suspended for 7 years after approx. 50% of money had been spent. Equipment, structures and documentation have been well protected, but majority of qualified personnel have been lost. Resumption of work awaits government decision and provision of funds. (author)

  12. Canada: Darlington NPP. Project Control. Annex 4

    International Nuclear Information System (INIS)

    Wieckowski, G.

    1999-01-01

    This annex deals with project control. The just slowed down and delayed. Senior engineering, construction and procurement staff stayed with the project. Documentation was preserved though normal functioning of the records department project was completed and put into service with a few years' delay. (author)

  13. NPP control command: Considerations for the future

    International Nuclear Information System (INIS)

    Trapp, J.P.

    1998-01-01

    Recent years have seen considerable improvements in the performance available from instrumentation, computerized data acquisition and processing systems, signal processing and related display processing systems. This progress implies the need for a complete rethink of the approach to future surveillance, control and protection systems for use with nuclear reactors, especially regarding new reactor systems. These new systems will in the future need to ensure full compatibility between safety improvements and the enhanced economic competitively of nuclear power. This paper presents an exercise covering the main functions that can as of now be considered for future applications in this field. (author)

  14. Security Controls for NPP I and C Systems

    International Nuclear Information System (INIS)

    Kim, Y. M.; Jeong, C. H.; Kim, T. H.

    2014-01-01

    In Korea, regulatory body have required cyber security plan for nuclear I and C system. Also, all I and C systems and equipment must be classified according to cyber security level and technical, operational and managerial security controls must be provided based on each level. It is necessary to determine the best set of security controls for NPP I and C system. In our research, selection, implementation and verification process of security controls which can be used for I and C systems has developed. For establishing the cyber security of the nuclear I and C system, special cyber security system which consider the difference between general IT system and nuclear I and C system is needed. This research, we developed security improvement methodology for NPP I and C system through establishing security control, applying and verifying activity. Also, the cyber security activities which are needed during development are defined. It is expected that the methodology which has been developed by this research can be used for establish, implement, evaluate the security controls for protecting nuclear I and C system from cyber-attacks

  15. Security Controls for NPP I and C Systems

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. M.; Jeong, C. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, T. H. [Formal Works Inc., Seoul (Korea, Republic of)

    2014-05-15

    In Korea, regulatory body have required cyber security plan for nuclear I and C system. Also, all I and C systems and equipment must be classified according to cyber security level and technical, operational and managerial security controls must be provided based on each level. It is necessary to determine the best set of security controls for NPP I and C system. In our research, selection, implementation and verification process of security controls which can be used for I and C systems has developed. For establishing the cyber security of the nuclear I and C system, special cyber security system which consider the difference between general IT system and nuclear I and C system is needed. This research, we developed security improvement methodology for NPP I and C system through establishing security control, applying and verifying activity. Also, the cyber security activities which are needed during development are defined. It is expected that the methodology which has been developed by this research can be used for establish, implement, evaluate the security controls for protecting nuclear I and C system from cyber-attacks.

  16. Nuclear power station main control room habitability

    International Nuclear Information System (INIS)

    Paschal, W.B.; Knous, W.S.

    1989-01-01

    The main control room at a nuclear power station must remain habitable during a variety of plant conditions and postulated events. The control room habitability requirement and the function of the heating, ventilating, air-conditioning, and air treatment system are to control environmental factors, such as temperature, pressure, humidity, radiation, and toxic gas. Habitability requirements provide for the safety of personnel and enable operation of equipment required to function in the main control room. Habitability as an issue has been gaining prominence with the Advisor Committee of Reactor Safeguards and the Nuclear Regulatory Commission since the incident at Three Mile Island. Their concern is the ability of the presently installed habitability systems to control the main control room environment after an accident. This paper discusses main control room HVAC systems; the concern, requirements, and results of NRC surveys and notices; and an approach to control room habitability reviews

  17. Advanced control room caters for the operator

    International Nuclear Information System (INIS)

    George, C.R.; Rygg, D.E.

    1980-01-01

    In existing control rooms the operators' efficiency is often limited by widely scattered and sometimes illogically arranged controls which tend to increase the potential for outages or equipment damage. The advanced control room described allows instant and ready access to preselected information and control by one or two operators from a seated or standing position. (author)

  18. The collaborative tokamak control room

    International Nuclear Information System (INIS)

    Schissel, D.P.

    2006-01-01

    Magnetic fusion experiments keep growing in size and complexity resulting in a concurrent growth in collaborations between experimental sites and laboratories worldwide. In the US, the National Fusion Collaboratory Project is developing a persistent infrastructure to enable scientific collaboration for all aspects of magnetic fusion energy research by creating a robust, user-friendly collaborative environment and deploying this to the more than 1000 US fusion scientists in 40 institutions who perform magnetic fusion research. This paper reports on one aspect of the project which is the development of the collaborative tokamak control room to enhance both collocated and remote scientific participation in experimental operations. This work includes secured computational services that can be scheduled as required, the ability to rapidly compare experimental data with simulation results, a means to easily share individual results with the group by moving application windows to a shared display, and the ability for remote scientists to be fully engaged in experimental operations through shared audio, video, and applications. The project is funded by the USDOE Office of Science, Scientific Discovery through Advanced Computing (SciDAC) Program and unites fusion and computer science researchers to directly address these challenges

  19. Human reliability and the man/machine interface: what do we do after the control room review

    International Nuclear Information System (INIS)

    Folley, J.D. Jr.; Schurman, D.L.

    1983-01-01

    The nuclear industry has focused on only one aspect of the man/machine interface--human factors engineering of control rooms - to enhance nuclear power plant (NPP) safety. There are other factors that profoundly affect the reliability of the operators and maintenance personnel of NPP which, thus, affect NPP safety and availability. This paper discusses the factors of training, selection, job engineering, and work satisfaction, describing the potential effects on reactor safety of these factors at the man/machine interface. The impact of these factors on safety and plant availability is illustrated with examples of results obtained in other fields

  20. Control room habitability during severe accidents

    International Nuclear Information System (INIS)

    Siu, R.P.

    1989-01-01

    The requirements for protection of control room personnel against radiation hazards are specified in 10CFR50, Appendix A, GDC 19. The conventional approach involves a mechanistic evaluation of the radiation doses to control room personnel during design-basis accidents. In this study, an assessment of control room habitability during severe accidents is conducted. The potential levels of radiation hazards to control room personnel are evaluated in terms of both magnitude and probability of occurrence. The expected values for the probabilities of exceeding GDC-19 limits and the cumulative probability distributions of control room doses are determined. In this study, a pressurized water reactor with a large dry containment has been selected for analysis. The types of control rooms evaluated in this study include designs with: (a) filtered local intakes only, (b) filtered recirculation only, (c) filtered local intakes and recirculation, and (d) filtered dual remote intakes and recirculation. From the observations, it is concluded that, except for control room D, all other control room designs may require improvements in order to provide adequate radiation protection during severe accidents, particularly in terms of reducing whole-body gamma doses and skin doses. Potential design improvements include reduction of intake flows for concepts relying on pressurization, reduction in overall leakages, and control room pressurization through the use of bottled air supply

  1. Computer programme for operator support in primary frequency control of NPP Dukovany

    International Nuclear Information System (INIS)

    Kurka, J.; Petruzela, I.; Piroutek, Z.

    1996-01-01

    The computer programme for the control room operator support in the primary frequency control operation of the NPP Dukovany power unit is described. This operational mode has recently been implemented. Until now, the plant has been exclusively operated in the based-load mode at nominal power. The stability of the main unit parameters, unit power output and main steam header pressure, is the characteristic feature for this mode of operation of units with WWER 440 type of reactors. This does no more hold in the new mode in which these both principal parameters vary in dependency on the power network frequency changes. This fact, however, has an important impact on the activities of the control room operators. Therefore, to help them to adapt themselves easily and without unnecessary stresses to new conditions the regulatory body when licensing the new mode finally approved its implementation only if computerized operator support system would be installed in the control room. Such a computer program for the operator support has been recently developed in EGU Prague and has already been implemented into the unit information system on all four Dukovany units. (author). 3 refs, 7 figs

  2. Concept of Advanced Back-up Control Panel Design of Digital Main Control Room

    International Nuclear Information System (INIS)

    Jiang, Guo Jin; Sun, Yong Bin; Tan, Ke; Zhang, Li Ming; Shi, Ji; Zhang, Xue Gang; Huang, Wei Jun; Mao, Ting; Liu Yanzi

    2011-01-01

    Back-up control panel (BCP) of digital main control room (DMCR) is the backup means for main computerized control means (MCM). This paper focus on technical issues for advanced design of Backup Panel (BCP) for CPR1000 using qualified computer-based video display unit to display plant process indication and alarms. HFE issues also have been considered in the BCP design. Then, mean to fulfill safety target of NPP, best ergonomic effect has been described. At last conclusion on advanced BCP design is provided

  3. Concept of Advanced Back-up Control Panel Design of Digital Main Control Room

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Guo Jin; Sun, Yong Bin; Tan, Ke; Zhang, Li Ming; Shi, Ji; Zhang, Xue Gang; Huang, Wei Jun; Mao, Ting; Liu Yanzi [China Nuclear Power Engineering Company, Shenzen (China)

    2011-08-15

    Back-up control panel (BCP) of digital main control room (DMCR) is the backup means for main computerized control means (MCM). This paper focus on technical issues for advanced design of Backup Panel (BCP) for CPR1000 using qualified computer-based video display unit to display plant process indication and alarms. HFE issues also have been considered in the BCP design. Then, mean to fulfill safety target of NPP, best ergonomic effect has been described. At last conclusion on advanced BCP design is provided.

  4. Control room philosophy: Principles of control room design and control room work; Kontrollrumsfilosofi: Principer foer kontrollrumsutformning och kontrollrumsarbete

    Energy Technology Data Exchange (ETDEWEB)

    Skriver, Jan; Ramberg, Jasmine; Allwin, Pernilla [Scandpower Risk Management AB, Uppsala (Sweden)

    2006-01-15

    In order to provide insights for improvement of work in control rooms several factors have to be considered. Knowledge of principles including control room philosophies will guide the recommended improvements. In addition to knowledge about specific principles an advantage for an organization can be an understanding of similarities and policies used in other high risk industry. The report has been developed on the basis of a document analysis of international standards and other guiding documents. (NUREG 0711, ISO 11064, ISO 6385, IEC 60964). In addition to the document analysis which has strived to compare the documents to see similarities in important principals, experience from working with control room design, modifications and evaluations in other high risk industries has pervaded the report. Important principles have been identified which are recommended to be included in a control room philosophy. Many of these are similar to the principles identified in the international standards. An additional principal which is regarded as important is the utilization of Key Performance Indicators (KPI) which can be used as a measure to target preventative means. Further more it is critical that the control room philosophy is easy to access and comprehend for all users. One of the challenges that remain after having developed a control room philosophy is how to utilize it in the daily work situation. It is vital that the document remains as a living document, guiding the continual improvement of the control room in the various life cycle stages.

  5. Ergonomics influence on control room layout

    International Nuclear Information System (INIS)

    Hartfiel, H.D.

    1984-01-01

    Nowadays, human factors has become an important aspect of the design of work places. Since the control room in a nuclear power plant is a work place, too, its layout is also influenced by ergonomics. With the KWU control room concept for the 1300 MW PWR as an example, we show how assured and applicable ergonomic findings enter into the control room design. On the basis of general design principles for work places, specific methods for control room planning have been developed. By working with these methods a concept that makes it possible to build a man-machine interface able to fulfill the process control tasks with all their underlying conditions has been derived. (author)

  6. New technologies for control room habitability assessment

    International Nuclear Information System (INIS)

    Lahti, G.P.; Muraida, J.E.; Perchiazzi, W.T.; Harden, P.A.

    1994-01-01

    Older nuclear power plants typically considered only a nominal amount of unfiltered inleakage (typically 10 cfm) impacting their postaccident control room habitability. However, recent measurements of unfiltered inleakage show values in excess of the nominal 10 cfm. A reassessment for two of these ''older'' stations has been completed recently to show that the measured inleakage did not jeopardize the safety of the control room occupants. Recent concerns at the Zion Station and the Palisades Station about control room habitability in the event of a loss-of-coolant accident have led to an extensive effort to increase control room habitability margin. The heating, ventilating and air-conditioning (HVAC) system servicing each of the control rooms has the potential for unfiltered in-leakage through many locations. For example, at the Palisades Station, the current limiting control room habitability analysis allows for 25 cfm unfiltered in-leakage through its normal outside air intake louvered isolation dampers during emergency mode into the control room envelope. This leakage value was not thought to be achievable with the existing as-built configuration. Repairing the system was considered a potential solution; however, this would be costly and could negatively affect plant operation. In addition, the system would still be required to meet the low specified unfiltered in-leakage. An alternate approach was to review the analysis and reassess the most important parameters. The key effort was to determine the atmospheric dispersion factors (χ/Qs) through wind tunnel tests using scale models of the stations. The results of the wind tunnel testing could yield more realistic χ/Qs for control room habitability than previously employed methods. The wind tunnel study options were selected based on their ease of implementation, realistic results, and low cost. More importantly, the results of the studies would allow more realistic values of unfiltered inleakage

  7. Discussion on control room habitability assessment

    International Nuclear Information System (INIS)

    Li Bing; Chen Yingying; Xiao Jun; Yang Duanjie; Cui Hao

    2014-01-01

    The discussion on control room envelope integrity, source term analysis in habitability assessments and other impact factors for dose consequence is provided combined with regulatory requirements and the current status of domestic NPPs. Considering that the infiltration is an important factor for control room habitability assessment, CRE integrity test should be performed to demonstrate the CRE's infiltration characteristics. The consequence assessment should be performed based on different DBAs and different pathways, such as pathways internal to the plant. (authors)

  8. Control rooms in German nuclear power plants

    International Nuclear Information System (INIS)

    Hoffmann, E.

    1999-01-01

    The paper explains and illustrates the dissimilarity in design and equipment of control rooms in German NPPs, as well as a historical survey of the general principles and approaches applied in the evolution of control room technology, including backfitting activities. Experience obtained from daily operation as well training at the simulators is taken as a basis to formulate fundamental requirements for modification or novel design approaches. (orig./CB) [de

  9. Dose assessment method for control room habitability in accident condition in nuclear power plants

    International Nuclear Information System (INIS)

    Yang Dong; Tang Shaohua; Wang Jianhua

    2012-01-01

    Based on the NRC. technical requirements on NPP control room habitability assessment, and considering the characteristics of the improved second generation NPPs in China, this paper developed a complete dose assessment model for control room habitability. Contrasting to the existing model in China, this model is applicable for DBA and sever accident, and the short term atmospheric diffusion factor can be calculated using the combined wake mode. By considering the zoning of habitable area and the design characteristics of the ventilation system, the effects of un-filtrated air leakage from the building and the ventilation system on the assessment calculation can be considered. (authors)

  10. On the systems of automatic non-destructive control of NPP metallic structures

    International Nuclear Information System (INIS)

    Grebennik, V.S.; Lantukh, V.M.

    1980-01-01

    The main stages of developing automatic systems of non- destructive control (NC) of NPP metallic structures are pointed out. The main requirements for automatic NC systems are formulated. Recommendations on the use of the developed experimental automatic facilities for control of certain NPP components are given. It is noted that the present facilities may be used in the future in development of modular sets of non-destructive control systems [ru

  11. A HUMAN FACTORS META MODEL FOR U.S. NUCLEAR POWER PLANT CONTROL ROOM MODERNIZATION

    Energy Technology Data Exchange (ETDEWEB)

    Joe, Jeffrey C.

    2017-03-01

    Over the last several years, the United States (U.S.) Department of Energy (DOE) has sponsored human factors research and development (R&D) and human factors engineering (HFE) activities through its Light Water Reactor Sustainability (LWRS) program to modernize the main control rooms (MCR) of commercial nuclear power plants (NPP). Idaho National Laboratory (INL), in partnership with numerous commercial nuclear utilities, has conducted some of this R&D to enable the life extension of NPPs (i.e., provide the technical basis for the long-term reliability, productivity, safety, and security of U.S. NPPs). From these activities performed to date, a human factors meta model for U.S. NPP control room modernization can now be formulated. This paper discusses this emergent HFE meta model for NPP control room modernization, with the goal of providing an integrated high level roadmap and guidance on how to perform human factors R&D and HFE for those in the U.S. nuclear industry that are engaging in the process of upgrading their MCRs.

  12. Guidelines on ergonomic aspects of control rooms

    Science.gov (United States)

    Mitchell, C. M.; Bocast, A. K.; Stewart, L. J.

    1983-01-01

    The anthropometry, workstation design, and environmental design of control rooms are outlined. The automated interface and VDTs and displays and various modes of communication between the system and the human operator using VDTs are discussed. The man in the loop is examined, the single controller single task framework and multiple controller multiple tasks issues are considered.

  13. Control room habitability study: findings and recommendations

    International Nuclear Information System (INIS)

    Driscoll, J.W.

    1986-01-01

    The Advisory Committee on Reactor Safeguards (ACRS) has raised a number of concerns related to control room habitability and has recommended actions which they believe could alleviate these concerns. As a result of the ACRS's concerns, the US Nuclear Regulatory Commission's (NRC) Office of Nuclear Reactor Regulation (NRR) in conjunction with the Offices of Research and Inspection and Enforcement, and the NRC regional offices, embarked upon a program to reevaluate Control Room Habitability. Argonne National Laboratory was contracted by the NRC to perform a Control Room Habitability Study on twelve licensed power reactors. The plants selected for the study were chosen based upon architect engineer, nuclear steam system supplier, utility, and plant location. Participants in the study review the plant design as contained in the Updated Safety Analysis Report, Technical Specifications, Three Mile Island action item III.D.3.4 submittal on Control Room Habitability, NRC staff evaluation of the III.D.3.4 submittal, appropriate plant operating procedures, system drawings, and significant Licensee Event Reports on Loss of Cooling to the Control Room Envelope. A two-day visit is then made to the plant to determine if the as-built systems are built, operated, and surveillance performed as described in the documentation reviewed prior to the visit. The major findings of this study are included in this report along with generic recommendations of the review team that apply to control room HVAC systems. Although the study is not complete, at the time of publication of this report, the results obtained to date should be useful to persons responsible for Control Room Habitability in evaluating their own systems

  14. Configuration management and change control at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Gheorghiu, Virgil

    1998-01-01

    Effective configuration management requires that: 1. the design basis of station structures, systems, equipment and components be maintained at all times; 2. only accurate and approved technical, operational and maintenance information is available for performance of station activities; 3. correct operating manuals, flowsheets, operating sequences, operating task and training manuals are prepared and maintained currently. Design Engineering at Cernavoda NPP is primarily the responsibility of the Engineering Services Department supported if necessary by the Technical Unit. The key elements needed to achieve excellence in design engineering support for station operation, including design process and implementation of modification are investigated by answering the questions: 1. What is the station expectation for design change control?; 2. How is this provided?. Concerning design, the following aspects are stressed: Detailed Design Development; Design Verification; Design Change Implementation. The present design process is auditable and well documented. It consists of detailed design development, and design output documents such as applicable drawings, procurement specifications, installation and test requirement and the results of design and safety reviews. The design change implementation does not proceed until an Inspection Test Plan has been developed and approved as required. (author)

  15. Engineering Process Monitoring for Control Room Operation

    CERN Document Server

    Bätz, M

    2001-01-01

    A major challenge in process operation is to reduce costs and increase system efficiency whereas the complexity of automated process engineering, control and monitoring systems increases continuously. To cope with this challenge the design, implementation and operation of process monitoring systems for control room operation have to be treated as an ensemble. This is only possible if the engineering of the monitoring information is focused on the production objective and is lead in close collaboration of control room teams, exploitation personnel and process specialists. In this paper some principles for the engineering of monitoring information for control room operation are developed at the example of the exploitation of a particle accelerator at the European Laboratory for Nuclear Research (CERN).

  16. Control room habitability study - findings and recommendations

    International Nuclear Information System (INIS)

    Driscoll, J.W.

    1987-01-01

    The Advisory Committee on Reactor Safeguards (ACRS) has raised a number of concerns related to control room habitability and has recommended actions which they believe could alleviate these concerns. As a result of the ACRS's concerns, the US Nuclear Regulatory Commission's (NRC) Office of Nuclear Reactor Regulation (NRR) in conjunction with the Offices of Research and Inspection and Enforcement, and the NRC regional offices, embarked upon a program to reevaluate Control Room Habitability. Argonne National Laboratory was contracted by the NRC to perform a Control Room Habitability Study on twelve licensed power reactors. The plants selected for the study were chosen based upon architect engineer, nuclear steam system supplier, utility, and plant location. The major findings of this study are included in this report along with generic recommendations of the review team that apply to control room HVAC systems. Although the study is not complete, at the time of publication of this report, the results obtained to date should be useful to persons responsible for Control Room Habitability in evaluating their own systems

  17. Control room habitability system review models

    International Nuclear Information System (INIS)

    Gilpin, H.

    1990-12-01

    This report provides a method of calculating control room operator doses from postulated reactor accidents and chemical spills as part of the resolution of TMI Action Plan III.D.3.4. The computer codes contained in this report use source concentrations calculated by either TACT5, FPFP, or EXTRAN, and transport them via user-defined flow rates to the control room envelope. The codes compute doses to six organs from up to 150 radionuclides (or 1 toxic chemical) for time steps as short as one second. Supporting codes written in Clipper assist in data entry and manipulation, and graphically display the results of the FORTRAN calculations. 7 refs., 22 figs

  18. Use of control room simulators for training of nuclear power plant personnel

    International Nuclear Information System (INIS)

    2004-09-01

    Safety analysis and operational experience consistently indicate that human error is the greatest contributor to the risk of a severe accident in a nuclear power plant. Subsequent to the Three Mile Island accident, major changes were made internationally in reducing the potential for human error through improved procedures, information presentation, and training of operators. The use of full scope simulators in the training of operators is an essential element of these efforts to reduce human error. The operators today spend a large fraction of their time training and retraining on the simulator. As indicated in the IAEA Safety Guide on Recruitment, Qualification and Training of Personnel for Nuclear Power Plants, NS-G-2.8, 2002, representative simulator facilities should be used for training of control room operators and shift supervisors. Simulator training should incorporate normal, abnormal and accident conditions. The ability of the simulator to closely represent the actual conditions and environment that would be experienced in a real situation is critical to the value of the training received. The objective of this report is to provide nuclear power plant (NPP) managers, training centre managers and personnel involved with control room simulator training with practical information they can use to improve the performance of their personnel. While the emphasis in this publication is on simulator training of control room personnel using full scope simulators, information is also provided on how organizations have effectively used control room simulators for training of other NPP personnel, including simulators other than full-scope simulators

  19. Modern control room design experience and speculation

    International Nuclear Information System (INIS)

    Smith, J.E.

    1993-01-01

    Can operators trained to use conventional control panels readily adapt to CRT based control rooms? Does automation make the design of good man-machine interfaces more or less difficult? In a conventional, hard-wired control room is the operator's peripheral vision always an asset and how can one do better in a CRT based control room? Are Expert System assisted man-machine interfaces a boon or a bust? This paper explores these questions in the light of actual experience with advanced power plant control environments. This paper discusses how automation has in fact simplified the problem of ensuring that the operator has at all times a clear understanding of the plant state. The author contends that conventional hard-wired control rooms are very poor at providing the operator with a good overview of the plant status particularly under startup, or upset conditions and that CRT-based control rooms offer an opportunity for improvement. Experience with some early attempts at this are discussed together with some interesting proposals from other authors. Finally the paper discusses the experience to date with expert system assisted man-machine interfaces. Although promising for the future progress has been slow. The amount of knowledge research required is often formidable and consequently costly. Often when an adequate knowledge base is finally acquired it turns out to be better to use it to increase the level of automation and thus simplify the operator's task. The risks are not any greater and automation offers more consistent operation. It is important also to carefully distinguish between expert system assisted display selection and expert system operator guidance. The first is intended to help the operator in his quest for information. The second attempts to guide the operator actions. The good and the bad points of each of these approaches is discussed

  20. Design and Validation of Control Room Upgrades Using a Research Simulator Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Jeffrey C. Joe; Julius J. Persensky

    2012-11-01

    Since 1981, the United States (U.S.) Nuclear Regulatory Commission (NRC) [1] requires a plant- specific simulator facility for use in training at U.S. nuclear power plants (NPPs). These training simulators are in near constant use for training and qualification of licensed NPP operators. In the early 1980s, the Halden Man-Machine Laboratory (HAMMLab) at the Halden Reactor Project (HRP) in Norway first built perhaps the most well known set of research simulators. The HRP offered a high- fidelity simulator facility in which the simulator is functionally linked to a specific plant but in which the human-machine interface (HMI) may differ from that found in the plant. As such, HAMMLab incorporated more advanced digital instrumentation and controls (I&C) than the plant, thereby giving it considerable interface flexibility that researchers took full advantage of when designing and validating different ways to upgrade NPP control rooms. Several U.S. partners—the U.S. NRC, the Electrical Power Research Institute (EPRI), Sandia National Laboratories, and Idaho National Laboratory (INL) – as well as international members of the HRP, have been working with HRP to run control room simulator studies. These studies, which use crews from Scandinavian plants, are used to determine crew behavior in a variety of normal and off-normal plant operations. The findings have ultimately been used to guide safety considerations at plants and to inform advanced HMI design—both for the regulator and in industry. Given the desire to use U.S. crews of licensed operators on a simulator of a U.S. NPP, there is a clear need for a research simulator facility in the U.S. There is no general-purpose reconfigurable research oriented control room simulator facility in the U.S. that can be used for a variety of studies, including the design and validation of control room upgrades.

  1. Survey of licensee control room habitability practices

    International Nuclear Information System (INIS)

    Boland, J.F.; Brookshire, R.L.; Danielson, W.F.; Driscoll, J.W.; Graham, E.D.; McConnell, R.J.; Thompson, V.N.

    1985-04-01

    This document presents the results of a survey of Licensee control-room-habitability practices. The survey is part of a comprehensive program plan instituted in August 1983 by the NRC to respond to ongoing questions from the Advisory Committee on Reactor Safeguards (ACRS). The emphasis of this survey was to determine by field review the control-room habitability practices at three different plants, one of which is still under construction and scheduled to receive an operating license in 1986. The other two plants are currently operating, having received operating licenses in the mid-1970's and early 1980's. The major finding of this survey is that despite the fact that the latest control-room-habitability systems have become larger and more complex than earlier systems surveyed, the latest systems do not appear to be functionally superior. The major recommendation of this report is to consolidate into a single NRC document, based upon a comprehensive systems engineering approach, the pertinent criteria for control-room-habitability design

  2. Enhancing training in the main control room

    International Nuclear Information System (INIS)

    McGuigan, K.; O'Leary, K.; Canavan, K.

    2004-01-01

    In 2003 Pickering B Nuclear of Ontario Power Generation installed a Desktop Simulator (DTS) in the Main Control Room (MCR) for training purposes. This paper will outline why this training enhancement was undertaken and the approach taken to secure its use in an active MCR environment while minimizing distractions to plant operations. (author)

  3. Developing control room operator selection procedures

    International Nuclear Information System (INIS)

    Bosshardt, M.J.; Bownas, D.A.

    1979-01-01

    PDRI is performing a two-year study to identify the tasks performed and attributes required in electric power generating plant operating jobs, and focusing on the control room operator position. Approximately 65 investor-owned utilities are participating in the study

  4. Evaporation Controlled Emission in Ventilated Rooms

    DEFF Research Database (Denmark)

    Topp, Claus; Nielsen, Peter V.; Heiselberg, Per

    -scale ventilated room when the emission is fully or partly evaporation controlled. The objective of the present research work has been to investigate the change of emission rates from small-scale experiments to full-scale ventilated rooms and to investigate the influence of the local air velocity field near......Emission of volatile organic compounds (VOCs) from materials is traditionally determined from tests carried out in small-scale test chambers. However, a difference in scale may lead to a difference in the measured emission rate in a small-scale test chamber and the actual emission rate in a full...

  5. PS Main Control Room (partial view)

    CERN Multimedia

    1974-01-01

    Jean-Pierre Potier (turning buttons) and Bertran Frammery (telephoning) on shift. The 26 GeV Synchrotron and later also its related machines (Linacs 1,2,3; PS-Booster; LEP-Injector Linacs and Electron-Positron Accumulator; Antiproton Accumulator, Antiproton Collector, Low Energy Antiproton Ring and more recently Antiproton Decelerator) were all controlled from the PS control room situated on the Meyrin site. The SPS and LEP were controlled from a separat control centre on the Prevessin site. In 2005 all controls were transferred to the Prevessin centre.

  6. Turbine Control System Replacement at NPP NEK; System Specifics, Project Experience and Lessons Learned

    International Nuclear Information System (INIS)

    Mandic, D.; Zilavy, M. J.

    2010-01-01

    The main intention of this paper is to present feedback from the implementation of the new Turbine Control System (TCS) replacement project at Nuclear Power Plant (NPP) NEK - Krsko. From the plant construction time and the first plant start-up in 1981, the NPP NEK TG (Turbine-Generator) set was controlled and monitored by DEH (Digital Electro Hydraulic) Mod II Control System designed in 70's based on P2500 CPU and number of I/O controllers and modules. The P2500 CPU and associated controllers were built with discrete TTL components (TTL logic chips) and the P2500 CPU had 64k of 16 bit words of ferrite core memory. For that time, DEH Mod II had sophisticated MCR (Main Control Room) HMI (Human Machine Interface) based on digital functional keyboards, one alphanumeric black and white CRT monitor and printer. After twenty eight years of operation and because of several other reasons that are explained in the paper, NEK decided to replace the old DEH Mod II Control system with the new Emerson Ovation based DCS (Distributed Control System) on redundant platform for the control and monitoring of secondary plant systems in the NPP Krsko (NEK), and the new system was named PDEH (Programmable Digital Electro Hydraulic) TCS. In May 2007, NEK signed the turn-key contract with Westinghouse Electric Company (WEC) for the project of replacement of the TCS, Turbine Emergency Trip System (ETS), Moisture Separator Reheater (MSR) control and some other control and monitoring functions. WEC subcontracted a number of other companies for equipment delivery, AE (Architect Engineering Design) activities, specific software development tasks (changes of KFSS - Krsko Full Scope Simulator and PIS - Process Information System interface) and field installation activities. The subject project enveloped implementation of PDEH system on three application platforms: BG KFSS (Background KFSS), FG KFSS (Foreground KFSS) and PDEH system installed in the plant. The HMI for the BG KFSS platform

  7. Engineering Process Monitoring for Control Room Operation

    OpenAIRE

    Bätz, M

    2001-01-01

    A major challenge in process operation is to reduce costs and increase system efficiency whereas the complexity of automated process engineering, control and monitoring systems increases continuously. To cope with this challenge the design, implementation and operation of process monitoring systems for control room operation have to be treated as an ensemble. This is only possible if the engineering of the monitoring information is focused on the production objective and is lead in close coll...

  8. Current Approaches for Control Room I and C Modernization

    International Nuclear Information System (INIS)

    Lopez, Alberto; Jimenez, Alfonso

    2002-01-01

    In general, instrumentation and control (I and C) systems for nuclear power plants were made using analogic systems and relays, since this was the only technology available by the time these systems were designed. This fact impacts on the operational and maintenance capabilities required to these systems. For this reason, nuclear power plants are facing nowadays two challenges: on one hand, the obsolescence of these systems contributes to the increase in the operation and maintenance costs - due to the difficulties for getting spare parts and support from the system vendors -. On the other hand, there has been an increase in the utilities competitiveness due to the electric power market liberalization. All this, of course, along with the commitment to maintain the current safety levels and meet the new requirements and standards that may arise in the near future. The application of current technologies, especially digital technology, solves the obsolescence problems and allows for a more functional and updated human-machine interface. Nevertheless, the cost associated to these modifications makes it necessary to develop strategies to determine which systems need to be modified and how to implement modifications effectively, so that these systems can work jointly with others using different technologies. Other issues inherent to digital technology must be considered, such as verification and validation of the software and of the human-machine interface, which are required for its licensing. This presentation describes the current approaches for I and C modernization, the main reasons, technologies and implementation plans, focusing on the control room and on the impact on operations. The main issues to be considered for developing a specific modernization plan are analysed. The goals and status of the 'Feasibility Study of the Control Room I and C Modernization' are described. This study is currently being developed by Endesa, Iberdrola and Tecnatom, and is included

  9. A Business Case for Nuclear Plant Control Room Modernization

    International Nuclear Information System (INIS)

    Thomas, Ken; Lawrie, Sean; Niedermuller, Josef M.

    2016-01-01

    This paper presents a generic business case for implementation of technology that supports Control Room Modernization (CRM). The analysis presented in two forms; 1) a standalone technology upgrade, and 2) a technology upgrade that is built upon and incremental to a prior business case created for Mobile Work Packages (MWP). The business case contends that advanced communication and networking and analytical technologies will allow NPP to conduct control room operations with improved focus by reducing human factors and redundant manpower, and therefore operate with fewer errors. While some labor savings can be harvested in terms of overtime, the majority of savings are demonstrated as reduced time to take the plant off line and bring back on line in support of outages. The benefits are quantified to a rough order of magnitude that provides directional guidance to NPPs that are interested in developing a similar business case. This business case focuses on modernization of the operator control room and does not consider a complete overhaul and modernization of a plants instrument and control systems. While operators may be considering such an investment at their plants, the sizable capital investment required is not likely supported by a cost/benefit analysis alone. More likely, it is driven by obsolescence and reliability issues, and requires consideration of mechanical condition of plant systems, capital depreciation, financing, relicensing and overall viability of the plant asset over a 20-year horizon in a competitive market. Prior studies [REF] have indicated that such a modernization of plant I&C systems, alone or as part of a larger modernization effort, can yield very significant reductions in O&M costs. However, the depth of research and analysis required to develop a meaningful business case for a plant modernization effort is well beyond the scope of this study. While CRM as considered in this study can be easily integrated as part of grander plant

  10. A Business Case for Nuclear Plant Control Room Modernization

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, Ken [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lawrie, Sean [Idaho National Lab. (INL), Idaho Falls, ID (United States); Niedermuller, Josef M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-06-01

    This paper presents a generic business case for implementation of technology that supports Control Room Modernization (CRM). The analysis presented in two forms; 1) a standalone technology upgrade, and 2) a technology upgrade that is built upon and incremental to a prior business case created for Mobile Work Packages (MWP). The business case contends that advanced communication and networking and analytical technologies will allow NPP to conduct control room operations with improved focus by reducing human factors and redundant manpower, and therefore operate with fewer errors. While some labor savings can be harvested in terms of overtime, the majority of savings are demonstrated as reduced time to take the plant off line and bring back on line in support of outages. The benefits are quantified to a rough order of magnitude that provides directional guidance to NPPs that are interested in developing a similar business case. This business case focuses on modernization of the operator control room and does not consider a complete overhaul and modernization of a plants instrument and control systems. While operators may be considering such an investment at their plants, the sizable capital investment required is not likely supported by a cost/benefit analysis alone. More likely, it is driven by obsolescence and reliability issues, and requires consideration of mechanical condition of plant systems, capital depreciation, financing, relicensing and overall viability of the plant asset over a 20-year horizon in a competitive market. Prior studies [REF] have indicated that such a modernization of plant I&C systems, alone or as part of a larger modernization effort, can yield very significant reductions in O&M costs. However, the depth of research and analysis required to develop a meaningful business case for a plant modernization effort is well beyond the scope of this study. While CRM as considered in this study can be easily integrated as part of grander plant

  11. The role of the control room operator

    International Nuclear Information System (INIS)

    Williams, M.C.

    A control room operator at an Ontario Hydro nuclear power plant operates a reactor-turbine unit according to approved procedures within imposed constraints to meet the objectives of the organization. A number of operating and administrative tasks make up this role. Control room operators spend approximately six percent of their time physically operating equipment exclusive of upset conditions, and another one percent operating in upset conditions. Testing occupies five percent of an operator's time. Operators must be trained to recognize the entire spectrum of inputs available to them and use them all effectively. Any change in system or unit state is always made according to an approved procedure. Extensive training is required; operators must be taught and pracised in what to do, and must know the reasons behind their actions. They are expected to memorize emergency procedures, to know when to consult operating procedures, and to have sufficient understanding and practice to perform these procedures reliably

  12. Palo Verde receives new control room simulator

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    A new control room simulator was delivered to Arizona Public Service Company's Palo Verde nuclear generating station in late August. The system, the second simulator on site, will be used for training beginning in January 1994, said David C. Brown, manager of the simulator upgrade project. Having two simulators will ease the current tight training schedule, and allow expansion of instruction to personnel other than licensed operators

  13. White Paper for Virtual Control Room

    Science.gov (United States)

    Little, William; Tully-Hanson, Benjamin

    2015-01-01

    The Virtual Control Room (VCR) Proof of Concept (PoC) project is the result of an award given by the Fourth Annual NASA T&I Labs Challenge Project Call. This paper will outline the work done over the award period to build and enhance the capabilities of the Augmented/Virtual Reality (AVR) Lab at NASA's Kennedy Space Center (KSC) to create the VCR.

  14. Method for control-room display design

    International Nuclear Information System (INIS)

    Montmayeul, R.

    1988-01-01

    This document describes a method for control-room displays design. It can be used either for isolated display to add to an existing system either for the design of a full system of operator aids. The method is a top-down design with steps of possible iteration. The emphasis is put on display design rather than on system design; system aspects are just mentioned. Advantages of using a method are described [fr

  15. NRC study of control room habitability

    International Nuclear Information System (INIS)

    Hayes, J.J. Jr.; Muller, D.R.; Gammill, W.P.

    1985-01-01

    Since 1980, the Advisory Committee on Reactor Safeguards (ACRS) has held several meetings with the NRC staff to discuss the subject of control room habitability. Several meetings between the ACRS and the staff have resulted in ACRS letters that express specific concerns, and the staff has provided responses in reports and meetings. In June of 1983, the NRC Executive Director for Operations directed the Offices of Nuclear Reactor Regulation and Inspection and Enforcement to develop a plan to handle the issues raised by the ACRS and to report to him specific proposed courses of action to respond to the ACRS's concerns. The NRC control room habitability working group has reviewed the subject in such areas as NRR review process, transformation of control room habitability designs to as-built systems, and determination of testing protocol. The group has determined that many of the ACRS concerns and recommendations are well founded, and has recommended actions to be taken to address these as well as other concerns which were raised independent of the ACRS. The review has revealed significant areas where the approach presently utilized in reviews should be altered

  16. Recent Development in the ATLAS Control Room

    CERN Document Server

    Armen Vartapetian

    Only recently the name ATLAS Control Room (ACR) was more associated with the building at Point 1 (SCX1) than with the real thing. But just within the last several months, with the installation of the ACR hardware, that perception has changed significantly. The recently furnished ATLAS control room. But first of all, if you are not familiar with the ATLAS experimental site and are interested in visiting the ATLAS control room to see the place that in the near future will become the brain of the detector operations, it is quite easy to do so. You don't even need safety helmet or shoes! The ACR is located on the ground floor of a not so typical, glass-covered building in Point 1. The building number on the CERN map is 3162, or SCX1 as we call it. It is also easy to recognize that building by its shiny appearance within the cluster of Point 1 buildings if you are driving from Geneva. Final design and prototyping of the ACR hardware started at the beginning of 2006. Evaluation of the chosen hardware confi...

  17. Advanced tools for enhancing control room collaborations

    International Nuclear Information System (INIS)

    Abla, G.; Flanagan, S.M.; Peng, Q.; Burruss, J.R.; Schissel, D.P.

    2006-01-01

    The US National Fusion Collaboratory (NFC) project has been exploring a variety of computer and network technologies to develop a persistent, efficient, reliable and convenient collaborative environment for magnetic fusion research. One goal is to enhance remote and collocated team collaboration by integrating collaboration software tools into control room operations as well as with data analysis tools. To achieve this goal, the NFC recently introduced two new collaboration technologies into the DIII-D tokamak control room. The first technology is a high-resolution, large format Shared Display Wall (SDW). By creating a shared public display space and providing real time visual information about the multiple aspects of complex experiment activity, the large SDW plays an important role in increasing the rate of information dissemination and promoting interaction among team members. The second technology being implemented is the 'tokamak control room aware' Instant Messaging (IM) service. In addition to providing text-chat capabilities for research scientists, it enables them to automatically receive information about experiment operations and data analysis processes to remotely monitor the status of ongoing tokamak experiment. As a result, the IM service has become a unified portal interface for team collaboration and remote participation

  18. Advanced tools for enhancing control room collaborations

    Energy Technology Data Exchange (ETDEWEB)

    Abla, G. [General Atomics, P.O. Box 85608, San Diego, CA 92186 5608 (United States)]. E-mail: abla@fusion.gat.com; Flanagan, S.M. [General Atomics, P.O. Box 85608, San Diego, CA 92186 5608 (United States); Peng, Q. [General Atomics, P.O. Box 85608, San Diego, CA 92186 5608 (United States); Burruss, J.R. [General Atomics, P.O. Box 85608, San Diego, CA 92186 5608 (United States); Schissel, D.P. [General Atomics, P.O. Box 85608, San Diego, CA 92186 5608 (United States)

    2006-07-15

    The US National Fusion Collaboratory (NFC) project has been exploring a variety of computer and network technologies to develop a persistent, efficient, reliable and convenient collaborative environment for magnetic fusion research. One goal is to enhance remote and collocated team collaboration by integrating collaboration software tools into control room operations as well as with data analysis tools. To achieve this goal, the NFC recently introduced two new collaboration technologies into the DIII-D tokamak control room. The first technology is a high-resolution, large format Shared Display Wall (SDW). By creating a shared public display space and providing real time visual information about the multiple aspects of complex experiment activity, the large SDW plays an important role in increasing the rate of information dissemination and promoting interaction among team members. The second technology being implemented is the 'tokamak control room aware' Instant Messaging (IM) service. In addition to providing text-chat capabilities for research scientists, it enables them to automatically receive information about experiment operations and data analysis processes to remotely monitor the status of ongoing tokamak experiment. As a result, the IM service has become a unified portal interface for team collaboration and remote participation.

  19. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-04-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple “pathways,” or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  20. Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

    International Nuclear Information System (INIS)

    Kovesdi, Casey Robert; Joe, Jeffrey Clark

    2016-01-01

    The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple ''pathways,'' or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

  1. Skill retention and control room operator competency

    International Nuclear Information System (INIS)

    Stammers, R.B.

    1981-12-01

    The problem of skill retention in relation to the competency of control room operators is addressed. Although there are a number of related reviews of the literature, this particular topic has not been examined in detail before. The findings of these reviews are summarised and their implications for the area discussed. The limited research on skill retention in connection with process control is also reviewed. Some topics from cognitive and instructional psychology are also raised. In particular overlearning is tackled and the potential value of learning strategies is assessed. In conclusion the important topic of measurement of performance is introduced and a number of potentially valuable training approaches are outlined. (author)

  2. Future control room design (modernization of control room systems); Zukuenftiges Wartendesign (Modernisierung von Warteneinrichtungen)

    Energy Technology Data Exchange (ETDEWEB)

    Reischl, Ludwig; Freitag, Timo; Dergel, Rene [AREVA NP (Germany). NLLR-G ' ' Reactor I and C' '

    2009-07-01

    In the frame of lifetime extension for nuclear power plants the modernization of the complete safety and operational control technology will be digitalized. It is also recommended to modernize the operator facilities, monitoring systems in the control room, the back-up shut-down center and the local control stations. The authors summarize the reasons for the modernization recommendations and discuss possible solutions for display-oriented control rooms. A concept for control room backfitting includes generic requirements, requirements of the local authorities, ergonomic principles information content and information density, and the design process. The backfitting strategy should include a cooperation with the operational personnel, The quality assurance and training via simulator needs sufficient timing during the implementation of the backfitting.

  3. Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

    Energy Technology Data Exchange (ETDEWEB)

    Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I. [Research and Production Corporation Radiy, 29 Geroev Stalingrada Str., Kirovograd 25006 (Ukraine); Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A., E-mail: marketing@radiy.co [Center for Safety Infrastructure-Oriented Research and Analysis, 37 Astronomicheskaya Str., Kharkiv 61085 (Ukraine)

    2010-10-15

    The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY{sup TM} platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY{sup TM} platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY{sup TM} platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

  4. Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

    International Nuclear Information System (INIS)

    Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I.; Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A.

