Development of human factors engineering guide for nuclear power project

International Nuclear Information System (INIS)

Wu Dangshi; Sheng Jufang

1997-01-01

'THE PRACTICAL GUIDE FOR APPLICATION OF HUMAN FACTORS ENGINEERING TO NUCLEAR POWER PROJECT (First Draft, in Chinese)', which was developed under a research program sponsored by National Nuclear Safety Administration (NNSA) is described briefly. It is hoped that more conscious, more systematical and more comprehensive application of Human Factors Engineering to the nuclear power projects from the preliminary feasibility studies up to the commercial operation will benefit the safe, efficient and economical operations of nuclear power plants in China

US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

International Nuclear Information System (INIS)

1984-09-01

The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

Human factors guidelines for nuclear power plant applications

International Nuclear Information System (INIS)

Ketchel, J.

1993-01-01

In 1989, Waters et al. reported to the Human Factors Society on developing human factors criteria for a new reactor plant. They correctly indicated that much of the guidance documentation in human factors engineering has derived from MIL-STD-1472 and its antecedents. Guidelines for human-computer interface have sprung primarily from the Smith and Mosier compendium and its source documents. NUREG-0700, which is currently being updated, was developed by the US Nuclear Regulatory Commission (NRC) as a general evaluation guide for inspecting control rooms. In addition, the Electric Power Research Institute, Institute of Nuclear Power Operations, US Department of Energy, the NRC, and others have published a number of specialized documents on a range of subjects. The number of guidelines and standards has grown in the past few years to an impressive number, including those published by international organizations and professional societies. This paper provides an update on current efforts to provide appropriate guidance for the power industry and, perhaps more importantly, offers a perspective on how users should think about using the available materials and what else is needed. The Electric Power Research Institute (EPRI) continues to be one of the principal participants in providing guidance to the utilities. Human factors guidelines is indeed a timely topic, currently of great interest to EPRI's constituents and to designers of new and upgraded nuclear power plants (NPMs) in the Advanced Light Water Reactor and the Instrumentation and Control Upgrade Initiative programs

Quality management in the nuclear industry: the human factor

International Nuclear Information System (INIS)

1990-01-01

In the nuclear industry it is vital to understand the 'human factor' with regard to plant performance and plant safety. A proper management system ensures that personnel perform their duties correctly. 'Quality Management in the Nuclear Industry: the Human Factor', was a conference organized by the Institution of Mechanical Engineers in October 1990. The conference covered a wide range of topics on an international level including: standards, licensing and regulatory procedures; selection assessment and training of personnel; feedback from experience of good practice and of deviations; management and support of personnel performance; modelling and evaluation of human factors. The papers presented at the conference are contained in this volume. All twenty papers are indexed separately. (author)

Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

International Nuclear Information System (INIS)

Li Tianshu

2013-01-01

Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

Human factors aspects of advanced instrumentation in the nuclear industry

International Nuclear Information System (INIS)

Carter, R.J.

1989-01-01

An important consideration in regards to the use of advanced instrumentation in the nuclear industry is the interface between the instrumentation system and the human. A survey, oriented towards identifying the human factors aspects of digital instrumentation, was conducted at a number of United States (US) and Canadian nuclear vendors and utilities. Human factors issues, subsumed under the categories of computer-generated displays, controls, organizational support, training, and related topics were identified. 20 refs., 2 tabs

Human factors in the Canadian nuclear industry: future needs

International Nuclear Information System (INIS)

Harrison, F.

2008-01-01

Currently the industry is facing refurbishment and new builds. At present most licensees in Canada do not have sufficient numbers of Human Factors staff. As a result, the activities of the CNSC are too often focused on providing guidance regarding the application of Human Factors, in addition to reviewing work submitted by the licensee. Greater efficiencies for both the licensee and the CNSC could be realized if licensee staff had greater Human Factors expertise. Strategies for developing Human Factors expertise should be explored through cooperative partnerships with universities, which could be encouraged to include Human Factors courses specific to nuclear. (author)

Human factor engineering applied to nuclear power plant design

International Nuclear Information System (INIS)

Manrique, A.; Valdivia, J.C.; Jimenez, A.

2001-01-01

For the design and construction of new nuclear power plants as well as for maintenance and operation of the existing ones new man-machine interface designs and modifications are been produced. For these new designs Human Factor Engineering must be applied the same as for any other traditional engineering discipline. Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. Additionally, the big saving achieved by a nuclear power plant having an operating methodology which significantly decreases the risk of operating errors makes it necessary and almost vital its implementation. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. (author)

A regulatory perspective on human factors in nuclear power

International Nuclear Information System (INIS)

Whitfield, D.