    2010-10-01

    The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY TM platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY TM platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY TM platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

  5. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    International Nuclear Information System (INIS)

    Yang, Chih Wei; Cheng, Tsung Chieh; Lin, Chiuhsiang Joe

    2011-01-01

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner

  6. Anthropometric Considerations in the Modernized Main Control Room: Application to a Virtual Nuclear Power Plant Control Panel

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih Wei; Cheng, Tsung Chieh [Institute of Nuclear Energy Research, Taoyuan (China); Lin, Chiuhsiang Joe [Chung-Yuan Christian University, Chung Li (China)

    2011-08-15

    This study investigates the anthropometric considerations in the main control room (MCR) application to a virtual nuclear power plant (NPP) control panel. Influences of working postures and physical demands on the operational performance are also discussed. Finally, the present research provides a case example to illustrate the influences of anthropometric considerations on the control panel design for MCR operators by applying virtual reality (VR) technology. The MCR design primarily evolved in different countries. The datasets available is usually insufficient or inconsistent for the end users. To solve the upper mentioned problem, this study put emphasis on applying VR technology to anthropometric considerations support control panel design in the modernized MCR. Although the concept of applying VR technology on anthropometric considerations in this paper is related to the MCR in NPPs, it could be easily applied for the purposes of any type of control room in a similar manner.

  7. Subjective task complexity in the control room

    International Nuclear Information System (INIS)

    Braarud, Per Oeivind

    2000-05-01

    Understanding of what makes a control room situation difficult to handle is important when studying operator performance, both with respect to prediction as well as improvement of the human performance. Previous exploratory work on complexity showed a potential for prediction and explanation of operator performance. This report investigates in further detail the theoretical background and the structure of operator rated task complexity. The report complements the previous work on complexity to make a basis for development of operator performance analysis tools. The first part of the report outlines an approach for studying the complexity of the control room crew's work. The approach draws upon man-machine research as well as problem solving research. The approach identifies five complexity-shaping components: 'task work characteristics', 'teamwork characteristics', 'individual skill', 'teamwork skill', and 'interface and support systems'. The crew's work complexity is related to concepts of human performance quality and human error. The second part of the report is a post-hoc exploratory analysis of four empirical HRP studies, where operators' conception of the complexity of control room work is assessed by questionnaires. The analysis deals with the structure of complexity questionnaire ratings, and the relationship between complexity ratings and human performance measures. The main findings from the analysis of structure was the identification of three task work factors which were named Masking, Information load and Temporal demand, and in addition the identification of one interface factor which was named Navigation. Post-hoc analysis suggests that operator's subjective complexity, which was assessed by questionnaires, is related to workload, task and system performance, and operator's self-rated performance. (Author). 28 refs., 47 tabs

  8. Evaluation of human factors in interface design in main control rooms

    International Nuclear Information System (INIS)

    Hwang, S.-L.; Liang, S.-F.M.; Liu, T.-Y.Y.; Yang, Y.-J.; Chen, P.-Y.; Chuang, C.-F.

    2009-01-01

    An evaluation of human factors in a new nuclear power plant was conducted prior to the beginning of any business operations. After the task analysis and observation of training, two stages of interviews were carried out with the operators in the Fourth Nuclear Power Plant (NPP4). The main concerns identified were problems resulting from the operating interface of the display and controls in the main control room, usability of procedures, and the layout of the main control room. The latent human errors and suggestions were listed, and the top three problems were analyzed. The operators indicated that the alarm design issues and the critical problem of the operating mode with the VDU were worth further study in order to provide suggestions for a new interface design for future power plants.

  9. Noble gas control room accident filtration system for severe accident conditions (N-CRAFT)

    International Nuclear Information System (INIS)

    Hill, Axel; Stiepani, Cristoph; Drechsler, Michael

    2015-01-01

    Severe accidents might cause the release of airborne radioactive substances to the environment of the NPP either due to containment leakages or due to intentional filtered containment venting. In the latter case aerosols and iodine are retained, however noble gases are not retainable by the FCVS or by conventional air filtration systems like HEPA filters and iodine absorbers. Radioactive noble gases nevertheless dominate the activity release depending on the venting procedure and the weather conditions. To prevent unacceptable contamination of the control room atmosphere by noble gases, AREVA GmbH has developed a noble gas control room accident filtration system (CRAFT) which can supply purified fresh air to the control room without time limitation. The retention process is based on dynamic adsorption of noble gases on activated carbon. The system consists of delay lines (carbon columns) which are operated by a continuous and simultaneous adsorption and desorption process. CRAFT allows minimization of the dose rate inside the control room and ensures low radiation exposure to the staff by maintaining the control room environment suitable for prolonged occupancy throughout the duration of the accident. CRAFT consists of a proven modular design either transportable or permanently installed. (author)

  10. Retrofitting of NPP Computer systems

    International Nuclear Information System (INIS)

    Pettersen, G.

    1994-01-01

    Retrofitting of nuclear power plant control rooms is a continuing process for most utilities. This involves introducing and/or extending computer-based solutions for surveillance and control as well as improving the human-computer interface. The paper describes typical requirements when retrofitting NPP process computer systems, and focuses on the activities of Institute for energieteknikk, OECD Halden Reactor project with respect to such retrofitting, using examples from actual delivery projects. In particular, a project carried out for Forsmarksverket in Sweden comprising upgrade of the operator system in the control rooms of units 1 and 2 is described. As many of the problems of retrofitting NPP process computer systems are similar to such work in other kinds of process industries, an example from a non-nuclear application area is also given

  11. Stress, performance, and control room operations

    International Nuclear Information System (INIS)

    Fontaine, C.W.

    1990-01-01

    The notion of control room operator performance being detrimentally affected by stress has long been the focus of considerable conjecture. It is important to gain a better understanding of the validity of this concern for the development of effective severe-accident management approaches. This paper illustrates the undeniable negative impact of stress on a wide variety of tasks. A computer-controlled simulated work environment was designed in which both male and female operators were closely monitored during the course of the study for both stress level (using the excretion of the urine catecholamines epinephrine and norepinephrine as an index) and job performance. The experimental parameters employed by the study when coupled with the subsequent statistical analyses of the results allow one to make some rather striking comments with respect to how a given operator might respond to a situation that he or she perceives to be psychologically stressful (whether the stress be externally or internally generated). The findings of this study clearly indicated that stress does impact operator performance on tasks similar in nature to those conducted by control room operators and hence should be seriously considered in the development of severe-accident management strategies

  12. Using the calculational simulating complexes when making the computer process control systems for NPP

    International Nuclear Information System (INIS)

    Zimakov, V.N.; Chernykh, V.P.

    1998-01-01

    The problems on creating calculational-simulating (CSC) and their application by developing the program and program-technical means for computer-aided process control systems at NPP are considered. The abo- ve complex is based on the all-mode real time mathematical model, functioning at a special complex of computerized means

  13. Cyber secure systems approach for NPP digital control systems

    Energy Technology Data Exchange (ETDEWEB)

    McCreary, T. J.; Hsu, A. [HF Controls Corporation, 16650 Westgrove Drive, Addison, TX 75001 (United States)

    2006-07-01

    an intruder attempting to disrupt network communications by entering the system from an attached utility network or utilizing a modem connected to a control system PC that is in turn connected to a publicly accessible phone; 2)Threat from a user connecting an unauthorized computer to the control network; 3)Threat from a security attack when an unauthorized user gains access to a PC connected to the plant network;. 4)Threat from internal disruption (by plant staff, whether, malicious or otherwise) by unauthorized usage of files or file handling media that opens the system to security threat (as typified in current situation in most control rooms). The plant I and C system cyber security design and the plant specific procedures should adequately demonstrate protection from the four pertinent classes of cyber security attacks. The combination of these features should demonstrate that the system is not vulnerable to any analyzed cyber security attacks either from internal sources or through network connections. The authors will provide configurations that will demonstrate the Cyber Security Zone. (authors)

  14. Cyber secure systems approach for NPP digital control systems

    International Nuclear Information System (INIS)

    McCreary, T. J.; Hsu, A.

    2006-01-01

    disrupt network communications by entering the system from an attached utility network or utilizing a modem connected to a control system PC that is in turn connected to a publicly accessible phone; 2)Threat from a user connecting an unauthorized computer to the control network; 3)Threat from a security attack when an unauthorized user gains access to a PC connected to the plant network;. 4)Threat from internal disruption (by plant staff, whether, malicious or otherwise) by unauthorized usage of files or file handling media that opens the system to security threat (as typified in current situation in most control rooms). The plant I and C system cyber security design and the plant specific procedures should adequately demonstrate protection from the four pertinent classes of cyber security attacks. The combination of these features should demonstrate that the system is not vulnerable to any analyzed cyber security attacks either from internal sources or through network connections. The authors will provide configurations that will demonstrate the Cyber Security Zone. (authors)

  15. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-02-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative—intended to catalog final products—rather than formative—intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  16. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-01-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative–intended to catalog final products–rather than formative–intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  17. [Controlling systems for operating room managers].

    Science.gov (United States)

    Schüpfer, G; Bauer, M; Scherzinger, B; Schleppers, A

    2005-08-01

    Management means developing, shaping and controlling of complex, productive and social systems. Therefore, operating room managers also need to develop basic skills in financial and managerial accounting as a basis for operative and strategic controlling which is an essential part of their work. A good measurement system should include financial and strategic concepts for market position, innovation performance, productivity, attractiveness, liquidity/cash flow and profitability. Since hospitals need to implement a strategy to reach their business objectives, the performance measurement system has to be individually adapted to the strategy of the hospital. In this respect the navigation system developed by Gälweiler is compared to the "balanced score card" system of Kaplan and Norton.

  18. Requirements for Control Room Computer-Based Procedures for use in Hybrid Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    Le Blanc, Katya Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States); Oxstrand, Johanna Helene [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-05-01

    Many plants in the U.S. are currently undergoing control room modernization. The main drivers for modernization are the aging and obsolescence of existing equipment, which typically results in a like-for-like replacement of analogue equipment with digital systems. However, the modernization efforts present an opportunity to employ advanced technology that would not only extend the life, but enhance the efficiency and cost competitiveness of nuclear power. Computer-based procedures (CBPs) are one example of near-term advanced technology that may provide enhanced efficiencies above and beyond like for like replacements of analog systems. Researchers in the LWRS program are investigating the benefits of advanced technologies such as CBPs, with the goal of assisting utilities in decision making during modernization projects. This report will describe the existing research on CBPs, discuss the unique issues related to using CBPs in hybrid control rooms (i.e., partially modernized analog control rooms), and define the requirements of CBPs for hybrid control rooms.

  19. Design of control rooms. Collaboration between different actors during the design of new and modernized control rooms

    International Nuclear Information System (INIS)

    Johansson, Bjoern J. E.; Gonzalez, Natalia

    2012-01-01

    Swedish nuclear power industry is currently undergoing, as well as planning, a number of upgrades of their control rooms. When changes are made to an NPP, they are conducted within the frame of a design process. The design process controls a number of different domains, such as technical solutions etc, but also affects and is affected by the interactions between Man, Technology and Organisation (MTO). MTO is central for creating safe system solutions. However, in the design process, unplanned events often occur in comparison to what was originally planned. This work aimed to analyse the design process and the involved actors' roles using activity theory with the purpose of creating an understanding of the design process. Activity theory can be seen as a way of understanding individuals and groups and the context they create by analysing the structure and process that their activities are part of. It can therefore be a good tool for analysing the complexity of the design process of a control room. The study has shown that many actors are involved in the design process and that all of them partly drive their own agendas, which may lead to contradictions within the design process. Important conclusions are that it perhaps not is necessary to eliminate all contradictions, but it is important to be aware of them. It is considered, among the informants in the study, that a working communication exists between the actors in the design process, but it is also evident that there is no given method for this, something that also counts for MTO-questions and the communication regarding those. A number of recommendations on how to support the communication process are given. Although there were some difficulties in using activity theory, it is believed that it could be useful for creating an overview of the design process and its actors from different organisations. Activity networks could be bound together in different ways and this provided opportunities to identify possible

  20. A HUMAN AUTOMATION INTERACTION CONCEPT FOR A SMALL MODULAR REACTOR CONTROL ROOM

    Energy Technology Data Exchange (ETDEWEB)

    Le Blanc, Katya; Spielman, Zach; Hill, Rachael

    2017-06-01

    Many advanced nuclear power plant (NPP) designs incorporate higher degrees of automation than the existing fleet of NPPs. Automation is being introduced or proposed in NPPs through a wide variety of systems and technologies, such as advanced displays, computer-based procedures, advanced alarm systems, and computerized operator support systems. Additionally, many new reactor concepts, both full scale and small modular reactors, are proposing increased automation and reduced staffing as part of their concept of operations. However, research consistently finds that there is a fundamental tradeoff between system performance with increased automation and reduced human performance. There is a need to address the question of how to achieve high performance and efficiency of high levels of automation without degrading human performance. One example of a new NPP concept that will utilize greater degrees of automation is the SMR concept from NuScale Power. The NuScale Power design requires 12 modular units to be operated in one single control room, which leads to a need for higher degrees of automation in the control room. Idaho National Laboratory (INL) researchers and NuScale Power human factors and operations staff are working on a collaborative project to address the human performance challenges of increased automation and to determine the principles that lead to optimal performance in highly automated systems. This paper will describe this concept in detail and will describe an experimental test of the concept. The benefits and challenges of the approach will be discussed.

  1. Human Factors methods concerning integrated validation of nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Oskarsson, Per-Anders; Johansson, Bjoern J.E.; Gonzalez, Natalia

    2010-02-01

    The frame of reference for this work was existing recommendations and instructions from the NPP area, experiences from the review of the Turbic Validation and experiences from system validations performed at the Swedish Armed Forces, e.g. concerning military control rooms and fighter pilots. These enterprises are characterized by complex systems in extreme environments, often with high risks, where human error can lead to serious consequences. A focus group has been performed with representatives responsible for Human Factors issues from all Swedish NPP:s. The questions that were discussed were, among other things, for whom an integrated validation (IV) is performed and its purpose, what should be included in an IV, the comparison with baseline measures, the design process, the role of SSM, which methods of measurement should be used, and how the methods are affected of changes in the control room. The report brings different questions to discussion concerning the validation process. Supplementary methods of measurement for integrated validation are discussed, e.g. dynamic, psychophysiological, and qualitative methods for identification of problems. Supplementary methods for statistical analysis are presented. The study points out a number of deficiencies in the validation process, e.g. the need of common guidelines for validation and design, criteria for different types of measurements, clarification of the role of SSM, and recommendations for the responsibility of external participants in the validation process. The authors propose 12 measures for taking care of the identified problems

  2. Human Factors methods concerning integrated validation of nuclear power plant control rooms; Metodutveckling foer integrerad validering

    Energy Technology Data Exchange (ETDEWEB)

    Oskarsson, Per-Anders; Johansson, Bjoern J.E.; Gonzalez, Natalia (Swedish Defence Research Agency, Information Systems, Linkoeping (Sweden))

    2010-02-15

    The frame of reference for this work was existing recommendations and instructions from the NPP area, experiences from the review of the Turbic Validation and experiences from system validations performed at the Swedish Armed Forces, e.g. concerning military control rooms and fighter pilots. These enterprises are characterized by complex systems in extreme environments, often with high risks, where human error can lead to serious consequences. A focus group has been performed with representatives responsible for Human Factors issues from all Swedish NPP:s. The questions that were discussed were, among other things, for whom an integrated validation (IV) is performed and its purpose, what should be included in an IV, the comparison with baseline measures, the design process, the role of SSM, which methods of measurement should be used, and how the methods are affected of changes in the control room. The report brings different questions to discussion concerning the validation process. Supplementary methods of measurement for integrated validation are discussed, e.g. dynamic, psychophysiological, and qualitative methods for identification of problems. Supplementary methods for statistical analysis are presented. The study points out a number of deficiencies in the validation process, e.g. the need of common guidelines for validation and design, criteria for different types of measurements, clarification of the role of SSM, and recommendations for the responsibility of external participants in the validation process. The authors propose 12 measures for taking care of the identified problems

  3. Human-system interface evaluation system for advanced control room based on SQL database

    International Nuclear Information System (INIS)

    Zhang Yan; Zhou Zhiwei; Bian Zhiqiang; Xu Li

    2005-01-01

    User Interface (UI) plays an important role in the advanced control room (ACR) of a nuclear power plant (NPP). In this paper, we present a rule-based ACR Human-system Interface Evaluation System (AHSIES) using expert system technology, which can evaluate UI design shortcomings, propose modification suggestions, and help designer improve the ACR interface design. AHSIES consists of four programs: the UI Editor, the Operation Procedure Manager, the Operation Simulator and the UI Design Evaluator. These four parts respectively function for: editing a set of UI icons employed as the operation screens of an advanced control room; for editing operation procedures aiming at any specified operation with simple language; for simulate the operation sequences dynamically and recording the relevant information for design performance of the UIs; and for evaluating both static and dynamic performance of the ACR UI design according to well established design guidelines and criteria with the information gained from the first three programs. Microsoft SQL Server 2000 DBMS is adopted to manage the voluminous data and its complex relationships. The preliminary test application of AHSIES for a simplified ACR UI design of a PWR NPP has shown that the expert evaluation system is capable of achieving satisfactory evaluation results. (authors)

  4. Considerations concerning the ergonomics of power plant control rooms

    International Nuclear Information System (INIS)

    Herbst, L.; Hinz, W.

    1981-01-01

    Modern control rooms for the monitoring and control of large power plants have a high degree of automation. However, it is the responsibility of the control room personnel to ensure optimum process control during all operational states. The proper ergonomic design of a control room is one of the prerequisites to ensure that the operators are able to perceive the often large flow of current information and, after processing, to respond properly. (orig.) [de

  5. Information presentation in power plant control rooms

    International Nuclear Information System (INIS)

    Kautto, A.

    1984-11-01

    The objective of this study is to support operators' work especially in the control rooms of power plant. The exemplified process is a pressurized water (nuclear) reactor (PWR). The man-process interface is an information system that covers information refining, information presentation, information system handling, and process control. THe emphasis in this study is on the organization and presentation of information and on the alert function that is part of the information system. Another goal is to design the alert function so as to radically reduce the number of alarms during plant shutdown, e.g. during the refuelling or maintenance period and during a disturbance. Further, the experimental validation of CFMS (Critical Function Monitoring System), developed by Combustion Engineering, Inc. in the U.S.A. is described briefly. The validation was made at the Loviisa training simulator in the autumn of 1982. CFMS is a safety-related functional alarm system. The functional decomposition of information has turned out to be successful and it is helpful in designing displays. Preliminary criteria for designing displays, the structure of the information presentation system and the illustration of main interactions are presented. General practical ideas on designing the alert function seem very promising. Preliminary results of the CFMS validation are presented. Further, some ideas are presented on how to carry out the analysis and how to make such validations in the future. A new idea for the evaluation of core safety is presented, based on control theory concepts

  6. Calculation of the effectiveness of manual control rods for the reactor of Ignalina NPP Unit 2

    International Nuclear Information System (INIS)

    Bubelis, E.; Pabarcius, R.

    2001-01-01

    On the basis of one of the recent databases of the reactor of Ignalina NPP Unit 2, calculations of the effectiveness of separate manual control rods, groups of manual control rods and axial characteristic of effectiveness of separate manual control rods were performed. The results of the calculations indicated, that all analyzed separate manual control rods have approximately the same effectiveness, which doesn't depend on the location of a control rod in the reactor core layout Manual control rod of the new design has about 10% greater effectiveness than manual control rod of the old design. (author)

  7. Psychological factors of professional success of nuclear power plant main control room operators

    Directory of Open Access Journals (Sweden)

    Kosenkov A.A.

    2014-12-01

    Full Text Available Aim: to conduct a comparative analysis of the psychological characteristics of the most and least successful main control room operators. Material and Methods. Two NPP staff groups: the most and least successful main control room operators, who worked in routine operating conditions, were surveyed. Expert evaluation method has been applied to identify the groups. The subjects were administered the Minnesota Multiphasic Personality Inventory (MMPI, Cattell's Sixteen Personality Factor Questionnaire (16PF form A and Raven's Progressive Matrices test. Results. Numerous significant psychological differences between the groups of most and least successful control room operators were obtained: the best operators were significantly more introverted and correctly solved more logical tasks with smaller percentage of mistakes under time pressure than worst ones. Conclusions: 1. The psychodiagnostic methods used in the study were adequate to meet research objective 2. Tendency to introversion, as well as developed the ability to solve logic problems undertime pressure, apparently, are important professional qualities for control room operators. These indicators should be considered in the process of psychological selection and professional guidance of nuclear power plant operators.

  8. Reliability Analysis on NPP's Safety-Related Control Module with Field Data

    International Nuclear Information System (INIS)

    Lee, Sang Yong; Jung, Jae Hyun; Kim, Seong Hun

    2006-01-01

    The automatic control systems used in nuclear power plant (NPP) consists of numerous control modules that can be considered to be a network of components various complex ways. The control modules require relatively high reliability than industrial electronic products. Reliability prediction provides the rational basis of system designs and also provides the safety significance of system operations. The aim of this paper is to minimize the deficiencies of the traditional reliability prediction method calculation using the available field return data. This way is possible to do more realistic reliability assessment. SAMCHANG Enterprise Company (SEC) has established database containing high quality data at the module and component level from module maintenance in NPP. On the basis of these, this paper compares results that add failure record (field data) to Telcordia-SR-332 reliability prediction model with MIL-HDBK-217F prediction results

  9. The Investigation of NPP Control and Monitoring Functional Analysis Applied to Functional Displays’ Implementation

    International Nuclear Information System (INIS)

    Yan, J.

    2015-01-01

    NPP Control and Monitoring System has been recognised as extreme and safe as well as large scale product, thus it was one of the most major design activities that fully, accurately and operationally functional analysis. The results of functional analysis would be employed as initial instruction through the whole lifecycle of NPP Control and Monitoring System. In this paper, it was discovered that several disadvantages of present functional analysis methods included FAST, The Subtract and Operate Procedure and Functional Procedure Method; owing to the identity methods enveloped here was the combination of Functional Tree and System Structure, as well as its decomposition steps; and RCS Inventory Control function which is defined as one of the most significant control functions in Advanced Light Water Reactor Utility Requirement Document has been employed to demonstrate the feasibility of this method; the analysis results of RCS Inventory function has been applied to direct the design and implementation of related displays, here the functional display of RCS Inventory Control function has been implemented on NuCON which is originated by SNPAS. Owing to the analyzing results, it would be ensured that the accuracy of information displayed to operators, thus the operator would be aware the condition of systems and then make the proper move to ensure the safety and productivity of NPP based on the received data. (author)

  10. NPP life management (abstracts)

    International Nuclear Information System (INIS)

    Litvinskij, L.L.; Barbashev, S.V.

    2002-01-01

    Abstracts of the papers presented at the International conference of the Ukrainian Nuclear Society 'NPP Life Management'. The following problems are considered: modernization of the NPP; NPP life management; waste and spent nuclear fuel management; decommissioning issues; control systems (including radiation and ecological control systems); information and control systems; legal and regulatory framework. State nuclear regulatory control; PR in nuclear power; training of personnel; economics of nuclear power engineering

  11. Pilot exemption of the controlled area from regulatory control at NPP A1 -lessons learned

    International Nuclear Information System (INIS)

    Slaninka, A.; Listjak, M.; Slavik, O.; Rau, L.

    2014-01-01

    The contribution includes the lessons learned within frame of the radiological characterisation of surface ground layer in the NPP A1 site of area approximately 60 m2 (9 x 7 m) that was a part of Controlled area. Aim of the characterisation was a demonstration that the area fulfils the requirements to exemption from Controlled area for purpose of decommissioning activities carry out within frame of II. stage of NPP A1 decommissioning project.The requirements on free release of materials into the environment were applied (e.g. 300 Bq/kg for single 137 Cs). Radiological characterisation was performed by two independent methods; in situ scintillation gamma spectrometry and systematic sampling in regular grid followed by gamma spectrometry analyses in accredited laboratory of VUJE, Inc. (S-219). This improved the quality of monitoring and at the same time it enabled the inter-comparison of results obtained by both mentioned independent methods.Characterised ground area was partitioned to smaller sub-areas of 4 m2. At ground layer of 20 cm it means approximately 1000 kg of ground (in compliance with requirements on reference area at even activity distribution according to government regulation No 345/2006) The results of measurements showed that under appropriate conditions (sufficiently low radiation background, on interfering external sources) also the designed in situ method is effective and reliable tool for contaminated ground layer identification. In addition the in situ method is more effective in terms of time and cost consumption on unit of monitored area. (authors)

  12. Creys-Malville control room and data processing

    International Nuclear Information System (INIS)

    Decuyper, J.

    1984-01-01

    After a brief definition of the control of a plant, this article presents the Creys-Malville control room: control means display and considerations on ergonomy and specific features in respect of the PWR control room. The Creys-Malville data processing is then rapidly presented with a brief description, the different data treatments and the specificity of the centralised data computer [fr

  13. Human reliability analysis of control room operators

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Isaac J.A.L.; Carvalho, Paulo Victor R.; Grecco, Claudio H.S. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)

    2005-07-01

    Human reliability is the probability that a person correctly performs some system required action in a required time period and performs no extraneous action that can degrade the system Human reliability analysis (HRA) is the analysis, prediction and evaluation of work-oriented human performance using some indices as human error likelihood and probability of task accomplishment. Significant progress has been made in the HRA field during the last years, mainly in nuclear area. Some first-generation HRA methods were developed, as THERP (Technique for human error rate prediction). Now, an array of called second-generation methods are emerging as alternatives, for instance ATHEANA (A Technique for human event analysis). The ergonomics approach has as tool the ergonomic work analysis. It focus on the study of operator's activities in physical and mental form, considering at the same time the observed characteristics of operator and the elements of the work environment as they are presented to and perceived by the operators. The aim of this paper is to propose a methodology to analyze the human reliability of the operators of industrial plant control room, using a framework that includes the approach used by ATHEANA, THERP and the work ergonomics analysis. (author)

  14. Replacement of the complete control system of the NPP Oskarshamn 1 by digital distributed control system

    International Nuclear Information System (INIS)

    Berger, E.

    1998-01-01

    As part of an ongoing modernization program, Oskarshamn 1's I and C system and control room will be upgraded by ABB using its Advant Power range of digital, programmable process control system. Besides ensuring the higher level of safety that is demanded today, the new equipment provides the plant with an integrated system which will improve operator overview of operation and reduce risk of human error and serve as a platform for further improvements of the control room. This paper discusses in the example of Oskarshamn 1 how the complete control system of a nuclear power plant may be exchanged, the technical solution and the time schedule. Oskarshamn 1 is the first nuclear power plant in Sweden. It is a boiling water reactor built by ABB ATOM in Sweden between 1966 and 1971. According to this age the control system is semiconductor based and the reactor protection system is relays based. This makes the maintenance expensive and extensions nearly impossible. To extend the life period of this plant the owner has decided to improve the safety system and to replace the reactor protection system and safety related control and the non safety related control by a state of the art digital distributed control system of ABB. In March 1997 ABB got the order to replace the reactor protection system, the safety control system, to start the replacement of all control systems and to replace the old control room by a new ergonomically designed control room. Together with the exchange of the control system an enhancement of the safety system and of the emergency power supply will be implemented

  15. Innovative approach to implementation of FPGA-based NPP instrumentation and control systems

    International Nuclear Information System (INIS)

    Andrashov, Anton; Kharchenko, Vyacheslav; Sklyar, Volodymir; Siora, Alexander

    2011-01-01

    Advantages of application of Field Programmable Gates Arrays (FPGA) technology for implementation of Instrumentation and Control (I and C) systems for Nuclear Power Plants (NPP) are outlined. Specific features of FPGA technology in the context of cyber security threats for NPPs I and C systems are analyzed. Description of FPGA-based platform used for implementation of different safety I and C systems for NPPs is presented. Typical architecture of NPPs safety I and C system based on the platform, as well as approach to implementation of I and C systems using FPGA-based platform are discussed. Data on implementation experience of application of the platform for NPP safety I and C systems modernization projects are finalizing the paper. (author)

  16. Innovative Approach to Implementation of FPGA-based NPP Instrumentation and Control Systems

    International Nuclear Information System (INIS)

    Andrashov, Anton; Kharchenko, Vyacheslav; Sklyar, Volodymir; SIORA Alexander

    2011-01-01

    Advantages of application of Field Programmable Gates Arrays (FPGA) technology for implementation of Instrumentation and Control (I and C) systems for Nuclear Power Plants (NPP) are outlined. Specific features of FPGA technology in the context of cyber security threats for NPPs I and C systems are analyzed. Description of FPGA-based platform used for implementation of different safety I and C systems for NPPs is presented. Typical architecture of NPPs safety I and C system based on the platform, as well as approach to implementation of I and C systems using FPGA-based platform are discussed. Data on implementation experience of application of the platform for NPP safety I and C systems modernization projects are finalizing the paper

  17. Innovative Approach to Implementation of FPGA-based NPP Instrumentation and Control Systems

    Energy Technology Data Exchange (ETDEWEB)

    Andrashov, Anton; Kharchenko, Vyacheslav; Sklyar, Volodymir [Centre for Safety Infrastructure-Oriented Research and Analysis, Kharkov (Ukraine); SIORA Alexander [Research and Production Corporation Radiy, Kirovograd (Ukraine)

    2011-08-15

    Advantages of application of Field Programmable Gates Arrays (FPGA) technology for implementation of Instrumentation and Control (I and C) systems for Nuclear Power Plants (NPP) are outlined. Specific features of FPGA technology in the context of cyber security threats for NPPs I and C systems are analyzed. Description of FPGA-based platform used for implementation of different safety I and C systems for NPPs is presented. Typical architecture of NPPs safety I and C system based on the platform, as well as approach to implementation of I and C systems using FPGA-based platform are discussed. Data on implementation experience of application of the platform for NPP safety I and C systems modernization projects are finalizing the paper.

  18. Systematic elicitation of cyber-security controls for NPP I and C system

    Energy Technology Data Exchange (ETDEWEB)

    Lee, M. S.; Kim, T. H. [Formal Works Inc., Seoul (Korea, Republic of); Park, S. P. [AhnLab Inc., Seongnam (Korea, Republic of); Kim, Y. M. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    Cyber-security implementation starts with a development of a cyber security plan considering characteristics of I and C system. In this paper, we describe a method that develops a cyber security plan for NPP I and C system. Especially, we propose a method for systematic elicitation of technical security controls that should be applied to I and C system. We expect that this study can provide a basis to develop a cyber-security plan for I and C system. Also, the study can contribute enhancing security to NPP I and C system. The rest of the paper is organized as follows: Section 2 introduces activities to develop a cyber-security plan and presents the result of each activity of the security plan. Section 3 concludes the paper. We proposed a method for systematic elicitation of security controls and described the method through examples. Development companies that want to implement cyber-security in I and C system can develop a cyber-security plan and apply the cyber-security program to their system according to our method. We expect that this study can provide a basis to develop a cyber-security plan for I and C system. Also, the study can contribute enhancing security to NPP I and C system.

  19. Systematic elicitation of cyber-security controls for NPP I and C system

    International Nuclear Information System (INIS)

    Lee, M. S.; Kim, T. H.; Park, S. P.; Kim, Y. M.

    2015-01-01

    Cyber-security implementation starts with a development of a cyber security plan considering characteristics of I and C system. In this paper, we describe a method that develops a cyber security plan for NPP I and C system. Especially, we propose a method for systematic elicitation of technical security controls that should be applied to I and C system. We expect that this study can provide a basis to develop a cyber-security plan for I and C system. Also, the study can contribute enhancing security to NPP I and C system. The rest of the paper is organized as follows: Section 2 introduces activities to develop a cyber-security plan and presents the result of each activity of the security plan. Section 3 concludes the paper. We proposed a method for systematic elicitation of security controls and described the method through examples. Development companies that want to implement cyber-security in I and C system can develop a cyber-security plan and apply the cyber-security program to their system according to our method. We expect that this study can provide a basis to develop a cyber-security plan for I and C system. Also, the study can contribute enhancing security to NPP I and C system

  20. Under-reactor Room 305/2 of the unit 4 of Chernobyl 1 NPP: its state, fuel quantity evaluation

    International Nuclear Information System (INIS)

    Borovoj, A.A.; Lagunenko, A.S.; Pazukhin, Eh.M.

    1997-01-01

    The question of the quantity of the used up nuclear fuel in the under-reactor room is discussed. These are given the results of direct visual observation, TV-records and photographing in this room and their connection with the date of chemical analysis of core samples and dose rate measurement. On the basis of these results the detailed model of relative petitioning of the main elements in the volume space of the former active zone of the reactor is developed. The minimum quantity evaluation of nuclear fuel in the room 305/2 is given. 10 refs., 1 tab., 2 figs

  1. Digital control computer upgrade at the Cernavoda NPP simulator

    International Nuclear Information System (INIS)

    Ionescu, T.

    2006-01-01

    The Plant Process Computer equips some Nuclear Power Plants, like CANDU-600, with Centralized Control performed by an assembly of two computers known as Digital Control Computers (DCC) and working in parallel for safely driving of the plan at steady state and during normal maneuvers but also during abnormal transients when the plant is automatically steered to a safe state. The Centralized Control means both hardware and software with obligatory presence in the frame of the Full Scope Simulator and subject to changing its configuration with specific requirements during the plant and simulator life and covered by this subsection

  2. Operating experience of the automatic technological control system at the Kolsk NPP

    International Nuclear Information System (INIS)

    Volkov, A.P.; Ignatenko, E.I.; Kolomtsev, Yu.V.; Mel'nikov, E.F.; Trofimov, B.A.

    1981-01-01

    Briefly reviewed is operating experience of the automatic control systems of the kolsk NPP (KNPP) power units, where measuring technique of the neutron flux ''Iney'', ARM-4 power regulator, automatic turbine start-up system ATS are used. The main shortcomings of the technological process automatic control system (ACS) and ways of their removal are considered. It is noted that the KNPP ACS performs only limited start-up functions of the basic equipment and reactor power control as well as partially protection functions at instant loading drops and switch-off of the main circulating pump [ru

  3. Modernization of the Ukrainian NPP instrumentation and control systems

    International Nuclear Information System (INIS)

    Yastrebenetsky, M.

    1998-01-01

    Modernization of many instrumentation and control systems for all type of reactors is under way now in Ukraine. Main principles of modernization, standards that are used for modernization are described in the report. (author)

  4. Replacement of the complete control system of the NPP Oskarshamn 1 by digital distributed control system

    International Nuclear Information System (INIS)

    Berger, E.

    1998-01-01

    As part of an ongoing modernization program, the I and C system and the control room of Oskarshamn 1 will be upgraded by ABB using its 'Advant Power' range of digital, programmable process control system. Besides ensuring the higher level of safety that is demanded today, the new equipment provides the plant with an integrated system which will improve operator interaction with the plant and reduce the risk of human error. The newly installed DCS system will serve also as a platform for further improvements of the control room. This paper discusses Oskarshamn 1 exchange of the complete control system of a nuclear power plant, the technical solution and the time schedule. Oskarshamn 1 is the first nuclear power plant in Sweden. It is a boiling water reactor built between 1966 and 1971 by ABB ATOM in Sweden. According to the plant age the control system is relay-based, while instrumentation and analogue control is semiconductor-based. This makes maintenance expensive and even worse, makes extensions nearly impossible. According to the safety standards of the 1960s, there is no separation between safety and non safety control and no seismic qualification. To extend the life of this plant the owner has decided to improve the safety system as well as to replace the reactor protection system, the safety related control and the non safety related control by a state-of-the-art digital distributed control system from ABB. In March 1997, ABB got the order to replace the reactor protection system, the safety control system and to start the replacement of all control systems. The old control room has to be replaced by a new ergonomically design. Together with the exchange of the control system the safety features of the plant and the emergency power supply has to be extended. (author)

  5. Cernavoda NPP - Boiler and steam cycle chemistry control

    International Nuclear Information System (INIS)

    Zotica, D.

    2001-01-01

    Steam generators protection against corrosion and fouling is an ongoing issue for nuclear power plants. The true effectiveness of the secondary chemistry control program is best judged by the absence of secondary side corrosion related tube degradation particularly that leads to tube plugging or sleeving or tube support degradation. To continue striving for excellence in chemical control, the following issues should be considered: Continuous evaluation of the effectiveness of the chemistry control program in mitigating SG damage; Evaluation of plant compliance with the program; Laboratory quality assurance program to assure that laboratory analyses are accurate and reproductibile; Quality assurance program for on-line monitoring equipment to assure that results from this equipment are accurate. (R.P.)

  6. Control room habitability in Spanish Nuclear Power Plants

    International Nuclear Information System (INIS)

    Mediavilla, F.; Sierra, J. J.

    2007-01-01

    Since the NRC published in 2003 the Generic Letter 2003-01 Control room Habitability and the Regulatory guide 1.197 Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors, where it is emphasized the importance of verifying the control room habitability by means of alternative methods, Spanish Nuclear Power Plants are undertaking the different necessary activities to fulfill the requirements of the regulatory commission. This paper describes the main mechanisms included in NEI 99-03 Nuclear Energy Institute publication Control room Habitability Assessment guidance, to demonstrate and maintain Control room Habitability. In addition, in this article it Ds shown the theoretical principle of the test used to quantify air in-leakage in a control room envelope by using tracer gas techniques. The necessary activities to perform the initial in leakage testing are also put forward. Since 2006 Tecnatom, S. A. has performed the baseline testing in four Spanish Units, all of them with successful results. The rest of the Plants are scheduled to perform the tests during the second half of this year. Finally, this document summarises the more important aspects to be taken into account in the development of control room Habitability Programs, which are expected to ensure the integral maintenance of the Control room Envelope during the life a plant. (Author)

  7. A new main control room for the AGS complex

    International Nuclear Information System (INIS)

    Ingrassia, P.F.; Zaharatos, R.M.; Dyling, O.H.

    1991-01-01

    A new Main Control Room (MCR) has been built to control the accelerators of the AGS Complex. A new physical environment was produced to better control light, sound, temperature, and traffic. New control consoles were built around the work-stations that make up the distributed control system. Equipment placement within consoles and console placement within the room reflect attention to the ''human factors'' needs of the operator. 1 ref., 2 figs

  8. A new Main Control Room for the AGS complex

    International Nuclear Information System (INIS)

    Ingrassia, P.F.; Zaharatos, R.M.; Dyling, O.H.

    1991-01-01

    A new Main Control Room (MCR) has been built to control the accelerators of the AGS Complex. A new physical environment was produced to better control light, sound, temperature, and traffic. New control consoles were built around the work-stations that make up the distributed control system. Equipment placement within consoles and console placement within the room reflect attention to the 'human factors' needs of the operator

  9. Islamic Republic of Iran: Bushehr NPP. Project control. Annex 8

    International Nuclear Information System (INIS)

    Saboury

    1999-01-01

    This annex deals with project control. After almost 17 years of delay due to revolution and war, the work on BNPP-1 resumed. The new plant will be a combination of German and Russian designs and as such will present many unique technical and managerial problems. These will be accentuated by the fact that Iranian nuclear personnel are relatively young and inexperienced. In spite of hostile environmental conditions at the site, the equipment, structures and documentation have been relatively well presented. (author)

  10. Control room human engineering influences on operator performance

    International Nuclear Information System (INIS)

    Finlayson, F.C.

    1977-01-01

    Three general groups of factors influence operator performance in fulfilling their responsibilities in the control room: (1) control room and control system design, informational data displays (operator inputs) as well as control board design (for operator output); (2) operator characteristics, including those skills, mental, physical, and emotional qualities which are functions of operator selection, training, and motivation; (3) job performance guides, the prescribed operating procedures for normal and emergency operations. This paper presents some of the major results of an evaluation of the effect of human engineering on operator performance in the control room. Primary attention is given to discussion of control room and control system design influence on the operator. Brief observations on the influences of operator characteristics and job performance guides (operating procedures) on performance in the control room are also given. Under the objectives of the study, special emphasis was placed on the evaluation of the control room-operator relationships for severe emergency conditions in the power plant. Consequently, this presentation is restricted largely to material related to emergency conditions in the control room, though it is recognized that human engineering of control systems is of equal (or greater) importance for many other aspects of plant operation

  11. Overview of the LHD central control room data monitoring environment

    International Nuclear Information System (INIS)

    Emoto, M.; Yoshinuma, M.; Yoshida, M.; Nakanishi, H.; Iwata, C.; Ohsuna, M.; Nonomura, M.; Imazu, S.; Yokota, M.; Aoyagi, M.; Ogawa, H.; Ida, K.; Watanabe, K.; Kaneko, O.

    2016-01-01

    Highlights: • In this paper, the data monitoring environments in the LHD central control room, for example, summary data graph and video monitoring tools are introduced. Also, the environments for the remote participants are introduced. - Abstract: During the Large Helical Device (LHD) experiments, many scientists and technical staff are working in the central control room to operate the experiment. They must manage the diagnostics and controlling devices referring to the results of the last plasma shot. Also, the experiment coordinator must decide the conditions for the subsequent experiments using the results. Furthermore, many scientists are participating in the experiment from remote sites. Therefore, it is important to share the information in the control room quickly, such as the results of the last plasma discharge, with the remote user as well as with the staff in the room. In this paper, the data monitoring environment in the LHD central control room is introduced.

  12. Overview of the LHD central control room data monitoring environment

    Energy Technology Data Exchange (ETDEWEB)

    Emoto, M., E-mail: emoto.masahiko@nifs.ac.jp; Yoshinuma, M.; Yoshida, M.; Nakanishi, H.; Iwata, C.; Ohsuna, M.; Nonomura, M.; Imazu, S.; Yokota, M.; Aoyagi, M.; Ogawa, H.; Ida, K.; Watanabe, K.; Kaneko, O.

    2016-11-15

    Highlights: • In this paper, the data monitoring environments in the LHD central control room, for example, summary data graph and video monitoring tools are introduced. Also, the environments for the remote participants are introduced. - Abstract: During the Large Helical Device (LHD) experiments, many scientists and technical staff are working in the central control room to operate the experiment. They must manage the diagnostics and controlling devices referring to the results of the last plasma shot. Also, the experiment coordinator must decide the conditions for the subsequent experiments using the results. Furthermore, many scientists are participating in the experiment from remote sites. Therefore, it is important to share the information in the control room quickly, such as the results of the last plasma discharge, with the remote user as well as with the staff in the room. In this paper, the data monitoring environment in the LHD central control room is introduced.

  13. Development of a hardware-in- loop simulation platform for NPP main control systems

    Directory of Open Access Journals (Sweden)

    Liu Pengfei

    2017-01-01

    Full Text Available The simulation technology of the nuclear power plant are gradually applying to the nuclear power industry. However, most of the research on nuclear power plant simulation system only focus on pure computerized simulation at present, and it is difficult to fully display the characteristics of the simulating objects. In order to simulate the response characteristics of control system more really, a hardware-in-loop simulation platform of main control systems in the nuclear power plant has been developed in this paper. This simulation platform consists of thermal-hydraulic model, control and protection system model, physical DCS system and real-time interactive database. A physical industrial DCS system has been coupled to this platform to simulate the main control systems in the NPP, which makes the simulation result much closer to the actual control systems. The devoloped simulation platform has been validated by some steady and transient cases in this paper. This hardware-in-loop simulation platform can be used in the simulation and optimal design of NPP control systems. Furthermore, it can be used in the failure mode and effect analysis of the instrumentation and control systems in the nuclear power plant.

  14. Acoustic control of sodium leakage in valve gates of NPP

    International Nuclear Information System (INIS)

    Trykov, E.L.; Kovtun, S.N.; Anan'ev, A.A.; Yugov, S.I.

    2014-01-01

    Short description of sodium bench and acoustic investigation results on leakage monitoring of valves DN10 and DN40 are given. It is shown that acoustic method can be used successfully to control the leakages of sodium valves. Leakages on both type of valves increase the acoustic signal dispersion by 2-3 orders. For each type of valve acoustic system of leakage determination allows to conduct the preliminary graduation of signal dispersion on the sodium discharge rate. It make possible not only to record the leakage presence but also to determine the sodium discharge rate through the valve during the leakage [ru

  15. Control assembly ejection accident analysis for WWER-440 (Armenian NPP)

    International Nuclear Information System (INIS)

    Bznuni, S.; Malakyan, Ts.; Amirjanyan, A.; Ghasabyan, L.

    2007-01-01

    Control Assembly ejection in WWER-440 initiated by the loss of integrity of the Control Assemblies drive housing has been analyzed. This event causes a very rapid reactivity insertion to the core and small break LOCA which potentially could lead to rapid power increase and redistribution of heat release in the core resulting in a fuel, cladding and coolant temperature rise; primary pressure increase, radiological consequences due to loss of primary coolant and potential loss of cladding integrity and fuel disintegration (if applicable). Methodology of the analysis is based on conservative assumptions as well as on deterministic approach for selection of functioning logic of systems and equipment's to maximize reactor core power and minimize power decreasing reactivity feedback. Computational analyses were performed by 3D kinetics PARCS-RELAP coupled code. WWER-440 fuel cross-section libraries, diffusion coefficients and kinetics parameters were calculated by HELOS code. In this paper analysis of accident for Hot Full Power was presented. Results of analysis show that ANPP WWER-440 reactor design meets acceptance criteria prescribed for RIA type design based accidents (Authors)

  16. A remote control room at DIII-D

    International Nuclear Information System (INIS)

    Abla, G.; Schissel, D.P.; Penaflor, B.G.; Wallace, G.