1987-01-01

This paper sets out the approaches being taken by the United Kingdom Nuclear Installations Inspectorate (NII) to monitoring the application of human factors principles and practice in the UK industry. The role of NII is outlined, the development of human factors concerns is reviewed, the assessment of the Sizewell 'B' safety case is presented as a particular example, and pertinent future developments in the human factors discipline are proposed. (author)

A report on human factors in nuclear safety

International Nuclear Information System (INIS)

1983-03-01

Following the Three Mile Island incident of 1979, studies were undertaken by the Atomic Energy Control Board (AECB), in-house and through outside consultants, to address the role of human factors in the regulatory process. This report by the Advisory Committee on Nuclear Safety (ACNS) comments briefly on these studies and offers suggestions which would promote a more formal treatment of human factors by the AECB

Human factors engineering plan for reviewing nuclear plant modernization programs

International Nuclear Information System (INIS)

O'Hara, John; Higgins, James

2004-12-01

The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation

Human factors engineering plan for reviewing nuclear plant modernization programs

Energy Technology Data Exchange (ETDEWEB)

O' Hara, John; Higgins, James [Brookhaven National Laboratory, Upton, NY (United States)

2004-12-01

The Swedish Nuclear Power Inspectorate reviews the human factors engineering (HFE) aspects of nuclear power plants (NPPs) involved in the modernization of the plant systems and control rooms. The purpose of a HFE review is to help ensure personnel and public safety by verifying that accepted HFE practices and guidelines are incorporated into the program and nuclear power plant design. Such a review helps to ensure the HFE aspects of an NPP are developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The review addresses eleven HFE elements: HFE Program Management, Operating Experience Review, Functional Requirements Analysis and Allocation, Task Analysis, Staffing, Human Reliability Analysis, Human-System Interface Design, Procedure Development, Training Program Development, Human Factors Verification and Validation, and Design Implementation.

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

Human factor engineering applied to nuclear power plant design

International Nuclear Information System (INIS)

Manrique, A.; Valdivia, J.C.

2007-01-01

Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. Such a plan should state: -) Activities to be performed, and -) Creation of a Human Factor Engineering team adequately qualified. The Human Factor Engineering team is an integral part of the design team and is strongly linked to the engineering organizations but simultaneously has independence to act and is free to evaluate designs and propose changes in order to enhance human behavior. TECNATOM S.A. (a Spanish company) has been a part of the Design and Human Factor Engineering Team and has collaborated in the design of an advanced Nuclear Power Plant, developing methodologies and further implementing those methodologies in the design of the plant systems through the development of the plant systems operational analysis and of the man-machine interface design. The methodologies developed are made up of the following plans: -) Human Factor Engineering implementation in the Man-Machine Interface design; -) Plant System Functional Requirement Analysis; -) Allocation of Functions to man/machine; -) Task Analysis; -) Human-System Interface design; -) Control Room Verification and -) Validation

Review of EPRI Nuclear Human Factors Program

International Nuclear Information System (INIS)

Hanes, L.F.; O'Brien, J.F.

1996-01-01

The Electric Power Research Institute (EPRI) Human Factors Program, which is part of the EPRI Nuclear Power Group, was established in 1975. Over the years, the Program has changed emphasis based on the shifting priorities and needs of the commercial nuclear power industry. The Program has produced many important products that provide significant safety and economic benefits for EPRI member utilities. This presentation will provide a brief history of the Program and products. Current projects and products that have been released recently will be mentioned

The human factor in the organisation and regulation of nuclear safety

International Nuclear Information System (INIS)

Bordes, F.; Savagner, J.-M.; Snanoudj, G.

1981-10-01

The TMI accident has brought to light the importance of the human factor in the safe operation of complex installations such as nuclear power plants. On this basis, the paper outlines the institutional framework for nuclear safety in France and reports on EDF practices in human resources management as well as in the improvement of working premises (control rooms) to optimize human behaviour in accident conditions. Finally, the interaction of labour laws on nuclear law in connection with safety is described. (NEA) [fr

Human factors engineering applied to Control Centre Design of a research nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Farias, Larissa P. de; Santos, Isaac J.A. Luquetti dos; Carvalho, Paulo V.R., E-mail: larissapfarias@ymail.com [Instituto de Engenharia Nuclear (DENN/SEESC/IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab, de Usabilidade e Confiabilidade Humana; Monteiro, Beany G. [Universidade Federal do Rio Janeiro (UFRJ), Rio Janeiro, RJ (Brazil). Departamento de Desenho Industrial

2017-07-01

The Human Factors Engineering (HFE) program is an essential aspect for the design of nuclear installations. The overall aim of the HFE program is the improvement of the operational reliability and safety of plant operation. The HFE program main purpose is to ensure that human factor practices are incorporated into the plant design, emphasizing man-machine interface issues and design improvement of the nuclear reactor Control Centre. The Control Centre of nuclear reactor is a combination of control rooms, control suites and local control stations, which are functionally connected and located on the reactor site. The objective of this paper is to present a design approach for the Control Centre of a nuclear reactor used to produce radioisotopes and for nuclear research, including human factor issues. The design approach is based on participatory design principles, using human factor standards, ergonomic guidelines, and the participation of a multidisciplinary team during all design phases. Using the information gathered, an initial sketch 3D of the Control Centre was developed. (author)

Human factors engineering applied to Control Centre Design of a research nuclear reactor

International Nuclear Information System (INIS)

Farias, Larissa P. de; Santos, Isaac J.A. Luquetti dos; Carvalho, Paulo V.R.; Monteiro, Beany G.

2017-01-01

The Human Factors Engineering (HFE) program is an essential aspect for the design of nuclear installations. The overall aim of the HFE program is the improvement of the operational reliability and safety of plant operation. The HFE program main purpose is to ensure that human factor practices are incorporated into the plant design, emphasizing man-machine interface issues and design improvement of the nuclear reactor Control Centre. The Control Centre of nuclear reactor is a combination of control rooms, control suites and local control stations, which are functionally connected and located on the reactor site. The objective of this paper is to present a design approach for the Control Centre of a nuclear reactor used to produce radioisotopes and for nuclear research, including human factor issues. The design approach is based on participatory design principles, using human factor standards, ergonomic guidelines, and the participation of a multidisciplinary team during all design phases. Using the information gathered, an initial sketch 3D of the Control Centre was developed. (author)

The human factor and organization to support nuclear power plant operators

International Nuclear Information System (INIS)

Naumov, V.I.

1993-01-01

Analysis reveals three basic factors which affect the safety of nuclear power reactors: (1) Internal physical properties of the reactor which provide self protection under breakdown and accident conditions; (2) The reliability of technical systems which provide monitoring, control, accident prevention, heat release, and localization of hazardous products during accidents; (3) Reliability of the reactor control personnel. The last of these factors is usually called the human factor. From published data, this factor makes a large contribution to the downtime and accident statistics at nuclear power plants: from 30 to 80% in various countries. Today the importance of the human factor in operating a nuclear power units is rather well recognized. Current ideas on how to increase the reliability of a human operator are reflected in IAEA recommendations and domestic official documents. The concept of 'a culture of safety' is introduced. Basic types of actions to increase the reliability of personnel who control a nuclear reactor are discussed, including: (1) The qualifying and psychological selection and the training of candidates on the operator's obligations. (2) The automation of routine operations which do not require the operator's intellect. (3) Perfecting the work place, information input to the operator, and the organization of the controls

Studies on human factors in nuclear power plants

International Nuclear Information System (INIS)

Tsukuda, H.; Miyaoka, S.

1988-01-01

In order to raise the reliability and safety of nuclear power plants to the highest possible level, improvements to the mechanical system alone are not sufficient. Human factors must be systematically analysed and the causes and mechanisms of human error clarified to allow the development of countermeasures that will reduce error as much as possible. The paper introduces research in two areas, fundamental clarification of human behavioural, physiological and psychological characteristics to aid in the development of preventive measures for reducing error, and studies involving analysis of actual cases of accidents and failures related to man along with development of countermeasures to prevent the recurrence of such cases. The paper especially considers the latter area. The Human Performance Evaluation System (HPES) developed by the Institute of Nuclear Power Operations (INPO) in the USA was applied on a trial basis to 31 recent accidents and failures at Japanese nuclear power plants. The effectiveness of and possible improvement to HPES were considered. Also, cases that were not directly linked to accidents or failures were analysed using a method developed independently in Japan using data collected from a survey of approximately 3,000 power plant personnel. Fundamental research on human behaviour, physiology and psychology are also introduced. (author). 4 figs

Discussion on verification criterion and method of human factors engineering for nuclear power plant controller

International Nuclear Information System (INIS)

Yang Hualong; Liu Yanzi; Jia Ming; Huang Weijun

2014-01-01

In order to prevent or reduce human error and ensure the safe operation of nuclear power plants, control device should be verified from the perspective of human factors engineering (HFE). The domestic and international human factors engineering guidelines about nuclear power plant controller were considered, the verification criterion and method of human factors engineering for nuclear power plant controller were discussed and the application examples were provided for reference in this paper. The results show that the appropriate verification criterion and method should be selected to ensure the objectivity and accuracy of the conclusion. (authors)

Human factor in the problem of Russian nuclear industry safety

International Nuclear Information System (INIS)

Abramova, V.