    2008-01-01

    This paper describes a remote control room built at DIII-D to support remote participation activities of DIII-D research staff. In order to create a persistent, efficient, and reliable remote participation environment for DIII-D scientists, a remote control room has been built in a 640-ft 2 dedicated area. The purpose of this room is to experiment and define a remote control room framework that can facilitate the remote participation needs of current and future fusion experiments such as ITER. A variety of hardware equipment has been installed and several remote participation and collaboration technologies have been deployed. Objectivity and practical consideration has been the key while designing the room and deploying the technologies. Although, the DIII-D remote control room is still a work in progress and new software tools are being implemented, it has been already useful for a number of international remote participation activities. For example, it has been used for remote support of the EAST Tokamak in China during the start up operation and proven effective for other collaborative experiment activities. The description of the remote control room design is given along with technologies deployed for remote collaboration needs. We will also discuss our recent experiences involving the DIII-D remote control room as well as future plans for improvements

  17. Single room control for user-optimised room air conditions; Einzelraumregelung fuer nutzungsoptimiertes Raumklima

    Energy Technology Data Exchange (ETDEWEB)

    Lezius, A. [Staefa Control System GmbH, Leinfelden-Echterdingen (Germany)

    1995-12-31

    In chapter 14 of the anthology about building control the single room control for achieving user-optimised room air conditions is described. The following aspects are discussed: What is comfort? What is economic efficiency? Systems for secondary air treatment, adapted functions of the measurement and control technique, management functions, orientation of the demand at the use, investment and amortisation. (BWI) [Deutsch] Kapitel 14 des Sammelbandes ueber Building control ist dem Thema der Einzelraumregelung zur Erzielung eines nutzungsoptimierten Raumklimas gewidmet. In diesem Zusammenhang werden folgende Themenbereiche angesprochen: Was ist Komfort? Was ist Wirtschaftlichkeit? Systeme fuer sekundaere Luftbehandlung; Angepasste Funktionen der MSR-Technik; Managementfunktionen; Bedarfsorientierung an der Nutzung; Investition und Amortisation. (BWI)

  18. Control console of the gamma calibration room

    International Nuclear Information System (INIS)

    Vilchis P, A.E.; Romero G, M.

    1999-01-01

    The Nuclear Centre of Mexico has a Ionizing Radiation Metrology Center (CMRI). This is in charge of the calibration in Mexico and Latin America of equipment dedicated to radiation measurement as industrial, medical as other fields. The importance to ensure that the equipment stay justly calibrated, it is imposed the necessity of automating the different rooms which the CMRI has. in this case it will be exposed the Calibration room for gamma radiation type. The operation of this application was carried out with the LabVIEW development platform and also in C language. The hardware associated is: personal computer with two cards using the 8255 device, 16 channels with optical isolation to manage input/output TTL type, 16 channels with optical isolation to management of charges to 127 V a.c., and 2 channels for 90V d.c. motors. (Author)

  19. Belene NPP

    International Nuclear Information System (INIS)

    Tsvetanov, P.

    1990-01-01

    The book presents the main results of the studies of the Bulgarian Academy of Sciences (BAS) on the construction of a new nuclear power plant at Belene on the Danube river. The programme of the studies comprises five areas: the socio-economic and energy development and the necessity of the commissioning; a technical project and design level of the equipment (safety, radioactivity control, waste disposal and economic efficiency of the power plant); the seismic properties of the construction site; the corresponding risk and design features of the plant; the ecological impacts of the NPP and public opinion. The studies in the different areas have been carried out by independent teams, fully responsible for the formulated topical conclusions. The general opinion of the BAS voiced in the book is that the construction of Belene NPP is not sufficiently substantiated and is considered unacceptable. 94 refs., 53 fig., 56 tabs. (R.Ts.)

  20. Risk Assessment of the Main Control Room Fire Using Fire Simulations

    International Nuclear Information System (INIS)

    Kang, Dae Il; Kim, Kilyoo; Jang, Seung Cheol

    2013-01-01

    KAERI is performing a fire PSA for a reference plant, Ulchin Unit 3, as part of developing the Korean site risk profile (KSRP). Fire simulations of the MCR fire were conducted using the CFAST (Consolidated Fire Growth and Smoke Transport) model and FDS (fire dynamic simulator) to improve the uncertainty in the MCR fire risk analysis. Using the fire simulation results, the MCR abandonment risk was evaluated. Level 1 PSA (probabilistic safety assessment) results of Ulchin Unit 3 using the EPRI PRA (probabilistic risk assessment) implementation guide showed that the MCR (main control room) fire was the main contributor to the core damage frequency. Recently, U. S. NRC and EPRI developed NUREG/CR-6850 to provide state-of-the-art methods, tools, and data for the conduct of a fire PSA for a commercial NPP

  1. Development of Alarm System link Drawing for Operation Support for APR1400 Digital Main Control Room

    International Nuclear Information System (INIS)

    Kim, Ki-Hwan

    2016-01-01

    Digitalized MMI(Man-Machine Interface) including Digital Main Control Room(MCR) and digital I and C system was being applied for SKN 3 and 4 Nuclear Power Plant(NPP) and subsequent APR1400 NPP type. But, operators can not easily find instrument for alarm immediately. Therefore, Alarm system is required to easily find instrument for Alarm. For this implementation, we will plan system design considering design feature without affecting network load and CPU load. We have developed Alarm system link drawing for digital MCR. Operators of the digitalized MCR navigates from their consoles to the drawings related to the plant alarms and their instruments or the operation status. Such method gives cognitive load to the operators having to travel to different locations in finding the related information. Screen Sharing System, which is the fundamental technique for Drawing Interconnection Alarm System is close to completion, and it should be functionally tested and verified by the human factor engineering. For the actual application to the operating plants, the drawings to be interconnected to the alarms and the opinions from the operators/maintenance departments for designating alarm number should be surveyed, Also, another function that allows the access to the alarm related drawings not only from the MCR but also from the other offices

  2. Development of Alarm System link Drawing for Operation Support for APR1400 Digital Main Control Room

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki-Hwan [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    Digitalized MMI(Man-Machine Interface) including Digital Main Control Room(MCR) and digital I and C system was being applied for SKN 3 and 4 Nuclear Power Plant(NPP) and subsequent APR1400 NPP type. But, operators can not easily find instrument for alarm immediately. Therefore, Alarm system is required to easily find instrument for Alarm. For this implementation, we will plan system design considering design feature without affecting network load and CPU load. We have developed Alarm system link drawing for digital MCR. Operators of the digitalized MCR navigates from their consoles to the drawings related to the plant alarms and their instruments or the operation status. Such method gives cognitive load to the operators having to travel to different locations in finding the related information. Screen Sharing System, which is the fundamental technique for Drawing Interconnection Alarm System is close to completion, and it should be functionally tested and verified by the human factor engineering. For the actual application to the operating plants, the drawings to be interconnected to the alarms and the opinions from the operators/maintenance departments for designating alarm number should be surveyed, Also, another function that allows the access to the alarm related drawings not only from the MCR but also from the other offices.

  3. Multinodal control room envelope model used for habitability analysis

    International Nuclear Information System (INIS)

    Blumberg, W.M.; Gore, D.E.

    1995-01-01

    This work analyzes the habitability of the control room envelope (CRE) during an off-normal ventilation system condition. The most limiting design basis accident utilized for this analysis is the postulated loss-of-coolant accident. The off-normal condition assumes two rooms within the CRE are at pressures that are lower than adjoining rooms outside the CRE. This pressure differential allows unfiltered in-leakage to enter the CRE through the doors and penetrations in these rooms. This paper quantifies the maximum unfiltered in-leakage

  4. Gaining control room habitability margin at the Palisades Plant

    International Nuclear Information System (INIS)

    Harden, P.A.

    1993-01-01

    The bounding design-basis accident for control room habitability is the loss-of-coolant accident (LOCA). At Palisades, very little margin existed between the calculated control room operator thyroid dose and the 0.3-Sv (30-rem) limit of Standard Review Plan (SRP) 6.4. Also, a low rate of unfiltered air leakage into the control room during the emergency mode of operation, 5.5 x 10 -3 m 3 /s (11.6 ft 3 /min), was accounted for in the control room habitability analysis. The control room heating, ventilating and air-conditioning system at Palisades has louvered isolation dampers for the normal air intake that are exposed to a negative pressure. Considering the small margin to the thyroid dose limits and the leakage characteristics of louvered dampers, a low allowable rate of unfiltered air in-leakage raised some concern. A significant effort has been initiated to alleviate control room habitability concerns at Palisades. The first step in this effort was to evaluate the calculational models for control room habitability and gain margin through updated analytical methods. To accomplish this, a new radiological consequence analysis for the LOCA was completed

  5. Study on the power control system for NPP power unit with the WWER-440 reactor

    International Nuclear Information System (INIS)

    Aleksandrova, N.D.; Naumov, A.V.

    1981-01-01

    Results of model investigations into basic version of the power control systems (PCS) conformably to the WWER-440 NPP power unit are stated. Transient processes in the power unit system when being two PCS versions during perturbations of different parameters: unit power, vapour pressure or position of control rods have been simulated. Investigations into the different PCS versions show that quality of operation of a traditional scheme with a turbine power controller and reactor pressure controller can be significantly improved with the introduction of a high-speed signal of pressure into the reactor controller. The PCS version with the compensation of interrelations between the turbine and reactor controllers constructed according to the same principles as the standard schemes of power units of thermal electric power plant is perspective as well [ru

  6. Use of task analysis in control room evaluations

    International Nuclear Information System (INIS)

    Ross, K.C.

    1981-01-01

    Responding to recently formulated regulatory requirements, the BWR Owners' Group, working in conjunction with General Electric, has formulated a method for performing human factors design reviews of nuclear power plant control rooms. This process incorporates task analyses to analyze operational aspects of panel layout and design. Correlation of operator functions defined by emergency procedures against required controls and displays has proven successful in identifying instrumentation required in the control room to adequately respond to transient conditions, and in evaluating the effectiveness of panel design and physical arrangement. Extensions of the analysis have provided information on operator response paths, frequency of use of instruments, and control room layout. The techniques used were based on a need to identify primary controls and indications required by the operator in performing each step of the applicable procedure. The relative locations of these instruments were then analyzed for information on the adequacy of the control room design for those conditions

  7. HABIT, Toxic and Radioactive Release Hazards in Reactor Control Room

    International Nuclear Information System (INIS)

    Stage, S.A.

    2005-01-01

    1 - Description of program or function: HABIT is a package of computer codes designed to be used for the evaluation of control room habitability in the event of an accidental release of toxic chemicals or radioactive materials. 2 - Methods: Given information about the design of a nuclear power plant, a scenario for the release of toxic or radionuclides, and information about the air flows and protection systems of the control room, HABIT can be used to estimate the chemical exposure or radiological dose to control room personnel

  8. Preliminary considerations on safety of computerized control rooms

    International Nuclear Information System (INIS)

    Vittet, J.

    1983-02-01

    Safety problems are analyzed in this report by the study of the interaction: ''human behavior in a rigid environment/information overload in perturbed situation''. For pedagogy the study is presented as a research of factors influencing operator performance in a control room and a dialogue between an analyst and a conceiving engineer. Danger of all control room where the strategy for data acquisition is too rigid and without spatial reference is stressed in conclusion. Orientations for an advanced control room are outlined [fr

  9. Algorithmization of problems on the personnel information support in the automatic chemical control systems at NPP

    International Nuclear Information System (INIS)

    Vilkov, N.Ya.; Kryukov, Yu.V.; Cheshun, A.V.

    2001-01-01

    When elaborating software for the standard algorithms of the information support of the efficient control (keeping) of water chemistry operation (WCO) at the NPP power units one introduces an approach when the systems of chemical control are realized as the systems of quality control of in-loop physical and chemical processes gathering force in the course of time. Elaboration of algorithms to proceed data of the operational chemical control seeks for elaboration of the statistic procedures to detect anomalies of the processes at the early stages of their development more efficient in contrast to the standard procedures of control. The introduced procedure is used in the demonstration model of the system for diagnostics of some typical reasons of violation of the first circuit WCO of WWER-1000 power units [ru

  10. Control Room Habitability for Accidental Sulfuric Acid Release

    International Nuclear Information System (INIS)

    Cho, Sungmin; Lee, Heedo; Song, Dongsoo

    2006-01-01

    The 10 CFR 50 Appendix A Criterion 19, 'Control Room', requires that a control room be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions. For compliance with the requirement, the control room of a nuclear power plant should be appropriately protected from hazardous chemicals that may be discharged as a result of equipment failures, operator errors, or events and conditions outside the control of the nuclear power plant. We have excluded sulfuric acid from a target of estimation for control room habitability merely because its boiling point is too high; qualitative analysis in this paper shows that we can exclude sulfuric acid from the target of habitability estimation

  11. Design of a multisystem remote maintenance control room

    International Nuclear Information System (INIS)

    Draper, J.V.; Handel, S.J.; Kring, C.T.; Kawatsuma, S.

    1988-01-01

    The Remote Systems Development Section of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory (ORNL) and Japan's Power Reactor and Nuclear Fuel Development Corporation (PNC) recently collaborated in the development of a control room concept for remote operations. This report describes design methods and the resulting control room concept. The design project included five stages. The first was compilation of a complete function list; functions are tasks performed by operators in the control room while operating equipment located in the remote area. The second step was organization of the function list into ''function groups;'' function groups are sets of functions that operate one piece of equipment. The third stage was determination of crew size and requirements for supervision. The fourth stage was development of conceptual designs of displays and controls. The fifth stage was development of plans for placement of crew stations within the control room. 5 figs., 1 tab

  12. Using a Research Simulator for Validating Control Room Modernization Concepts

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Agarwal, Vivek; Persensky, Julius J.; Joe, Jeffrey C.

    2012-01-01

    The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the United States Department of Energy. The program is operated in close collaboration with industry research and development programs to provide the technical foundations for licensing and managing the long-term, safe, and economical operation of nuclear power plants that are currently in operation. Advanced instrumentation and control (I and C) technologies are needed to support the continued safe and reliable production of power from nuclear energy systems during sustained periods of operation up to and beyond their expected licensed lifetime. This requires that new capabilities to achieve process control be developed and eventually implemented in existing nuclear control rooms. It also requires that approaches be developed and proven to achieve sustainability of I and C systems throughout the period of extended operation. Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe life extension of current reactors. One of the main areas of focus is control room modernization. Current analog control rooms are growing obsolete, and it is difficult for utilities to maintain them. Using its reconfigurable control room simulator adapted from a training simulator, INL serves as a neutral test bed for implementing new control room system technologies and assisting in control room modernization efforts across. (author)

  13. Using a Research Simulator for Validating Control Room Modernization Concepts

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; Vivek Agarwal; Julius J. Persensky; Jeffrey C. Joe

    2012-05-01

    The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the United States Department of Energy. The program is operated in close collaboration with industry research and development programs to provide the technical foundations for licensing and managing the long-term, safe, and economical operation of nuclear power plants that are currently in operation. Advanced instrumentation and control (I&C) technologies are needed to support the continued safe and reliable production of power from nuclear energy systems during sustained periods of operation up to and beyond their expected licensed lifetime. This requires that new capabilities to achieve process control be developed and eventually implemented in existing nuclear control rooms. It also requires that approaches be developed and proven to achieve sustainability of I&C systems throughout the period of extended operation. Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe life extension of current reactors. One of the main areas of focus is control room modernization. Current analog control rooms are growing obsolete, and it is difficult for utilities to maintain them. Using its reconfigurable control room simulator adapted from a training simulator, INL serves as a neutral test bed for implementing new control room system technologies and assisting in control room modernization efforts across.

  14. Non-destructive control at the Kozloduy NPP; Nerazrushayushchij kontrol` v AEhS `Kozloduy`

    Energy Technology Data Exchange (ETDEWEB)

    Mikhovsky, M [Institute of Mechanics, Bulgarian Academy of Sciences, Sofia (Bulgaria); Skordev, A [SIME-CONTROL, Sofia (Bulgaria); Nichev, V; Tsokov, P; Popova, N [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1996-12-31

    A program for technical diagnostics using non-destructive methods is being carried out at the Kozloduy NPP. The main target is to test mechanical equipment integrity (metal control, mechanical stress control, etc.) as well as electrical equipment. Computer methods and simulation are widely used in program implementation. Non-destructive testing is based on methods involving optical, radiation, ultrasonic and magnetic processes. Control procedures are standardised in special technological documents and one of them is described as an example. It refers to ultrasonic control of the austenitic steel welds of the WWER-440 piping system (DU-500). Graphic representing the microstructure of the welds, the distribution of surface ultrasonic wave and the longitudinal and vertically polarised perpendicular waves are presented. 6 refs. 8 figs.

  15. Atmospheric diffusion model for control room habitability assessments

    International Nuclear Information System (INIS)

    Ramsdell, J.V.; Lee, J.Y.

    1993-01-01

    General Design Criterion 19 for nuclear power plants (Appendix A to 10CFR50) requires control room radiation protection adequate to limit radiation exposures to control room personnel. Murphy and Campe proposed the procedure currently used in evaluating control room habitability. However, data from building-wake diffusion experiments at nuclear power plants indicate that the Murphy-Campe procedure tends to overestimate concentrations, particularly during low wind speeds. This paper describes an alternative procedure developed by the Pacific Northwest Laboratory that is acceptable to U.S. Nuclear Regulatory Commission (NRC) staff. The procedure estimates control room air intake concentrations that are generally lower than those estimated by the Murphy-Campe procedure, yet are still conservative

  16. Virtual Training of Compressor Control Room, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — MYMIC will analyze, design, develop and evaluate the Virtual Control Room – Compressor Station (VCoR-CS) training system. VCoR-CS will provide procedural training to...

  17. Taking account of human factors in control-room design

    International Nuclear Information System (INIS)

    Dien, Y.; Montmayeul, R.

    1995-07-01

    Since the Three Mile Island accident two ways for improving the Human-Machine Interface have mainly been followed: the development of computerized operator aids in existing control-rooms and the design of advanced control-rooms. Insufficient attention paid to human factors in the design of operator aids has generally led to these aids being neglected or unused by their potential users. While for the design of advanced control-rooms efforts have been made for dealing with human factors in more extensive way. Based upon this experience, a general method for taking account of human factors in a control-room design has been devised and is described in this paper. (author)

  18. Human factors methods for nuclear control room design. Volume 2. Human factors survey of control room design practices

    International Nuclear Information System (INIS)

    Seminara, J.L.; Parsons, S.O.

    1979-11-01

    An earlier review of the control rooms of operating nuclear power plants identified many design problems having potential for degrading operator performance. As a result, the formal application of human factors principles was found to be needed. This report demonstrates the use of human factors in the design of power plant control rooms. The approaches shown in the report can be applied to operating power plants, as well as to those in the design stage. This study documents human factors techniques required to provide a sustained concern for the man-machine interface from control room concept definition to system implementation

  19. The application of human engineering in control room of HFETR

    International Nuclear Information System (INIS)

    Yang Shuchun; Shan Songlin

    2003-01-01

    The human-machine system for improving the working environment in the control room of HFETR is described. The reliability of the equipment, instruments and operation by human engineering is increased. The relations between human engineering and lowering human failure in HFETR are also discussed. It is concluded that the further application of human engineering can increase interaction of the human and machine in the control room and provide assurances for the safe and reliable operation of reactor. (authors)

  20. Responsibilities for control room design in the USA

    International Nuclear Information System (INIS)

    Leary, J.E.; Barnhart, C.G.

    1980-01-01

    In the design and construction of nuclear power plants in the United States, the architect-engineering firm usually serves as the principal co-ordinator for the various parties involved. Recent events such as the Three Mile Island accident have focused attention on operability and human factors engineering in the design of the control room. This article describes current trends in control room design and the division of responsibility between the plant owner, the reactor vendor, and the architect-engineer. (author)

  1. Control room concept for remote maintenance in high radiation areas

    International Nuclear Information System (INIS)

    Clarke, M.M.; Kreifeldt, J.G.

    1984-01-01

    This paper summarizes the design of a control room concept for an operator interface with remote maintenance equipment consisting of force-reflecting manipulators, tools, hoists, cranes, cameras, and lights. The design development involved two major activities. First, detailed requirements were defined for foreseeable functions that will be performed by the control room operators. Second, concepts were developed, tested, and refined to meet these requirements. Each of these activities is summarized below. 6 references, 3 figures

  2. Control room concept for remote maintenance in high radiation areas

    International Nuclear Information System (INIS)

    Clarke, M.M.; Kreifeldt, J.G.

    1984-01-01

    This paper summarizes the design of a control room concept for an operator interface with remote maintenance equipment consisting of force-reflecting manipulators, tools, hoists, cranes, cameras, and lights. The design development involved two major activities. First, detailed requirements were defined for foreseeable functions that will be performed by the control room operators. Second, concepts were developed, tested, and refined to meet these requirements. 6 references, 3 figures

  3. The application of human engineering in control room of HFETR

    Energy Technology Data Exchange (ETDEWEB)

    Shuchun, Yang; Songlin, Shan [Nuclear Power Inst. of China, Chengdu (China)

    2003-07-01

    The human-machine system for improving the working environment in the control room of HFETR is described. The reliability of the equipment, instruments and operation by human engineering is increased. The relations between human engineering and lowering human failure in HFETR are also discussed. It is concluded that the further application of human engineering can increase interaction of the human and machine in the control room and provide assurances for the safe and reliable operation of reactor. (authors)

  4. Wind tunnel testing to predict control room atmospheric dispersion factors

    International Nuclear Information System (INIS)

    Holmquist, L.J.; Harden, P.A.; Muraida, J.E.

    1993-01-01

    Recent concerns at Palisades about control room habitability in the event of a loss-of-coolant accident have led to an extensive effort to increase control room habitability margin. The heating, ventilating and air-conditioning (HVAC) system servicing the control room has the potential for unfiltered in-leakage through its normal outside air intake louvered isolation dampers during emergency mode. The current limiting control room habitability analysis allows for 1.2 x 10 -2 m 3 /s (25 ft 3 /min) unfiltered in-leakage into the control room envelope. This leakage value was not thought to be achievable with the existing as-built configuration. Repairing the system was considered as a potential solution; however, this would be costly and could negatively affect plant operation. In addition, the system would still be required to meet the low specified unfiltered in-leakage. A second approach to this problem was to determine the atmospheric dispersion factors (x/Q's) through a wind tunnel test using a scale model of Palisades. The results of the wind tunnel testing could yield more realistic x/Q's for control room habitability than previously employed methods. Palisades selected the wind tunnel study option based on its ease of implementation, realistic results, and low cost. More importantly, the results of the study could increase the allowable unfiltered in-leakage

  5. Control of the aerozol-gaseous effluents at the Novovoronezh NPP and study of the environmental impact

    International Nuclear Information System (INIS)

    Baranov, M.A.; Sedov, V.K.

    1981-01-01

    The system of dosimetric control of environment in the vicinity of the Novovoronezh NPP (NVNPP) is described. Annual values of gaseous- aerozol radioactive effluents (including their isotope composition) during the operation of the two NVNPP WWER-440 reactors since 1972 up to 1979 are presented. Concentrations of radioactive substances (total and separately by 30 Sr and 137 Cs isotopes) in the air as well as dose rates of the population in the control region of the NV NPP from 1965 up to 1979 are given. It is concluded that essential statistical material characterizing the environment state that testifies to the absence of harmful NPP effect on the environment objects and population is accumulated during 15 year NVNPP operation [ru

  6. Advanced display concepts in nuclear control rooms

    International Nuclear Information System (INIS)

    Clark, M.T.; Banks, W.W.; Blackman, H.S.; Gertman, D.I.

    1982-01-01

    Precursors necessary for the development of a full-scale predictor display/control system have been under development since the mid 1940's. The predictor display itself has been available for use in manual control systems since 1958. However, the nuclear industry has not yet explored the uses and benefits of predictor systems. The purpose of this paper is to provide information on the application of this technology to the nuclear industry. The possibility of employing a simulation-based control system for nuclear plant systems that currently use conventional auto/manual schemes is discussed. By employing simulation-based systems, a predictor display could be made available to the operator during manual operations, thus facilitating control without outwardly affecting the overall control scheme

  7. 75 FR 67450 - Pipeline Safety: Control Room Management Implementation Workshop

    Science.gov (United States)

    2010-11-02

    ... regulations to address human factors and other aspects of control room management for certain pipelines where controllers use supervisory control and data acquisition (SCADA) systems. Under the final rule, pipeline... Washington, DC on October 22, 2010. Jeffrey D. Wiese, Associate Administrator for Pipeline Safety. [FR Doc...

  8. Cognitive allocation and the control room

    International Nuclear Information System (INIS)

    Paradies, M.W.

    1985-01-01

    One of the weakest links in the design of nuclear power plants is the inattention to the needs and capabilities of the operators. This flaw causes decreased plant reliability and reduced plant safety. To solve this problem the designer must, in the earliest stages of the design process, consider the operator's abilities. After the system requirements have been established, the designer must consider what functions to allocate to each part of the system. The human must be considered as part of this system. The allocation of functions needs to consider not only the mechanical tasks to be performed, but also the control requirements and the overall control philosophy. In order for the designers to consider the control philosophy, they need to know what control decisions should be automated and what decisions should be made by an operator. They also need to know how these decisions will be implemented: by an operator or by automation. ''Cognitive Allocation'' is the allocation of the decision making process between operators and machines. It defines the operator's role in the system. When designing a power plant, a cognitive allocation starts the process of considering the operator's abilities. This is the first step to correcting the weakest link in the current plant design

  9. Operator reliability analysis during NPP small break LOCA

    International Nuclear Information System (INIS)

    Zhang Jiong; Chen Shenglin

    1990-01-01

    To assess the human factor characteristic of a NPP main control room (MCR) design, the MCR operator reliability during a small break LOCA is analyzed, and some approaches for improving the MCR operator reliability are proposed based on the analyzing results

  10. New technologies for a postaccident control room habitability assessment

    International Nuclear Information System (INIS)

    Lahti, G.P.; Perchiazzi, W.T.

    1993-01-01

    Older nuclear power plants typically considered only a nominal amount of unfiltered in-leakage (typically 10 ft 3 /min) affecting their postaccident habitability. However, recent measurements of unfiltered in-leakage show leakages in excess of the nominal 10 ft 3 /m in. The assessment of postaccident doses in control rooms is done in a number of well-defined steps: (1) Determine the initial release of radioactivity to the containment (the open-quotes source termclose quotes). (2) Determine the release of radioactivity to the environment. (3) Determine the atmospheric dispersion and the concentration at the control room air intake. (4) Determine within-building dilution (if any). (5) Determine unfiltered in-leakage. (6) Determine the concentration of radioactivity in the control room. (7) Determine the dose to control room occupants. The prescriptive methodology of the Murphy-Campe paper and Standard Review Plan (SRP) 6.4 has been used by the U.S. Nuclear Regulatory Commission (NRC) to assess control room designs. However, a number of new technologies have been employed to reevaluate an existing pressurized water reactor plant design

  11. Control console for the X-ray room

    International Nuclear Information System (INIS)

    Garcia H, J.M.; Aguilar B, M.A.; Torres B, M.A.

    1998-01-01

    It is presented the design and construction of Control console for the X-ray room of Metrology Center for ionizing radiations at National Institute of Nuclear Research (ININ). This system controls the positioning of 6 different filters for an X-ray beam. Also it controls a shutter which blockades the beam during periods established by user, these periods can be fixed from hours until tenth of second. The shutter opening periods, as well as the X-ray beam filter are establish and monitoring from a Personal computer outside of room. (Author)

  12. Feasibility study on use of virtual collaborator for remote NPP control

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Lee, Seung Jun; Seong, Poong Hyun

    2001-01-01

    In this paper, we study the feasibility of Virtual Collaborator for Remote NPP Control as long-term research theme. And we present similar and related researches that are fulfilled at I and C laboratory in nuclear department of KAIST. Yoshikawa's laboratory, Kyoto University in Japan, is developing 'virtual collaborator', agent robot, which realized in virtual reality. Virtual Collaborator is a new type of human-machine interface which works as 'intelligent interface agent' to help machine operators manipulating large scale machine system such as power plant. The Virtual Collaborator is a sort of 'virtual robot' which behaves as if an intelligent agent robot in virtual space, who can communicate naturally with human like humans do with each other

  13. Intelligent systems supporting the control room operators

    International Nuclear Information System (INIS)

    Berger, E.

    1997-01-01

    The operational experience obtained with the various applications of the systems discussed in this paper shows that more consequent use of the systems will make detection and management of disturbances still more efficient and faster. This holds true both for a low level of process automation and for power plants with a high level of automation. As for conventional power plants, the trend clearly is towards higher degrees of automation and consequent application of supporting systems. Thus, higher availability and rapid failure management are achieved, at low effects on normal operation. These systems are monitoring and process control systems, expert systems, and systems for optimal use of the equipment, or systems for post-incident analyses and computer-assisted on-shift protocols, or operating manuals. (orig./CB) [de

  14. 49 CFR 192.631 - Control room management.

    Science.gov (United States)

    2010-10-01

    ... control room who monitors and controls all or part of a pipeline facility through a SCADA system. Each... sections 1, 4, 8, 9, 11.1, and 11.3 of API RP 1165 are not practical for the SCADA system used; (2) Conduct... or SCADA displays; (3) Test and verify an internal communication plan to provide adequate means for...

  15. Replacement of the Advanced Test Reactor control room

    International Nuclear Information System (INIS)

    Durney, J.L.; Klingler, W.B.

    1989-01-01

    The control room for the Advanced Test Reactor has been replaced to provide modern equipment utilizing current standards and meeting the current human factors requirements. The control room was designed in the early 1960 era and had not been significantly upgraded since the initial installation. The replacement did not change any of the safety circuits or equipment but did result in replacement of some of the recorders that display information from the safety systems. The replacement was completed in concert with the replacement of the control room simulator which provided important feedback on the design. The design successfully incorporates computer-based systems into the display of the plant variables. This improved design provides the operator with more information in a more usable form than was provided by the original design. The replacement was successfully completed within the scheduled time thereby minimizing the down time for the reactor. 1 fig., 1 tab

  16. Replacement of the Advanced Test Reactor control room

    International Nuclear Information System (INIS)

    Durney, J.L.; Klingler, W.B.

    1990-01-01

    The control room for the Advanced Test Reactor has been replaced to provide modern equipment utilizing current standards and meeting the current human factors requirements. The control room was designed in the early 1960 era and had not been significantly upgraded since the initial installation. The replacement did not change any of the safety circuits or equipment but did result in replacement of some of the recorders that display information from the safety systems. The replacement was completed in concert with the replacement of the control room simulator which provided important feedback on the design. The design successfully incorporates computer-based systems into the display of the plant variables. This improved design provides the operator with more information in a more usable form than was provided by the original design. The replacement was successfully completed within the scheduled time thereby minimizing the down time for the reactor

  17. Teamwork and problem solving in the control room

    International Nuclear Information System (INIS)

    Nygard, F.I.; Dedon, J.M.; Fuld, R.B.

    1989-01-01

    The importance of teamwork and communications in the control room of a nuclear power plant has been the subject of significant attention during the 10 yr since the Three Mile Island accident. The ability to conduct effective problem solving, especially under unexpected conditions, requires that the control room crew be well trained in techniques that produce synergism and avoid ambiguous or conflicting interactions. This paper describes the foundations of a training program developed and conducted by Combustion Engineering to produce a winning team in the control room. The complete licensed operations staffs of three utilities, Florida Power ampersand Light, Louisiana Power ampersand Light, and Omaha Public Power District, have completed this program. Thus, the results of the experience of ∼150 licensed operators is reported

  18. Room Thermostat with Servo Controlled by PIC Microcontroller

    Directory of Open Access Journals (Sweden)

    Jan Skapa

    2013-01-01

    Full Text Available This paper describes the design of room thermostat with Microchip PIC microcontroller. Thermostat is designated for two-pipe heating system. The microprocessor controls thermostatic valve via electric actuator with mechanical gear unit. The room thermostat uses for its activity measurements of air temperature in the room and calorimetric measurement of heat, which is served to the radiator. These features predestinate it mainly for underfloor heating regulation. The thermostat is designed to work in a network. Communication with heating system's central control unit is proceeded via RS485 bus with proprietary communication protocol. If the communication failure occurs the thermostat is able to work separately. The system uses its own real time clock circuit and memory with heating programs. These programs are able to cover the whole heating season. The method of position discontinuous PSD control is used in this equipment.

  19. Assessment of control rooms of nuclear power plants

    International Nuclear Information System (INIS)

    Norros, L.; Ranta, J.; Wahlstroem, B.

    1983-05-01

    To identify and correct the lacks in control rooms of operating power plants and plants under construction an extensive program has been started in the USA. In Finland as in other countries using nuclear power, the development in the USA particularly with regard to the requirements imposed on nuclear power plants is carefully followed. The changes in these requirements are sooner or later also reflected in the guidelines given by the Finnish authorities. It is therefore important to be able to form a notion of how the new requirements apply to Finnish conditions. Especially it is important to review the latest assessment guidelines for control room implementation (NUREG-0700). Thus we can avoid possible over hasty conclusions. The aim of the analysis of the method and experiments presented in NUREG 0700 report was to create a basis for assessment of the suitability of the method for Finnish control room implementation. The task group has made a general methodical analysis of the method, and partly tried it in assessment of the TVO2 control room. It is obvious that direct conclusions from the American situation are misleading. It can be considered unfeasible to follow the American requirements as such, because they can lead to unwanted results. If the review is limited to control room details, the NRC program (checklist) can be considered successful. It can also be used during planning to observation of small discrepancies. However, we can question the applicability of some requirements. It is, though, more essential that the control room entity has neither in this nor in several other programs been reached or standardized. In spite of the difficulties we should try to reach this most important goal. (author)

  20. An alternative atmospheric diffusion model for control room habitability assessments

    International Nuclear Information System (INIS)

    Ramsdell, J.V. Jr.

    1990-01-01

    The US Nuclear Regulatory (NRC) staff uses procedures to evaluate control room designs for compliance with General Design Criterion 19 of the Code of Federal Regulations, Appendix A, 10 CRF Part 50. These procedures deal primarily with radiation protection. However, other hazardous materials, for example, chlorine, pose a potential threat to control room habitability. The NRC is considering changes in their current procedures to update methods and extend their applicability. Two changes to the current procedures are suggested: using a puff diffusion model to estimate concentrations at air intakes and using a new method to estimate diffusion coefficients

  1. Control room systems design for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This publication provides a resource for those who are involved in researching, managing, conceptualizing, designing, manufacturing or backfitting power plant control room systems. It will also be useful to those responsible for performing reviews or evaluations of the design and facilities associated with existing power plant control room systems. The ultimate worth of the publication, however, will depend upon how well it can support its users. Readers are invited to provide comments and observations to the IAEA, Division of Nuclear Power. If appropriate, the report will subsequently be re-issued, taking such feedback into account. Refs, figs and tabs.

  2. Control room systems design for nuclear power plants

    International Nuclear Information System (INIS)

    1995-07-01

    This publication provides a resource for those who are involved in researching, managing, conceptualizing, designing, manufacturing or backfitting power plant control room systems. It will also be useful to those responsible for performing reviews or evaluations of the design and facilities associated with existing power plant control room systems. The ultimate worth of the publication, however, will depend upon how well it can support its users. Readers are invited to provide comments and observations to the IAEA, Division of Nuclear Power. If appropriate, the report will subsequently be re-issued, taking such feedback into account. Refs, figs and tabs

  3. The development of an advanced computerised control room

    International Nuclear Information System (INIS)

    Haugset, K.

    1988-01-01

    Control room improvements by use of computer technology is a major activity within the OECD Halden Reactor Project. The goal is to improve operational efficiency and safety by supplying the operator with the information relevant for the specific operational situation, assisting him both in identifying plant state, plan operational strategies and implement such plans. The research activity consists of development of specific operator support systems, validation of such systems under realistic conditions and integration under the scope of an advanced control room concept. The work is carried out in close cooperation with the many member organisations. (author) 2 figs., 8 refs

  4. Advanced control room design for nuclear power plants

    International Nuclear Information System (INIS)

    Scarola, K.

    1987-01-01

    The power industry has seen a continuous growth of size and complexity of nuclear power plants. Accompanying these changes have been extensive regulatory requirements resulting in significant construction, operation and maintenance costs. In response to related concerns raised by industry members, Combustion Engineering developed the NUPLEX 80 Advanced Control Room. The goal of NUPLEX 80 TM is to: reduce design and construction costs; increase plant safety and availability through improvements in the man-machine interface; and reduce maintenance costs. This paper provides an overview of the NUPLEX 80 Advanced Control Room and explains how the stated goals are achieved. (author)

  5. A new remote control room for tokamak operations

    Energy Technology Data Exchange (ETDEWEB)

    Schissel, D.P., E-mail: schissel@fusion.gat.com [General Atomics, P.O. Box 85608, San Diego, CA (United States); Abla, G.; Flanagan, S.; Kim, E.N. [General Atomics, P.O. Box 85608, San Diego, CA (United States)

    2012-12-15

    This paper presents a summary of a new remote tokamak control room constructed near the offices of DIII-D's scientific staff. This integrated system combines hardware, software, data, and control of the room (R-232) into a unified package that has been designed and constructed in a generic fashion so that it can be used with any tokamak operating worldwide. The room is approximately 300 ft{sup 2} and can accommodate up to 12 seated participants. Mounted on the wall facing each scientist are five 52 Double-Prime LCD televisions and mounted to the wall on their right are six 24 Double-Prime LCD monitors. Each seat has associated with it a 24 Double-Prime monitor, network connection, and power and the scientist is either provided with a computer or they can use their own. The room has been used for operation of DIII-D, EAST, and KSTAR. Due to the long distances, data from EAST and KSTAR was brought back to local DIII-D computers in one large parallel network transfer and subsequently served to scientists in the remote control room to other US collaborators. This parallel data transfer allowed the data to be available to US participants between pulses making remote experimental participation highly effective.

  6. Cooperative research for human factors review of advanced control rooms

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Park, Jae Chang; Lee, Yong Hee; Oh, In Seok; Lee, Hyun Chul

    2000-12-01

    This project has been performed as cooperative research between KAERI and USNRC. Human factors issues related to soft controls, which is one of key features of advanced HSI, are identified in this project. The issues are analyzed for the evaluation approaches in either experimental or analytical ways. Also, issues requiring additional researches for the evaluation of advanced HSI are identified in the areas of advanced information systems design, computer-based procedure systems, soft controls, human systems interface and plant modernization process, and maintainability of digital systems. The issues are analyzed to discriminate the urgency of researches on it to high, medium, and low levels in consideration of advanced HSI development status in Korea, and some of the issues that can be handled by experimental researches are identified. Additionally, an experimental study is performed to compare operator's performance on human error detection in advanced control rooms vs. in conventional control rooms. It is found that advanced control rooms have several design characteristics hindering operator's error detection performance compared to conventional control rooms.

  7. Cooperative research for human factors review of advanced control rooms

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Park, Jae Chang; Lee, Yong Hee; Oh, In Seok; Lee, Hyun Chul

    2000-12-01

    This project has been performed as cooperative research between KAERI and USNRC. Human factors issues related to soft controls, which is one of key features of advanced HSI, are identified in this project. The issues are analyzed for the evaluation approaches in either experimental or analytical ways. Also, issues requiring additional researches for the evaluation of advanced HSI are identified in the areas of advanced information systems design, computer-based procedure systems, soft controls, human systems interface and plant modernization process, and maintainability of digital systems. The issues are analyzed to discriminate the urgency of researches on it to high, medium, and low levels in consideration of advanced HSI development status in Korea, and some of the issues that can be handled by experimental researches are identified. Additionally, an experimental study is performed to compare operator's performance on human error detection in advanced control rooms vs. in conventional control rooms. It is found that advanced control rooms have several design characteristics hindering operator's error detection performance compared to conventional control rooms

  8. Controlling allergens in animal rooms by using curtains

    DEFF Research Database (Denmark)

    Krohn, Thomas Cæcius; Itter, Gabi; Fosse, Richard

    2006-01-01

    The reduction and control of allergens in the animal facility is important for staff working with laboratory animals. This study was designed to evaluate the efficiency of perforated Makrolon curtains in front of racks as a method to reduce the amount of allergen in the animal room. The experimen......The reduction and control of allergens in the animal facility is important for staff working with laboratory animals. This study was designed to evaluate the efficiency of perforated Makrolon curtains in front of racks as a method to reduce the amount of allergen in the animal room....... The experimental situation we studied provides some information regarding allergen disposition in animal rooms but is clearly artificial and does not reflect a typical, ‘real-world’ environment in terms of preventing exposure of workers to allergens. Plastic curtains with holes were placed in front of racks......, and a corridor between the racks and a curtain was present. The room was ventilated with air, which was blown into the room through the middle of the corridor, flowing downstream and passing through the holes in the curtain. This set-up resulted in air flow from the corridor through the curtain. Air samples were...

  9. Main control system verification and validation of NPP digital I and C system based on engineering simulator

    International Nuclear Information System (INIS)

    Lin Meng; Hou Dong; Liu Pengfei; Yang Zongwei; Yang Yanhua

    2010-01-01

    Full-scope digital instrumentation and controls system (I and C) technique is being introduced in Chinese new constructed Nuclear Power Plant (NPP), which mainly includes three parts: control system, reactor protection system and engineered safety feature actuation system. For example, SIEMENS TELEPERM XP and XS distributed control system (DCS) have been used in Ling Ao Phase II NPP, which is located in Guangdong province, China. This is the first NPP project in China that Chinese engineers are fully responsible for all the configuration of actual analog and logic diagram, although experience in NPP full-scope digital I and C is very limited. For the safety, it has to be made sure that configuration is right and control functions can be accomplished before the phase of real plant testing on reactor. Therefore, primary verification and validation (V and V) of I and C needs to be carried out. Except the common and basic way, i.e. checking the diagram configuration one by one according to original design, NPP engineering simulator is applied as another effective approach of V and V. For this purpose, a virtual NPP thermal-hydraulic model is established as a basis according to Ling Ao Phase II NPP design, and the NPP simulation tools can provide plant operation parameters to DCS, accept control signal from I and C and give response. During the test, one set of data acquisition equipments are used to build a connection between the engineering simulator (software) and SIEMENS DCS I/O cabinet (hardware). In this emulation, original diagram configuration in DCS and field hardware structures are kept unchanged. In this way, firstly judging whether there are some problems by observing the input and output of DCS without knowing the internal configuration. Then secondly, problems can be found and corrected by understanding and checking the exact and complex configuration in detail. At last, the correctness and functionality of the control system are verified. This method is

  10. NPP service life management

    International Nuclear Information System (INIS)

    Elagin, Yu.P.

    2001-01-01

    Problems of NPP service life management and service life prolongation are reviewed. Methods for the prolongation of the French NPP service life are discussed, priority directions of nuclear block service life management in regard to aging in the context of the European program of investigation into the materials aging are identified. Questions of the provision of the 60 years service life of the Mihama 1 block (Japan) and decision of the problem of the control equipment aging in Great Britain are discussed. Situation with the prolongation of licenses on the NPP operation in the USA and Spain is considered [ru

  11. A Control Room Design Support system using virtual reality

    International Nuclear Information System (INIS)

    Sakuma, Akira; Fukumoto, Akira; Hatanaka, Takahiro; Saijou, Nobuyuki; Masugi, Tsuyoshi

    1999-01-01

    To enhance the efficiency of design and evaluation of the control and monitoring system in the main control room of nuclear power plants, we have been developing a COntrol Room Design Support system (CORDS) using virtual reality technology. Using CORDS, vendor designers and customers can visually check and review human interface design of the proposed control and monitoring systems. The geometry of panels and consoles of the control and monitoring system represented as 3-dimensional static CG (computer graphics) models. Dynamic components, such as control switches, CRT displays and so on, are modeled as dynamic objects in the geometric CG model environment. CORDS is linked with real-time plant simulator. The dynamic objects respond to the corresponding process variables in the simulator, which enables visual evaluation of the response of the control and monitoring system for the various normal and abnormal plant status. The behavior of plant operators can be simulated in 3-dimensional CG control room environment. The operators can be displayed as CG figures and their motions are modeled and controlled based on plant operation manuals. A prototype of CORDS has constructed on a graphics workstation and two engineering workstations. (author)

  12. Ergonomic requirements to control room design - evaluation method

    International Nuclear Information System (INIS)

    Hinz, W.

    1985-01-01

    The method of evaluation introduced is the result of work carried out by the sub-committee 'Control Room Design' of the Engineering Standards Committee in DIN Standards, Ergonomy. This committee compiles standards for the design of control rooms (instrumentation and control) for the monitoring and operation of process engineering cycles. With the agreement of the committee - whom we wish to take the opportunity of thanking at this point for their constructive collaboration - a planned partial standard will be introduced thematically in the following, in order that knowledge gained from the discussion can be included in further work on the subject. The matter in question is a procedure for the qualitative evaluation of the duties to be performed under the control of operators in order that an assessment can be made of existing control concepts or such concepts as are to be found in the draft phase. (orig./GL) [de

  13. Low frequency sound field control for loudspeakers in rectangular rooms using CABS (Controlled Acoustical Bass System)

    DEFF Research Database (Denmark)

    Nielsen, Sofus Birkedal; Celestinos, Adrian

    2010-01-01

    Rectangular rooms are the most common shape for sound reproduction, but at low frequencies the reflections from the boundaries of the room cause large spatial variations in the sound pressure level.  Variations up to 30 dB are normal, not only at the room modes, but basically at all frequencies....... As sound propagates in time, it seems natural that the problems can best be analyzed and solved in the time domain. A time based room correction system named CABS (Controlled Acoustical Bass System) has been developed for sound reproduction in rectangular listening rooms. It can control the sound...... sound field in the whole room, and short impulse response.  In a standard listening room (180 m3) only 4 loudspeakers are needed, 2 more than a traditional stereo setup. CABS is controlled by a developed DSP system. The time based approached might help with the understanding of sound field control...

  14. Computer codes for evaluation of control room habitability (HABIT)

    International Nuclear Information System (INIS)

    Stage, S.A.

    1996-06-01

    This report describes the Computer Codes for Evaluation of Control Room Habitability (HABIT). HABIT is a package of computer codes designed to be used for the evaluation of control room habitability in the event of an accidental release of toxic chemicals or radioactive materials. Given information about the design of a nuclear power plant, a scenario for the release of toxic chemicals or radionuclides, and information about the air flows and protection systems of the control room, HABIT can be used to estimate the chemical exposure or radiological dose to control room personnel. HABIT is an integrated package of several programs that previously needed to be run separately and required considerable user intervention. This report discusses the theoretical basis and physical assumptions made by each of the modules in HABIT and gives detailed information about the data entry windows. Sample runs are given for each of the modules. A brief section of programming notes is included. A set of computer disks will accompany this report if the report is ordered from the Energy Science and Technology Software Center. The disks contain the files needed to run HABIT on a personal computer running DOS. Source codes for the various HABIT routines are on the disks. Also included are input and output files for three demonstration runs

  15. An electronic logbook for the HEP control room

    International Nuclear Information System (INIS)

    Roediger, G.; Pomatto, P.; Kyriakopulos, J.; Panacek, S.; Canal, P.; Kubarovsky, A.

    2001-01-01

    The Control Room Logbook (CRL) is designed to improve and replace the paper logbooks traditionally used in the HEP accelerator control room. Its features benefit the on-line coordinator, the shift operators, and the remote observers. The author explains some of the most attractive features for each of these roles. The features include the ability to configure the logbook for the specific needs of a collaboration, a large variety of entry types an operator can add by simply clicking and dragging, and a flexible web interface for the remote observer to keep up with control room activities. The entries and saved as UTF-8 based XML files, which allowed us to give the data structure and meaning such that it can easily be parsed in the present and far into the future. The XML tag data is also indexed in a relational database, making queries on dates, keywords, entry type and other criteria feasible and fast. The CRL is used in the D0 control room. This presentation also discusses our experience with deployment, platform independence and other interesting issues that arose with the installation and use of logbook

  16. An Electronic Logbook for the HEP Control Room

    International Nuclear Information System (INIS)

    Gary Roediger

    2001-01-01

    The Control Room Logbook (CRL) is designed to improve and replace the paper logbooks traditionally used in the HEP accelerator control room. Its features benefit the on-line coordinator, the shift operators, and the remote observers. This paper explains some of the most attractive features for each of these roles. The features include the ability to configure the logbook for the specific needs of a collaboration, a large variety of entry types an operator can add by simply clicking and dragging, and a flexible web interface for the remote observer to keep up with control room activities. The entries are saved as UTF-8 based XML files, which allowed us to give the data structure and meaning such that it can easily be parsed in the present and far into the future. The XML tag data is also indexed in a relational database, making queries on dates, keywords, entry type and other criteria feasible and fast. The CRL is used in the D0 control room. This presentation also discusses our experience with deployment, platform independence and other interesting issues that arose with the installation and use of the logbook

  17. Inside the LEP control room at start-up

    CERN Multimedia

    1989-01-01

    Physicists grouped around a screen in the LEP control room at the strat-up of LEP on 14 July 1989. The emotion of the moment is clear. Carlo Rubbia, Director-General of CERN at the time, is in the centre and on his left, Herwig Schopper, former Director-General of the Organization.

  18. Response Times of Operators in a Control Room

    DEFF Research Database (Denmark)

    Platz, O.; Rasmussen, Jens; Skanborg, Preben Zacho

    A statistical analysis was made of operator response times recorded in the control room of a research reactor during the years 1972-1974. A homogeneity test revealed that the data consist of a mixture of populations. A small but statistically significant difference is found between day and night...

  19. Information Foraging in Nuclear Power Plant Control Rooms

    International Nuclear Information System (INIS)

    Boring, R.L.

    2011-01-01

    nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

  20. Control room envelope unfiltered air inleakage test protocols

    International Nuclear Information System (INIS)

    Lagus, P.L.; Grot, R.A.

    1997-01-01

    In 1983, the Advisory Committee on Reactor Safeguards (ACRS) recommended that the US NRC develop a control room HVAC performance testing protocol. To date no such protocol has been forthcoming. Beginning in mid-1994, an effort was funded by NRC under a Small Business Innovation Research (SBIR) grant to develop several simplified test protocols based on the principles of tracer gas testing in order to measure the total unfiltered inleakage entering a CRE during emergency mode operation of the control room ventilation system. These would allow accurate assessment of unfiltered air inleakage as required in SRP 6.4. The continuing lack of a standard protocol is unfortunate since one of the significant parameters required to calculate operator dose is the amount of unfiltered air inleakage into the control room. Often it is assumed that, if the Control Room Envelope (CRE) is maintained at +1/8 in. w.g. differential pressure relative to the surroundings, no significant unfiltered inleakage can occur it is further assumed that inleakage due to door openings is the only source of unfiltered air. 23 refs., 13 figs., 2 tabs

  1. Information Foraging in Nuclear Power Plant Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    R.L. Boring

    2011-09-01

    nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

  2. Control room envelope unfiltered air inleakage test protocols

    Energy Technology Data Exchange (ETDEWEB)

    Lagus, P.L. [Lagus Applied Technology, San Diego, CA (United States); Grot, R.A. [Lagus Applied Technology, Olney, MD (United States)

    1997-08-01

    In 1983, the Advisory Committee on Reactor Safeguards (ACRS) recommended that the US NRC develop a control room HVAC performance testing protocol. To date no such protocol has been forthcoming. Beginning in mid-1994, an effort was funded by NRC under a Small Business Innovation Research (SBIR) grant to develop several simplified test protocols based on the principles of tracer gas testing in order to measure the total unfiltered inleakage entering a CRE during emergency mode operation of the control room ventilation system. These would allow accurate assessment of unfiltered air inleakage as required in SRP 6.4. The continuing lack of a standard protocol is unfortunate since one of the significant parameters required to calculate operator dose is the amount of unfiltered air inleakage into the control room. Often it is assumed that, if the Control Room Envelope (CRE) is maintained at +1/8 in. w.g. differential pressure relative to the surroundings, no significant unfiltered inleakage can occur it is further assumed that inleakage due to door openings is the only source of unfiltered air. 23 refs., 13 figs., 2 tabs.

  3. Game-based training environment for nuclear plant control room

    International Nuclear Information System (INIS)

    Hung Tamin; Sun Tienlung; Yang Chihwei; Yang Lichen; Cheng Tsungchieh; Wang Jyhgang

    2011-01-01

    Nuclear power plant's safety is very important problem. In this very conscientious environment if operator has a little mistake, they may threaten with many people influence their safety. Therefore, operating training of control room is very important. However, the operator training is in limited space and time. Each operator must go to simulative control room do some training. If we can let each trainee having more time to do training and does not go to simulative control room. It may have some advantages for trainee. Moreover, in the traditional training ways, each operator may through the video, teaching manual or through the experienced instructor to learn the knowledge. This training way may let operator feel bored and stressful. So, in this paper aims, we hope utilizing virtual reality technology developing a game-based virtual training environment of control room. Finally, we will use presence questionnaire evaluating realism and feasibility of our virtual training environment. Expecting this initial concept of game-based virtual training environment can attract trainees having more learning motivation to do training in off-hour. (author)

  4. Two managerial grids in NPP

    International Nuclear Information System (INIS)

    Zhao Hui

    2012-01-01

    Today, the nuclear power corporation (NPC) enjoys the profit of LCEP (the low carbon economic policy). at the same time, they also enduring more and more pressure. For example, the partner competition or the NPP potential occupational risk . The efficient counterplot of risk is the self-ability cultivation. It is essential to research the NPP managerial flow. The nuclear power plant (NPP) unit is a carrier of the NPC enterprise management system, and has taken on a new look 'pull one portion then the whole moving'. The NPP has three systematical characters, the security responsibility center, the man-machine system and the input-output system. The manufacturing system and the enterprise management system are the great constituents of the NPP managerial flows. Means of systems analysis, we can find out the truth of the NPP running interface. In CHINA, there are many operating experiences near 20 years. It indicates that the NPP manufacturing system and the enterprise system are the roots of the nuclear power corporation, the core of the all NPP systems must be based on it. So the ability cultivation is the work core to NPP. It is reliably to ensure the NPP to be up against problems, for instance, the security duty, the costing control and the man-machine system running harmoniously. This paper introduces the NPP managerial flow and the present state of QNPC, also come up with a proposal to refer for the NPC development actions of collective measure, specialization, standardization, fine. (author)

  5. Improving 900 MW(e) PWR control rooms

    International Nuclear Information System (INIS)

    Bouat, M.; Marcille, R.

    1983-01-01

    Analyses of the behaviour of operators during operating tests on PWR units and the lessons learned from the TMI-2 accident have demonstrated the need to improve the interface between operators and the facilities they control. To that end, and to complement its establishment of safety panels, Electricite de France (EDF) embarked upon a study on the ''Modification of Control Desks and Boards'' in control rooms. This study, involving twenty-eight 900 MW(e) units, almost all of which are currently in service, began with an ergonomic analysis of control rooms by an external consultant, the ADERSA GERBIOS Association. This analysis was based on interviews with simulator instructors and operators, a study of the operation of the unit, and a general review of previous studies. The analysis began in October 1980 and resulted, in April 1981, in a critical report and a proposal to create a full-scale mock-up of a 900 MW(e) control room. Improvements to this were subsequently proposed, enabling options to be made between, among other things, active overall control panels and function-by-function control panels. Finally, a number of general principles, which largely encompass the operators' suggestions, were defined. The alterations to be made will make it necessary to revamp the control panels completely. The work and tests involved should match the duration of refuelling shut-downs. Audio-visual training programmes are planned (portable model). (author)

  6. The analysis in real time, during the pre-commissioning period, of the overall plant control system of the CANDU NPP unit

    International Nuclear Information System (INIS)

    Tapu, C.; Irimia, M.

    1994-01-01

    The physical processes in the CANDU NPP are controlled by a computer system which, based on the associated package of programmes, performs both the monitoring function at the level of the operational area, and the digital regulation function of the technological systems within the NPP. For an optimal operation of the NPP, in dynamic as well as in stationary regime, the correlation of the direct digital control of the technological systems is very important for the NPP's overall digital control system. Taking into account the fact that during the pre-commissioning period of a CANDU unit it is necessary to test in dynamic regime the performance of the overall digital control function of the NPP, a system of verification and testing in real time was developed, by connecting a micro simulator of the physical process in the NPP to the actual computer system of the unit. The paper presents the methods and techniques used, as well as the results of the tests for various operational modes, which highlight the functioning of the digital control system of the CANDU NPP unit. (Author)

  7. Replacement of the level control of draining tanks MSRS and powered water heaters with the OVATION system in Asco NPP

    International Nuclear Information System (INIS)

    Serrano Jimenez, J.

    2012-01-01

    The current MSR drains and heaters tanks level control is local control individual, pneumatic and without action from Control room. The system has level switches for the generation of alarms, isolations and shots of bombs. Single control room operators have level alarms, final race of valves of control and indication of temperature and pressure of some tanks.

  8. Control room design and human engineering in power plants

    International Nuclear Information System (INIS)

    Herbst, L.; Hinz, W.

    1982-01-01

    The concept for modern plant control rooms is primary influenced by: The automation of protection, binary control and closed loop control functions; organization employing functional areas; computer based information processing; human engineered design. Automation reduces the human work load. Employment of functional areas permits optimization of operational sequences. Computer based information processing makes it possible to output information in accordance with operating requirements. Design based on human engineering principles assures the quality of the interaction between the operator and the equipment. The degree to which these conceptional features play a role in design of power plant control rooms depends on the unit rating, the mode of operation and on the requirements respecting safety and availability of the plant. (orig.)

  9. Look into the PS Main Control Room (partial view)

    CERN Multimedia

    1974-01-01

    Jean-Pierre Potier at work. The 26 GeV Synchrotron and later also its related machines (Linacs 1,2,3; PS-Booster, LEP-Injector Linacs and Electron-Positron Accumulator; Antiproton Accumulator, Antiproton Collector, Low Energy Antiproton Ring and more recently Antiproton Decelerator) were all controlled from the PS control room situated at the Meyrin site. The SPS and LEP were controlled from a separat control centre on the Prevessin site. In 2005 all controls were transferred to the Prevessin centre.

  10. Feasibility of touch-less control of operating room lights.

    Science.gov (United States)

    Hartmann, Florian; Schlaefer, Alexander

    2013-03-01

    Today's highly technical operating rooms lead to fairly complex surgical workflows where the surgeon has to interact with a number of devices, including the operating room light. Hence, ideally, the surgeon could direct the light without major disruption of his work. We studied whether a gesture tracking-based control of an automated operating room light is feasible. So far, there has been little research on control approaches for operating lights. We have implemented an exemplary setup to mimic an automated light controlled by a gesture tracking system. The setup includes a articulated arm to position the light source and an off-the-shelf RGBD camera to detect the user interaction. We assessed the tracking performance using a robot-mounted hand phantom and ran a number of tests with 18 volunteers to evaluate the potential of touch-less light control. All test persons were comfortable with using the gesture-based system and quickly learned how to move a light spot on flat surface. The hand tracking error is direction-dependent and in the range of several centimeters, with a standard deviation of less than 1 mm and up to 3.5 mm orthogonal and parallel to the finger orientation, respectively. However, the subjects had no problems following even more complex paths with a width of less than 10 cm. The average speed was 0.15 m/s, and even initially slow subjects improved over time. Gestures to initiate control can be performed in approximately 2 s. Two-thirds of the subjects considered gesture control to be simple, and a majority considered it to be rather efficient. Implementation of an automated operating room light and touch-less control using an RGBD camera for gesture tracking is feasible. The remaining tracking error does not affect smooth control, and the use of the system is intuitive even for inexperienced users.

  11. Room air conditioner load control under summer comfort constraint

    OpenAIRE

    Da Silva , David; Brancaccio , M; Duplessis , Bruno; Adnot , J

    2010-01-01

    International audience; Load control options interest is growing because it can represent a response to future network investments and to congestion problems. In this frame, the present paper gives a methodology to quantify the value of load control for heat pumps (room air conditioners), in small tertiary and residential buildings, considering the occupant's comfort and the electrical grid needs for load shift. This methodology was applied to a small office building where simulations were ma...

  12. Development of NPP control room operators's mental workload measurement system using bioelectric signals

    International Nuclear Information System (INIS)

    Shim, Bong Sik; Oh, In Seok; Lee, Hyun Cheol; Cha, Kyung Ho; Lee, Dong Ha

    1996-09-01

    This study developed mentalload measurement system based on the relations between mentalload and physiological responses of the human operators. The measurement system was composed of the telemetry system for EEG, EOG, ECG and respiration pattern of the subjects, A/D converter, the physiological signal processing programs (compiled by the Labview). The signal processing programs transformed the physiological signal into the scores indicating mentalload status of the subjects and recorded the mentalload scores in the form of the table of a database. The acqknowledge and the labview programs additionally transformed the mentalload score database and the operator behavior database so that both database were consolidated into one. 94 figs., 57 refs. (Author)

  13. Comparative analysis of methods for workload assessment of the main control room operators of NPP

    International Nuclear Information System (INIS)

    Georgiev, V.; Petkov, G.

    2008-01-01

    The paper presents benchmarking workload results obtained by a method for operator workload assessment – NASA Task Load Index, and a method for human error probability assessment - Performance Evaluation of Teamwork. Based on the archives of FSS-1000 training in the accident “Main Steam Line Tube Rupture at the WWER-1000 Containment” the capacities of the two methods for direct and indirect workload assessment are evaluated

  14. Development of NPP control room operators`s mental workload measurement system using bioelectric signals

    Energy Technology Data Exchange (ETDEWEB)

    Shim, Bong Sik; Oh, In Seok; Lee, Hyun Cheol; Cha, Kyung Ho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Lee, Dong Ha [Suwon Univ., Suwon (Korea, Republic of)

    1996-09-01

    This study developed mentalload measurement system based on the relations between mentalload and physiological responses of the human operators. The measurement system was composed of the telemetry system for EEG, EOG, ECG and respiration pattern of the subjects, A/D converter, the physiological signal processing programs (compiled by the Labview). The signal processing programs transformed the physiological signal into the scores indicating mentalload status of the subjects and recorded the mentalload scores in the form of the table of a database. The acqknowledge and the labview programs additionally transformed the mentalload score database and the operator behavior database so that both database were consolidated into one. 94 figs., 57 refs. (Author).

  15. Quality Control Activities Related to Mechanical Maintenance of Safety Related Components at Krsko NPP

    International Nuclear Information System (INIS)

    Djakovic, D.

    2016-01-01

    For successful, safe and reliable operation of nuclear power plant, maintenance processes have to be systematically controlled and procedures for quality control of maintenance activities shall be established. This is requested by the quality assurance program, which shall provide control over activities affecting the quality of structures, systems, and components, considering their importance to safety. As a part of Quality and Nuclear Oversight Division (QNOD; SKV), the Quality Control Department (QC) provides quality control activities, which are deeply involved in maintenance processes at Krsko NPP, both on safety related and non-safety related (non-nuclear safety) components. QC activities on safety related components have to fulfil all requirements, which will enable the components to perform their intended safety functions. This paper describes quality control activities related to mechanical maintenance of safety related components at Krsko NPP and significant role of the Krsko plant QC Department in three particular maintenance cases connected with safety related components. In these three specific cases, the QC has confirmed its importance in compliance with quality assurance program and presented its significant added value in providing safe and reliable operation of the plant. The first maintenance activity was installation of nozzle check valves in the scope of a modification for improving regulation of spent fuel pit pumps. The QC Department performed receipt inspection of the valves. Using non-destructive examination methods and X-ray spectrometry, it was found out that the valve diffuser was made of improper material, which could cause progressive corrosion of the valve diffuser in borated water and consequently a loss of safety function of the valves followed by long-term consequences. The second one was the receipt inspection of containment ventilation fan coolers. The coolers were claimed and sent back to the supplier because the QC Department

  16. Design on human supervisory control of safety management for advance NPP

    International Nuclear Information System (INIS)

    Nugroho, D.H.; Soentono, S.; Taryo, T.; Wahyon, P.I.

    2006-01-01

    Full text: Full text: Characteristics of an advance NPP related with economic and safety enhancement was represented on capabilities in intelligent control and diagnostic to provide nearly autonomous operation with anticipatory maintenance. An autonomous control system should enable automatic operation while adapting to component faults and system variable upsets. It needs therefore to have many intelligent capabilities, such as modeling, analysis, self-validation, diagnosis and decision. This paper describes a human supervisory control design for nuclear reactor fault management which collaborates between human and autonomous control. The beneficial of collaboration is provided based on belief of information value evaluated from Dempster's rule of evidence. The belief of the collaboration is better compared with single usage. The collaboration was conducted in which agent will autonomously and periodically be conducting surveillance by checking the component abnormalities in the plant if anomalies occur. The anomalies were determined using fault detection module. Thereby the system will be able to conduct preventive maintenance. In the situation of accident happened, hence the system will diagnose to determine the location of component failure autonomously. A human supervisor will then determine the action of decison making based on the prediction result. The decision making will be conducted based on the 4th Sheridan's autonomous level in which the autonomous control will execute the duty autonomously when the plant is in normal condition, or in the predictable accident range. But if the unpredictable accident occurs in the plant, the supervisor will then take over the role to control the plant, and the machine will do what commanded by the supervisor. Sistematically, the system explained before was represented by Traveling Salesman Problem-based surveillance, modified ART-2 artificial neural networks-based fault detection and Bayesian Networks-based fault

  17. Study on the main control room design for Hamaoka Unit No.5

    International Nuclear Information System (INIS)

    Tsuruta, Tadakazu; Sakamoto, Minoru; Maruyama, Tohru; Saito, Tadashi

    2000-01-01

    The main control room of nuclear power station is important to operate the power station and to promote public acceptance of nuclear power station. To enhance them, there is an idea of high ceiling control room with a gallery room located in backside middle upper floor. The control room is expected to enhance habitability and to offer visitors the fine view of the control room. In this study, psychological and physiological influence of such a high ceiling control room design on operators was investigated first. And then some human engineering requirements for desirable main control room were identified. A control room (ceiling height: about 5 meters) adequate to the requirements was designed, and finally the validity of the design was verified by means of full mockup model room tests. The results of this study are applied to the main control room design of Hamaoka Nuclear Power Station Unit No.5 (Chubu Electric Power Co., Inc.) (author)

  18. Safety parameter display system for Kalinin NPP

    International Nuclear Information System (INIS)

    Andreev, V.I.; Videneev, E.N.; Tissot, J.C.; Joonekindt, D.; Davidenko, N.N.; Shaftan, G.I.; Dounaev, V.G.; Neboyan, V.T.

    1995-01-01

    The paper discusses the safety parameter display system (SPDS), which is being designed for Kalinin NPP. The assessment of the safety status of the plant is done by the continuous monitoring of six critical safety functions and the corresponding status trees. Besides, a number of additional functions are realized within the scope of KlnNPP, aimed at providing the operator and the safety engineer in the main control room with more detailed information in accidental situation as well as during the normal operation. In particular, these functions are: archiving, data logs and alarm handling, safety actions monitoring, mnemonic diagrams indicating the state of main technological equipment and basic plant parameters, reference data, etc. As compared with the traditional scope of functions of this kind of systems, the functionality of KlnNPP SPDS is significantly expanded due to the inclusion in it the operator support function ''computerized procedures''. The basic SPDS implementation platform is ADACS of SEMA GROUP design. The system architecture includes two workstations in the main control room: one is for reactor operator and the other one for safety engineer. Every station has two CRT screens which ensures computerized procedures implementation and provides for extra services for the operator. Also, the information from the SPDS is transmitted to the local crisis center and to the crisis center of the State utility organization concern ''Rosenergoatom''. (author). 3 refs, 6 figs, 1 tab

  19. CERN opens up its control rooms to youngsters

    CERN Multimedia

    CERN Bulletin

    2011-01-01

    CERN is inviting 13 to 18 year-olds to come and spend a couple of hours in the control rooms of the LHC and its experiments. Registration is now open.   Is your neighbour's kid eager to come and see what's going on in the CERN control rooms for himself? Is your niece from Germany fascinated by the famous accelerator near Geneva that she's heard about and asking to know more? Then Researchers Night is for them! From 6.00 p.m. on Friday 23 September until 1.00 a.m. the following morning, the LHC and its experiments will open their doors to 13 to 18 year-olds. They are invited to come and spend a couple of hours in the control rooms watching the physicists and taking part in various activities. ALICE, ATLAS, CMS, LHCb, TOTEM, and the CERN Control Centre (CCC) will all be welcoming visitors. For this second year of CERN's involvement in European Researchers Night, the CERN exhibitions will be open late and special activities will be organised in Microcosm....

  20. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    International Nuclear Information System (INIS)

    Haas, P.M.; Selby, D.L.; Hanley, M.J.; Mercer, R.T.

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model

  1. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    Energy Technology Data Exchange (ETDEWEB)

    Haas, P M; Selby, D L; Hanley, M J; Mercer, R T

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model.

  2. Human Factors Engineering Aspects of Modifications in Control Room Modernization

    Energy Technology Data Exchange (ETDEWEB)

    Hugo, Jacques [Idaho National Lab. (INL), Idaho Falls, ID (United States); Clefton, Gordon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-06-01

    This report describes the basic aspects of control room modernization projects in the U.S. nuclear industry and the need for supplementary guidance on the integration of human factors considerations into the licensing and regulatory aspects of digital upgrades. The report pays specific attention to the integration of principles described in NUREG-0711 (Human Factors Engineering Program Review Model) and how supplementary guidance can help to raise general awareness in the industry regarding the complexities of control room modernization projects created by many interdependent regulations, standards and guidelines. The report also describes how human factors engineering principles and methods provided by various resources and international standards can help in navigating through the process of licensing digital upgrades. In particular, the integration of human factors engineering guidance and requirements into the process of licensing digital upgrades can help reduce uncertainty related to development of technical bases for digital upgrades that will avoid the introduction of new failure modes.

  3. Control room habitability Analysis and Testing for Wolsong Unit 1

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. B. [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    In response to this recommendation, KHNP has established CRH program and performed tracer gas in leakage tests. These activities are described herein including the emergency ventilation system analysis, acceptance criteria calculation for the test and Control Room Envelope (CRE) discrimination, and the results of the tracer gas tests are presented. CRH analysis including unfiltered in leakage tests according to the methodology in ASTM E741 was performed for Wolsong Unit 1. The results show that the integrity of the control room of Wolsong Unit 1 is in good condition to maintain the reactor in a safe condition under accident conditions, which complies with the US NRC regulatory guides 1.78, 1.196 and 1.197.

  4. Advanced control room evaluation: General approach and rationale

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Wachtel, J.

    1991-01-01

    Advanced control rooms (ACRs) for future nuclear power plants (NPPs) are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale and general approach to the development of a human factors review guideline for ACRs. The factors influencing the guideline development are discussed, including the review environment, the types of advanced technologies being addressed, the human factors issues associated with advanced technology, and the current state-of-the-art of human factors guidelines for advanced human-system interfaces (HSIs). The proposed approach to ACR review would track the design and implementation process through the application of review guidelines reflecting four review modules: planning, design process analysis, human factors engineering review, and dynamic performance evaluation. 21 refs

  5. Control room annunciation - problem assessment and selection of improvement priorities

    International Nuclear Information System (INIS)

    Hartley, P.; Yaraskavitch, E.; Davey, E.

    1998-01-01

    In 1997, Pickering B undertook a project to examine current annunciation practice and identify improvement opportunities and priorities. The objectives and scope of the study were to: document the deficiencies with control room annunciation and the subsequent operational and financial impacts to station operations, develop an operations-based definition of the requirements for annunciation to adequately support control room staff, propose annunciation improvements based on a comparison of the annunciation deficiencies identified and the operational needs to be met, assess the relative operational impact, and financial benefits and costs of the improvement initiatives proposed, and recommend annunciation improvement priorities that offer a mix of operational and financial return for improvement investment. This paper discusses the rationale for the project, outlines the approaches applied in achieving the assessment objectives, reviews the key assessment findings and describes the improvement initiatives recommended. (author)

  6. Empirical investigation of workloads of operators in advanced control rooms

    International Nuclear Information System (INIS)

    Kim, Yochan; Jung, Wondea; Kim, Seunghwan

    2014-01-01

    This paper compares the workloads of operators in a computer-based control room of an advanced power reactor (APR 1400) nuclear power plant to investigate the effects from the changes in the interfaces in the control room. The cognitive-communicative-operative activity framework was employed to evaluate the workloads of the operator's roles during emergency operations. The related data were obtained by analyzing the tasks written in the procedures and observing the speech and behaviors of the reserved operators in a full-scope dynamic simulator for an APR 1400. The data were analyzed using an F-test and a Duncan test. It was found that the workloads of the shift supervisors (SSs) were larger than other operators and the operative activities of the SSs increased owing to the computer-based procedure. From these findings, methods to reduce the workloads of the SSs that arise from the computer-based procedure are discussed. (author)

  7. EDP supported control room simulation for training of fault cases

    International Nuclear Information System (INIS)

    Weber, P.

    1984-01-01

    The picture used for simulation was the model of a power station control room designed by KWU for the German Museum, the cooling water circuit of which is illustrated, in order to avoid long training times by a manageable problem setting. A process video system equipped with a light pen made by KRUPP ATLAS was available for the VDU representation of simulation, which is used in industry, for the control and supervision of technical system. This process video system was controlled by a Digital PDP 11/40, which has several great advantages over stand-alone operation. (orig./DG) [de

  8. Human factors evaluation of the engineering test reactor control room

    International Nuclear Information System (INIS)

    Banks, W.W.; Boone, M.P.

    1981-03-01

    The Reactor and Process Control Rooms at the Engineering Test Reactor were evaluated by a team of human factors engineers using available human factors design criteria. During the evaluation, ETR, equipment and facilities were compared with MIL-STD-1472-B, Human Engineering design Criteria for Military Systems. The focus of recommendations centered on: (a) displays and controls; placing displays and controls in functional groups; (b) establishing a consistent color coding (in compliance with a standard if possible); (c) systematizing annunciator alarms and reducing their number; (d) organizing equipment in functional groups; and (e) modifying labeling and lines of demarcation

  9. The Prevessin Control Room during LEP's start up in 1989.

    CERN Multimedia

    1989-01-01

    The Prévessin Control Room saw its first momentous event when the 400 GeV beam for the SPS was commissioned in the presence of Project Leader John Adams. It was also here that the first proton-antiproton collisions were observed, in 1981. Eight years later, in 1989, operators and directors alike jumped for joy at the announcement of the first electron-positron collisions at the start up of LEP, the biggest accelerator in the world.

  10. Response times of operators in a control room

    International Nuclear Information System (INIS)

    Platz, O.; Rasmussen, J.; Skanborg, P.Z.

    1982-12-01

    A statistical analysis was made of operator response times recorded in the control room of a research reactor during the years 1972-1974. A homogeneity test revealed that the data consist of a mixture of populations. A small but statistically significant difference is found between day and night response times. Lognormal distributions are found to provide the best fit of the day and the night response times. (author)

  11. Ergonomic configuration of control rooms in nuclear power stations

    International Nuclear Information System (INIS)

    Becker, G.

    1984-01-01

    Human possibilities and limits of performance can be taken into account by work configuration measures, in order to make the optimum contribution to the total output of the human being/machine system. The results of and considerations for the level ergonomic configuration of the control room, for the elements of the information carrier, for the structuring of the work field and for communication centres are introduced. (DG) [de

  12. Improvement on main control room for Japanese PWR plants

    International Nuclear Information System (INIS)

    Matsumiya, Masayuki

    1996-01-01

    The main control room which is the information center of nuclear power plant has been continuously improved utilizing the state of the art ergonomics, a high performance computer, computer graphic technologies, etc. For the latest Japanese Pressurized Water Reactor (PWR) plant, the CRT monitoring system is applied as the major information source for facilitating operators' plant monitoring tasks. For an operating plant, enhancement of monitoring and logging functions has been made adopting a high performance computer

  13. Engineering human factors into the Westinghouse advanced control room

    International Nuclear Information System (INIS)

    Easter, J.R.

    1987-01-01

    By coupling the work of the Riso Laboratory in Denmark on human behaviour with new digital computation and display technology, Westinghouse has developed a totally new control room design. This design features a separate, co-ordinated work station to support the systems management role in decision making, as well as robust alarm and display systems. This coupling of the functional and physical data presentation is now being implemented in test facilities. (author)

  14. Simulation and System Analysis of Flow Pulsation at Normal and Emergency for Advanced On-line Monitoring and Control of NPP

    International Nuclear Information System (INIS)

    Proskouriakov, K.N.; Moukhine, V.S.

    2002-01-01

    In addition to investigation of thermal-hydraulic processes on NPP with use of computer codes the new system analysis of flow pulsation is worked out. System analysis shows that properties of heat rejection circuits of NPP as oscillatory system are not equal the sum of properties of its separate elements but gives the new properties which must be taken into account. Methods have been worked out for calculating and identifying the sources of thermal-hydraulic disturbances are intended to improve the means of early diagnostics of anomalies in the technological process, to forecast their development, to improve the efficiency of overhauling operations and safety in operation, and also to create advanced on-line monitoring and control of NPP. Conception of the control system development presents. Proposal for main topics R and D areas for advanced NPP monitoring, diagnostic and control are identified. (authors)

  15. First-of-A-Kind Control Room Modernization Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, Kenneth David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-02-01

    This project plan describes a comprehensive approach to the design of an end-state concept for a modernized control room for Palo Verde. It describes the collaboration arrangement between the DOE LWRS Program Control Room Modernization Project and the APS Palo Verde Nuclear Generating Station. It further describes the role of other collaborators, including the Institute for Energy Technology (IFE) and the Electric Power Research Institute (EPRI). It combines advanced tools, methodologies, and facilities to enable a science-based approach to the validation of applicable engineering and human factors principles for nuclear plant control rooms. It addresses the required project results and documentation to demonstrate compliance with regulatory requirements. It describes the project tasks that will be conducted in the project, and the deliverable reports that will be developed through these tasks. This project plan will be updated as new tasks are added and as project milestones are completed. It will serve as an ongoing description on the project both for project participants and for industry stakeholders.

  16. The Halden Reactor Project workshop meeting on control room development

    International Nuclear Information System (INIS)

    Miberg, Ann Britt; Green, Marie; Haukenes, Hanne; Larsen, Marit; Seim, Lars Aage; Veland, Oeystein

    1999-03-01

    The 'Control Room Development' workshop was organised in. Halden, November 5-6, 1998. The purpose of the workshop was to bring forward recommendations for the future use of HAMMLAB with respect to control room development. The workshop comprised thirteen presentations summarising current issues and status in control room development projects and related projects. Following the presentations, five working groups were formed. The purpose of the working groups was to establish a set of recommendations for the future use of HAMMLAB. Each working group developed a set of recommendations. The outcomes of the working groups' discussions were summarised in plenum by the working group chairs. During the workshop, all participants excluding the Halden Project staff were asked to fill in a questionnaire indicating which research topics they found most interesting to pursue in future HAMMLAB research. The purpose of this report is to summarise the workshop participants' presentations, the working groups' discussions, and the recommendations given by the workshop participants concerning the future use of HAMMLAB (author) (ml)

  17. Changes in control room at Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Kecklund, Lena

    2005-09-01

    The Swedish nuclear power plants were commissioned during a period between 1972 and 1985 and the instrumentation and control equipment are basically from that period. For several years there have been plans made for changes in all the nuclear power plants and to a certain extent the changes in control equipment and monitoring rooms have also been implemented. The object of this project was to make a comprehensive review of the changes in control room design implemented in the Swedish nuclear power plants and to describe how the MTO- (Man-Technology-Organisation) and (Man-Machine-Interface) -issues have been integrated in the process. The survey is intended to give an overall picture of the changes in control room design and man-machine-interface made in the Swedish control rooms, in order to get a deeper knowledge of the change management process and its results as well as of the management of MTO-issues in these projects. The units included in this survey are: Oskarhamn reactor 2 and 3; Ringhals reactor 2, 3 and 4; Forsmark reactor 1, 2 and 3. The Oskarshamn 1 unit has not been included in this report as it has recently undergone an extensive modernisation program as well as a detailed inspection by the SKI (Swedish Nuclear Power Inspectorate). At Ringhals 2 the modernisation work is carried out at present and the unit is also subjected to extensive inspection activities carried out by SKI and is therefore not part of this survey. This report also includes a short description of relevant standards and requirements. Then follows a presentation of the results of the plant survey, presented as case studies for three companies OKG, Ringhals and FKA. Control room changes are summarized as well as the results on specific MTO issues which has been surveyed. In all the power companies there is a joint way of working with projects concerning plant modifications. This process is described for each company separately. In the concluding of the report the strengths and

  18. Data collection on the unit control room simulator as a method of operator reliability analysis

    International Nuclear Information System (INIS)

    Holy, J.

    1998-01-01

    The report consists of the following chapters: (1) Probabilistic assessment of nuclear power plant operation safety and human factor reliability analysis; (2) Simulators and simulations as human reliability analysis tools; (3) DOE project for using the collection and analysis of data from the unit control room simulator in human factor reliability analysis at the Paks nuclear power plant; (4) General requirements for the organization of the simulator data collection project; (5) Full-scale simulator at the Nuclear Power Plants Research Institute in Trnava, Slovakia, used as a training means for operators of the Dukovany NPP; (6) Assessment of the feasibility of quantification of important human actions modelled within a PSA study by employing simulator data analysis; (7) Assessment of the feasibility of using the various exercise topics for the quantification of the PSA model; (8) Assessment of the feasibility of employing the simulator in the analysis of the individual factors affecting the operator's activity; and (9) Examples of application of statistical methods in the analysis of the human reliability factor. (P.A.)

  19. Verification and Validation of Digitally Upgraded Control Rooms

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lau, Nathan [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    As nuclear power plants undertake main control room modernization, a challenge is the lack of a clearly defined human factors process to follow. Verification and validation (V&V) as applied in the nuclear power community has tended to involve efforts such as integrated system validation, which comes at the tail end of the design stage. To fill in guidance gaps and create a step-by-step process for control room modernization, we have developed the Guideline for Operational Nuclear Usability and Knowledge Elicitation (GONUKE). This approach builds on best practices in the software industry, which prescribe an iterative user-centered approach featuring multiple cycles of design and evaluation. Nuclear regulatory guidance for control room design emphasizes summative evaluation—which occurs after the design is complete. In the GONUKE approach, evaluation is also performed at the formative stage of design—early in the design cycle using mockups and prototypes for evaluation. The evaluation may involve expert review (e.g., software heuristic evaluation at the formative stage and design verification against human factors standards like NUREG-0700 at the summative stage). The evaluation may also involve user testing (e.g., usability testing at the formative stage and integrated system validation at the summative stage). An additional, often overlooked component of evaluation is knowledge elicitation, which captures operator insights into the system. In this report we outline these evaluation types across design phases that support the overall modernization process. The objective is to provide industry-suitable guidance for steps to be taken in support of the design and evaluation of a new human-machine interface (HMI) in the control room. We suggest the value of early-stage V&V and highlight how this early-stage V&V can help improve the design process for control room modernization. We argue that there is a need to overcome two shortcomings of V&V in current practice

  20. Verification and Validation of Digitally Upgraded Control Rooms

    International Nuclear Information System (INIS)

    Boring, Ronald; Lau, Nathan

    2015-01-01

    As nuclear power plants undertake main control room modernization, a challenge is the lack of a clearly defined human factors process to follow. Verification and validation (V&V) as applied in the nuclear power community has tended to involve efforts such as integrated system validation, which comes at the tail end of the design stage. To fill in guidance gaps and create a step-by-step process for control room modernization, we have developed the Guideline for Operational Nuclear Usability and Knowledge Elicitation (GONUKE). This approach builds on best practices in the software industry, which prescribe an iterative user-centered approach featuring multiple cycles of design and evaluation. Nuclear regulatory guidance for control room design emphasizes summative evaluation - which occurs after the design is complete. In the GONUKE approach, evaluation is also performed at the formative stage of design - early in the design cycle using mockups and prototypes for evaluation. The evaluation may involve expert review (e.g., software heuristic evaluation at the formative stage and design verification against human factors standards like NUREG-0700 at the summative stage). The evaluation may also involve user testing (e.g., usability testing at the formative stage and integrated system validation at the summative stage). An additional, often overlooked component of evaluation is knowledge elicitation, which captures operator insights into the system. In this report we outline these evaluation types across design phases that support the overall modernization process. The objective is to provide industry-suitable guidance for steps to be taken in support of the design and evaluation of a new human-machine interface (HMI) in the control room. We suggest the value of early-stage V&V and highlight how this early-stage V&V can help improve the design process for control room modernization. We argue that there is a need to overcome two shortcomings of V&V in current practice

  1. Cutting of Control Rod Guide Tubes and Jet Pumps at Wuergassen NPP/ Germany

    International Nuclear Information System (INIS)

    Ralf Loock

    2006-01-01

    KWW Nuclear Power Plant has been erected and put into operation in the time period 1968 to end of 1971. In 23 years of operation about 73 billions kWh electric power have been generated. The electric rated power was 670 MW. In May 1995 the decommission was started for economical reasons, since April 1997 the demolition is in progress. In autumn 2003 FANP has been called upon to cut the Control Rod Guide Tubes and Jet Pumps. After a 10 months preparatory phase, cutting of the Control Rod Guide Tubes and Jet Pumps was started in September 2004. For radiation protection reasons the Control Rod Guide Tubes and Jet Pumps were cut and packed remote controlled under water. The cutting process had been selected particularly under consideration of radiation protection aspects. A combination of the technologies band sawing and nibbling was assigned for cutting of the Control Rod Guide Tubes and Jet Pumps. The band saw consists of a substructure and of a feed system installed on it. The feed system can be equipped with one or two band saws optionally. A turntable is integrated in the substructure. It is used to support the CRGT respectively the residual piece of the CRGT and to move it out of the cut position after finishing the cutting. After getting the agreement to the specification, the equipment has been designed and manufactured according to the specification preferences. After finishing the internal testing, the factory acceptance test as well as acceptance and functional tests of every facility were carried out. After cold testing being performed successfully, the cutting equipment was installed in the NPP and checked for operational safety additionally. Cutting of the Control Rod Guide Tubes and Jet Pumps has been carried out on two working places inside the fuel element storage pool. During the total project duration on site the processing has been supervised by the radiation protection staff permanently. As a result 110 Control Rod Guide Tubes and 18 Jet Pumps were

  2. A demonstrated method for upgrading existing control room interiors

    International Nuclear Information System (INIS)

    Brice, R.M.; Terrill, D.; Brice, R.M.

    1991-01-01

    The main control room (MCR) of any nuclear power plant can justifiably be called the most important area staffed by personnel in the entire facility. The interior workstation configuration, equipment arrangement, and staff placement all affect the efficiency and habitability of the room. There are many guidelines available that describe various human factor principles to use when upgrading the environment of the MCR. These involve anthropometric standards and rules for placement of peripheral equipment. Due to the variations in plant design, however, hard-and-fast rules have not and cannot be standardized for retrofits in any significant way. How then does one develop criteria for the improvement of a MCR? The purpose of this paper is to discuss, from the designer's point of view, a method for the collection of information, development of criteria, and creation of a final design for a MCR upgrade. This method is best understood by describing the successful implementation at Tennessee Valley Authority's Sequoyah nuclear plant

  3. Design of control rooms and ergonomics in power plants

    International Nuclear Information System (INIS)

    Herbst, L.; Hinz, W.

    1981-01-01

    Modern power plant control rooms are characterized by automation of protection and control functions, subdivision according to functions, computer-aided information processing, and ergonomic design. Automation relieves the personnel of stress. Subdivision according to functions permits optimized procedures. Computer-aided information processing results in variable information output tailored to the actual needs. Ergonomic design assures qualified man-machine interaction. Of course, these characteristics will vary between power plants in dependence of unit power, mode of operation, and safety and availability requirements. (orig.) [de

  4. Simon van der Meer in the AA Control Room

    CERN Multimedia

    CERN PhotoLab

    1984-01-01

    Simon van der Meer, spiritus rector of the Antiproton Accumulator, in the AA Control Room. Inventor of stochastic cooling, on which the AA was based, and of the magnetic horn, with which the antiprotons were focused, he also wrote most of the software with which the AA was controlled, and spent uncountable numbers of hours in this chair to tickle the AA to top performance. 8 months after this picture was taken, he received, in October 1984, the Nobel prize, together with Carlo Rubbia, the moving force behind the whole Proton-Antiproton Collider project that led to the discovery, in 1983, of the W and Z intermediate bosons.

  5. A brief account of Kozloduy 6 full-scope replica control room simulator upgrade experience: An engineering point of view

    International Nuclear Information System (INIS)

    Dinkov, Y.D.

    2006-01-01

    A short excursion throughout Kozloduy NPP history, and Kozloduy 6 Full-Scope Replica Control Room Simulator procurement, is proposed for a reader, which is not familiar with the Kozloduy circumstances. A brief account of five year operation and upgrade experience is presented as seen by the Kozloduy simulator engineering team. During the last five years Kozloduy 6 is going through a complex and expensive modernization programme so Simulator is a subject of a series of changes twice per year. Simulator is used for training six months of the year during spring and autumn most of this time in two shifts daily. Remaining six months during winter and summer are allocated to other simulator uses including five months downtime for hardware reconstruction, software integration, troubleshooting and testing. Quantitative information concerning scope of software and hardware changes is given. Kozloduy NPP simulator engineering team approach toward various upgrade projects is given in an attempt to facilitate a discussion about how a simulator upgrade should be performed. Projects mentioned vary from small to big, in-house or contracted, already completed or planned for future realization

  6. FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

    2008-09-01

    This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (i) the estimation of human error associated with advanced control room equipment and configurations, (ii) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (iii) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms.

  7. FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS

    International Nuclear Information System (INIS)

    Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

    2008-01-01

    This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (1) the estimation of human error associated with advanced control room equipment and configurations, (2) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (3) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms

  8. A model of a control-room crew

    International Nuclear Information System (INIS)

    Spurgin, A.J.; Beveridge, R.L.

    1986-01-01

    This paper discusses the development of a model of a control-room crew based on observations of crews and concepts developed by cognitive psychologists. The model can help define, among other things, the requirements for SPDS or other operator aids. The paper discusses the relationship of the shift supervisor, the control board operators, the control and instrumentation systems and the written procedures in the control of the plant during normal and abnormal plant transients. These relationships cover the communications between crew members, use of the control equipment by the board operators, use of information, such as the SPDS, by the shift supervisor and integration of crew actions by the use of the procedures. Also discussed are the potential causes of erroneous actions by the crew in accident situations. The model is at this time purely qualitative, but it can be considered to be the basis for the development of a mathematical model

  9. Job satisfaction among control room operators of electrical systems.

    Science.gov (United States)

    Macaia, Amanda A Silva; Marqueze, Elaine C; Rotenberg, Lúcia; Fischer, Frida Marina; Moreno, Claudia R C

    2012-01-01

    Shift workers from control centers of electrical systems are a group that has received little attention in Brazil. This study aimed to compare workers' job satisfaction at five control centers of a Brazilian company electrical system, and according to their job titles. The Organization Satisfaction Index (OSI) questionnaire to assess job satisfaction was used. ANOVA was used to compare OSI means, according to job title and control center. The results showed that there is no difference in job satisfaction among job titles, but a significant difference was found according to the control center. A single organizational culture cannot be applied to several branches. It is required to implement actions that would result in job satisfaction improvements among workers of all studied control rooms centers. The high level of education of operators working in all centers might have contributed to the similar values of perceived satisfaction among distinct job titles.

  10. IAEA activities in the field of NPP I and C

    International Nuclear Information System (INIS)

    Gloeckler, O.

    2006-01-01

    The paper discusses the current, and upcoming activities of the IAEA's Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). The following particular I and C-related subjects are discussed in more detail: (1) the relation between improvements in I and C and NPP power up-rating projects, and (2) the I and C and human factor engineering issues of integrating analog and digital I and C systems in hybrid control rooms. (authors)

  11. Control room design and human engineering in power plants

    International Nuclear Information System (INIS)

    Herbst, L.; Hinz, W.

    1981-01-01

    Automation reduces the human work load. Employment of functional areas permits optimization of operational sequences. Computer based information processing makes it possible to output information in accordance with operating requirements. Design based on human engineering principles assures the quality of the interaction between the operator and the equipment. The degree to which these conceptional features play a role in design of power plant control rooms depends on the unit rating, the mode of operation and on the requirements respecting safety and availability of the plant. (orig./RW)

  12. Results of control-room annunciator-systems evaluations

    International Nuclear Information System (INIS)

    Banks, W.W.

    1981-01-01

    Annunciator systems in nuclear power plants tax the operator's ability to cope with large amounts of information. Conventional annunciators do not provide the information in an acceptable way for efficient response, but computer-generated CRT displays have the potential for rectifying this situation. A multidisciplinary team of human factors engineers from EG and G Idaho conducted a study to (a) identify problem areas in reactor control rooms associated with annunciator display systems, (b) provide specific and generic solutions to the problems identified, and (c) provide recommendations and direction for future improvements and research focused on the man/display interface from a human factors engineering perspective

  13. Evaluation of team skills for control room crews

    International Nuclear Information System (INIS)

    Gaddy, C.D.; Koontz, J.L.

    1987-01-01

    Although team training has received considerable attention throughout industry, a systematic approach to team skills training has only recently been proposed for control room crews. One important step of the approach to team skills training is evaluation of team skills. This paper describes methods and resources, and program considerations in team skills evaluation. The three areas pertaining to methods and resources are: development of evaluation criteria, preparation of event scenarios, and instructor training and additional resources. The program considerations include sequencing and coordination of team skills evaluation in the context of an overall operator training program

  14. Nuclear power plant control room operators' performance research

    International Nuclear Information System (INIS)

    Gray, L.H.; Haas, P.M.

    1984-01-01

    A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis

  15. Communications involving the control room of a nuclear power plant

    International Nuclear Information System (INIS)

    MacGregor, J.; Cunningham, B.; Safayeni, F.; Duimering, R.

    1992-04-01

    This study investigated communications within the operations component of a nuclear power plant, with a primary emphasis on control room communications. A structured interview technique was developed following preliminary interviews at the plant, and pretested at AECB headquarters. Patterns were identified from questions asked on communications links, work relationships, miscommunications, procedures, instrumentation and responses to problems. The study was an exploratory one, conducted under a limited budget, to provide background information and to identify areas for further investigation. The report offers recommendations about areas for further research

  16. NFL Films music scoring stage and control room space

    Science.gov (United States)

    Berger, Russ; Schrag, Richard C.; Ridings, Jason J.

    2003-04-01

    NFL Films' new 200,000 sq. ft. corporate headquarters is home to an orchestral scoring stage used to record custom music scores to support and enhance their video productions. Part of the 90,000 sq. ft. of sound critical technical space, the music scoring stage and its associated control room are at the heart of the audio facilities. Driving the design were the owner's mandate for natural light, wood textures, and an acoustical environment that would support small rhythm sections, soloists, and a full orchestra. Being an industry leader in cutting-edge video and audio formats, the NFLF required that the technical spaces allow the latest in technology to be continually integrated into the infrastructure. Never was it more important for a project to hold true to the adage of ``designing from the inside out.'' Each audio and video space within the facility had to stand on its own with regard to user functionality, acoustical accuracy, sound isolation, noise control, and monitor presentation. A detailed look at the architectural and acoustical design challenges encountered and the solutions developed for the performance studio and the associated control room space will be discussed.

  17. Numerical simulation of manual operation at MID stand control room

    International Nuclear Information System (INIS)

    Doca, C.; Dobre, A.; Predescu, D.; Mielcioiu, A.

    2003-01-01

    Since 2000 at INR Pitesti a package of software products devoted to numerical simulation of manual operations at fueling machine control room was developed. So far, specified, designed, worked out and implemented was the PUPITRU code. The following issues were solved: graphical aspects of specific computer - human operator interface; functional and graphical simulation of the whole associated equipment of the control desk components; implementation of the main notation as used in the automated schemes of the control desk in view of the fast identification of the switches, lamps, instrumentation, etc.; implementation within PUPITRU code of the entire data base used in the frame of MID tests; implementation of a number of about 1000 numerical simulation equations describing specific operational MID testing situations

  18. CERN'S TECHNICAL CONTROL ROOM (TCR) A CENTRAL SERVICE FOR EVERYONE

    CERN Multimedia

    Mario Batz / TCR Responsible

    2000-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate equipment services. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number 72201. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity concerns the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, buildings. These systems can either be part of the administrative infrastructure, such as offices or restaurants, or part of the tec...

  19. CERN'S TECHNICAL CONTROL ROOM (TCR) A CENTRAL SERVICE FOR EVERYONE

    CERN Document Server

    Mario Batz

    2002-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate equipment services. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number '72201'. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity concerns the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, buildings. These systems can either be part of the administrative infrastructure, such as offices or restaurants, or part of the t...

  20. CERN'S TECHNICAL CONTROL ROOM (TCR) A CENTRAL SERVICE FOR EVERYONE

    CERN Multimedia

    Mario Batz (TCR Responsible)

    2001-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate equipment services. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number '72201'. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity concerns the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, buildings. These systems can either be part of the administrative infrastructure, such as offices or restaurants, or part of the t...

  1. CERN'S TECHNICAL CONTROL ROOM (TCR) A CENTRAL SERVICE FOR EVERYONE

    CERN Document Server

    Mario Batz

    2002-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate CERN equipment services or contractors. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number '72201'. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity covers the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, and buildings. These systems can either be part of the administrative infrastructure, such as offices or restaur...

  2. CERN's Technical Control Room (TCR) A Central Service for Everyone

    CERN Document Server

    Mario Batz

    2001-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate equipment services. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number '72201'. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity concerns the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, buildings. These systems can either be part of the administrative infrastructure, such as offices or restaurants, or part of the t...

  3. CERN'S TECHNICAL CONTROL ROOM (TCR) A CENTRAL SERVICE FOR EVERYONE

    CERN Multimedia

    Mario Batz (TCR Responsible)

    2001-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate equipment services. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number 72201. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity concerns the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, buildings. These systems can either be part of the administrative infrastructure, such as offices or restaurants, or part of the tec...

  4. CERN'S TECHNICAL CONTROL ROOM (TCR) A CENTRALSERVICE FOR EVERYONE

    CERN Multimedia

    Mario Batz / TCR Responsible

    2001-01-01

    The Technical Control Room (TCR) monitors and operates the entire technical infrastructure of CERN 24 hours a day, 365 days a year. It registers and dispatches troubleshooting requests to the appropriate equipment services. In addition, the TCR executes first-line interventions on the entire CERN site. Troubleshooting requests are transmitted to the TCR either via a computerised control system or via the phone number '72201'. More than 10'000 such requests are dispatched and dealt with every year. The TCR's diverse field of activity concerns the following systems: electrical and fluid distribution networks, heating, cooling, ventilation, air-conditioning and gas equipment, safety and communication installations, electromechanical systems (e.g. lifts, cranes, machine tools, motorised doors), sanitary systems (leaks, sewage), control and monitoring infrastructure equipment, buildings. These systems can either be part of the administrative infrastructure, such as offices or restaurants, or part of the t...

  5. Design process and philosophy of TVA's latest advance control room complex

    International Nuclear Information System (INIS)

    Owens, G.R.; Masters, D.W.

    1979-01-01

    TVA's latest nuclear power plant control room design includes a greater emphasis on human factors as compared to their earlier plant designs. This emphasis has resulted in changes in the overall design philosophy and design process. This paper discusses some of the prominent design features of both the control room and the surrounding control room complex. In addition, it also presents some of the important activities involved in the process of developing the advanced control room design

  6. Modeling Human Error Mechanism for Soft Control in Advanced Control Rooms (ACRs)

    International Nuclear Information System (INIS)

    Aljneibi, Hanan Salah Ali; Ha, Jun Su; Kang, Seongkeun; Seong, Poong Hyun

    2015-01-01

    To achieve the switch from conventional analog-based design to digital design in ACRs, a large number of manual operating controls and switches have to be replaced by a few common multi-function devices which is called soft control system. The soft controls in APR-1400 ACRs are classified into safety-grade and non-safety-grade soft controls; each was designed using different and independent input devices in ACRs. The operations using soft controls require operators to perform new tasks which were not necessary in conventional controls such as navigating computerized displays to monitor plant information and control devices. These kinds of computerized displays and soft controls may make operations more convenient but they might cause new types of human error. In this study the human error mechanism during the soft controls is studied and modeled to be used for analysis and enhancement of human performance (or human errors) during NPP operation. The developed model would contribute to a lot of applications to improve human performance (or reduce human errors), HMI designs, and operators' training program in ACRs. The developed model of human error mechanism for the soft control is based on assumptions that a human operator has certain amount of capacity in cognitive resources and if resources required by operating tasks are greater than resources invested by the operator, human error (or poor human performance) is likely to occur (especially in 'slip'); good HMI (Human-machine Interface) design decreases the required resources; operator's skillfulness decreases the required resources; and high vigilance increases the invested resources. In this study the human error mechanism during the soft controls is studied and modeled to be used for analysis and enhancement of human performance (or reduction of human errors) during NPP operation

  7. Modeling Human Error Mechanism for Soft Control in Advanced Control Rooms (ACRs)

    Energy Technology Data Exchange (ETDEWEB)

    Aljneibi, Hanan Salah Ali [Khalifa Univ., Abu Dhabi (United Arab Emirates); Ha, Jun Su; Kang, Seongkeun; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2015-10-15

    To achieve the switch from conventional analog-based design to digital design in ACRs, a large number of manual operating controls and switches have to be replaced by a few common multi-function devices which is called soft control system. The soft controls in APR-1400 ACRs are classified into safety-grade and non-safety-grade soft controls; each was designed using different and independent input devices in ACRs. The operations using soft controls require operators to perform new tasks which were not necessary in conventional controls such as navigating computerized displays to monitor plant information and control devices. These kinds of computerized displays and soft controls may make operations more convenient but they might cause new types of human error. In this study the human error mechanism during the soft controls is studied and modeled to be used for analysis and enhancement of human performance (or human errors) during NPP operation. The developed model would contribute to a lot of applications to improve human performance (or reduce human errors), HMI designs, and operators' training program in ACRs. The developed model of human error mechanism for the soft control is based on assumptions that a human operator has certain amount of capacity in cognitive resources and if resources required by operating tasks are greater than resources invested by the operator, human error (or poor human performance) is likely to occur (especially in 'slip'); good HMI (Human-machine Interface) design decreases the required resources; operator's skillfulness decreases the required resources; and high vigilance increases the invested resources. In this study the human error mechanism during the soft controls is studied and modeled to be used for analysis and enhancement of human performance (or reduction of human errors) during NPP operation.

  8. Re-envisioning the operator consoles for Dhruva control room

    International Nuclear Information System (INIS)

    Gaur, S.; Sridharan, P.; Nair, P.M.; Diwakar, M.P.; Gohel, N.; Pithawa, C.K.

    2012-01-01

    Control Room design is undergoing rapid changes with the progressive adoption of computerization and Automation. Advances in man-machine interfaces have further accelerated this trend. This paper presents the design and main features of Operator consoles (OC) for Dhruva control room developed using new technologies. The OCs have been designed so as not to burden the operator with information overload but to help him quickly assess the situation and timely take appropriate steps. The consoles provide minimalistic yet intuitive interfaces, context sensitive navigation, display of important information and progressive disclosure of situation based information. The use of animations, 3D graphics, and real time trends with the benefit of hardware acceleration to provide a resolution independent rich user experience. The use of XAML, an XML based Mark-up Language for User Interface definition and C for application logic resulted in complete separation of visual design, content, and logic. This also resulted in a workflow where separate teams could work on the UI and the logic of an application. The introduction of Model View View-Model has led to more testable and maintainable software. (author)

  9. 76 FR 35130 - Pipeline Safety: Control Room Management/Human Factors

    Science.gov (United States)

    2011-06-16

    ...: Control Room Management/Human Factors AGENCY: Pipeline and Hazardous Materials Safety Administration... the Control Room Management/Human Factors regulations in order to realize the safety benefits sooner... FR 5536). By this amendment to the Control Room Management/Human Factors (CRM) rule, an operator must...

  10. 75 FR 69912 - Pipeline Safety: Control Room Management/Human Factors

    Science.gov (United States)

    2010-11-16

    ... 192 and 195 [Docket ID PHMSA-2007-27954] RIN 2137-AE64 Pipeline Safety: Control Room Management/Human... Control Room Management/Human Factors rule at 49 CFR 192.631 and 195.446. The NPRM proposes to expedite... rule and to engage in open discussions with the agency at PHMSA's Control Room Management...

  11. Determination and elimination of the reasons for increased control rod insertion time of the Kozloduy NPP WWER-1000

    International Nuclear Information System (INIS)

    Nikolov, K.

    1996-01-01

    The emergency insertion speed of the control rod upon reactor shutdown is of crucial importance for reactor safety. The designed insertion time for WWER-1000 reactors should be in the limits 1,5 to 4 s. Having in mind some data about increased insertion times of WWER-1000 type reactors in Russia and Ukraine, a practice of measuring this parameters during each planned outage of the Kozloduy NPP Unit 6 is introduced. Some technical improvements of the fuel assembly are made in order to reach the nominal parameters of the unit

  12. Optimizing the human engineering design of control panels in nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Behrendt, V.; Krehbiehl, T.; Hartfiel, H.D.; Mannhaupt, H.R.

    1986-12-01

    The study contains two parts. In the first part an analytical procedure is developed to logically and reproducibly subdivide the control room personnel tasks resulting in a list of the elements (operations) and the structure (operations scheme) of a task. The second part lists together all knowledge of and influences on human engineering which are known at this time and which should be taken into account in designing control rooms. The content of this catalogue can best be used and presented by using a personal computer. Two fundamental different ways are possible to use the catalogue. Designing new control rooms or new parts of control rooms the results of the task analysis which should be done first, should guide the search in the catalogue to find the right human engineering factors. For assessing existing control room panels the performance shaping factors which are establishing the table of content, permit a quick access to the catalogue. Both the specific procedure of the task analysis and the different ways of access to the catalogue of human engineering knowledge for designing nuclear power plant control rooms have been proven by experienced system engineers and safety experts. The results are presented. They have been considered in this version of the study. (orig.) [de

  13. Consequences of modern information display technologies in power plant control rooms. What has changed in control rooms?

    International Nuclear Information System (INIS)

    Kruip, Jochen

    2007-01-01

    Control rooms of power plants have undergone major developments and changes, some of them considerable, over the past few years. The most visible change has been the display of information on a variety of video screens and projectors. The question examined in the article is whether the visible or invisible changes in power plant control rooms have any influence on the training of operators. In a contribution coming from the Simulator Center, this question naturally focuses on simulator training, which is to be discussed in the light of the basic objectives of this type of training. The main duty of the Essen Simulator Center is to offer first training and in-career training to the licensed operators of nuclear power plants. The experience accumulated in nearly thirty years of simulator training has been laid down in the 'Kompendium der Simulatorschulung' (Handbook of Simulator Training). Simulator training, as referred to above, is a major component of all training programs. The two main objectives of simulator training are 'reliability in operation' and 'experience' in handling the new information systems and digital I and C systems. In the future, simulators can also be used for advanced developments and for advance testing and training. (orig.)

  14. Evaluation of new control rooms by operator performance analysis

    International Nuclear Information System (INIS)

    Mori, M; Tomizawa, T.; Tai, I.; Monta, K.; Yoshimura, S.; Hattori, Y.

    1987-01-01

    An advanced supervisory and control system called PODIA TM (Plant Operation by Displayed Information and Automation) was developed by Toshiba. Since this system utilizes computer driven CRTs as a main device for information transfer to operators, thorough system integration tests were performed at the factory and evaluations were made of operators' assessment from the initial experience of the system. The PODIA system is currently installed at two BWR power plants. Based on the experiences from the development of PODIA, a more advanced man-machine interface, Advanced-PODIA (A-PODIA), is developed. A-PODIA enhances the capabilities of PODIA in automation, diagnosis, operational guidance and information display. A-PODIA has been validated by carrying out systematic experiments with a full-scope simulator developed for the validation. The results of the experiments have been analyzed by the method of operator performance analysis and applied to further improvement of the A-PODIA system. As a feedback from actual operational experience, operator performance data in simulator training is an important source of information to evaluate human factors of a control room. To facilitate analysis of operator performance, a performance evaluation system has been developed by applying AI techniques. The knowledge contained in the performance evaluation system was elicited from operator training experts and represented as rules. The rules were implemented by employing an object-oriented paradigm to facilitate knowledge management. In conclusion, it is stated that the feedback from new control room operation can be obtained at an early stage by validation tests and also continuously by comprehensive evaluation (with the help of automated tools) of operator performance in simulator training. The results of operator performance analysis can be utilized for improvement of system design as well as operator training. (author)

  15. An expert display system and nuclear power plant control rooms

    International Nuclear Information System (INIS)

    Beltracchi, L.

    1988-01-01

    An expert display system controls automatically the display of segments on a cathode ray tube's screen to form an image of plant operations. The image consists of an icon of: 1) the process (heat engine cycle), 2) plant control systems, and 3) safety systems. A set of data-driven, forward-chaining computer stored rules control the display of segments. As plant operation changes, measured plant data are processed through the rules, and the results control the deletion and addition of segments to the display format. The icon contains information needed by control rooms operators to monitor plant operations. One example of an expert display is illustrated for the operator's task of monitoring leakage from a safety valve in a steam line of a boiling water reactor (BWR). In another example, the use of an expert display to monitor plant operations during pre-trip, trip, and post-trip operations is discussed as a universal display. The viewpoints and opinions expressed herein are the author's personal ones, and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, or guidelines

  16. How does a change in the control room design affect diagnostic strategies in nuclear power plants?

    International Nuclear Information System (INIS)

    Kim, Dong Young; Kim, Jonghyun

    2014-01-01

    Recently, main control rooms have been considerably changed by modern computer techniques. Some of the features that distinguish digital control rooms from conventional, analog rooms in nuclear power plants include advanced alarm systems, graphic information display systems, computerized procedure systems, and soft control. These features can bring changes in operator tasks, changing the characteristics of tasks or creating new tasks for operators. It is especially expected that these features may bring out changes in the operator's diagnostic tasks and strategies in a digital control room as compared with an analog control room. This study investigates the differences in the operator's diagnostic tasks and strategies in analog and digital control rooms. This study also attempts to evaluate how new systems in a digital control room affect diagnostic strategies. Three different approaches, which are complementary, are used to identify diagnostic strategies in the digital control room and in the analog control room: (1) observation in the simulator, (2) interview with operators, and (3) a literature review. The results show that the digital control room introduces new diagnosis strategies compared with the analog control room while also changing the characteristics of the strategies, mostly by gaining more support from the computerized system. (author)

  17. Revised accident source terms and control room habitability

    International Nuclear Information System (INIS)

    Lahti, G.P.; Hubner, R.S.; Johnson, W.J.; Schwartz, B.C.

    1993-01-01

    In April 1992, the NRC staff presented to the Commissioners the draft NUREG open-quotes Revised Accident Source Terms for Light-Water Nuclear Power Plants.close quotes This document is the culmination of more than ten years of NRC-sponsored research and represents the first change in the NRC's position on source terms since TID-14844 was issued in 1962. The purpose of this paper is to investigate the impact of the revised source terms on the current approach to analyzing control room habitability as required by 10 CFR 50. Sample calculations are presented that identify aspects of the model requiring clarification before the implementation of the revised source terms. 6 refs., 4 tabs

  18. The using of the control room automation against human errors

    International Nuclear Information System (INIS)

    Kautto, A.

    1993-01-01

    The control room automation has developed very strongly during the 80's in IVO (Imatran Voima Oy). The former work expanded strongly with building of the full scope training simulator to the Loviisa plant. The important milestones has been, for example the testing of the Critical Function Monitoring System, a concept developed by Combustion Eng. Inc., in Loviisa training simulator 1982, the replacing of the process and simulator computers in Loviisa 1989, and 1990 and the presenting the use of the computer based procedures in training of operators 1993. With developing of automation and procedures it is possible to minimize the probability of human error. However, it is not possible totally eliminate the risks caused by human errors. (orig.)

  19. Advanced control room design review guidelines: Merging old and new

    International Nuclear Information System (INIS)

    Carter, R.J.; Wachtel, J.A.

    1992-01-01

    The nuclear power industry is currently developing operator interface systems based on innovative applications of digital computers. To assure that this advanced technology is incorporated in a way that maximizes the potential safety benefits of the technology and minimizes the potential negative effects on human performance, human factors principles must be considered. NUREG-0700 contains guidelines for the review of operator interfaces. However, in light of the rapid technological advances in digital technology which have taken place in the eleven years since its publication, it is no longer adequate to assess the rapidly changing human-system interfaces. A research program, the purpose of which is to upgrade NUREG-0700, has been initiated. Thus far a set of draft advanced control room design review (ACRDR) guidelines has been complied. Three tasks, which were oriented towards integrating the applicable guidelines in NUREG-0700 into the ACRDR document, are described in the paper

  20. LOFT advanced control room operator diagnostic and display system (ODDS)

    International Nuclear Information System (INIS)

    Larsen, D.G.; Robb, T.C.

    1980-01-01

    The Loss-of-Fluid Test (LOFT) Reactor Facility in Idaho includes a highly instrumented nuclear reactor operated by the Department of Energy for the purpose of establishing nuclear safety requirements. The results of the development and installation into LOFT of an Operator Diagnostic and Display System (ODDS) are presented. The ODDS is a computer-based graphics display system centered around a PRIME 550 computer with several RAMTEK color graphic display units located within the control room and available to the reactor operators. Use of computer-based color graphics to aid the reactor operator is discussed. A detailed hardware description of the LOFT data system and the ODDS is presented. Methods and problems of backfitting the ODDS equipment into the LOFT plant are discussed

  1. An approach to enhanced control room crew performance

    International Nuclear Information System (INIS)

    Frye, S.R.

    1988-01-01

    The function of a nuclear power plant control room team is similar to that of an airline cockpit crew or a critical task military team such as a flight crew, tank crew, combat squad or platoon. These teams encounter many of the same problems or challenges in their environments when dealing with abnormal or emergency situations. The competency of these teams in bringing about successful conclusions in situations depends on their ability to coordinate their actions. This is often referred to as teamwork and includes the interactions between team members which must occur during highly critical situations. The purpose of this paper is to present team skills training and the advances made in this crucial area by utilizing both classroom and high fidelity simulator training

  2. ARCON96, Radioactive Plume Concentration in Reactor Control Rooms

    International Nuclear Information System (INIS)

    Ramsdell, J.V.; Simonen, C.A.

    2003-01-01

    1 - Description of program or function: ARCON96 was developed to calculate relative concentrations in plumes from nuclear power plants at control room air intakes in the vicinity of the release point. 2 - Methods: ARCON96 implements a straight-line Gaussian dispersion model with dispersion coefficients that are modified to account for low wind meander and building wake effects. Hourly, normalized concentrations (X/Q) are calculated from hourly meteorological data. The hourly values are averaged to form X/Qs for periods ranging from 2 to 720 hours in duration. The calculated values for each period are used to form cumulative frequency distributions. 3 - Restriction on the complexity of the problem: ARCON96 is a single user program. If expanded output is selected by the user, the file includes the hourly input and X/Qs and the intermediate computational results. The output file may exceed a megabyte size

  3. Dukovany NPP maintenance management

    International Nuclear Information System (INIS)

    Siegel, F.

    2005-01-01

    Maintenance planning and management for the technological equipment of the Dukovany NPP are described. A Maintenance Control and Evaluation System has been developed and is in use to help manage the complex maintenance issue. Practical examples of outputs of the System, with a comprehensive use of the cost, reliability and safety related data, are presented. (author)

  4. Noble gas control room accident filtration system for severe accident conditions N-CRAFT. System design

    International Nuclear Information System (INIS)

    Hill, Axel

    2014-01-01

    Severe accidents might cause the release of airborne radioactive substances to the environment of the NPP. This can either be due to leakages of the containment or due to a filtered containment venting in order to ensure the overall integrity of the containment. During the containment venting process aerosols and iodine can be retained by the FCVS which prevents long term ground contamination. Noble gases are not retainable by the FCVS. From this it follows that a large amount of radioactive noble gases (e.g. xenon, krypton) might be present in the nearby environment of the plant dominating the activity release, depending on the venting procedure and the weather conditions. Accident management measures are necessary in case of severe accidents and the prolonged stay of staff inside the main control room (MCR) or emergency response center (ERC) is essential. Therefore, the in leakage and contamination of the MRC and ERC with airborne activity has to be prevented. The radiation exposure of the crises team needs to be minimized. The entrance of noble gases cannot be sufficiently prevented by the conventional air filtration systems such as HEPA filters and iodine absorbers. With the objective to prevent an unacceptable contamination of the MCR/ERC atmosphere by noble gases AREVA GmbH has developed a noble gas retention system. The noble gas control room accident filtration system CRAFT is designed for this case and provides supply of fresh air to the MCR/ERC without time limitation. The retention process of the system is based on the dynamic adsorption of noble gases on activated carbon. The system consists of delay lines (carbon columns) which are operated by a continuous and simultaneous adsorption and desorption process. These cycles ensure a periodic load and flushing of the delay lines retaining the noble gases from entering the MCR. CRAFT allows a minimization of the dose rate inside MCR/ERC and ensures a low radiation exposure to the staff on shift maintaining

  5. Ergonomic design of an overview display in a nuclear power plant control room. Integrated process status overview

    International Nuclear Information System (INIS)

    Bouwmeester, R.

    1996-03-01

    A major modification of the Borssele Nuclear Power Plant (NPP), scheduled in 1997, includes the installation of a new Integrated Process Status Overview (IPSO) display in the extensively modified control room. The IPSO display is to promote effective communications among all individuals present in the control room with a clear overview of the main process systems. The flexible LCD rear-projection technique is selected for the replacement of the existing IPSO display with engraved process symbols and hard-wired LEDs. The relation between the IPSO display and the CRT based Process Presentation System (PPS) is described after an elaborate introduction to the nuclear technology and the modification project. The followed IPSO design methodology includes interviews with all IPSO user groups to acquire their experience and comment on the current IPSO in order to enhance the functionality and the acceptance of the new IPSO graphics. The ergonomic design requirements for the new IPSO display concern both generic aspects of information presentation on human-machine interfaces, as well as specific issues related to the selected LCD rear-projection technique. Intermediate stages in the design of the IPSO graphics are outlined as well as the results of the concept evaluation by the user groups. For special interest the functionality of a three dimensional (3-D) display was explored. The design study concludes with a 'final' IPSO graphics design to be used for evaluations on the control room simulator. The presentation of one graphic was found to be most appropriate with adjustment of colour (grey) of components and systems which do not need to operate during the current process conditions or plant mode. (orig.)

  6. Room 305/2 of the unit 4 of the Chernobyl ChNPP: its condition, evaluation of the fuel bulk

    International Nuclear Information System (INIS)

    Borovoj, A.A.; Pazukhin, Eh.M.; Lagunenko, A.S.

    1998-01-01

    The question on the bulk of the spent nuclear fuel in the room 305/2 of the Unit 4 has been given consideration. On the basis of the results of direct observations, tele- and photo shooting, data of chemical analysis of samples and measurement of the maximum exposure dose rate on drilling detailed model of the main elements relative position in the former core has been developed. Minimum fuel bulk in the room 305/2 has been evaluated

  7. Control room inleakage testing using tracer gases at Zion Generating station

    International Nuclear Information System (INIS)

    Lagus, P.L.; Brown, J.H.; Dubois, L.J.; Fleming, K.M.

    1993-01-01

    In order to assess the amount of air inleakage into the Control Room Envelope at Zion Generating Station (ZGS), a series of tracer gas tests using sulfur hexafluoride (SF 6 ) were performed on the Control Room ventilation system (PV system) and the Computer Room/Miscellaneous Area ventilation system (OV system) during February, 1991. Two redundant trains, denoted A and B comprise the PV system. Inleakage was measured for each train. An OV supply duct passes through the Control Room Envelope. Leakage from this duct into the Control Room would constitute air leakage into the Control room Envelope and hence any potential leakage had to be quantified. Each test attempted to measure the contribution (if any) of a particular section of PV return duct or OV supply duct to the total air inleakage into the Control Room. This paper reviews the tracer gas tests. Described here are the control room inleakage testing, HVAC equipment room duct inleakage, purge plenum inleakage, OV duct leakage into the control room envelope, vestibule PV return inleakage, TSC duct inleakage, and cable spreading room inleakage. Conclusions from the testing are presented. 5 refs., 4 figs., 7 tabs

  8. 3D visualization based customer experiences of nuclear plant control room

    International Nuclear Information System (INIS)

    Sun Tienlung; Chou Chinmei; Hung Tamin; Cheng Tsungchieh; Yang Chihwei; Yang Lichen

    2011-01-01

    This paper employs virtual reality (VR) technology to develop an interactive virtual nuclear plant control room in which the general public could easily walk into the 'red zone' and play with the control buttons. The VR-based approach allows deeper and richer customer experiences that the real nuclear plant control room could not offer. When people know more about the serious process control procedures enforced in the nuclear plant control room, they will appropriate more about the safety efforts imposed by the nuclear plant and become more comfortable about the nuclear plant. The virtual nuclear plant control room is built using a 3D game development tool called Unity3D. The 3D scene is connected to a nuclear plant simulation system through Windows API programs. To evaluate the usability of the virtual control room, an experiment will be conducted to see how much 'immersion' the users could feel when they played with the virtual control room. (author)

  9. Multipurpose expert-robot system model for control, diagnosis, maintenance, and repairs at the steam generators of the NPP

    International Nuclear Information System (INIS)

    Popa, I.

    1994-01-01

    The paper presents the model concept for a multipurpose expert-robot system for control, diagnosis, forecast, maintenance, and repairs at the steam generators of CANDU type nuclear power plants. The system has two separate parts: the expert system and the robot (manipulator) system. These parts compose a hierarchic structure with the expert system on the upper level. The expert system has a blackboard architecture, to which tree interfaces with the robot system, with the control system of the NPP and with the methods and techniques of control, maintenance and repairs system of the steam generator are added. Due to complex nature of its activities the expert-robot system model combines the deterministic type reasons with probabilistic, fuzzy, and neural-networks type ones. The information that enter the expert system comes from the robot system, from process, from user, and human expert. The information that enter robot system comes from the expert system, from the human operator (when connected) and from process. Control maintenance and repair operations take place by means of the robot system that can be monitored either directly by the expert system or by the human operator who follows its activity. All these activities are performed in parallel with the adequate information of the expert system directly, by the human operator, about the status parameters and, possibly, operating parameters of the steam generator components. The expert-robot system can work independently, but it can be connected and integrated in the control system of NPP, to take over and develop some of its functions. The activities concerning diagnosis and characterization of the state of steam generator components subsequent to control, as well as the forecast of their future behavior, are performed by means of the expert system. Due to these characteristics the expert-robot system can be used successfully in personnel training activities. (Author)

  10. ISACS-1, a limited prototype of an advanced control room

    International Nuclear Information System (INIS)

    Follesoe, K.; Foerdestroemmen, N.; Haugset, K.; Holmstroem, C.

    1994-01-01

    The concept of an Integrated Surveillance And Control System (ISACS) has been developed into a prototype, ISACS-1, which presently is in operation at the simulator-based experimental control room HAMMLAB of the OECD Halden Reactor Project. Characteristics of ISACS is that it covers the whole interface between the process and the operator, and this interface is fully computerized using tools like Cathode Ray Tubes (CRTs) and dynamic keyboards. In addition, a large number of computerized operator support systems (COSSs) are included in ISACS, assisting the operator in functions like disturbance detection and diagnosis, identification of relevant actions, and implementation of procedures. An information coordinator called ''Intelligent Coordinator'' (IC) in ISACS observes the information received from the process and the COSSs, generates new high-level information and structures and prioritizes information to be presented to the operator. The limited ISACS-1 prototype was completed in early 1991. An extensive evaluation programme is in progress. This paper will describe main features of the system and some of the conclusions to be drawn from the evaluation programme. (author). 5 refs, 2 figs

  11. Deployment of a Full-Scope Commercial Nuclear Power Plant Control Room Simulator at the Idaho National Laboratory

    International Nuclear Information System (INIS)

    Boring, Ronald; Persensky, Julius; Thomas, Kenneth

    2011-01-01

    The INL operates the HSSL to conduct research in the design and evaluation of advanced reactor control rooms, integration of intelligent support systems to assist operators, development and assessment of advanced human performance models, and visualizations to assess advanced operational concepts across various infrastructures. This advanced facility consists of a reconfigurable simulator and a virtual reality capability (known as the Computer-Aided Virtual Environment (CAVE)) (Figure 2). It supports human factors research, including human-in-the-loop performance, HSI, and analog and digital hybrid control displays. It can be applied to the development and evaluation of control systems and displays for complex systems such as existing and advanced NPP control rooms, command and control systems, and advance emergency operations centers. The HSSL incorporates a reconfigurable control room simulator, which is currently housed in the Center for Advanced Energy Studies (CAES), a joint venture of the DOE and the Idaho University System. The simulator is a platform- and plant-neutral environment intended for full-scope and part-task testing of operator performance in various control room configurations. The simulator is not limited to a particular plant or even simulator architecture. It can support engineering simulator platforms from multiple vendors using digital interfaces. Due to its ability to be reconfigured, it is possible to switch the HSI - not just to digital panels but also to different control modalities such as those using greater plant automation or intelligent alarm filtering. The simulator currently includes three operator workstations, each capable of driving up to eight 30-inch monitors. The size and number of monitors varies depending on the particular front-end simulator deployed for a simulator study. These operator workstations would typically be used for the shift supervisor or senior reactor operator, reactor operator, and assistant reactor

  12. Deployment of a Full-Scope Commercial Nuclear Power Plant Control Room Simulator at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Ronald Boring; Julius Persensky; Kenneth Thomas

    2011-09-01

    The INL operates the HSSL to conduct research in the design and evaluation of advanced reactor control rooms, integration of intelligent support systems to assist operators, development and assessment of advanced human performance models, and visualizations to assess advanced operational concepts across various infrastructures. This advanced facility consists of a reconfigurable simulator and a virtual reality capability (known as the Computer-Aided Virtual Environment (CAVE)) (Figure 2). It supports human factors research, including human-in-the-loop performance, HSI, and analog and digital hybrid control displays. It can be applied to the development and evaluation of control systems and displays for complex systems such as existing and advanced NPP control rooms, command and control systems, and advance emergency operations centers. The HSSL incorporates a reconfigurable control room simulator, which is currently housed in the Center for Advanced Energy Studies (CAES), a joint venture of the DOE and the Idaho University System. The simulator is a platform- and plant-neutral environment intended for full-scope and part-task testing of operator performance in various control room configurations. The simulator is not limited to a particular plant or even simulator architecture. It can support engineering simulator platforms from multiple vendors using digital interfaces. Due to its ability to be reconfigured, it is possible to switch the HSI - not just to digital panels but also to different control modalities such as those using greater plant automation or intelligent alarm filtering. The simulator currently includes three operator workstations, each capable of driving up to eight 30-inch monitors. The size and number of monitors varies depending on the particular front-end simulator deployed for a simulator study. These operator workstations would typically be used for the shift supervisor or senior reactor operator, reactor operator, and assistant reactor

  13. Qinshan 300Mwe NPP full scope simulator upgrade

    International Nuclear Information System (INIS)

    Qi Kelin; Li Qing; Liu Wei, Lai Shengyuan

    2006-01-01

    On April 28,2004, RINPO was awarded the project for Qinshan 300Mwe NPP full scope simulator upgrade, the SAT (site acceptance test) was completed on June 30 2005 and the simulator put into operator training again. Scope of upgrade includes: computer system (DGI server and workstations) all replaced by microcomputers; G2 I/O controllers all replaced by RTP EIOBC; Unix-based simulation support environment replaced by RINPO's PC-based simulation environment RINSIMTM, Instructor software replaced by RINPO's PC-based instructor software with function and diagram redesigned; DEH, Feed-water control and some other digital control systems redeveloped to follow NPP modifications; desk-top simulator with soft panel control room developed as byproduct; most of the models not changed but it is planned the reactor core and PPC model will be upgraded in near future. SAT of upgrade demonstrates that the performance of the simulator much improved after the upgrade. (author)

  14. Ergonomics in the licensing and evaluation of nuclear reactors control room

    International Nuclear Information System (INIS)

    Santos, Isaac Jose Antonio Luquetti dos; Vidal, Mario Cesar Rodriguez

    2002-01-01

    A nuclear control room is a complex system that controls a thermodynamic process used to produce electrical energy. The operators interact with the control room through interfaces that have significant implications to nuclear plant safety and influence the operator activity. The TMI (Three Mile Island) accident demonstrated that only the anthropometric aspects were not enough for an adequate nuclear control room design. The studies showed that the accident was aggravated because the designers had not considered adequately human factor aspects. After TMI accident, the designers introduce in the nuclear control room development only human factors standards and human factors guidelines. The ergonomics approaches was not considered. Our objective is introduce in nuclear control room design and nuclear control room evaluation, a methodology that. includes human factors standards, human factors guidelines and ergonomic approaches, the operator activity analysis. (author)

  15. Virtual reality applied in the ergonomic evaluation of nuclear power plant control room

    International Nuclear Information System (INIS)

    Gatto, Leandro Barbosa da Silveira

    2012-01-01

    A nuclear power plant control room is a complex system that controls a nuclear and thermodynamic process used to produce electrical energy. The operators interact with the control room through interfaces that have significant implications to nuclear power plant safety and influence the operator activity. The operator activity presents complexity features and shows a series of mechanisms absents from the human factors guidelines, important to the evaluation and update of control rooms. The ergonomics approach considers the operation strategies, the interaction between the operators, the operator-system interaction, and interaction between operators and support groups. The main objective of this paper is propose the modeling of a nuclear control room, with the support of a game engine core. This tool will be used in the ergonomic evaluation of nuclear control room, generating information and data that will make possible the adequacy of control rooms features to the legal requirements of the regulating agency, assisting the nuclear licensing. (author)

  16. Criteria for the design of the control room complex for a nuclear power generating station

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This Standard addresses the central control room of a nuclear power generating station and the overall complex in which this room is housed. It is not intended to cover special or normally unattended control rooms, such as those provided for radioactive waste handling or for emergency shutdown operations. The nuclear power generating station control room complex provides a protective envelope for plant operating personnel and for instrument and control equipment vital to the operation of the plant during normal and abnormal conditions. In this capacity, the control room complex must be designed and constructed to meet the following criteria contained in Appendix A of 10CFR50, General Design criteria for Nuclear Power Plants: (1) Criterion 2: design bases for protection against natural phenomena; (2) Criterion 3: fire protection; (3) Criterion 4: environmental and missile design bases; (4) Criterion 5: sharing of structures, systems and components (multiunit stations only); and (5) Criterion 19: control room

  17. Analysis on nuclear power plant control room system design and improvement based on human factor engineering

    International Nuclear Information System (INIS)

    Gao Feng; Liu Yanzi; Sun Yongbin

    2014-01-01

    The design of nuclear power plant control room system is a process of improvement with the implementation of human factor engineering theory and guidance. The method of implementation human factor engineering principles into the nuclear power plant control room system design and improvement was discussed in this paper. It is recommended that comprehensive address should be done from control room system function, human machine interface, digital procedure, control room layout and environment design based on the human factor engineering theory and experience. The main issues which should be paid more attention during the control room system design and improvement also were addressed in this paper, and then advices and notices for the design and improvement of the nuclear power plant control room system were afforded. (authors)

  18. Exploring Bridge-Engine Control Room Collaborative Team Communication

    Directory of Open Access Journals (Sweden)

    Aditi Kataria

    2015-06-01

    Full Text Available The EC funded CyClaDes research project is designed to promote the increased impact of the human element in shipping across the design and operational lifecycle. It addresses the design and operation of ships and ship systems. One of the CyClaDes’ tasks is to create a crew-centered design case-study examination of the information that is shared between the Bridge and Engine Control Room that helps the crew co-ordinate to ensure understanding and complete interconnected tasks. This information can be provided in various ways, including communication devices or obtained from a common database, display, or even the ship environment (e.g., the roll of the ship. A series of semi-structured interviews were conducted with seafarers of diverse ranks to get a better idea of what communication does, or should, take place and any problems or challenges existing in current operations, as seen from both the bridge and ECR operators’ perspectives. Included in the interview were both the standard communications and information shared during planning and executing a voyage, as well as special situations such as safety/casualty tasks or heavy weather. The results were analyzed in terms of the goals of the communication, the primary situations of interest for communication and collaboration, the communication media used, the information that is shared, and the problems experienced. The results of seafarer interviews are presented in the paper to explore on-board inter-departmental communication.

  19. Signal validation with control-room information-processing computers

    International Nuclear Information System (INIS)

    Belblidia, L.A.; Carlson, R.W.; Russell, J.L. Jr.

    1985-01-01

    One of the 'lessons learned' from the Three Mile Island accident focuses upon the need for a validated source of plant-status information in the control room. The utilization of computer-generated graphics to display the readings of the major plant instrumentation has introduced the capability of validating signals prior to their presentation to the reactor operations staff. The current operations philosophies allow the operator a quick look at the gauges to form an impression of the fraction of full scale as the basis for knowledge of the current plant conditions. After the introduction of a computer-based information-display system such as the Safety Parameter Display System (SPDS), operational decisions can be based upon precise knowledge of the parameters that define the operation of the reactor and auxiliary systems. The principal impact of this system on the operator will be to remove the continuing concern for the validity of the instruments which provide the information that governs the operator's decisions. (author)

  20. The development of a model of control room operator cognition

    International Nuclear Information System (INIS)

    Harrison, C. Felicity

    1998-01-01

    The nuclear generation station CRO is one of the main contributors to plant performance and safety. In the past, studies of operator behaviour have been made under emergency or abnormal situations, with little consideration being given to the more routine aspects of plant operation. One of the tasks of the operator is to detect the early signs of a problem, and to take steps to prevent a transition to an abnormal plant state. In order to do this CRO must determine that plant indications are no longer in the normal range, and take action to prevent a further move away from normal. This task is made more difficult by the extreme complexity of the control room, and by the may hindrances that the operator must face. It would therefore be of great benefit to understand CRO cognitive performance, especially under normal operating conditions. Through research carried out at several Canadian nuclear facilities we were able to develop a deeper understanding of CRO monitoring of highly automated systems during normal operations, and specifically to investigate the contributions of cognitive skills to monitoring performance. The consultants were asked to develop a deeper understanding of CRO monitoring during normal operations, and specifically to investigate the contributions of cognitive skills to monitoring performance. The overall objective of this research was to develop and validate a model of CRO monitoring. The findings of this research have practical implications for systems integration, training, and interface design. The result of this work was a model of operator monitoring activities. (author)

  1. MIDA - Optimizing control room performance through multi-modal design

    International Nuclear Information System (INIS)

    Ronan, A. M.

    2006-01-01

    Multi-modal interfaces can support the integration of humans with information processing systems and computational devices to maximize the unique qualities that comprise a complex system. In a dynamic environment, such as a nuclear power plant control room, multi-modal interfaces, if designed correctly, can provide complementary interaction between the human operator and the system which can improve overall performance while reducing human error. Developing such interfaces can be difficult for a designer without explicit knowledge of Human Factors Engineering principles. The Multi-modal Interface Design Advisor (MIDA) was developed as a support tool for system designers and developers. It provides design recommendations based upon a combination of Human Factors principles, a knowledge base of historical research, and current interface technologies. MIDA's primary objective is to optimize available multi-modal technologies within a human computer interface in order to balance operator workload with efficient operator performance. The purpose of this paper is to demonstrate MIDA and illustrate its value as a design evaluation tool within the nuclear power industry. (authors)

  2. Automatic radiological control of the working room air at Valduc

    International Nuclear Information System (INIS)

    Herve, J.Y.; Camus, L.; Leroux, J.C.

    1991-01-01

    The facilities of the Centre d'etudes de Valduc, require air control in the different rooms where a radiological hazard exists. To this purpose, every day, the radiation protection technicians put 230 filters on the sampling heads in the working places proximity. To measure any radioactivity retained by the filters, the Valduc Radiation protection service uses an automated system, which identifies the filter origin, carries out the measurements and produces the results. Filters are identified by bar code labels, which are red by an optical reader located in each of the two measurement lines. These are Nu-16 (Numelec Ins.) type low α-and β-activity counting sets, equipped with proportional mode circulation counters. An IBM-PC type microcomputer is used for the whole assembly monitoring and the data centralization. Results can be edited in different forms: daily, monthly, trimestrial or annual results. The system operating mode is satisfying, and has allowed to clear an one-man equivalent work-load [fr

  3. Design And Implementation Of Smart Living Room Wireless Control For Safety Purpose

    OpenAIRE

    Aeindra Myint Lwin; Zaw Min Min Htun; Hla Myo Tun

    2015-01-01

    Abstract This research presents the microcontroller controlled smart living room system using Bluetooth wireless technology from mobile phone.An android apk is created in mobile for controlling the living room system. A 16F877A microcontroller is interfaced serially to a bluetooth module transceiver. It is used for controlling fan speed control dim light control lighting ONOFF and window angle control. An arduino controller is used for keypad control door security. It is connected to DC motor...

  4. The effects of virtual reality displays on visual attention and detection of signals performance for main control room training

    International Nuclear Information System (INIS)

    Lin Shiaufeng; Lin Chiuhsiang Joe; Wang Rouwen; Yang Lichen; Yang Chihwei; Cheng Tsungchieh; Wang Jyhgang

    2011-01-01

    The nuclear power plant (NPP) mainly serve the purpose to provide low-cost and stable electricity for the people, but this purpose must be dependent upon the premise of 'safety first.' The reason for this is that the occurrence of nuclear power plant accidents could cause catastrophic damage to the people, property, society, and the environment. Therefore, training in superior and high reliability system is very important in accident prevention. In recent years, the Virtual Reality (VR) technology advances very fast as well as the technology for e-learning environment. VR systems have been applied for education, safety training of NPP and flying simulators. In particular, VR is an interactive and reactive technology; it allows users to interact and navigate with objects in the virtual environment. Development of VR and simulation techniques contributes to an accurate and immersive training environment for NPP operators. Main Control Room (MCR) training simulator based on VR is a more cost effective and efficient alternative to traditional simulator based training methods. The VR simulation for MCR training is a complex task. Since VR not only reinforces the visual presentation of the training materials but also provides ways to interact with the training system, it becomes more flexible and possibly more powerful in the training system. In the VR training system, the MCR operators may use just one display to view the wide range of the real world displays. The field of view (FOV) will be different from the real MCR environment in which many displays exist for the operators to view. Thus operator's immersion and visual attention will be reduced. This is the problem of MCR virtual training compared with the traditional simulator based training systems. Therefore, improving the operator's visual attention and the detection of signals in VR training system is a very important issue. This investigation intends to contribute in assessing benefits of visual attention and

  5. Emergency control room design of a nuclear reactor used to produce radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Isaac J.A.L. dos; Farias, Larissa P. de; Ponte, Luana T.L.; Goncalves, Gabriel L.; Castro, Heraclito M.; Farias, Marcos S.; Carvalho, Paulo V.R. de; Vianna Filho, Alfredo M.V., E-mail: luquetti@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Departamento Engenharia Nuclear

    2015-07-01

    A control room is defined as a functional entity with an associated physical structure, where the operators carry out the centralized control, monitoring and administrative responsibilities. Emergency control room acts as an alternative control room for the purpose of shutting down or maintaining the facility in a safe shutdown state when the main control room is uninhabitable. The mission of emergency control room is to provide the resources to bring the plant to a safe shutdown condition after an evacuation of the main control room. An evacuation of the main control room is assumed when there is no possibility to accomplish tasks involved in the shutdown except reactor trip. The purpose of this paper is to present a specific approach for the design of the emergency control room of a nuclear reactor used to produce radioisotope. The approach is based on human factors standards and the participation of a multidisciplinary team in the development phase of the design. Using the information gathered from standards and from the multidisciplinary team a 3D Sketch and a 3D printing of the emergency control room were created. (author)

  6. Emergency control room design of a nuclear reactor used to produce radioisotope

    International Nuclear Information System (INIS)

    Santos, Isaac J.A.L. dos; Farias, Larissa P. de; Ponte, Luana T.L.; Goncalves, Gabriel L.; Castro, Heraclito M.; Farias, Marcos S.; Carvalho, Paulo V.R. de; Vianna Filho, Alfredo M.V.

    2015-01-01

    A control room is defined as a functional entity with an associated physical structure, where the operators carry out the centralized control, monitoring and administrative responsibilities. Emergency control room acts as an alternative control room for the purpose of shutting down or maintaining the facility in a safe shutdown state when the main control room is uninhabitable. The mission of emergency control room is to provide the resources to bring the plant to a safe shutdown condition after an evacuation of the main control room. An evacuation of the main control room is assumed when there is no possibility to accomplish tasks involved in the shutdown except reactor trip. The purpose of this paper is to present a specific approach for the design of the emergency control room of a nuclear reactor used to produce radioisotope. The approach is based on human factors standards and the participation of a multidisciplinary team in the development phase of the design. Using the information gathered from standards and from the multidisciplinary team a 3D Sketch and a 3D printing of the emergency control room were created. (author)

  7. Optimization of the main control room habitability system in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Guanghui; Zhao Xinyan

    2013-01-01

    This article describes the optimization of main control room habitability system in nuclear power plant. It also describes the design shortage in terms of habitability in the main control room. Through modification and optimization, habitable conditions are met for personnel staying in the emergency area of the main control room for a period of time, with an aim to take accident intervention measures smoothly and reduce the accident loss and radioactive contamination as low as possible. (authors)

  8. Human factors design review guidelines for advanced nuclear control room technologies

    International Nuclear Information System (INIS)

    O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

    1991-01-01

    Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

  9. Development of control room design in French PWR nuclear power plants

    International Nuclear Information System (INIS)

    Guesnier, G.

    1996-01-01

    The layouts of the control rooms of the French nuclear power stations have undergone great development in the period 1970-1990. The control rooms, with an architecture similar to that of the oil fired power stations, were similar to those of the 1300 MW blocks in which the human factor was emphasised. For the selection of a computerised control room for the N4 series, comprehensive functional and ergonomical validation on a full simulator was required. (author) 3 figs., 7 refs

  10. The Preparation of regulatory resources to control the NPP in Indonesia

    International Nuclear Information System (INIS)

    Aris Sanyoto; Eko Legowo

    2012-01-01

    There are many responses of public in line with the planning to develop nuclear power plant (NPP) in Indonesia; one of them is rejecting it. One of the reasons is worry on the resources as well as the competency of human resources who will operate it. To overcome this situation, therefore it is necessary presence of regulatory authority with capabilities to ensure all requirements to operate the NPP safety and securely. According to the IAEA Safety Guide No GS-G-1.1, in order to have capabilities as regulatory authority, BAPETEN shall have independence resources covering some aspects, such as political, legislative, financial, public information, international, and competency. The independence from the political aspects can be observed from the Act number 10 Year on Nuclear energy, where BAPETEN's organization is directly responsible to President of Republic of Indonesia, meanwhile the independence from legislative aspect where some function such as regulation and guide development, review and assessment , licensing, inspection, research & development, emergency response preparedness and international communication has been covered in its organization structure. Moreover, in order to do its function appropriately BAPETEN shall own technical expertise as recommended by IAEA Tecdoc 1254. Identification of training syllabus, most of the competency has been addressed in the BAPETEN's training program. However, to assess the competency level of every BAPETEN's personnel, especially those 262 with technical education background, it is necessary to do a training need assessment (TNA) process. The result of the process will figure out the gap between the required and existing competency. (author)

  11. Safety aspects on the Asea-Atom BWR 75 control room design

    International Nuclear Information System (INIS)

    Gemst, Paul van; Pedersen, Tor.

    1978-01-01

    The control room is an integrated part of the total plant layout and is located in a special building, known as the control building. The problems of designing a control room meeting all safety requirements and at the same time allowing for modifications to meet special customer specifications are described. (author)

  12. Authorization of nuclear power plant control room personnel: Methods and practices with emphasis on the use of simulators

    International Nuclear Information System (INIS)

    2006-07-01

    In 2002 the IAEA published a revision to Safety Guide NS-G-2.8, Recruitment, Qualification and Training of Personnel for Nuclear Power Plants. This Safety Guide provides recommendations on the authorization of designated personnel who have a direct impact on nuclear safety. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional report be prepared that provided information on the practices in Member States on the use of simulators in the authorization of control room staff. This publication has been prepared in response to that recommendation. In gathering information for the report, Member States were asked to: respond to a survey on the use of simulators and the involvement of regulatory body in operator authorization; and to complete a questionnaire on their practices in authorizing control room staff. Safety analysis and operating experience consistently indicate that human error is a major contributor to nuclear power plant (NPP) accident risk. With the recent world wide emphasis and implementation of full scope simulators for nuclear power plant personnel training, operators spend a large portion of their training time on simulators. As described in the foreword to IAEA-TECDOC-1411, Use of Control Room Simulators for Training of Nuclear Power Plant Personnel, simulators provide operators an opportunity to learn and practice the abilities that are required in accident and infrequently used plant evolutions. Because of their fidelity, full scope simulators are now used by most Member States in the authorization examinations of control room personnel. This situation is becoming more common as more plants acquire modern full scope plant referenced simulators. This publication provides information and examples based upon experience in a variety of Member States. The body of the report provides general information that represents the practices of the Member States that contributed to the

  13. Digital controls for plant control systems at the Ulchin 5 and 6 NPP: Lessons for the U.S. NPP retrofits?

    International Nuclear Information System (INIS)

    McCreary, T.; Stevens, J.

    2006-01-01

    South Korea, through its nuclear operating arm, Korea Hydro and Nuclear Power, Ltd. (KHNP), has been one of the leading countries in the routine construction and operation of nuclear power plants. While standardizing on certain design approaches in the plant, KHNP continues to stress the need for the most reliable and cutting edge I and C technologies available for safety and non safety related NSSS and BOP functions. Its specifications are among the most challenging in the world with regard to the system performance and reliability requirements that must be met for the systems to be supplied. The Ulchin Units 5 and 6 (1000 MW each) nuclear power plants have been recently commissioned (2004 and 2005 respectively) with advanced programmable digital control systems in the NSSS and BOP (which includes both safety and non-safety applications). The systems supplied met what the authors believe are the most rigorous performance and functional specification criteria in use today. The authors will highlight a number of the specification requirements, the rationale for same and the plant experiences in the resultant supplied systems. As the existing U.S. nuclear fleet is faced with the prospect of upgrading legacy controls with digital controls, there are valuable lessons to be learned in the Ulchin 5 and 6 experiences that can be applied to retrofits and even new U.S. plant designs. Ulchin 5 and 6 is one of the success stories in the application of advanced digital technology to nuclear power plants. The specification focus that guided the selection and project execution for the digital controls supplied for Ulchin was on several key areas: a) a high reliable fault tolerant system, b)functional segmentation to minimize the failure effects on operation, c) validation and verification of the owner's engineer's application design (for regulatory compliance) as well as validation and verification of the system architecture and operation (to assure system performance met

  14. A Research Framework for Demonstrating Benefits of Advanced Control Room Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Le Blanc, Katya [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boring, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hallbert, Bruce [Idaho National Lab. (INL), Idaho Falls, ID (United States); Thomas, Kenneth [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-12-01

    Control Room modernization is an important part of life extension for the existing light water reactor fleet. None of the 99 currently operating commercial nuclear power plants in the U.S. has completed a full-scale control room modernization to date. A full-scale modernization might, for example, entail replacement of all analog panels with digital workstations. Such modernizations have been undertaken successfully in upgrades in Europe and Asia, but the U.S. has yet to undertake a control room upgrade of this magnitude. Instead, nuclear power plant main control rooms for the existing commercial reactor fleet remain significantly analog, with only limited digital modernizations. Previous research under the U.S. Department of Energy’s Light Water Reactor Sustainability Program has helped establish a systematic process for control room upgrades that support the transition to a hybrid control. While the guidance developed to date helps streamline the process of modernization and reduce costs and uncertainty associated with introducing digital control technologies into an existing control room, these upgrades do not achieve the full potential of newer technologies that might otherwise enhance plant and operator performance. The aim of the control room benefits research presented here is to identify previously overlooked benefits of modernization, identify candidate technologies that may facilitate such benefits, and demonstrate these technologies through human factors research. This report serves as an outline for planned research on the benefits of greater modernization in the main control rooms of nuclear power plants.

  15. A Research Framework for Demonstrating Benefits of Advanced Control Room Technologies

    International Nuclear Information System (INIS)

    Le Blanc, Katya; Boring, Ronald; Joe, Jeffrey; Hallbert, Bruce; Thomas, Kenneth

    2014-01-01

    Control Room modernization is an important part of life extension for the existing light water reactor fleet. None of the 99 currently operating commercial nuclear power plants in the U.S. has completed a full-scale control room modernization to date. A full-scale modernization might, for example, entail replacement of all analog panels with digital workstations. Such modernizations have been undertaken successfully in upgrades in Europe and Asia, but the U.S. has yet to undertake a control room upgrade of this magnitude. Instead, nuclear power plant main control rooms for the existing commercial reactor fleet remain significantly analog, with only limited digital modernizations. Previous research under the U.S. Department of Energy's Light Water Reactor Sustainability Program has helped establish a systematic process for control room upgrades that support the transition to a hybrid control. While the guidance developed to date helps streamline the process of modernization and reduce costs and uncertainty associated with introducing digital control technologies into an existing control room, these upgrades do not achieve the full potential of newer technologies that might otherwise enhance plant and operator performance. The aim of the control room benefits research presented here is to identify previously overlooked benefits of modernization, identify candidate technologies that may facilitate such benefits, and demonstrate these technologies through human factors research. This report serves as an outline for planned research on the benefits of greater modernization in the main control rooms of nuclear power plants.

  16. Low frequency sound field control in rectangular listening rooms using CABS (Controlled Acoustic Bass System) will also reduce sound transmission to neighbor rooms

    DEFF Research Database (Denmark)

    Nielsen, Sofus Birkedal; Celestinos, Adrian

    2011-01-01

    Sound reproduction is often taking place in small and medium sized rectangular rooms. As rectangular rooms have 3 pairs of parallel walls the reflections at especially low frequencies will cause up to 30 dB spatial variations of the sound pressure level in the room. This will take place not only...... at resonance frequencies, but more or less at all frequencies. A time based room correction system named CABS (Controlled Acoustic Bass System) has been developed and is able to create a homogeneous sound field in the whole room at low frequencies by proper placement of multiple loudspeakers. A normal setup...... from the rear wall, and thereby leaving only the plane wave in the room. With a room size of (7.8 x 4.1 x 2.8) m. it is possible to prevent modal frequencies up to 100 Hz. An investigation has shown that the sound transmitted to a neighbour room also will be reduced if CABS is used. The principle...

  17. Human factors engineering control-room-design review/audit report: Palo Verde Nuclear Generating Station, Arizona Public Service Company

    International Nuclear Information System (INIS)

    Savage, J.W.; Lappa, D.A.

    1981-01-01

    A human factors engineering design review of the Palo Verde control room simulator was performed at the site on September 15 through September 17, 1981. Observed human factors design discrepancies were given priority ratings. This report summarizes the team's observations of the control room design and layout and of the control room operators' interface with the control room environment. A list of the human factors strengths observed in the Palo Verde control room simulator is given

  18. Training, education and qualification of NPP operating personnel in the Netherlands

    International Nuclear Information System (INIS)

    de Vrey, G.A.

    1987-01-01

    This paper outlines the organization and the requirements of the training, education and qualification of NPP operating personnel in the Netherlands. It describes the implementation of a formally required scheme of personnel qualification after TMI, and the current practice as developed by the training staff of both Dutch nuclear power plants. Attention is given to the specific circumstances and problems in the Netherlands, and the resulting program. The licensing criteria for control room operating personnel are discussed, including the level of government involvement. Measures are described to improve the approach to training of NPP personnel involved in safety relevant activities. Finally, some ideas are given for strategies to cope with adverse stress situations

  19. Toxic vapor concentrations in the control room following a postulated accidental release

    International Nuclear Information System (INIS)

    Wing, J.

    1979-05-01

    An acceptable method is presented for calculating the vapor concentrations in a control room as a function of time after a postulated accidental release. Included are the mathematical formulas for computing the rates of vaporization and evaporation of liquid spills, the vapor dispersion in air, and the control room air exchange. A list of toxic chemicals and their physical properties is also given

  20. On-the-job training and qualification of nuclear power plant personnel. OJT at the Loviisa NPP

    International Nuclear Information System (INIS)

    1996-01-01

    On-the-job training and qualification process of nuclear power plant personnel is described, including the following issues: educational system of technical studies in Finland; training methods at the Loviisa NPP; on-the-job training of control room operators,field operators, maintenance personnel, other groups of the plant; qualifying examinations for different jobs

  1. Control of the Environment in the Operating Room.

    Science.gov (United States)

    Katz, Jonathan D

    2017-10-01

    There is a direct relationship between the quality of the environment of a workplace and the productivity and efficiency of the work accomplished. Components such as temperature, humidity, ventilation, drafts, lighting, and noise each contribute to the quality of the overall environment and the sense of well-being of those who work there.The modern operating room is a unique workplace with specific, and frequently conflicting, environmental requirements for each of the inhabitants. Even minor disturbances in the internal environment of the operating room can have serious ramifications on the comfort, effectiveness, and safety of each of the inhabitants. A cool, well-ventilated, and dry climate is optimal for many members of the surgical team. Any significant deviation from these objectives raises the risk of decreased efficiency and productivity and adverse surgical outcomes. A warmer, more humid, and quieter environment is necessary for the patient. If these requirements are not met, the risk of surgical morbidity and mortality is increased. An important task for the surgical team is to find the correct balance between these 2 opposed requirements. Several of the components of the operating room environment, especially room temperature and airflow patterns, are easily manipulated by the members of the surgical team. In the following discussion, we will examine these elements to better understand the clinical ramifications of adjustments and accommodations that are frequently made to meet the requirements of both the surgical staff and the patient.

  2. Climate control of a bulk storage room for foodstuffs

    NARCIS (Netherlands)

    Mourik, van S.; Zwart, H.; Keesman, K.J.

    2006-01-01

    A storage room contains a bulk of agricultural products, such as potatoes, onions, fruits, etcetera. The products produce heat due to respiration, see for example [1, 2]. A ventilator blows cooled air around to keep the products at a steady temperature and prevent spoilage. The aim is to design a

  3. Empirical research on an ecological interface design for improving situation awareness of operators in an advanced control room

    International Nuclear Information System (INIS)

    Kim, Sa Kil; Suh, Sang Moon; Jang, Gwi Sook; Hong, Seung Kweon; Park, Jung Chul

    2012-01-01

    Highlights: ► An EID prototype for monitoring primary side of nuclear power plant is proposed. ► The effectiveness of the prototype is validated using a partial scoped dynamic mockup in terms of situation awareness. ► The validation is based on comparison of a mimic display with an EID plus mimics. - Abstract: The purpose of this study is to validate whether an ecological interface design (EID) improves operators’ situation awareness in an advanced control room of a nuclear power plant (NPP). EID is defined as an approach to interface design that was introduced specifically for complex socio-technical, real-time, and dynamic systems. The EID technology has not yet been adapted to the nuclear power industry due to lack of empirical studies. Especially in a situational awareness aspect, many researchers have predicted that the EID will support operators to detect unanticipated events. Just a few studies, however, unveiled the positive effect of the EID display on human performance using a full scoped simulator. In this study, to investigate whether an EID improves operators’ situational awareness, we developed an EID prototype for nuclear power operations and a partial scoped dynamic mockup to validate the effectiveness of the EID prototype. Three experienced operators were involved as subjects in our study and they were fully well trained for using the EID prototype. We compared two types of situations in terms of situation awareness. One is mimic based information display and the other is a mimic plus EID based information display. The result of our study revealed that a mimic plus EID based information display is more effective than a mimic based information display in terms of situation awareness. This study is significant in that the EID as an emerging technology is adoptable to a digitalized control room in an aspect of improving operators’ situation awareness.

  4. OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring

    2012-10-01

    This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

  5. Integration of analog and digital instrumentation and control systems in hybrid control rooms

    International Nuclear Information System (INIS)

    2010-01-01

    he IAEA's activities in the area of nuclear power plant operating performance and life cycle management are aimed at increasing Member State capabilities in utilizing good engineering and management practices as developed and transferred by the IAEA. In particular, the IAEA supports the improvement of nuclear power plant performance, plant life management, training, power uprating, operational license renewal, and the modernization of instrumentation and control (I and C) systems of plants. The issue of the integration of analog and digital I and C systems in hybrid control rooms was suggested by the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) at its meetings in 2003 and 2005. The subject was then approved by the IAEA and included in its work programmes for 2006-2009. The purpose of this report is to help nuclear utilities in planning control room and other human system interface (HSI) changes, making appropriate use of modern technologies. These technologies would aid in managing ageing and obsolescence, and facilitate improvements in plant performance and safety. This report covers a broad spectrum of potential changes to the control room ranging from the replacement of a few obsolete components with newer digital devices to a fully computerized control room. New digital technologies offer significant opportunities to improve access to and presentation of information to the user, e.g. operators, maintenance staff and management. However, this technology should be used prudently. In some cases, modernization is undertaken to resolve ageing and obsolescence or to meet regulatory requirements for license renewal. The integration of new technologies during main control room (MCR) modernizations should be performed cautiously and all affected aspects of plant maintenance, and operation should be carefully considered, paying particular attention to the human factors elements of these aspects. This report describes a

  6. Controlled laser biochemistry in room-temperature polar liquids by ultrashort laser pulses

    DEFF Research Database (Denmark)

    Gruzdev, Vitaly; Korkin, Dmitry; Mooney, Brian P.

    2018-01-01

    Traditional laser methods to control chemical modifications of biomolecules are not applicable under biologically relevant conditions. We report controlled modifications of peptides and insulin by femtosecond laser in water, methanol, and acetonitrile at room temperature...

  7. Using three-dimension virtual reality main control room for integrated system validation and human reliability analysis

    International Nuclear Information System (INIS)

    Yang Chihwei; Cheng Tsungchieh

    2011-01-01

    This study proposes the performance assessment in three-dimension virtual reality (3D-VR) main control room (MCR). The assessment is conducted for integrated system validation (ISV) purposes, and also for human reliability analyses (HRA). This paper describes the latest developments in 3D-VR applications, designated for the familiarization with MCR, specially taking into account the ISV and HRA. The experiences in 3D-VR application, the benefits and advantages of use of VR in training and maintenances of MCR operators in the target NPP are equally presented in this paper. Results gathered from the performance measurement lead to hazard mitigation and reduces the risk of human error in the operation and maintenance of nuclear equipments. The latest developments in simulation techniques, including 3D presentation enhances the above mentioned benefits, brings the MCR simulators closer to reality. In the near future, this type of 3D solutions should be applied more and more often in the design of MCR simulators. The presented 3D-VR are related to the MCR in NPPs, but the concept of composition and navigation through the system's elements can be easily applied for the purpose of any type of technical equipment and shall contribute in a similar manner to hazard prevention. (author)

  8. Control and diagnostics of technical state of main electro technical and thermal equipment of NPP, TPS and HPS on the basis of thermovision technologies

    International Nuclear Information System (INIS)

    Banduryan, B.B.; Fedorenko, G.M.; Ostapchuk, L.B.; Saratov, V.O.

    2006-01-01

    The opportunity of using of thermovision technologies for detection of defects NPP, TPS and HPS electro technical and power equipment is shown. The results of thermovision monitoring of a turbine generator stator technical state are represented. The method for thermovision control of a technical state of a electrical machines and apparatus construction elements, for which the patent of Ukraine have been obtained, is described. he verification of the offered expedient thermovision control and diagnostics at 'Elektrovazhmash' factory was carried out

  9. A computerized diagnostic system for nuclear plant control rooms based on statistical quality control

    International Nuclear Information System (INIS)

    Heising, C.D.; Grenzebach, W.S.

    1990-01-01

    In engineering science, statistical quality control techniques have traditionally been applied to control manufacturing processes. An application to commercial nuclear power plant maintenance and control is presented that can greatly improve safety. As a demonstration of such an approach to plant maintenance and control, a specific system is analyzed: the reactor coolant pumps of the St. Lucie Unit 2 nuclear power plant located in Florida. A 30-day history of the four pumps prior to a plant shutdown caused by pump failure and a related fire within the containment was analyzed. Statistical quality control charts of recorded variables were constructed for each pump, which were shown to go out of statistical control many days before the plant trip. The analysis shows that statistical process control methods can be applied as an early warning system capable of identifying significant equipment problems well in advance of traditional control room alarm indicators

  10. Investigation on the advanced control room design for next generation nuclear power plants

    International Nuclear Information System (INIS)

    Choi, Seong Soo

    1998-02-01

    An advanced human-machine interface (HMI) has been developed to enhance the safety and availability of a nuclear power plant (NPP) by improving operational reliability. The key elements of the proposed HMI are the large display panels which present synopsis of plant status and the compact, computer-based work stations for monitoring, control and protection functions. The work station consists of four consoles such as a dynamic alarm console (DAC), a system information console (SIC), a computerized operating-procedure console (COC), and a safety system information console (SSIC). The DAC provides clean alarm pictures, in which information overlapping is excluded and alarm impacts are discriminated, for quick situation awareness. The SIC supports a normal operation by offering all necessary system information and control functions over non-safety systems. In addition, it is closely linked to the other consoles in order to automatically display related system information according to situations of the DAC and the COC. The COC aids operators with proper operating procedures during normal plant startup and shutdown or after a plant trip, and it also reduces their physical/mental burden through soft automation. The SSIC continuously displays safety system status and enables operators to control safety systems. With regard to automation, the automating strategies of emergency operation are developed for achieving safe shutdown in pressurized water reactors. These strategies can make emergency operation optimal, and as well they considerably lengthen the operator response time. Decision-making and control are investigated in order to develop the automating strategies. In decision-making, diagnostic trees are established to automate the diagnostic tasks for selecting appropriate emergency operations, and the decision-making procedure is developed to automate some decisions which must be made on a plant- and event-specific basis. In control, cooldown is planned by

  11. Design for the human-machine interface of a digitalized reactor control-room

    International Nuclear Information System (INIS)

    Qu Ronghong; Zhang Liangju; Li Duo; Yu Hui

    2005-01-01

    Digitalized technology is implemented in the instrumentation and control system of an in-construction research reactor, which advances information display in both contents and styles in a nuclear reactor control-room, and greatly improves human-machine interface. In the design for a digitalized nuclear reactor control-room there are a series of new problems and technologies should be considered seriously. This paper mainly introduces the design for the digitalized control-room of the research nuclear reactor and covered topics include design principle of human-machine interface, organization and classification of interface graphics, technologies and principles based on human factors engineering and implemented in the graphics design. (authors)

  12. Implementing Data Acquisition Systems DAS1 and DAS2 at Cernavoda Full-Scope Simulator Main Control Room based on the SIEN2007 solution

    International Nuclear Information System (INIS)

    Ionescu, Ana Maria; Tutuianu, Bogdan; Ionescu, Teodor

    2009-01-01

    Modern personnel training, re-training and licensing is a guarantee of NPP's safe reliable operation. Cernavoda NPP personnel training system is the main objective of its specialized department built up as Training Center (TC), directly supervised by Administration of the National Nuclearelectrica Society (SNN) and National Regulatory Body for Nuclear Activities (CNCAN). It was implemented to ensure the abilities, skills and knowledge required by the safe reliable operation of the nuclear reactor by the Main Control Room (MCR) operators. This objective was reached through training lessons taught and tested on the Full Scope Simulator (FSS), the TC's main training tool, a replica of the MCR of the real plant. Its description is the subject of this paper. The TC's FSS includes a computer network equipped with a software connected to the specialized program DATAPATH supplied for Cernavoda FSS by the FSS provider, delivered by L-3/ MAPPS. An alternative to DATAPATH Communication of the L 3/MAPPS Simulation System, developed by Cernavoda Full Scope Simulator Staff, was presented in the previous edition of the symposium (see the SIEN 2007 paper). This original solution is now already applied in order to connect to simulation process Data Acquisition Systems DAS1 and DAS2, two new systems already installed in the real MCR but not included by the Cernavoda FSS initial design. Communication between simulation software and DAS1 and DAS2, considered to be simple receivers of simulated data both as much alike as the two DASs from real plant, is performed in parallel with DATAPATH in a safe mode and without affecting simulation process. This paperwork presents the above mentioned application of this communication solution, developed by the Cernavoda NPP Full Scope Simulator Staff with details about the hardware/software solutions and their performance, training impact, cost and benefits. (authors)

  13. Have it your way. A modular approach to custom compact control rooms

    International Nuclear Information System (INIS)

    Harmon, Daryl; Scarola, Ken

    2003-01-01

    In spite of the recent lack of growth in the nuclear power industry, a transition is taking place to compact main control rooms as the design of choice for power generating facilities. This is evident in the design and construction of new facilities, including Advanced Light Water Reactors such as the Korean Shin Kori 3 and 4 units, as well as Generation IV reactors. Also, compact control rooms are increasingly preferred for the modernization of current generation plants. This shift reflects that compact control rooms combine cost savings through equipment reduction and standardization with operability improvements through increased functionality and flexibility and improved presentation. Though compact control rooms feature significantly fewer Human Machine Interface (HMI) devices than their conventional counterparts, customers still require a wide variety of different configurations to accommodate their individual operations philosophies, cultural norms, licensing regulations and physical constraints. To meet this need, Westinghouse Electric Company has developed an innovative, modular approach to designing compact control rooms for nuclear power plants. This approach features a small set of standard HMI devices serving as building blocks for all compact control room functions. The building blocks include qualified and non-safety video devices for implementing displays, alarms, multi-channel soft controls, computerized procedures, etc. These building blocks can be used for (1) large screen overview displays, (2) console-based control and monitoring and (3) HMI devices for conventional, benchboard-style control panels. Their modular design allows these building blocks to be arranged in various physical configurations to meet a wide variety of customer's control room preferences and constraints. For example, a compact control room could use the qualified building blocks (1) to configure a dedicated safety panel independent of the normal operational consoles, or (2

  14. Forsmark NPP I and C modernization strategy

    International Nuclear Information System (INIS)

    Hallen, J.; Rydahl, I.; Kloow, L.

    2003-01-01

    By the year 2000, the Forsmark NPP was halfway through the planned plant life. As early as 1995, Forsmark realized that the old analog I and C equipment would need to be replaced before 2005. At the Forsmark NPP they had strength of a vision of an integrated modernization and a strategy to reach the vision. Without vision and strategy, the plant could end up with a fragmented plant I and C-architecture that is not cost-effective or operable. This paper will address several questions that led to the current modernization program in Forsmark, the more important questions are: What would happen if the modernization would be postponed? Which main requirements were to be achieved by means of the modernization strategy? The goal of a completed plant modernization program is a totally integrated system solution and what factors were considered during the modernization? How to gain acceptance from the operational staff in designing Control Room and Soft Control Displays? What are the important roles for the staff and organization to reach the end goal? What has been the experience to date and what are the lessons learned? Thanks to the long term co-operation between Forsmark and Westinghouse the modernization has been very successful for both parties. (orig.)

  15. Nuclear power plant control room ventilation system design for meeting general criterion 19

    International Nuclear Information System (INIS)

    Murphy, K.G.; Campe, K.M.

    1975-01-01

    The requirement for protection of control room personnel against radiation is specified in General Design Criterion 19 of Appendix A, 10 CFR Part 50. The evaluation of a control room design, especially its emergency ventilation system, with respect to radiation protection primarily consists of determining the radiation doses to control room personnel under accident conditions. The accident dose assessment involves modeling and evaluation of radiological source terms, atmospheric transport of airborne activity, and protection features of the control room ventilation system. Some of the assumptions and conservatisms used in the dose analyses are based on the technical review experience of existing or proposed control room designs. A review of over 50 control room designs has revealed a great variety of design concepts, not all of which seem to have been based on radiation protection criteria. A summary of the basic control room protection requirements, design features, dose acceptance criteria, and an outline of the methods used by the Regulatory staff for accident dose evaluation are presented. (U.S.)

  16. The measure and control system of mini-type radon room based on PC104

    International Nuclear Information System (INIS)

    Zhou Shumin; East China Inst. of Technology, Fuzhou; Tang Bin; Sun Yamin

    2005-01-01

    Radon room is one of the standard equipment which demarcates radon measure instrument. The paper discusses the dynamic method and mathematic model which keeps the radon consistence stability in radon room. The system is developed on PC104. The system can monitor the radon consistence and replenishment radon according the radon control parameter. (authors)

  17. Control room design with new automation structures. Leitwartengestaltung bei neuen Automatisierungsstrukturen

    Energy Technology Data Exchange (ETDEWEB)

    Gilson, W

    1984-01-01

    This brochure is concerned with the configuration of modern control rooms, taking new automation structures into account. The configuration of control rooms is treated taking note of new process control systems from the point of view of the requirements and performance, which is well known from process and powerstation technology. Apart from general technical and ergonomic considerations, aspects of work load and work stress are dealt with in detail.

  18. Measuring Human Performance in Simulated Nuclear Power Plant Control Rooms Using Eye Tracking

    Energy Technology Data Exchange (ETDEWEB)

    Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bower, Gordon Ross [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary Alexander [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hill, Rachael Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States); LeBlanc, Katya Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-11-01

    Control room modernization will be an important part of life extension for the existing light water reactor fleet. As part of modernization efforts, personnel will need to gain a full understanding of how control room technologies affect performance of human operators. Recent advances in technology enables the use of eye tracking technology to continuously measure an operator’s eye movement, which correlates with a variety of human performance constructs such as situation awareness and workload. This report describes eye tracking metrics in the context of how they will be used in nuclear power plant control room simulator studies.

  19. Measuring Human Performance in Simulated Nuclear Power Plant Control Rooms Using Eye Tracking

    International Nuclear Information System (INIS)

    Kovesdi, Casey Robert; Rice, Brandon Charles; Bower, Gordon Ross; Spielman, Zachary Alexander; Hill, Rachael Ann; LeBlanc, Katya Lee

    2015-01-01

    Control room modernization will be an important part of life extension for the existing light water reactor fleet. As part of modernization efforts, personnel will need to gain a full understanding of how control room technologies affect performance of human operators. Recent advances in technology enables the use of eye tracking technology to continuously measure an operator's eye movement, which correlates with a variety of human performance constructs such as situation awareness and workload. This report describes eye tracking metrics in the context of how they will be used in nuclear power plant control room simulator studies.

  20. Decommissioning of NPP A-1

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

    In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

  1. Control room design of a nuclear reactor used to produce radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Isaac Jose Antonio Luquetti dos; Carvalho, Paulo Vitor R.; Lacerda, Fabio de; Szabo, Andre P.; Vianna Filho, Alfredo Marques, E-mail: luquetti@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana; Falcao, Mariana A. [Escola de Belas Artes da Universidade Federal do Rio de Janeiro, RJ (Brazil)

    2011-07-01

    A control room is defined as a functional entity with an associated physical structure, where the operators carry out the centralized control, monitoring and administrative responsibilities. Inadequate integration between control room and operators reduces safety, increases the operation complexity, complicates operator training and increases the likelihood of human errors occurrence. The purpose of this paper is to present a specific approach for the design of the main control room of a nuclear reactor used to produce radioisotope. The approach is based on human factors standards and the participation of a multidisciplinary team in the conceptual and basic phases of the design. Using the information gathered from standards and from the multidisciplinary an initial sketch 3D of the main control room is being developed. (author)

  2. Control room design of a nuclear reactor used to produce radioisotope

    International Nuclear Information System (INIS)

    Santos, Isaac Jose Antonio Luquetti dos; Carvalho, Paulo Vitor R.; Lacerda, Fabio de; Szabo, Andre P.; Vianna Filho, Alfredo Marques

    2011-01-01

    A control room is defined as a functional entity with an associated physical structure, where the operators carry out the centralized control, monitoring and administrative responsibilities. Inadequate integration between control room and operators reduces safety, increases the operation complexity, complicates operator training and increases the likelihood of human errors occurrence. The purpose of this paper is to present a specific approach for the design of the main control room of a nuclear reactor used to produce radioisotope. The approach is based on human factors standards and the participation of a multidisciplinary team in the conceptual and basic phases of the design. Using the information gathered from standards and from the multidisciplinary an initial sketch 3D of the main control room is being developed. (author)

  3. Research on control function switch of nuclear power plant control room

    International Nuclear Information System (INIS)

    Mei Shibo; Mao Ting; Cheng Bo; Zhang Gang

    2014-01-01

    The nuclear power plant provides main control room (MCR) to the unit operators for the plant monitoring and control, and provides the remote shutdown station (RSS) as the back-up control room, which is used only when MCR is unavailable. The RSS could be used to monitor and control the plant, bring the plant into shutdown state and remove the residual heat. The command from MCR and RSS is blocked by each other and can not be executed at the same time. The operation mode switch function between MCR and RSS is carried out by MCR/RSS mode switches. The operation mode switch scheme of CPR1000, ERP and AP1000 were compared and researched, and some design bases for new nuclear power plant were submitted in this paper. These design bases could be referred during the design of control function switch for the new nuclear power plants, in order to put forward a more practical, simple, safe and convenient scheme. (authors)

  4. NPP Krsko full scope simulator verification and qualification

    International Nuclear Information System (INIS)

    Krajnc, B.; Glaser, B.; Novsak, M.; Spiler, J.

    1998-01-01

    NPP Krsko (NEK) will, as a part of the Modernization plan, obtain also Krsko Full Scope Simulator (KFSS). Contract has been awarded to CAE Electronics for the design, construction and integration. KFSS will support in real time, the training for the complete range of operation, which can be performed from the main control room and some selected plant areas (remote shutdown panels, etc). Based on the lessons learned on development of NPP Krsko Basic Principle Simulator we decided for active approach. That means that NPP Krsko personnel will be heavily involved into all phases of KFSS development and testing. Since NPP Krsko is going to replace the existing steam generators, raise the nominal power and perform necessary modifications to support the power uprate, it was decided that the development of the KFSS will be conducted in two steps: 1. Development of the models as well as all the hardware interface in the MCR for the existing plant Cycle 15 and then, 2. Models and hardware will be modified, added or replaced as needed to take into account the steam generator replacement and plant uprate projects. In spite of the fact that the simulator will be used for the training of the plant operators for the uprated conditions and with new steam generators, the upper described approach was selected since we want to be sure that the models will at the beginning adequately simulate the existing plant. For the existing conditions we have available reference data for different plant conditions, as well as data for different plant transients. By verifying that simulator will be able adequately simulate the existing conditions the level of confidence for the uprated simulator will be much higher. This is of special importance since it will support initial training for modernized plant conditions. In this paper the plan for verification and qualification of KFSS as well as the amount of the work needed on NPP Krsko side to develop the test acceptance criteria will be presented.(author)

  5. Diffusion and Evaporation-Controlled Emission in Ventilated Rooms

    DEFF Research Database (Denmark)

    Topp, Claus

    and sources. This work provides an investigation based on fundamental fluid dynamics and mass transfer theory to obtain a general understanding of the mechanisms involved in the emission from building materials in ventilated rooms. In addition, a generally applicable model for prediction of surface emission...... is proposed. The interest has been focused on the emission of vapours and gases as no particulate emissions have been considered. The methods used are numerical calculations by computational fluid dynamics (CFD) and full-scale laboratory experiments. It was found that the emission is a strong function of air......In emission studies reported in literature little effort has been made to investigate the emission from building materials in ventilated enclosures from a fluid dynamics point of view. Furthermore, most of the existing emission models are empirical relations that are based on specific pollutants...

  6. Verbal Communication in the APR1400 Advanced Control Room

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Shin, Young Cheol

    2007-01-01

    This paper introduces the characteristics of communication in advanced main controlghd rooms (MCRs) and some observations from a case study performed for APR1400 MCR. In advanced MCRs, operators need not maintain the same communication patterns as they do in conventional ones. For example, a senior reactor operator (SRO) does not have to rely on board operators for information acquisition and can get any information from his/her own workstation. This situation may also bring about new problems in MCRs such as lack of shared situation awareness and collaboration between MCR operators. To cope with these problems, the APR1400 MCR adapts several approaches in design and training for encouraging operators to communicate with each other. This paper introduces the possible changes of communication patterns and the countermeasures in design and training. Some findings from an integrated system validation for Shin Kori Units 3 and 4 are also presented

  7. Mathemetical performance analysis of a temperature controlled bulk storage room

    NARCIS (Netherlands)

    Mourik, van S.; Ploegaert, J.P.M.; Zwart, H.; Keesman, K.J.

    2007-01-01

    Usually, control design takes place after the plant has been designed. However, the performance of the plant connected to the controller might be improved by simultaneous design of the plant and the controller. In this paper, expressions are deduced that describe the dynamics of a controlled plant

  8. The Control Room Upgrade in Oskarshamn 2 Modernization Project Lesson Learned from Ongoing Human Factor design

    International Nuclear Information System (INIS)

    Thomas, Gunnarsson; Magnus, Eliasson

    2011-01-01

    Due to recent changes in Swedish commercial nuclear safety system requirements, OKG decided to make the changes required by the new safety requirements, apply for a 30-year license extension, and to concurrently make changes for a major power uprate; this project is called the Plant Life Extension project (PLEX). It was decided, in addition to several plant modifications, to re build the old control room to a new modern screen-based control room located in the same space as the old one, and with the same number of operators. This paper explains the approach taken when modernizing the control room as a part of the Oskarshamn 2 Modernization project PLEX, the results, and the lessons learned from this ongoing work. The combination of changes results in a modernization project that is expected to increase output power by approximately 50 MWe through increased efficiency and to result in an increase in thermal power from 1800 MWt to 2300 MWt (28%) and electrical power from 620 MWe to 840 MWe due to the power uprate. The license to operate OKG2 expires in 2012 The PLEX project is one of the most ambitious nuclear power plant modernization projects ever implemented, world-wide. The application of human factors engineering (HFE) and control room and HSI design is a complex challenge. The original main control room from 1975 in Oskarshamn 2, was quite compact and provided a fairly good overview of the process. New requirements for enhanced safety and other design changes in the process systems and instrumentation led to a step-wise installation of new information and control equipment in the control room. Since the control room was quite limited in space, the control room grew larger, and the new equipment was installed farther away from the operator workplaces into an adjacent control room. This was even the case for the new safety systems. These systems were functioning well separately as such, but in some cases their interfaces were inconsistent, leading to increased

  9. Nuclear power plant control room task analysis. Pilot study for pressurized water reactors

    International Nuclear Information System (INIS)

    Barks, D.B.; Kozinsky, E.J.; Eckel, S.

    1982-05-01

    The purposes of this nuclear plant task analysis pilot study: to demonstrate the use of task analysis techniques on selected abnormal or emergency operation events in a nuclear power plant; to evaluate the use of simulator data obtained from an automated Performance Measurement System to supplement and validate data obtained by traditional task analysis methods; and to demonstrate sample applications of task analysis data to address questions pertinent to nuclear power plant operational safety: control room layout, staffing and training requirements, operating procedures, interpersonal communications, and job performance aids. Five data sources were investigated to provide information for a task analysis. These sources were (1) written operating procedures (event-based); (2) interviews with subject matter experts (the control room operators); (3) videotapes of the control room operators (senior reactor operators and reactor operators) while responding to each event in a simulator; (4) walk-/talk-throughs conducted by control room operators for each event; and (5) simulator data from the PMS

  10. Near-term improvements for nuclear power plant control room annunciator systems

    International Nuclear Information System (INIS)

    Rankin, W.L.; Duvernoy, E.G.; Ames, K.R.; Morgenstern, M.H.; Eckenrode, R.J.

    1983-04-01

    This report sets forth a basic design philosophy with its associated functional criteria and design principles for present-day, hard-wired annunciator systems in the control rooms of nuclear power plants. It also presents a variety of annunciator design features that are either necessary for or useful to the implementation of the design philosophy. The information contained in this report is synthesized from an extensive literature review, from inspection and analysis of control room annunciator systems in the nuclear industry and in related industries, and from discussions with a variety of individuals who are knowledgeable about annunciator systems, nuclear plant control rooms, or both. This information should help licensees and license applicants in improving their hard-wired, control room annunciator systems as outlined by NUREG-0700

  11. 75 FR 5536 - Pipeline Safety: Control Room Management/Human Factors, Correction

    Science.gov (United States)

    2010-02-03

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts...: Control Room Management/Human Factors, Correction AGENCY: Pipeline and Hazardous Materials Safety... following correcting amendments: PART 192--TRANSPORTATION OF NATURAL AND OTHER GAS BY PIPELINE: MINIMUM...

  12. What's getting in the way of teamwork in our nuclear control rooms?

    International Nuclear Information System (INIS)

    Harrington, D.K.

    1991-01-01

    Nuclear control room crews, like teams of any kind, develop their own unique personalities, or ways of getting things done. These personalities contain both good news and bad news when it comes to teamwork, and evolve from the beliefs and attitudes of the individual supervisors and operators. These beliefs and attitudes translate into behaviors that contribute to, or become barriers to, the teamwork so vital in today's modem nuclear control room. The writer, a consultant who has worked with control room crews at twelve US nuclear plants over the past five years in developing teamwork skills, describes his experiences, observations, and successes with the use of videotape to help operators change or modify their behavior to make them more effective as members of a control room team

  13. Experience in the review of utility control room design review and safety parameter display system programs

    International Nuclear Information System (INIS)

    Moore, V.A.

    1985-01-01

    The Detailed Control Room Design Review (DCRDR) and the Safety Parameter Display System (SPDS) had their origins in the studies and investigations conducted as the result of the TMI-2 accident. The President's Commission (Kemeny Commission) critized NRC for not examining the man-machine interface, over-emphasizing equipment, ignoring human beings, and tolerating outdated technology in control rooms. The Commission's Special Inquiry Group (Rogovin Report) recommended greater application of human factors engineering including better instrumentation displays and improved control room design. The NRC Lessons Learned Task Force concluded that licensees should review and improve control rooms using NRC Human engineering guidelines, and install safety parameter display systems (then called the safety staff vector). The TMI Action Plan Item I.D.1 and I.D.2 were based on these recommendations

  14. Human-factors engineering-control-room design review: Shoreham Nuclear Power Station. Draft audit report

    International Nuclear Information System (INIS)

    Peterson, L.R.; Preston-Smith, J.; Savage, J.W.; Rousseau, W.F.

    1981-01-01

    A human factors engineering preliminary design review of the Shoreham control room was performed at the site on March 30 through April 3, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The presented sections are numbered to conform to the guidelines of the draft version of NUREG-0700. They summarize the teams's observations of the control room design and layout, and of the control room operators' interface with the control room environment

  15. Mochovce NPP simulator

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

    Mochovce NPP simulator basic features and detailed description of its characteristics are presented with its performance, certification and application for training of NPP operators as well as the training scenario

  16. Three alternatives to a full scope control room simulator for nuclear power plants

    International Nuclear Information System (INIS)

    Roman, C.P.

    1988-01-01

    Many utilities are purchasing full scope control room simulators for training purposes. But, depending upon training requirements and finances, an alternative to a full scope control room simulator may be a viable option. Westinghouse has recently built and delivered two styles of alternative simulators. This paper discusses the design and operation of both of these simulators, including advantages and limitations of each design. In addition, the design of a hybrid system which combines features from both of these designs is presented

  17. Research on design method of main control room intake air radioactive monitoring

    International Nuclear Information System (INIS)

    Li Lei; Sun Yu; Wang Jiaoya; Liu Hongtao

    2014-01-01

    According to the design of the main control room intake gamma radiation dose rate monitoring channels in CPR1000 project and the study of relevant regulations and standards, a design method of main control room air inlet radioactive monitoring was presented. The measured object, equipment layout and chain operation were described. The threshold setting was explored using a calculation model established by MCNP software. The advantages, disadvantages and improvement ideas of this design were presented on the basis of calculation results. (authors)

  18. Study on comprehensive evaluation model for nuclear power plant control room layout

    International Nuclear Information System (INIS)

    Zhu Yiming; Liu Yuan; Fan Huixian

    2010-01-01

    A comprehensive evaluation model for layout of the main control room of nuclear power plants was proposed. Firstly the design scope and principle for the layout of the main control room were defined based on the standards, and then the index system for the comprehensive evaluation was established. Finally, comprehensive evaluation was carried out for the layout design by applying the fuzzy comprehensive evaluation method in the index system. (authors)

  19. Conversion of control systems, protection and engineering safeguard system signals of Almaraz NPP model from RELAP5 into TRAC-M

    International Nuclear Information System (INIS)

    Mulas, J.; Queral, C.; Collazo, I.; Concejal, A.; Burbano, N.; Lopez Lechas, A.; Tarrega, I.

    2002-01-01

    In the scope of a joint project between the Spanish Regulatory Commission (CSN) and the electric energy industry of Spain (UNESA) about the USNRC state-of-art thermal hydraulic code, TRAC-M, there is a task relating to the translation of the Spanish NPP models from other TH codes to the new one. As a part of this project, our team is working on the translation of Almaraz NPP model from RELAP5/MOD3.2 to TRAC-M. One of the goals of the project is to analyze the conversion of control blocks, signal variables and trips in order to correct modelling all instrumentation and control systems, and also protection and engineering safeguard system-signals of the NPP. At present, several portions of the input deck have been converted to TRAC-M, and the output data have also been compared with RELAP5 data. This paper describes the problems found in the conversion and the solutions achieved.(author)

  20. Research study on the effects of illumination on performance of control room tasks

    International Nuclear Information System (INIS)

    Silverman, E.B.; Horst, R.L.; Parris, H.L.; O'Brien, J.

    1990-01-01

    The illumination in the control rooms of many operating nuclear plants falls below the levels specified in the NUREG-0700 guidelines. However, these guidelines are based on human perception and performance data which were acquired under laboratory conditions and with tasks very different from those typically found in control rooms. The objective of the present studies was to gather empirical data regarding the levels of illumination sufficient for performing tasks analogous to those performed in control rooms. Several tasks were designed to engage the perceptual and cognitive processes that are representative of actual control room performance. In a computerized laboratory test-bed, subjects scanned edgewise meters, examined hard-copy X-Y plots to discern the value of the displayed function at specific coordinates, and proofread hard-copy plant procedures. In a power plant control room simulator, data were likewise collected in a meter reading task and similar tasks representing elements of specific job-performance measures. For each task, response time and accuracy were measured under a range of illumination levels. Subjective comfort ratings were also obtained for each illumination level. The results from both settings indicated that with decreasing illumination, increased errors and/or longer response times occurred only for levels below ten footcandles, if at all. These data suggest that adequate performance in control room tasks can be achieved at illumination levels below those recommended in NUREG-0700

  1. Software Development for Remote Control and Firing Room Displays

    Science.gov (United States)

    Zambrano Pena, Jessica

    2014-01-01

    The Launch Control System (LCS) developed at NASA's Kennedy Space Center (KSC) will be used to launch future spacecraft. Two of the many components of this system are the Application Control Language (ACL) and remote displays. ACL is a high level domain specific language that is used to write remote control applications for LCS. Remote displays are graphical user interfaces (GUIs) developed to display vehicle and Ground Support Equipment (GSE) data, they also provide the ability to send commands to control GSE and the vehicle. The remote displays and the control applications have many facets and this internship experience dealt with several of them.

  2. Research of quality control during development of NPP DCS 1E classified software

    International Nuclear Information System (INIS)

    Shi Weihua; Lu Zhenguo; Xie Qi

    2012-01-01

    The Nuclear safety depends on right behavior of 1E software, which is a important part of 1E DCS system. Nowadays, user focus on good function of 1E system, but pay little attention to quality control of 1E software. In fact, it's declared in IEC61513 and IEC60880 that 1E software should under strict quality control during all stages of development. This article is related to the practice of 1E DCS system quality control and explores the QC surveillance for 1E software from the user's point of view. (authors)

  3. Model predictive control of room temperature with disturbance compensation

    Science.gov (United States)

    Kurilla, Jozef; Hubinský, Peter

    2017-08-01

    This paper deals with temperature control of multivariable system of office building. The system is simplified to several single input-single output systems by decoupling their mutual linkages, which are separately controlled by regulator based on generalized model predictive control. Main part of this paper focuses on the accuracy of the office temperature with respect to occupancy profile and effect of disturbance. Shifting of desired temperature and changing of weighting coefficients are used to achieve the desired accuracy of regulation. The final structure of regulation joins advantages of distributed computing power and possibility to use network communication between individual controllers to consider the constraints. The advantage of using decoupled MPC controllers compared to conventional PID regulators is demonstrated in a simulation study.

  4. Analysis of the operator's tasks: An aid to control room design

    International Nuclear Information System (INIS)

    Blanc, P.; Guesnier, G.P.; Heilbronn, B.; Monnier, B.

    1983-01-01

    The control room designer usually has no knowledge of the tasks performed by the operator in the control room since an overall picture of the situation only becomes available once the whole facility has been constructed. In order to study and design control rooms for its future PWR units, Electricite de France (EDF) felt it was essential to analyse these tasks: the work was facilitated by the existence of 900 MW PWR units which were already in operation and which are controlled in much the same manner as future units of the same type. Accordingly, by analysing the control procedures of these 900 MW PWR units, a data base describing the control and monitoring tasks performed by operators in normal, incident and accident situations has been built up. The data-base files, which were established from a study of 130 control procedures, record all the commands given and data available in the control room (about 7000), describe the tasks connected with these commands and data, and identify the times at which they are made use of by the operator. Using this data base, the principle of operator-system communication and of data processing in the control room of the future has been established: in such a control room, most controls and data will be accessible through computer communication systems to ensure that control and monitoring systems are closely integrated under normal operating conditions as well as in incident and post-accident situations and to enable the plant to be controlled by one or two operators in a seated position. (author)

  5. Design of a Control Room for Jordan Research and Training Reactor (JRTR)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yong Jun; Suh, Sang Moon; Lee, Hyun Chul; Park, Je Yun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Since the main role of JRTR(Jordan Research and Training Reactor) operating personnel is safe and reliable operation of the reactor, MCR(Main Control Room) and SCR(Supplementary Control Room) must provide them with sufficient information and controls needed to optimize their performance. Before the TMI accident, control room were generally designed just with intuitive common sense, without using any proper HFE(human factors engineering) practices. Many results derived from the analysis of TMI accident showed that a more comprehensive and systematic approaches to develop MCR design requirements were needed. Moreover changes of operators' role as a decision maker from a physical controller in rapid improvement of control system which resulted in higher automation clearly needed more featured regulatory requirements and guidelines. So many regulatory and industrial guidance for control room design have been developed by relevant institution and regulatory bodies. In this paper, a conceptual design of the JRTR control room in the effort of satisfying current regulatory requirements and guidelines are presented. And some information display design is also presented

  6. Computer based plant display and digital control system of Wolsong NPP Tritium Removal Facility

    International Nuclear Information System (INIS)

    Jung, C.; Smith, B.; Tosello, G.; Grosbois, J. de; Ahn, J.

    2007-01-01

    The Wolsong Tritium Removal Facility (WTRF) is an AECL-designed, first-of-a-kind facility that removes tritium from the heavy water that is used in systems of the CANDUM reactors in operation at the Wolsong Nuclear Power Plant in South Korea. The Plant Display and Control System (PDCS) provides digital plant monitoring and control for the WTRF and offers the advantages of state-of-the-art digital control system technologies for operations and maintenance. The overall features of the PDCS will be described and some of the specific approaches taken on the project to save construction time and costs, to reduce in-service life-cycle costs and to improve quality will be presented. The PDCS consists of two separate computer sub-systems: the Digital Control System (DCS) and the Plant Display System (PDS). The PDS provides the computer-based Human Machine Interface (HMI) for operators, and permits efficient supervisory or device level monitoring and control. A System Maintenance Console (SMC) is included in the PDS for the purpose of software and hardware configuration and on-line maintenance. A Historical Data System (HDS) is also included in the PDS as a data-server that continuously captures and logs process data and events for long-term storage and on-demand selective retrieval. The PDCS of WTRF has been designed and implemented based on an off-the-self PDS/DCS product combination, the Delta-V System from Emerson. The design includes fully redundant Ethernet network communications, controllers, power supplies and redundancy on selected I/O modules. The DCS provides field bus communications to interface with 3rd party controllers supplied on specialized skids, and supports HART communication with field transmitters. The DCS control logic was configured using a modular and graphical approach. The control strategies are primarily device control modules implemented as autonomous control loops, and implemented using IEC 61131-3 Function Block Diagram (FBD) and Structured

  7. Human factors methods for nuclear control room design. Volume I. Human factors enhancement of existing nuclear control rooms. Final report

    International Nuclear Information System (INIS)

    Seminara, J.L.; Seidenstein, S.; Eckert, S.K.; Smith, D.L.

    1979-11-01

    Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. Human factors approaches were applied in the design of representative nuclear power plant control panels. First, methods for upgrading existing operational control panels were examined. Then, based on detailed human factors analyses of operator information and control requirements, designs of reactor, feedwater, and turbine-generator control panels were developed to improve the operator-control board interface, thereby reducing the potential for operator errors. In addition to examining present-generation concepts, human factors aspects of advanced systems and of hybrid combinations of advanced and conventional designs were investigated. Special attention was given to warning system designs. Also, a survey was conducted among control board designers to (1) develop an overview of design practices in the industry, and (2) establish appropriate measures leading to a more systematic concern for human factors in control board design

  8. Operative and postoperative control of variations in characteristics of physicochemical processes in NPP circuits

    International Nuclear Information System (INIS)

    Vilkov, N.Ya.; Krjukov, Yu.V.; Blinov, S.V.; Fedoseev, M.V.

    2002-01-01

    Based on actual data obtained from operative chemical monitoring in operating NPPs, the authors show the use of some probability diagnosis methods in practical applications such as identification of anomalies of the water chemistry condition, specifically, in the following: detecting violation of control limits a priori determined for the water chemistry parameters, using the control card method; construction of detectors for identifying probably (statistically) significant stepwise changes in the current arithmetical mean of the water chemistry parametric values; identifying successive changes in the behavior of robust estimators of the monitored parameters values; construction of robust linear regression prognostic models for dynamic changes in the monitored parameters values; correlation analysis of time series formed from the measured data on the water chemistry connected parameters (which are lumped (concentrated at one control point) and/or distributed along the coolant path). (author)

  9. HuRECA: Human Reliability Evaluator for Computer-based Control Room Actions

    International Nuclear Information System (INIS)

    Kim, Jae Whan; Lee, Seung Jun; Jang, Seung Cheol

    2011-01-01

    As computer-based design features such as computer-based procedures (CBP), soft controls (SCs), and integrated information systems are being adopted in main control rooms (MCR) of nuclear power plants, a human reliability analysis (HRA) method capable of dealing with the effects of these design features on human reliability is needed. From the observations of human factors engineering verification and validation experiments, we have drawn some major important characteristics on operator behaviors and design-related influencing factors (DIFs) from the perspective of human reliability. Firstly, there are new DIFs that should be considered in developing an HRA method for computer-based control rooms including especially CBP and SCs. In the case of the computer-based procedure rather than the paper-based procedure, the structural and managerial elements should be considered as important PSFs in addition to the procedural contents. In the case of the soft controllers, the so-called interface management tasks (or secondary tasks) should be reflected in the assessment of human error probability. Secondly, computer-based control rooms can provide more effective error recovery features than conventional control rooms. Major error recovery features for computer-based control rooms include the automatic logic checking function of the computer-based procedure and the information sharing feature of the general computer-based designs

  10. The application of AI-based refueling control system to the Fugen NPP

    International Nuclear Information System (INIS)

    Maeda, Koichi; Nakamura, Shinji; Kawasaki, Noboru; Nanko, Takashi; Nishimura, Hiroshi; Tanaka, Koichi

    1996-01-01

    In a refueling operation of the Advanced Thermal Reactor Fugen, it is essential to precisely handle fuel assemblies to guarantee quality and from the standpoint of safety guard. In order to plan and execute efficient operations, knowledge of experienced operators based on experiences is required. Therefore, an automatic control system based on the Artificial Intelligence (AI) technology has been developed, and has been put into operation in actual refueling operations. This system prepares an optimum refueling plan, controls the fuel handling facilities by that plan, displays and prints out the history of transfer and storage of items by automatically sampled data on a work station, a network to express fuel handling facilities and operational rules acquired through operating experiences. The development of this system has made it possible to optimize refueling schedule, save control labor of items and improve reliability of refueling. Firstly the development started the off-line system that prepares optimum refueling plan and gives to the operator step by step instructions for operation, secondly developed the on-line system that automatically controls facilities by that plan. The development of this system started in 1989, the off-line system has been put into practical operation in the 17th refueling in 1991, the 22nd (12th annual inspection) refueling in 1995 has been done by using the on-line system automatically

  11. Man-machine considerations in nuclear power plant control room design

    International Nuclear Information System (INIS)

    Tennant, D.V.

    1987-01-01

    Although human factors is a subject that has been around for a number of years, this area of design has only recently become known to the power industry. As power plants have grown in size and complexity, the instrumentation required to control and monitor plant processes has increased tremendously. This has been especially true in nuclear power facilities. Although operators are better trained and qualified, very little consideration has been devoted to man-machine interface and the limitations of human operators. This paper explores the historic aspects and design philosophy associated with nuclear plant control rooms. Current problems and solutions are explored along with the components of a control room review. Finally, a survey of future advances in control room design are offered. This paper is concerned with instrumentation, controls, and displays

  12. Reviewing the impact of advanced control room technology

    International Nuclear Information System (INIS)

    Wilhelmsen, C.A.; Gertman, D.I.; Ostrom, L.T.; Nelson, W.R.; Galyean, W.J.; Byers, J.C.

    1992-01-01

    Progress to date on assessing the nature of the expected changes in human performance and risk associated with the introduction of digital control, instrumentation, and display systems is presented. Expected changes include the shift toward more supervisory tasks, development of intervention strategies, and reallocation of function between human and machine. Results are reported in terms of the scope of new technology, human performance issues, and crews experience with digital control systems in a variety of industries petrochemical and aerospace. Plans to conduct a limited Probabilistic Risk Assessment/Human Reliability Assessment (PRA/HRA) comparison between a conventional NUREG-1150 series plant and that same plant retrofit with distributed control and advanced instrumentation and display are also presented. Changes needed to supplement existing HRA modeling methods and quantification techniques are discussed

  13. Influence of room heating on ambulatory blood pressure in winter: a randomised controlled study.

    Science.gov (United States)

    Saeki, Keigo; Obayashi, Kenji; Iwamoto, Junko; Tanaka, Yuu; Tanaka, Noriyuki; Takata, Shota; Kubo, Hiroko; Okamoto, Nozomi; Tomioka, Kimiko; Nezu, Satoko; Kurumatani, Norio

    2013-06-01

    Previous studies have proposed that higher blood pressure (BP) in winter is an important cause of increased mortality from cardiovascular disease during the winter. Some observational and physiological studies have shown that cold exposure increases BP, but evidence from a randomised controlled study assessing the effectiveness of intensive room heating for lowering BP was lacking. The present study aimed to determine whether intensive room heating in winter decreases ambulatory BP as compared with weak room heating resulting in a 10°C lower target room temperature when sufficient clothing and bedclothes are available. We conducted a parallel group, assessor blinded, simple randomised controlled study with 1:1 allocation among 146 healthy participants in Japan from November 2009 to March 2010. Ambulatory BP was measured while the participants stayed in single experimental rooms from 21:00 to 8:00. During the session, participants could adjust the amount of clothing and bedclothes as required. Compared with the weak room heating group (mean temperature ± SD: 13.9 ± 3.3°C), systolic morning BP (mean BP 2 h after getting out of bed) of the intensive room heating group (24.2 ± 1.7°C) was significantly lower by 5.8 mm Hg (95% CI 2.4 to 9.3). Sleep-trough morning BP surges (morning BP minus lowest night-time BP) in the intensive room heating group were significantly suppressed to about two thirds of the values in the weak room heating group (14.3 vs 21.9 mm Hg; pheating decreased morning BP and the morning BP surge in winter.

  14. Safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    1995-01-01

    Preparation of safety practices on assessment and management of aging of major NPP components important to safety, CRP on management of aging of concrete containment buildings, CRP on management of aging of in-containment instrumentation and control cables are outlined

  15. Human-machine interface aspects and use of computer-based operator support systems in control room upgrades and new control room designs for nuclear power plants

    International Nuclear Information System (INIS)

    Berg, O.

    1997-01-01

    At the Halden Project efforts are made to explore the possibilities through design, development and validation of Computer-based Operator Support Systems (COSSes) which can assist the operators in different operational situations, ranging from normal operation to disturbance and accident conditions. The programme comprises four main activities: 1) verification and validation of safety critical software systems; 2) man-machine interaction research emphasizing improvements in man-machine interfaces on the basis of human factors studies; 3) computerized operator support systems assisting the operator in fault detection/diagnosis and planning of control actions; and 4) control room development providing a basis for retrofitting of existing control rooms and for the design of advanced concepts. The paper presents the status of this development programme, including descriptions of specific operator support functions implemented in the simulator-based, experimental control room at Halden (HAMMLAB, HAlden Man-Machine LABoratory). These operator aids comprise advanced alarms systems, diagnostic support functions, electronic procedures, critical safety functions surveillance and accident management support systems. The different operator support systems development at the Halden Project are tested and evaluated in HAMMLAB with operators from the Halden Reactor, and occasionally from commercial NPPs, as test subjects. These evaluations provide data on the merits of different operator support systems in an advanced control room setting, as well as on how such systems should be integrated to enhance operator performance. The paper discusses these aspects and the role of computerized operator support systems in plant operation based on the experience from this work at the Halden Project. 15 refs, 5 figs

  16. Human-machine interface aspects and use of computer-based operator support systems in control room upgrades and new control room designs for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Berg, O [Institutt for Energiteknikk, OECD Halden Reactor Project (Netherlands)

    1997-07-01

    At the Halden Project efforts are made to explore the possibilities through design, development and validation of Computer-based Operator Support Systems (COSSes) which can assist the operators in different operational situations, ranging from normal operation to disturbance and accident conditions. The programme comprises four main activities: 1) verification and validation of safety critical software systems; 2) man-machine interaction research emphasizing improvements in man-machine interfaces on the basis of human factors studies; 3) computerized operator support systems assisting the operator in fault detection/diagnosis and planning of control actions; and 4) control room development providing a basis for retrofitting of existing control rooms and for the design of advanced concepts. The paper presents the status of this development programme, including descriptions of specific operator support functions implemented in the simulator-based, experimental control room at Halden (HAMMLAB, HAlden Man-Machine LABoratory). These operator aids comprise advanced alarms systems, diagnostic support functions, electronic procedures, critical safety functions surveillance and accident management support systems. The different operator support systems development at the Halden Project are tested and evaluated in HAMMLAB with operators from the Halden Reactor, and occasionally from commercial NPPs, as test subjects. These evaluations provide data on the merits of different operator support systems in an advanced control room setting, as well as on how such systems should be integrated to enhance operator performance. The paper discusses these aspects and the role of computerized operator support systems in plant operation based on the experience from this work at the Halden Project. 15 refs, 5 figs.

  17. 49 CFR 195.446 - Control room management.

    Science.gov (United States)

    2010-10-01

    ... for the safe operation of a pipeline facility. (e) Alarm management. Each operator using a SCADA... controls all or part of a pipeline facility through a SCADA system. Each operator must have and follow... certain provisions of API RP 1165 are not practical for the SCADA system used; (2) Conduct a point-to...

  18. The potential of soft computing methods in NPP instrumentation and control

    International Nuclear Information System (INIS)

    Hampel, R.; Chaker, N.; Kaestner, W.; Traichel, A.; Wagenknecht, M.; Gocht, U.

    2002-01-01

    The method of signal processing by soft computing include the application of fuzzy logic, synthetic neural networks, and evolutionary algorithms. The article contains an outline of the objectives and results of the application of fuzzy logic and methods of synthetic neural networks in nuclear measurement and control. The special requirements to be met by the software in safety-related areas with respect to reliability, evaluation, and validation are described. Possible uses may be in off-line applications in modeling, simulation, and reliability analysis as well as in on-line applications (real-time systems) for instrumentation and control. Safety-related aspects of signal processing are described and analyzed for the fuzzy logic and synthetic neural network concepts. Application are covered in selected examples. (orig.)

  19. The development of KNGR control room man-machine interface design

    International Nuclear Information System (INIS)

    Sung-Jae Cho; Yeong-Cheol Shin

    2000-01-01

    KNGR MMI design has been developed for the last 7 years as a part of Korea Next Generation Reactor (KNGR) design development. The KNGR control room has the common features of advanced control room such as large display panel, redundant compact workstations, soft control, and computerized procedure system. A conventional type safety console is provided as a backup when operation at the workstations is impossible. The strong points of an advanced control room are based on the powerful information processing and flexible graphic presentation capability of computer technology. On the other hand, workstation based design has a weak point that the amount of information to be presented in one VDU is limited. This can cause navigational overload and inconsistent interfaces and provide chances for performance errors/failures, if not designed carefully. From this background, the regulators require licensees to follow strict top-down human factor engineering design process. Analysis of operating experiences and iterative evaluations are used to address the potential problems of the KNGR advanced control room MMI design. But, further study is necessary in design area like CPS design, where experiences or design guidance is insufficient. Further study topics for KNGR advanced control room MMI design development are discussed briefly in this paper. (author)

  20. Survey of control-room design practices with respect to human factors engineering

    International Nuclear Information System (INIS)

    Seminara, J.L.; Parsons, S.O.

    1980-01-01

    Human factors engineering is an interdisciplinary speciality concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. This emphasis has been applied to most military and space systems in the past 30 y. A review of five nuclear power-plant control rooms, reported in the November-December 1977 issue of Nuclear Safety, revealed that human factors principles of design have generally not been incorporated in present-generation control rooms. This article summarizes the findings of a survey of 20 control-board designers from a mix of nuclear steam-supply system and architect-engineering firms. The interviews with these designers probed design methods currently used in developing control rooms. From these data it was concluded that there is currently no consistent, formal, uniform concern for the human factors aspects of control-room design on the part of the design organizations, the utilities, or the Nuclear Regulatory Commission. Although all the parties involved are concerned with human factors issues, this responsibility is not focused, and human factors yardsticks, or design standards, specific to power plants have not been evolved and applied in the development and verification of control-room designs from the standpoint of the man-machine interface

  1. Task analysis methods applicable to control room design review (CDR)

    International Nuclear Information System (INIS)

    Moray, N.P.; Senders, J.W.; Rhodes, W.

    1985-06-01

    This report presents the results of a research study conducted in support of the human factors engineering program of the Atomic Energy Control Board in Canada. It contains five products which may be used by the Atomic Enegy Control Board in relation to Task Analysis of jobs in CANDU nuclear power plants: 1. a detailed method for preparing for a task analysis; 2. a Task Data Form for recording task analysis data; 3. a detailed method for carrying out task analyses; 4. a guide to assessing alternative methods for performing task analyses, if such are proposed by utilities or consultants; and 5. an annotated bibliography on task analysis. In addition, a short explanation of the origins, nature and uses of task analysis is provided, with some examples of its cost effectiveness. 35 refs

  2. Development of new process network for gas chromatograph and analyzers connected with SCADA system and Digital Control Computers at Cernavoda NPP Unit 1

    International Nuclear Information System (INIS)

    Deneanu, Cornel; Popa Nemoiu, Dragos; Nica, Dana; Bucur, Cosmin

    2007-01-01

    The continuous monitoring of gas mixture concentrations (deuterium/ hydrogen/oxygen/nitrogen) accumulated in 'Moderator Cover Gas', 'Liquid Control Zone' and 'Heat Transport D 2 O Storage Tank Cover Gas', as well as the continuous monitoring of Heavy Water into Light Water concentration in 'Boilers Steam', 'Boilers Blown Down', 'Moderator heat exchangers', and 'Recirculated Water System', sensing any leaks of Cernavoda NPP U1 led to requirement of developing a new process network for gas chromatograph and analyzers connected to the SCADA system and Digital Control Computers of Cernavoda NPP Unit 1. In 2005 it was designed and implemented the process network for gas chromatograph which connected the gas chromatograph equipment to the SCADA system and Digital Control Computers of the Cernavoda NPP Unit 1. Later this process network for gas chromatograph has been extended to connect the AE13 and AE14 Fourier Transform Infrared (FTIR) analyzers with either. The Gas Chromatograph equipment measures with best accuracy the mixture gases (deuterium/ hydrogen/oxygen/nitrogen) concentration. The Fourier Transform Infrared (FTIR) AE13 and AE14 Analyzers measure the Heavy Water into Light Water concentration in Boilers Steam, Boilers BlownDown, Moderator heat exchangers, and Recirculated Water System, monitoring and signaling any leaks. The Gas Chromatograph equipment and Fourier Transform Infrared (FTIR) AE13 and AE14 Analyzers use the new OPC (Object Link Embedded for Process Control) technologies available in ABB's VistaNet network for interoperability with automation equipment. This new process network has interconnected the ABB chromatograph and Fourier Transform Infrared analyzers with plant Digital Control Computers using new technology. The result was an increased reliability and capability for inspection and improved system safety

  3. The development of AI-based refueling control system to the FUGEN NPP

    International Nuclear Information System (INIS)

    Nanko, Takashi; Tanaka, Koichi.

    1996-01-01

    Since even skilled workers spent a considerable time to perform the refueling work previously, an automatic control system was developed by using φNET, an AI tool and its application to refueling works was started in practice. In this system, the optimum plan for the refueling work was constructed using a network which allows to present the equipments to handle the fuel, as well as the operational roles obtained from the worker's experiences. Based on the plan, the instruments concerned were automatically operated to collect the data on the actual operation, the expression and/or printing was made on the movement histories of the articles and the status of their storages. By the development of the system, optimization of refueling works, rationalization of the management and the improvement of reliability for the works became possible. The development was performed in the following two steps; the first was development of an off-line system providing an operational guidance ot the operator according to the optimum operation plan and the second was development of an on-line system which allows to automatically control the instruments according to the operational plan. The off-line system has been put into practice since 1991 and the automatic operation of refueling has been started with the on-line system from 1995. (M.N.)

  4. Improving safety margins for control room habitability, through heating/ventilation/air conditioning modifications

    International Nuclear Information System (INIS)

    Beach, D.R.; Fillingim, W.; Bell, G.; Eurich, R.G.

    1989-01-01

    The Fort Calhoun power station began operation in September 1973. Since that time, modifications to the plant have required the addition of a substantial number of electrical and control components in the control room, which has resulted in an increased heat load in this area. Additionally, NUREG-0737, Item III.D.3.4, imposed requirements on the ventilating system related to protection of personnel from the effects of toxic and radioactive gas releases, which were not considered in the original design. Omaha Public Power District (OPPD) has recently undertaken a major modification to the Fort Calhoun station control room ventilating system to improve the safety margins for control room habitability. The goals of the modification were to achieve adequate cooling capacity with fully redundant equipment, improve habitability under accident conditions, and eliminate several potential problems related to steam line break and equipment qualification. Additionally, the scope of the project grew as design problems emerged

  5. Uncertainty analysis for parameters of CFAST in the main control room fire scenario

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Wanhong; Guo, Yun; Peng, Changhong [Univ. of Science and Technology of China No. 96, Anhui (China). School of Nuclear Science and Technology

    2017-07-15

    The fire accident is one of important initial events in the nuclear power plant. Moreover, the fire development process is extremely difficult and complex to predict accurately. As a result, the plant internal fire accidents have become one of the most realistic threat on the safety of the nuclear power plants. The main control room contains all the control and monitoring equipment that operators need. Once it is on fire, hostile environments would greatly impact on the safety of human operations. Therefore, fire probability safety analysis on the main control room has become a significant task. By using CFAST and Monte Carlo sampling method as a tool for fire modeling to simulate main control room on fire, we can examine uncertainty analysis for the important parameters of CFAST.

  6. HYBRID ALARM SYSTEMS: COMBINING SPATIAL ALARMS AND ALARM LISTS FOR OPTIMIZED CONTROL ROOM OPERATION

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring; J.J. Persensky

    2012-07-01

    The US Department of Energy (DOE) is sponsoring research, development, and deployment on Light Water Reactor Sustainability (LWRS), in which the Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe operational life extension of current nuclear power plants. One of the main areas of focus is control room modernization. Within control room modernization, alarm system upgrades present opportunities to meet the broader goals of the LWRS project in demonstrating the use and safety of the advanced instrumentation and control (I&C) technologies and the short-term and longer term objectives of the plant. In this paper, we review approaches for and human factors issues behind upgrading alarms in the main control room of nuclear power plants.

  7. Use of 2.5-D and 3-D technology to evaluate control room upgrades

    International Nuclear Information System (INIS)

    Hanes, L. F.; Naser, J.

    2006-01-01

    This paper describes an Electric Power Research Inst. (EPRI) study in which 2.5-D and 3-D visualization technology was applied to evaluate the design of a nuclear power plant control room upgrade. The study involved converting 3-D CAD flies of a planned upgrade into a photo-realistic appearing virtual model, and evaluating the value and usefulness of the model. Nuclear utility and EPRI evaluators viewed and interacted with the control room virtual model with both 2.5-D and 3-D representations. They identified how control room and similar virtual models may be used by utilities for design and evaluation purposes; assessed potential economic and other benefits; and identified limitations, potential problems, and other issues regarding use of visualization technology for this and similar applications. In addition, the Halden CREATE (Control Room Engineering Advanced Tool-kit Environment) Verification Tool was applied to evaluate features of the virtual model against US NRC NUREG 0700 Revision 2 human factors engineering guidelines (NUREG 0700) [1]. The study results are very favorable for applying 2.5-D visualization technology to support upgrading nuclear power plant control rooms and other plant facilities. Results, however, show that today's 3-D immersive viewing systems are difficult to justify based on cost, availability and value of information provided for this application. (authors)

  8. Application of heat-resistant non invasive acoustic transducers for coolant control in the NPP pipelines

    International Nuclear Information System (INIS)

    Melnikov, V.; Nigmatulin, B.

    1997-01-01

    The use of ultrasonic waves enables remote testing of the coolant flow, detection of solid and gaseous occlusions and measuring of the water velocity and level. Analysis of the acoustic noise makes it possible to detect coolant leaks and diagnose the state and operation of the rotating mechanisms and bearings. Results are given of the research in the development of highly reliable waveguide-type non-invasive acoustic transducers with a long service life. Examples are given of the use of transducers in various fields of nuclear technology: detection of gas in coolant, indication of the coolant level, control of pipe filling and drainage, measurement of liquid film velocity at the pipe inner surface. (M.D.)

  9. Light Water Reactor Sustainability Program A Reference Plan for Control Room Modernization: Planning and Analysis Phase

    Energy Technology Data Exchange (ETDEWEB)

    Jacques Hugo; Ronald Boring; Lew Hanes; Kenneth Thomas

    2013-09-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) program is collaborating with a U.S. nuclear utility to bring about a systematic fleet-wide control room modernization. To facilitate this upgrade, a new distributed control system (DCS) is being introduced into the control rooms of these plants. The DCS will upgrade the legacy plant process computer and emergency response facility information system. In addition, the DCS will replace an existing analog turbine control system with a display-based system. With technology upgrades comes the opportunity to improve the overall human-system interaction between the operators and the control room. To optimize operator performance, the LWRS Control Room Modernization research team followed a human-centered approach published by the U.S. Nuclear Regulatory Commission. NUREG-0711, Rev. 3, Human Factors Engineering Program Review Model (O’Hara et al., 2012), prescribes four phases for human factors engineering. This report provides examples of the first phase, Planning and Analysis. The three elements of Planning and Analysis in NUREG-0711 that are most crucial to initiating control room upgrades are: • Operating Experience Review: Identifies opportunities for improvement in the existing system and provides lessons learned from implemented systems. • Function Analysis and Allocation: Identifies which functions at the plant may be optimally handled by the DCS vs. the operators. • Task Analysis: Identifies how tasks might be optimized for the operators. Each of these elements is covered in a separate chapter. Examples are drawn from workshops with reactor operators that were conducted at the LWRS Human System Simulation Laboratory HSSL and at the respective plants. The findings in this report represent generalized accounts of more detailed proprietary reports produced for the utility for each plant. The goal of this LWRS report is to disseminate the technique and provide examples sufficient to

  10. Evaluation of shielding capability of controlled area for CT examination room

    International Nuclear Information System (INIS)

    Suzuki, Shoichi; Asada, Yasuki; Nakai, Takayo; Takeuchi, Kichito; Kinoshita, Kazuo; Watanabe, Nobuyuki; Koga, Sukehiko

    2002-01-01

    With the revision of the law in April, 2001, the effective dose at the boundary of the controlled area was set at 1.3 mSv/3M. Whether the shielding capability of the CT room satisfied the provisions of the law or not was confirmed by actual measurements. Both thermo luminescence dosemeter (TLD) and electronic dosemeter were used to measure the radiation doses. The shielding capability of the gantry was studied both inside and outside the room for a week as a basic experiment. On the basis of the data thus obtained doses accumulated in 3 months were estimated. According to the results of 3 month-measurement, the doses outside the wall of the CT room were about 200μ Sv. This numerical value was comparable to the background level of the evaluation point. The results above assured that the shielding capability of the CT room satisfied the provisions of the law well. (author)

  11. Demonstration of visualization techniques for the control room engineer in 2030

    DEFF Research Database (Denmark)

    Marinelli, Mattia; Heussen, Kai; Strasser, Thomas

    2017-01-01

    Deliverable 8.1 reports results on analytics and visualizations of real time flexibility in support of voltage and frequency control in 2030+ power system. The investigation is carried out by means of relevant control room scenarios in order to derive the appropriate analytics needed for each spe...

  12. The design and operation of the THORP central control room: a human factors perspective

    International Nuclear Information System (INIS)

    Reed, Julie.

    1996-01-01

    The new Thermal Oxide Reprocessing Plant (THORP) at British Nuclear Fuels (BNFL) Sellafield Site is now operational. This paper describes the Central Control Room (CCR), focusing on the control system components. Throughout the design, commissioning and operation of THORP, human factors played an important part. (author)

  13. Bridging the gap: adapting advanced display technologies for use in hybrid control rooms

    International Nuclear Information System (INIS)

    Jokstad, Håkon; Boring, Ronald

    2015-01-01

    The Institute for Energy Technology (IFE), runs the OECD Halden Reactor Project (HRP), featuring a state-of-the-art research simulator facility in Halden, Norway, called HAMMLAB. HAMMLAB serves two main purposes: the study of human behaviour in interaction with complex process systems; and the development, test and evaluation of prototype control centres and their individual systems. By studying operator performance in HAMMLAB and integrating the knowledge gained into new designs, the HRP contributes to improving operational safety, reliability, efficiency and productivity. The U.S. Department of Energy's (DOE) Light Water Reactor Sustainability (LWRS) Program has contracted IFE to assist DOE national laboratory staff at Idaho National Laboratory (INL) in adapting HAMMLAB design concepts for the purpose of control room modernization at nuclear power plants in the U.S. In support of this effort, the DOE has built a simulator research facility at INL called the Human Systems Simulation Laboratory (HSSL). The HSSL is centered on control room modernization, in which industry provided plant instrumentation and controls are modified for upgrade opportunities. The HSSL houses the LWRS simulator, which is a reconfigurable full-scale and full-scope control room simulator. Consisting of 45 large touchscreens on 15 panels, the LWRS simulator is currently using this glass top technology to digitally represent and replicate the functionality of the analog I&C systems in existing control rooms. The LWRS simulator is reconfigurable in that different plant training simulator models obtained from the utilities can be run on the panels, and the panels can be physically moved and arranged to mimic the layout of those control rooms. The glass top technology and reconfigurability capabilities allow the LWRS simulator to be the research platform that is necessary to design, prototype, and validate human-system interface (HSI) technologies that can replace existing analog I&C. IFE

  14. Bridging the gap: adapting advanced display technologies for use in hybrid control rooms

    Energy Technology Data Exchange (ETDEWEB)

    Jokstad, Håkon [Inst. for Energy Technology, Halden (Norway); Boring, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    The Institute for Energy Technology (IFE), runs the OECD Halden Reactor Project (HRP), featuring a state-of-the-art research simulator facility in Halden, Norway, called HAMMLAB. HAMMLAB serves two main purposes: the study of human behaviour in interaction with complex process systems; and the development, test and evaluation of prototype control centres and their individual systems. By studying operator performance in HAMMLAB and integrating the knowledge gained into new designs, the HRP contributes to improving operational safety, reliability, efficiency and productivity. The U.S. Department of Energy’s (DOE) Light Water Reactor Sustainability (LWRS) Program has contracted IFE to assist DOE national laboratory staff at Idaho National Laboratory (INL) in adapting HAMMLAB design concepts for the purpose of control room modernization at nuclear power plants in the U.S. In support of this effort, the DOE has built a simulator research facility at INL called the Human Systems Simulation Laboratory (HSSL). The HSSL is centered on control room modernization, in which industry provided plant instrumentation and controls are modified for upgrade opportunities. The HSSL houses the LWRS simulator, which is a reconfigurable full-scale and full-scope control room simulator. Consisting of 45 large touchscreens on 15 panels, the LWRS simulator is currently using this glass top technology to digitally represent and replicate the functionality of the analog I&C systems in existing control rooms. The LWRS simulator is reconfigurable in that different plant training simulator models obtained from the utilities can be run on the panels, and the panels can be physically moved and arranged to mimic the layout of those control rooms. The glass top technology and reconfigurability capabilities allow the LWRS simulator to be the research platform that is necessary to design, prototype, and validate human-system interface (HSI) technologies that can replace existing analog I&C. IFE has

  15. Main Control Room Upgrade for Kori Unit 1 in Korea

    International Nuclear Information System (INIS)

    Ha, Jae Taeg; Choi, Moon Jae

    2014-01-01

    Kori Unit 1 is a 30 years old nuclear power plant and its MCR and MCB was upgraded based on the latest Human Factors Engineering (HFE) principles. The objectives of applying the Human Factors Engineering (HFE) principles are to minimize the human errors and to enhance the safe operation of the plant. In order to systematically incorporate the HFE design principles into the Human System Interface (HSI) design, HFE Program Plan (HFEPP) for Kori Unit 1 was developed and the plan provided an overview of the HSI design process along with detailed methods and results. The upgrade includes addition of Bypassed and Inoperable Status Indication System (BISI) and the replacement of the conventional MMI devices such as hardwired hand switches, recorders and indicators with new advanced control and display devices using VDUs (Video Display Units). The VDUs significantly improve the effectiveness and efficiency of the monitoring function. Plant Monitoring System (PMS) and Plant Annunciator System (PAS) were upgraded also by replacing the outdated systems with advanced digital systems with future expansion capability. In addition, the MCR related equipment and/or facilities were replaced or improved. Some of these include the enhancement of MCR interior designs for better working environment, dimmable ceiling lighting, aesthetically pleasing decor of ceiling, wall and floor as well as ergonomically improved operator consoles

  16. Evaluation of information display at advanced main control room

    Energy Technology Data Exchange (ETDEWEB)

    Min, Dae Hwan; Yu, Seon Jae; Choi, Eui Sun [Korea Univ., Seoul (Korea, Republic of)

    2000-03-15

    This year we plan to survey information in order to have basic understanding of digital information display and control at the advanced MCR. At first we collect different ways of presenting information at the advanced MCR. Secondly, we conduct literature survey on studies that have investigated information representation techniques and their effects. Then, we need compare differences between conventional NPPs and advanced NPPs. Thirdly, we need to check HMI styles and evaluation techniques that are used currently at foreign NPPs. Indeed, HMI at the advanced MCR is quite different from that at a conventional MCR. It is not desirable to apply the same evaluation technique that has veen used at the conventional MCR. We need to develop an evaluation technique that is valid in theory and applicable in practice. Finally, we identify the requirements for a support system for an HMI evaluator, since it is not easy to carry out an evaluation task even though one has firm background on cognitive engineering theories and practical experiences.

  17. Main Control Room Upgrade for Kori Unit 1 in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Taeg; Choi, Moon Jae [KEPCO, Daejeon (Korea, Republic of)

    2014-08-15

    Kori Unit 1 is a 30 years old nuclear power plant and its MCR and MCB was upgraded based on the latest Human Factors Engineering (HFE) principles. The objectives of applying the Human Factors Engineering (HFE) principles are to minimize the human errors and to enhance the safe operation of the plant. In order to systematically incorporate the HFE design principles into the Human System Interface (HSI) design, HFE Program Plan (HFEPP) for Kori Unit 1 was developed and the plan provided an overview of the HSI design process along with detailed methods and results. The upgrade includes addition of Bypassed and Inoperable Status Indication System (BISI) and the replacement of the conventional MMI devices such as hardwired hand switches, recorders and indicators with new advanced control and display devices using VDUs (Video Display Units). The VDUs significantly improve the effectiveness and efficiency of the monitoring function. Plant Monitoring System (PMS) and Plant Annunciator System (PAS) were upgraded also by replacing the outdated systems with advanced digital systems with future expansion capability. In addition, the MCR related equipment and/or facilities were replaced or improved. Some of these include the enhancement of MCR interior designs for better working environment, dimmable ceiling lighting, aesthetically pleasing decor of ceiling, wall and floor as well as ergonomically improved operator consoles.

  18. Evaluation of information display at advanced main control room

    International Nuclear Information System (INIS)

    Min, Dae Hwan; Yu, Seon Jae; Choi, Eui Sun

    2000-03-01

    This year we plan to survey information in order to have basic understanding of digital information display and control at the advanced MCR. At first we collect different ways of presenting information at the advanced MCR. Secondly, we conduct literature survey on studies that have investigated information representation techniques and their effects. Then, we need compare differences between conventional NPPs and advanced NPPs. Thirdly, we need to check HMI styles and evaluation techniques that are used currently at foreign NPPs. Indeed, HMI at the advanced MCR is quite different from that at a conventional MCR. It is not desirable to apply the same evaluation technique that has veen used at the conventional MCR. We need to develop an evaluation technique that is valid in theory and applicable in practice. Finally, we identify the requirements for a support system for an HMI evaluator, since it is not easy to carry out an evaluation task even though one has firm background on cognitive engineering theories and practical experiences

  19. Is function-based control room design human-centered?

    International Nuclear Information System (INIS)

    Norros, L.; Savioja, P.

    2006-01-01

    Function-based approaches to system interface design appears an appealing possibility in helping designers and operators to cope with the vast amount of information needed to control complex processes. In this paper we provide evidence of operator performance analyses showing that outcome-centered performance measures may not be sufficiently informative for design. We need analyses indicating habitual patterns of using information, operator practices. We argue that practices that portray functional orienting to the task support mastery of the process. They also create potential to make use of function-based information presentation. We see that functional design is not an absolute value. Instead, such design should support communication of the functional significance of the process information to the operators in variable situations. Hence, it should facilitate development of practices that focus to interpreting this message. Successful function-based design facilitates putting operations into their contexts and is human-centered in an extended sense: It aids making sense in the complex, dynamic and uncertain environment. (authors)

  20. Human reliability analysis for advanced control room of KNGR

    International Nuclear Information System (INIS)

    Kim, Myung-Ro; Park, Seong-Kyu

    2000-01-01

    There are two purposes in Human Reliability Analysis (HRA) which was performed during Korean Next Generation Reactor (KNGR) Phase 2 research project. One is to present the human error probability quantification results for Probabilistic Safety Assessment (PSA) and the other is to provide a list of the critical operator actions for Human Factor Engineering (HFE). Critical operator actions were identified from the KNGR HRA/RSA based on selection criteria and incorporated in the MMI Task Analysis, where they receive additional treatment. The use of HRA/PSA results in design, procedure development, and training was ensured by their incorporation in the MMI task analysis and MCR design such as fixed position alarms, displays and controls. Any dominant PSA sequence that takes credit for human performance to achieve acceptable results was incorporated in MMIS validation activities through the PSA-based critical operator actions. The integration of KNGR HRA into MMI design was sufficiently addressed all applicable review criteria of NUREG-0800, Chapter 18, Section 2 F and NUREG-0711. (S.Y.)

  1. Enhancing the NCSU PULSTAR reactor control room with human factors considerations

    International Nuclear Information System (INIS)

    Glover, B.L.; Pupons, D.E.; Perez, P.B.

    1993-01-01

    The North Carolina PULSTAR research reactor was constructed to support teaching, training, and research. The training provided is not limited to academic students but encompasses plant operators, managers, engineers, designers, and supporting organizations in the nuclear industry. Our facility is under-going design changes to maximize teaching effectiveness and continued safe operation by providing current technology in the control room. The opportunity for the enhancements is a result of the generosity of neighboring utilities and the US Department of Energy instrumentation upgrade funds. Our objective, to provide a control room environment that conforms to selected industry practices, required human factors input. A human factors course, offered jointly between the industrial engineering and the psychology departments, included the PULSTAR control room enhancement as a case study

  2. Control rooms and man-machine interface in nuclear power plants

    International Nuclear Information System (INIS)

    1990-08-01

    The importance of man-machine interface for ensuring safe and reliable operation of nuclear power plants has always been recognized. Since the early 1970's, the concepts of operator support and human factors have been increasingly used to better define the role of control rooms. In the late 1970's, the lessons learned from experience considerably accelerated the development of recommendations and regulatory requirements governing the resources and data available to operators in nuclear power plant control rooms, and specified the expertise required to assist them in case of need. This document summarizes the steps which have been taken and are being planned around the world to improve the man-machine interface for safe and economic power generation. It intends to present to the reader useful examples on some selected control room design and man-machine interface practices for operation and surveillance of nuclear power plants. 53 refs, 94 figs, 27 tabs

  3. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 7. Part 1. Localization of accident consequences at the 4th power unit, operating site of the Chernobyl NPP and adjoining territories

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    The next data on the accident consequence elimination are presented: temperature monitoring results, gamma radiation exposure dose rates, neutron and gamma fields, aerosol disperse composition. The information system for scientific researches FINISH and automatic subsystems for radiation control and the Ukrytie object diagnostics are described. Decontamination of the Chernobyl' NPP territory, equipment and rooms is described too

  4. Chernobyl'-88. Reports of the 1. All-Union scientific and technical meeting on results of accident effect elimination at the Chernobyl' NPP. V. 7. Part 2. Localization of accident consequences at the 4th power unit, operating site of the Chernobyl' NPP and adjoining territories

    International Nuclear Information System (INIS)

    Ignatenko, E.I.

    1989-01-01

    The next data on the accident consequence elimination are presented: temperature monitoring results, gamma radiation exposure dose rates, neutron and gamma fields, aerosol disperse composition. The information system for scientific researches FINISH and automatic subsystems for radiation control and the Ukrytie object diagnostics are described. Decontamination of the Chernobyl' NPP territory, equipment and rooms is described too

  5. Operational Strategy of CBPs for load balancing of Operators in Advanced Main Control Room

    International Nuclear Information System (INIS)

    Kim, Seunghwan; Kim, Yochan; Jung, Wondea

    2014-01-01

    With the using of a computer-based control room in an APR1400 (Advanced Pressurized Reactor-1400), the operators' behaviors in the main control room had changed. However, though the working environment of operators has been changed a great deal, digitalized interfaces can also change the cognitive tasks or activities of operators. First, a shift supervisor (SS) can confirm/check the conduction of the procedures and the execution of actions of board operators (BOs) while confirming directly the operation variables without relying on the BOs. Second, all operators added to their work the use of a new CBP and Soft Controls, increasing their procedural workload. New operational control strategies of CBPs are necessary for load balancing of operator's task load in APR1400. In this paper, we compared the workloads of operators in an APR1400 who work with two different usages of the CBP. They are SS oriented usage and SS-BO collaborative usage. In this research, we evaluated the workloads of operators in an advanced main control room by the COCOA method. Two types of CBP usages were defined and the effects of these usages on the workloads were investigated. The obtained results showed that the workloads between operators in a control room can be balanced according to the CBP usages by assigning control authority to the operators

  6. Operational Strategy of CBPs for load balancing of Operators in Advanced Main Control Room

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seunghwan; Kim, Yochan; Jung, Wondea [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    With the using of a computer-based control room in an APR1400 (Advanced Pressurized Reactor-1400), the operators' behaviors in the main control room had changed. However, though the working environment of operators has been changed a great deal, digitalized interfaces can also change the cognitive tasks or activities of operators. First, a shift supervisor (SS) can confirm/check the conduction of the procedures and the execution of actions of board operators (BOs) while confirming directly the operation variables without relying on the BOs. Second, all operators added to their work the use of a new CBP and Soft Controls, increasing their procedural workload. New operational control strategies of CBPs are necessary for load balancing of operator's task load in APR1400. In this paper, we compared the workloads of operators in an APR1400 who work with two different usages of the CBP. They are SS oriented usage and SS-BO collaborative usage. In this research, we evaluated the workloads of operators in an advanced main control room by the COCOA method. Two types of CBP usages were defined and the effects of these usages on the workloads were investigated. The obtained results showed that the workloads between operators in a control room can be balanced according to the CBP usages by assigning control authority to the operators.

  7. Control Room Tasks During Refueling in Ringhals 1 Nuclear Power Plant - Operator performance during refuelling outages

    International Nuclear Information System (INIS)

    Stroebeck, Einar; Olausson, Jesper; Van Gemst, Paul

    1998-01-01

    This paper discusses the performance and tasks of the operators in the control room during refuelling outages. Analyses of such events have, during the last years, shown that the risk for nuclear accidents is not negligible compared with the risk at higher reactor power levels. Some experts have the opinion that, due to mistakes during an outage, the risk for such accidents during the outage and other accidents later on during power operation is higher than in other plant situations. The high risk level is mainly a result of errors at maintenance actions and supervision of lining up of safety systems. Most of the control rooms in existing NPPs were designed more than 10 years ago. At that time the activities and the tasks for the operators were not very well understood. Procedures for refuelling and other activities during the outages were not described very well. Often the utility organisation for refuelling outages was not established at the start of the control room design. Experience from operation during many years has shown that the performance of operators can be improved in existing plant, and thus risks be reduced, by upgrading the control room. These issues have been studied as a part of the modernisation project for Ringhals 1, an ABB Atom BWR owned by Vattenfall AB in Sweden. The paper will describe the working model for upgrading the control room and important issues to take care of with respect to refuelling outages. The identified issues will be used as the input for improving control room philosophy and the individual technical systems. (authors)

  8. Simulator experiments: effects of NPP operator experience on performance

    International Nuclear Information System (INIS)

    Beare, A.N.; Gray, L.H.

    1985-01-01

    Experiments are being conducted on nuclear power plant (NPP) control room training simulators by the Oak Ridge National Laboratory, its subcontractor, General Physics Corporation, and participating utilities. The experiments are sponsored by the Nuclear Regulatory Commission's (NRC) Human Factors and Safeguards Branch, Division of Risk Analysis and Operations, and are a continuation of prior research using simulators, supported by field data collection, to provide a technical basis for NRC human factors regulatory issues concerned with the operational safety of nuclear power plants. During the FY83 research, a simulator experiment was conducted at the control room simulator for a GE boiling water reactor (BWR) NPP. The research subjects were licensed operators undergoing requalification training and shift technical advisors (STAs). This experiment was designed to investigate the effects of (a) senior reactor operator (SRO) experience, (b) operating crew augmentation with an STA and (c) practice, as a crew, upon crew and individual operator performance, in response to anticipated plant transients. The FY84 experiments are a partial replication and extension of the FY83 experiment, but with PWR operators and simulator. Methodology and results to date are reported

  9. Decommissioning of Brennilis NPP

    International Nuclear Information System (INIS)

    Baize, Jean-Marc

    1998-01-01

    This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

  10. Multichannel active control of random noise in a small reverberant room

    DEFF Research Database (Denmark)

    Laugesen, Søren; Elliott, Stephen J.

    1993-01-01

    An algorithm for multichannel adaptive IIR (infinite impulse response) filtering is presented and applied to the active control of broadband random noise in a small reverberant room. Assuming complete knowledge of the primary noise, the theoretically optimal reductions of acoustic energy are init...... with the primary noise field generated by a panel excited by a loudspeaker in an adjoining room. These results show that far better performances are provided by IIR and FIR filters when the primary source has a lightly damped dynamic behavior which the active controller must model...

  11. Large screen mimic display design research for advanced main control room in nuclear power plant

    International Nuclear Information System (INIS)

    Zheng Mingguang; Yang Yanhua; Xu Jijun; Zhang Qinshun; Ning Zhonghe

    2002-01-01

    Firstly the evolution of mimic diagrams or displays used in the main control room of nuclear power plant was introduced. The active functions of mimic diagrams were analyzed on the release of operator psychological burden and pressure, the assistance of operator for the information searching, status understanding, manual actuation, correct decision making as well as the safe and reliable operation of the nuclear power plant. The importance and necessity to use the (large screen) mimic diagrams in advanced main control room of nuclear power plant, the design principle, design details and verification measures of large screen mimic display are also described

  12. Design and modernization of the control room with of the new digital I and C systems

    International Nuclear Information System (INIS)

    Fernandez, L. A.; Ortega, F.; Rejas, L.

    2011-01-01

    The use of the new digital I and c systems in the design of the new nuclear power plants, as well as the modernization of the existing ones, implies relevant changes in the control room design. New I and C systems provide new features that affect the control room operating concept, therefore a detailed analysis is required to take into consideration all the operating and human factor aspects. based on Tecnatom's experience, this article presents the methodological approach used as well as the most relevant aspects of this kind of project. (Author)

  13. Design of a Clean Room for Quality Control of an Environmental Sampling in KINAC

    International Nuclear Information System (INIS)

    Yoon, Jongho; Ahn, Gil Hoon; Seo, Hana; Han, Kitek; Park, Il Jin

    2014-01-01

    The objective of environmental sampling and analysis for safeguards is to characterize the nuclear materials handled and the activities conducted at the specific locations. The KINAC is responsible for the conclusions drawn from the analytical results provided by the analytical laboratories. To assure the KINAC of the continuity of the quality of the analytical results provided by the laboratories, the KINAC will implement a quality control(QC) programme. One of the QC programme is to prepare QC samples. The establishment of a clean room is needed to handle QC samples due to stringent control of contamination. The KINAC designed a clean facility with cleanliness of ISO Class 6, the Clean Room for Estimation and Assay of trace Nuclear materials(CREAN) to meet conflicting requirements of a clean room and for handling of nuclear materials according to Korean laws. The clean room will be expected to acquire of a radiation safety license under these conditions in this year and continue to improve it. The construction of the CREAN facility will be completed by the middle of 2015. In terms of QC programme, the establishment of a clean room is essential and will be not only very helpful for setting of quality control system for the national environmental sampling programme but also be applied for the environmental sample analysis techniques to the nuclear forensics

  14. Performance evaluation of control room HVAC and air cleaning systems under accident conditions

    International Nuclear Information System (INIS)

    Almerico, F.; Machiels, A.J.; Ornberg, S.C.; Lahti, G.P.

    1985-01-01

    In light water reactors, control rooms and technical support centers must be designed to provide habitable environments in accordance with the requirements specified in General Design Criterion 19 of Appendix A, 10 CFR Part 50. Therefore, the effectiveness of HVAC and air cleaning system designs with respect to plant operator protection has to be evaluated by the system designer. Guidance for performing the analysis has been previously given in ANSI/ASME N509-1980 as well as in presentations at past Air Cleaning Conferences. The previous work is extended and the methodology used in a generic, interactive computer program that performs Main Control Room and Technical Support Center (TSC) habitability analyses for LWR nuclear power plants is presented. For given accident concentrations of radionuclides or hazardous gases in the outdoor air intakes and plant spaces surrounding the Main Control Room (or TSC), the program models the performance of the HVAC and air cleaning system designs, and determines control room (or TSC) contaminant concentrations and plant operator protection factors. Calculated or actual duct leakage, air cleaning efficiency, and airborne contamination are taken into account. Flexibility of the model allows for the representation of most control rooms (or TSC) and associated HVAC and air cleaning system conceptual designs that have been used by the US architect/engineers. The program replaced tedious calculations to determine the effects of HVAC ductwork and equipment leakage and permits (1) parametric analyses of various HVAC system design options early in the conceptual phase of a project, and (2) analysis of the effects of leakage test results on contaminant room concentrations, and therefore operator doses

  15. Study of the thermal comfort, of the energy consumption and of the indoor environment control in surgery rooms

    NARCIS (Netherlands)

    Melhado, M.D.A.; Beyer, P.O.; Hensen, J.L.M.; Siqueira, L.F.G.

    2005-01-01

    In this research were investigated the influence of different layouts of operating rooms on thermal comfort, on the indoor environment control and on energy consumption. The layouts studied were: Case 1 (a surgery room and a hallway); Case 2 (a surgery room and two hallways); and Case 3 (a surgery

  16. Study on human factor at NPP

    International Nuclear Information System (INIS)

    Nopp, I.

    1984-01-01

    Factors affecting the reliabilty of the reactor control by an NPP operator are considered on the base of the Czechoslovakia NPP operating experience. The reliability level of NPP operators depends on objective factors (conditions and regime of labour) determining the labour productivity and on subjective ones (psychological morale, physical and mental abilities and occupational level of personnel). Problems of the effect of physical and mental abilities and professional level on the reliability of personnel are considered to be the most important ones. The effect of individual abilities and specific features of the human body on changes in his occupational abilities can be estimated only to a certain degree

  17. Development of Universal Methodology of Specimen Free Nondestructive Inspection (Control) of Mechanical Properties of NPP Equipment Metal in all Stages of Lifetime

    International Nuclear Information System (INIS)

    Bakirov, M.; Chubarov, S.; Frolov, I.; Kiselev, I.; Gastrock, J.; Dripke, M.

    2011-01-01

    Ever-increasing requirements for reliability and safety of equipment in nuclear power plants (NPP) dictate a necessity to obtain reliable and validated information about the condition of materials in the most safety-relevant and economically vital systems structures and components (SSC). Thus it is a state of science and technology approach to use one method, one methodic and one methodology to facilitate these goals with the purpose of keeping NPPs operating safely by virtue of knowing the state of ageing they are in (with respect to design limits and margins). Method of the control/measurement/testing - how to conduct measurements; methodic - how to interpret the results of measurement; methodology - the program of the control/inspection and testing programmes: localities to conduct the tests, how often, and to follow evolution of test results with the aim of acting before a failure occurs. Such methodology should be based on the use of specimen-free nondestructive method of the inspection (control), which could be used, successfully at all stages of life cycle of the equipment: manufacturing, construction, installation of NPP, operation and during the NPP operation through integration into the Plant Life Management (PLiM) Programme. It will facilitate a real picture of change (degradation) of a SSC material's condition in the zones subjected to the harshest stressors (neutron irradiation, erosion-corrosion/flow, thermal fatigue, vibration etc). Currently, there are various approaches used in the world to follow NPP ageing degradation, but until now, no specific methodology is used that could supply all the necessary information. Therefore, there is no way to use various results. Thanks to considerable advances over the last 20 years or so, the science of hardness testing offers an elegant, non-destructive way to obtain vital materials properties - even in-situ on operating SSC. In particular, the material's elastic-plastic condition may be measured, giving

  18. Assessing mental workload and situation awareness in the evaluation of computerized procedures in the main control room

    International Nuclear Information System (INIS)

    Yang, Chih-Wei; Yang, Li-Chen; Cheng, Tsung-Chieh; Jou, Yung-Tsan; Chiou, Shian-Wei

    2012-01-01

    Highlights: ► This study investigates procedure types’ effects on operators’ performance. ► The computer-based procedure is suggested to be implemented in the main control room. ► The computer-based procedure brings lowest mental workload. ► And it also generates fewer error of omission, and the highest situation awareness. ► The shift supervisor has the highest workload and the lowest situation awareness. - Abstract: Computerized procedure (CP) system has been developed in nuclear power plant (NPP) instrumentation and control (I and C) system. The system may include normal operating procedures (OPs), abnormal operating procedures (AOPs), alarm response procedures (ARPs), surveillance test procedures (STPs) and/or emergency operating procedures (EOPs). While there are many ways to evaluate computerized procedures design, the user's mental workload and situation awareness (SA) are particularly important considerations in the supervisory control of safety-critical systems. Users’ mental workload and situation awareness may be influenced by human factor issues relating to computerized procedures, e.g., level of automation, dealing with (partially) unavailable I and C, switching to back-up system (e.g., paper-based procedures). Some of the positive impacts of CPs on operator performance include the following: tasks can be performed more quickly; overall workload can be reduced; cognitive workload can be minimized; fewer errors may be made in transitioning through or between procedures. However, various challenges have also been identified with CP systems. These should be addressed in the design and implementation of CPs where they are applicable. For example, narrower “field of view” provided by CP systems than with paper-based procedures could reduce crew communications and crewmember awareness of the status and progress through the procedure. Based on a human factors experiment in which each participant monitored and controlled multiple simulated

  19. Assessing mental workload and situation awareness in the evaluation of computerized procedures in the main control room

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Chih-Wei, E-mail: yangcw@iner.gov.tw [Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yang, Li-Chen; Cheng, Tsung-Chieh [Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Jou, Yung-Tsan; Chiou, Shian-Wei [Department of Industrial Engineering, Chung-Yuan Christian University, 200, Chung Pei Rd., Chung-Li 32023, Taiwan (China)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer This study investigates procedure types' effects on operators' performance. Black-Right-Pointing-Pointer The computer-based procedure is suggested to be implemented in the main control room. Black-Right-Pointing-Pointer The computer-based procedure brings lowest mental workload. Black-Right-Pointing-Pointer And it also generates fewer error of omission, and the highest situation awareness. Black-Right-Pointing-Pointer The shift supervisor has the highest workload and the lowest situation awareness. - Abstract: Computerized procedure (CP) system has been developed in nuclear power plant (NPP) instrumentation and control (I and C) system. The system may include normal operating procedures (OPs), abnormal operating procedures (AOPs), alarm response procedures (ARPs), surveillance test procedures (STPs) and/or emergency operating procedures (EOPs). While there are many ways to evaluate computerized procedures design, the user's mental workload and situation awareness (SA) are particularly important considerations in the supervisory control of safety-critical systems. Users' mental workload and situation awareness may be influenced by human factor issues relating to computerized procedures, e.g., level of automation, dealing with (partially) unavailable I and C, switching to back-up system (e.g., paper-based procedures). Some of the positive impacts of CPs on operator performance include the following: tasks can be performed more quickly; overall workload can be reduced; cognitive workload can be minimized; fewer errors may be made in transitioning through or between procedures. However, various challenges have also been identified with CP systems. These should be addressed in the design and implementation of CPs where they are applicable. For example, narrower 'field of view' provided by CP systems than with paper-based procedures could reduce crew communications and crewmember awareness of the

  20. Ukrainian Nuclear Society International Conference 'Modernization of the NPP with VVER reactor' (abstracts)

    International Nuclear Information System (INIS)

    Bar'yakhtar, V.G.

    1999-01-01

    Abstracts of the papers presented at International conference of the Ukrainian Nuclear Society 'Modernization of the NPP with VVER reactor'. The following problems are considered: improving the NPP's safety and reliability; reactor modernization, the lifetime prolongation; increasing of the reactor operating characteristics; methods of capacity factor increasing: refueling control, maintenance control; technical and economical aspects of NPP modernization; modernization of the automated control system of the fuel process at the NPP's; technical features and methods for the continued radiation and technology control at the NPP's; training, increasing the staff qualification and NPP modernization

  1. GUIDANCE FOR NUCLEAR POWER PLANT CONTROL ROOM AND HUMAN-SYSTEM INTERFACE MODERNIZATION

    International Nuclear Information System (INIS)

    Naser, J.; Morris, G.

    2004-01-01

    Several nuclear power plants in the United States are starting instrumentation and control (I and C) modernization programs using digital equipment to address obsolescence issues and the need to improve plant performance while maintaining high levels of safety. As an integral part of the I and C modernization program at a nuclear power plant, the control room and other human-system interfaces (HSIs) are also being modernized. To support safe and effective operation, it is critical to plan, design, implement, train for, operate, and maintain the control room and HSI changes to take advantage of human cognitive processing abilities. A project, jointly funded by the Electric Power Research Institute (EPRI) and the United States Department of Energy (DOE) under the Nuclear Energy Plant Optimization (NEPO) Program, is developing guidance for specifying and designing control rooms, remote shut-down panels, HSIs etc. The guidance is intended for application by utilities and suppliers of control room and HSI modernization. The guidance will facilitate specification, design, implementation, operations, maintenance, training, and licensing activities. This guidance will be used to reduce the likelihood of human errors and licensing risk, to gain maximum benefit of implemented technology, and to increase performance. The guidance is of five types. The first is planning guidance to help a utility develop its plant-specific control room operating concepts, its plant-specific endpoint vision for the control room, its migration path to achieve that endpoint vision, and its regulatory, licensing, and human factors program plans. The second is process guidance for general HSI design and integration, human factors engineering analyses, verification and validation, in-service monitoring processes, etc. The third is detailed human factors engineering guidance for control room and HSI technical areas. The fourth is guidance for licensing. The fifth is guidance for special topics

  2. The V-1 NPP and V-2 NPP upgrading

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities in the V-1 NPP and V-2 NPP upgrading as well as maintenance carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. The V-1 NPP applied the so called 'Small Backfitting Programme'covering 81 points of the Czechoslovak Atomic energy Commission Decree No 5/91. Continual upgrading continued after the Backfitting Programme completion with the Safety Report and following Nuclear Regulatory Authority of Slovak Republic (NRA SR) Decrees No 1/94 and 110/94 setting spheres and procedure for adopting and implementation of measures enabling the units to operate further on. Results of expert missions, analyses and assessments of components identified by Basic Engineering became the basis for the development of the Gradual Reconstruction Programme. The Programme outputs underwent economic and probabilistic assessing their contribution to nuclear safety. This process resulted in finalizing the Gradual Reconstruction Programme which started to be implemented in 1996 and will be completed in 1999. It is implemented by the REKON consortium and covers 17 areas including Instrumentation and Control, self-consumption emergency supply, leakage monitoring, emergency core cooling system, seismic reinforcement and radioactivity localisation. Both units will reach internationally acceptable safety standards for the remaining life-time period. The V-2 NPP Upgrading and Safety Enhancement Programme includes results of activities performed in the course of last years to define all important activities leading to enhancement of nuclear safety and performance reliability and effectiveness within the plant life-time period and to establish conditions for extending the life-time of these units for 40 years. The V-2 NPP Upgrading and Safety Enhancement Programme aims to assure safe operation with a probability of the core damages less than 10 -4 /reactor · year

  3. Statistical process control as a tool for controlling operating room performance: retrospective analysis and benchmarking.

    Science.gov (United States)

    Chen, Tsung-Tai; Chang, Yun-Jau; Ku, Shei-Ling; Chung, Kuo-Piao

    2010-10-01

    There is much research using statistical process control (SPC) to monitor surgical performance, including comparisons among groups to detect small process shifts, but few of these studies have included a stabilization process. This study aimed to analyse the performance of surgeons in operating room (OR) and set a benchmark by SPC after stabilized process. The OR profile of 499 patients who underwent laparoscopic cholecystectomy performed by 16 surgeons at a tertiary hospital in Taiwan during 2005 and 2006 were recorded. SPC was applied to analyse operative and non-operative times using the following five steps: first, the times were divided into two segments; second, they were normalized; third, they were evaluated as individual processes; fourth, the ARL(0) was calculated;, and fifth, the different groups (surgeons) were compared. Outliers were excluded to ensure stability for each group and to facilitate inter-group comparison. The results showed that in the stabilized process, only one surgeon exhibited a significantly shorter total process time (including operative time and non-operative time). In this study, we use five steps to demonstrate how to control surgical and non-surgical time in phase I. There are some measures that can be taken to prevent skew and instability in the process. Also, using SPC, one surgeon can be shown to be a real benchmark. © 2010 Blackwell Publishing Ltd.

  4. Concept and design of a fully computerized control room for future nuclear power plant

    International Nuclear Information System (INIS)

    Hinz, W.; Kollmannsberger, J.

    1991-01-01

    The development of digital process control equipment and of safety engineering equipment together with the CRT - based information visualization systems is advanced to a state allowing process control of nuclear power plant to be done by these equipments. The systems have been tested in the control room of the fossil-fuel Staudinger reactor station, unit 5, and the computer-assisted PRISCA process information system has been tested in the Konvoi-type nuclear reactor series. These tests serve as a basis for further process control system development by Siemens KWU, to be used in their future nuclear power plants. The advantages of digital process control and CRT-based information display are intended to be used for further optimization of the man-machine interface in nuclear power plant. One important aspect is to give the control room personnel complete insight into the operational processes of the entire plant, and to establish for detail recognition for process monitoring a very close mental link between operators and the system processes. In addition, the control room operator has to be given appropriate means and tools for process monitoring and control, fulfilling the requirements of guaranteeing the plant's availability and safety. These requirements put very high demands on the process monitoring and control equipment. (orig.) [de

  5. Control console for the X-ray room; Consola de control para la sala de rayos X

    Energy Technology Data Exchange (ETDEWEB)

    Garcia H, J.M.; Aguilar B, M.A.; Torres B, M.A

    1998-07-01

    It is presented the design and construction of Control console for the X-ray room of Metrology Center for ionizing radiations at National Institute of Nuclear Research (ININ). This system controls the positioning of 6 different filters for an X-ray beam. Also it controls a shutter which blockades the beam during periods established by user, these periods can be fixed from hours until tenth of second. The shutter opening periods, as well as the X-ray beam filter are establish and monitoring from a Personal computer outside of room. (Author)

  6. Advanced control rooms and crew performance issues: Implications for human reliability

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Hall, R.E.

    1991-01-01

    Recent trends in advanced control room (ACR) design are considered with respect to their impact on human performance. It is concluded that potentially negative influences exist, however, a variety of factors make it difficult to model, analyze, and quantify these effects for human reliability analyses (HRAs)

  7. Design of nuclear power plant control rooms: some findings and possible improvements

    International Nuclear Information System (INIS)

    Bohr, E.

    1984-01-01

    Major findings are described of a study on the present status and possible improvements in the design of nuclear power plant control rooms according to ergonomic principles and criteria. The findings have been acquired by observing the performance of control room operators, by interviewing operators and management personnel, and by analysing major characteristics of the man-machine interface. The methods currently used for developing and designing control rooms have also been examined. The results of the study indicate that there is a growing awareness and consideration of physical factors affecting performance. More attention should be paid to the essential cognitive characteristics of work in the control room with the aim of avoiding unnecessary hindrances and possible errors. Examples are given of some of these problems, and approaches, ways and means for solving or mitigating them are indicated. A more deliberate consideration of factors affecting operator performance and reliability is suggested, based on a systems ergonomics approach. Analyses of critical tasks would be a major feature of this approach. Its main objective is to ensure that operators are able to carry out their tasks reliably. (author)

  8. Ergonomic principles of control rooms in nuclear power plants. Vol. 1 and 2

    International Nuclear Information System (INIS)

    Becker, G.; Bohr, E.; Thau, G.

    1983-03-01

    This report describes the findings of a study on the present status and possible improvements in the design of nuclear power plant control rooms according to ergonomic principles and criteria. The findings have been acquired by observing the performance of control room operators, by interviewing operators and management personnel, and by analyzing major characteristics of the man-machine interface. The methods currently used for developing and designing control rooms have also been examined, and the pertinent scientific and technical literature has been reviewed. The results of the study indicate that there is a growing awareness and consideration of physical factors affecting operator performance and reliability whereas less attention is paid to the essential cognitive characteristics of work in the control room. The tasks of operators thus may contain avoidable hindrances and error possibilities that may adversely affect their contribution to reliable plant operation. Major areas of possible ergonomic advancements are set out in the study, and most of them are discussed in depth. Ergonomic requirements are identified for further improving the situation, and approaches, ways and means for solving of mitigating individual problems are indicated wherever possible. A more deliberate consideration of factors affecting operator performance and reliability is suggested, based on a systems ergonomics approach. Design objectives and criteria as well as specific design recommendations for individual areas are given separately. In conclusion, gaps in our existing knowledge are identified which require further research. (orig.) [de

  9. Workflow in Almaraz NPP

    International Nuclear Information System (INIS)

    Gonzalez Crego, E.; Martin Lopez-Suevos, C.

    2000-01-01

    Almaraz NPP decided to incorporate Workflow into its information system in response to the need to provide exhaustive follow-up and monitoring of each phase of the different procedures it manages. Oracle's Workflow was chosen for this purpose and it was integrated with previously developed applications. The objectives to be met in the incorporation of Workflow were as follows: Strict monitoring of procedures and processes. Detection of bottlenecks in the flow of information. Notification of those affected by pending tasks. Flexible allocation of tasks to user groups. Improved monitoring of management procedures. Improved communication. Similarly, special care was taken to: Integrate workflow processes with existing control panels. Synchronize workflow with installation procedures. Ensure that the system reflects use of paper forms. At present the Corrective Maintenance Request module is being operated using Workflow and the Work Orders and Notice of Order modules are about to follow suit. (Author)

  10. Instrumentation and equipment for monitoring and controlling NPP post-accident situations. Working material. Proceedings of a specialists' meeting held in Dimitrovgrad, Russian Federation, 12-15 September 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The objectives of the Specialist's Meeting were: To provide an international forum for presentation and discussion on experience with instrumentation and equipment for monitoring and controlling NPP post-accident situations; to share experience on the design and improvements in the subject area; to identify and describe advanced features for safety and post-accident management improvements. In order to facilitate a structure discussion and not to omit important problem areas, papers on the following subjects were considered to be within the scope of the Specialist's Meeting: Analysis of existing post-accident instrumentation (in terms of range, qualification and redundancy) to support post-accident management. Requirements for post accident instrumentation and equipment - operating experience, regulations, standards; experience in upgrading of the existing instrumentation; instrumentation and equipment for emergency management systems (emergency rooms and national centers); post-accident computerized aids to assist operators; post-accident operating procedures; R and D in post-accident instrumentation, future trends. The present volume contains: (1) the papers presented by national delegates; (2) programme of the meeting; (3) description of the RIAR research facilities; and (4) list of participants. Refs, figs and tabs

  11. IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    issues apply to new build projects as well. Technical experts and managers from the field of instrumentation and control, process control, human factors engineering, licensing, and computer applications are invited to a Technical Meeting dealing with all important aspects of control room modernization projects. The subject of the present technical meeting was suggested by the members of the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) and supported by a number of IAEA meetings on NPP I and C Systems. Additional information on the Technical Working Group, and on the activities of the IAEA Division of Nuclear Power is available on The purpose of the meeting is to provide an international forum for presentations and discussions of experience with various aspects of the integration of analog and digital instrumentation and control systems in hybrid main control rooms, as applicable to both existing plants and planned (or in-progress) new plant builds. Promising new technologies and future trends in development will be also discussed. The meeting is intended for experts and managers in the I and C field from nuclear power utilities, vendor companies, licensing bodies, research organizations and academic institutions.

  12. Control room, emergency control system and local control panels in nuclear power plants

    International Nuclear Information System (INIS)

    1988-01-01

    The requirements on planning and construction of control boards including ergonomic-technical designing are specified in this rule. The specifications put the requirements on the design of place, process and environment of work, which are mentioned in the sections 90 and 91 of the labor-management relations act, into more concrete terms for the safety-relevant control panels as work places in a nuclear power station. The work places at control panels are not considered as video workstations in the sense of the 'Safety Rules for Video Workstations in the Office Sector' published by the General Association of the Industrial Trade Associations. The requirements are based on the operation and information technology realized at present in control panels of stationary nuclear power plants. (orig./HP) [de

  13. A work process and information flow description of control room operations

    International Nuclear Information System (INIS)

    Davey, E.; Matthews, G.

    2007-01-01

    The control room workplace is the location from which all plant operations are supervised and controlled on a shift-to-shift basis. The activities comprising plant operations are structured into a number of work processes, and information is the common currency that is used to convey work requirements, communicate business and operating decisions, specify work practice, and describe the ongoing plant and work status. This paper describes the motivation for and early experience with developing a work process and information flow model of CANDU control room operations, and discusses some of the insights developed from model examination that suggest ways in which changes in control centre work specification, organization of resources, or asset layout could be undertaken to achieve operational improvements. (author)

  14. Application of process computers and colour CRT displays in the plant control room of a BWR

    International Nuclear Information System (INIS)

    Itoh, M.; Hayakawa, H.; Kawahara, H.; Neda, T.; Wakabayashi, Y.

    1983-01-01

    The recent application of a CRT display system in an 1100-MW(e) BWR plant control room and the design features of a new control room whose installation is planned for the next generation are discussed. As reactor unit capacity and the need for plant safety and reliability continue to increase, instrumentation and control equipment is growing in number and complexity. In consequence, control and supervision of plant operations require improvement. Thus, because of recent progress in the field of process computers and display equipment (colour CRTs), efficient improvements of the control room are under way in the Japanese BWR plant. In the recently constructed BWR plant (1100 MW(e)), five CRTs on the bench board and two process computers were additionally installed in the control room during the construction stage to improve plant control and supervisory functions by implementing the lessons learned from the Three Mile Island incident. The major functions of the new computers and display systems are to show integrated graphic displays of the plant status, to monitor the standby condition of the safety system, to show the condition of the integrated alarm system, etc. In practice, in the actual plant, this newly installed system performs well. On the basis of the experience gained in these activities, a new computerized control and monitoring system is now being designed for subsequent domestic BWR plants. This advanced system will incorporate not only the functions already mentioned, but also a surveillance guide system and plant automation. For future plants, a diagnostic system and an instructional system that can analyse a disturbance and give operational guidance to the plant operator are being developed in a government-sponsored programme. (author)

  15. Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.; Harris, T.; Keithline, K.

    2006-01-01

    There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

  16. new developments for control room habitability evaluation and analysis. Panel Discussion

    International Nuclear Information System (INIS)

    Cozens, Kurt O.; Harvey, Robert B. Jr.; Hayes, John J. Jr.; Jarosz, Gregory; Lagus, Peter L.; Taplett, Kenneth J.; Schultz, Stephen P.

    2001-01-01

    In 2000, the Nuclear Energy Institute (NEI), nuclear utilities, and the U.S. Nuclear Regulatory Commission (NRC) embarked on a series of working meetings designed to develop means to assess the post-accident performance of control room ventilation systems to ensure required control room habitability (CRH). Through monthly meeting interactions beginning in January 2000, teams from the industry and the NRC have been working to develop an industry approach for assessment of existing systems. New system evaluation techniques are being developed that will allow for evaluation and/or identification of potential performance improvement options. NRC review of the documentation of this approach, as well as broad industry comment, was performed in the first part of 2001. This session will examine technical development topics covering licensing, analysis, testing, and control room refurbishment. NRC, NEI, utility, vendor, and consultant presentations will be followed by a panel session that will explore both process and technical recommendations for improvements. Since the mid-1980's, the NRC has communicated concerns on the inadequacies of control room designs relating to CRH requirements. In the mid-1990's, testing of some control room envelopes indicated that key assumptions supporting the radiological dose analysis might be incorrect. In 1998, the NRC held a public workshop to address CRH concerns. In late 1999, the NRC and the industry agreed to work together on issues affecting CRH and develop the NEI 99-03 guidance document for resolving those issues. This NEI 99-03 industry document defines a process for licensees to assess a plant's design and licensing bases for CRH to ensure that they are established and maintained throughout the life of the plant. The assessment process describes a comparative approach to determine if the plant configuration and operation are consistent with the CRH licensing basis and analysis. The process includes evaluation, testing, and

  17. Tritium monitoring at NPP and enviromental area under survey

    International Nuclear Information System (INIS)

    Nurislamov, I.R.; Kham'yanov, L.P.; Panichkin, V.F.

    1983-01-01

    Methods and devices for tritium monitoring at NPP with the WWER-type reactors and the environment are described. Aqueous solutions of inorganic and organic compounds, water vapours in the air of NPP rooms and the environment atmosphere, free and bound water in soils and vegetation were the objects for monitoring. Methods of tritium sampling from the atmosphere as well as determination of its content in samples are presented. Special attention is paid to sample enrichment with tritium

  18. The use of operator surveys by the CEGB to evaluate nuclear control room design and initiatives in the design of alarm systems and control room operating procedures

    International Nuclear Information System (INIS)

    Jackson, A.R.G.

    1988-01-01

    This paper reports on the use of operator surveys and trip report analysis methods which the Central Electricity Generating Board has developed to assess the extent and adequacy of operator support systems currently installed on its four twin-reactor, first generation Advanced Gas Cooled Reactor nuclear power plants. The survey consisted of a programme of structured interviews with control room engineers. The scope of the questions addressed; working environment, communications, man-machine interface, procedural information, and the diagnostic and predictive support system. The analysis of trip reports was targetted at identifying aspects of the performance of the operator support systems which might have been contributory to the cause of reactor trip. The results of this work are being used to assist in determining guidelines for the development of operator support systems, computerised controls and the structure of station operating procedures

  19. Analysis of man-machine interaction for control and display system in main control room of light water reactor

    International Nuclear Information System (INIS)

    Santosa, Kussigit; Supriatna, Piping; Karlina, Itjeu; Widagdo, Suharyo; Darlis; Sudiono, Bambang

    1998-01-01

    One of potential hazard in Nuclear Power Plant is the failure of its operation. The accident or operation failure in the reactor must be concerned event its probability is low. The important thing should be concerned is 'Analysis of Man-Machine Interaction (MMI) for Control and Display System in Main Control Room (MCR) of Nuclear Power Reactor', especially LWR type. Control and Display System in MCR of Reactor is the main part of MMI link process in Reactor MCR work system. Signal from display system showed performance process in reactor, while this signal will be received by operator. This signal will be described through central nerve for making decision what kind must be done. Then the operator manage the next process of reactor operation through control system. So by knowing Analysis of Man-Machine Interaction for Control and Display System in Main Control Room of Power Reactor, we can understand human error probability of the operator in reactor operation

  20. Nuclear Fuel in Cofrentes NPP

    International Nuclear Information System (INIS)

    2002-01-01

    Fuel is an essential in the nuclear power generating business because of its direct implications on safety, generating costs and the operating conditions and limitations of the facility. Fuel management in Cofrentes NPP has been targeted at optimized operation, enhanced reliability and the search for an in-depth knowledge of the design and licensing processes that will provide Iberdrola,as the responsible operator, with access to independent control of safety aspects related to fuel and free access to manufacturing markets. (Author)