2002-01-01

The approach to human factor definition, considered in the paper, consists of recognition of as many as possible factors for developing a complete list of factors, which have influence on mistakes or successful work of NPP personnel. Safety culture is considered as the main factor. The enhancement in nuclear power industry includes an optimization of organizational structures and development of personnel safety attitudes. The organizational factors, as possible root causes for human errors, need to be identified, assessed and improved. The organizational activities taken in Russia are presented

Human-factor operating concept for Borssele Nuclear Power Station

International Nuclear Information System (INIS)

Wieman, J.L.

1995-01-01

The safety level in the operation of a reactor is determined basically by human beings. The Borssele Nuclear Power Station has carried out measures for improving the man-machine interface through training and operating instructions for the shift personnel. The retrofitting of control technology relevant to safety engineering should avoid operating instructions which can cause potential failures. A safety study has shown that the remaining risk following all retrofitting measures remains dependent to the extent of 80% on human factors and that human factors as a whole have a positive effect on reactor safety. (orig.) [de

UNC Nuclear Industries' human-factored approach to the operating or maintenance procedure

International Nuclear Information System (INIS)

Nelson, A.A.; Clark, J.E.

1982-01-01

The development of Human Factors Engineering (HFE) and UNC Nuclear Industries' (UNC) commitment to minimizing the potential for human error in the performance of operating or maintenance procedures have lead to a procedure upgrade program. Human-factored procedures were developed using information from many sources including, but not limited to, operators, a human factors specialist, engineers and supervisors. This has resulted in the Job Performance Aid (JPA). This paper presents UNC's approach to providing human-factored operating and maintenance procedures

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

An improvement of the applicability of human factors guidelines for coping with human factors issues in nuclear power plants

International Nuclear Information System (INIS)

Lee, Y. H.; Lee, J. Y.

2003-01-01

Human factors have been well known as one of the key factors to the system effectiveness as well as the efficiency and safety of nuclear power plants(NPPs). Human factors engineering(HFE) are included in periodic safety review(PSR) on the existing NPPs and the formal safety assessment for the new ones. However, HFE for NPPs is still neither popular in practice nor concrete in methodology. Especially, the human factors guidelines, which are the most frequent form of human factors engineering in practice, reveal the limitations in their applications. We discuss the limitations and their casual factors found in human factors guidelines in order to lesson the workload of HFE practitioners and to improve the applicability of human factors guidelines. According to the purposes and the phases of HFE for NPPs, more selective items and specified criteria should be prepared carefully in the human factors guidelines for the each HFE applications in practice. These finding on the human factors guidelines can be transferred to the other HFE application field, such as military, aviation, telecommunication, HCI, and product safety

Transferring aviation human factors technology to the nuclear power industry

International Nuclear Information System (INIS)

Montemerlo, M.D.

1981-01-01

The purpose of this paper is to demonstrate the availability of aviation safety technology and research on problems which are sufficiently similar to those faced by the nuclear power industry that an agressive effort to adapt and transfer that technology and research is warranted. Because of time and space constraints, the scope of this paper is reduced from a discussion of all of aviation safety technology to the human factors of air carrier safety. This area was selected not only because of similarities in the human factors challenges shared by both industries (e.g. selection, training, evaluation, certification, etc.) but because experience in aviation has clearly demonstrated that human error contributes to a substantially greater proportion of accidents and incidents than does equipment failure. The Congress of the United States has placed a great deal of emphasis on investigating and solving human factors problems in aviation. A number of recent examples of this interest and of the resulting actions are described. The opinions of prominent aviation organizations as to the human factors problems most in need of research are presented, along with indications of where technology transfer to the nuclear power industry may be viable. The areas covered include: fatigue, crew size, information transfer, resource management, safety data-bases, the role of automation, voice and data recording systems, crew distractions, the management of safety regulatory agencies, equipment recertification, team training, crew work-load, behavioural factors, human factors of equipment design, medical problems, toxicological factors, the use of simulators for training and certification, determining the causes of human errors, the politics of systems improvement, and importance of both safety and public perception of safety if the industry is to be viable. (author)

Human factors review of nuclear power plant control room design. Final report

International Nuclear Information System (INIS)

Seminara, J.L.; Gonzalez, W.R.; Parsons, S.O.

1976-11-01

The human factors aspects of five representative nuclear power plant control rooms were evaluated using such methods as a checklist guided observation system, structured interviews with operators and trainers, direct observations of operator behavior, task analyses and procedure evaluation, and historical error analyses. The human factors aspects of design practices are illustrated, and many improvements in current practices are suggested. The study recommends that a detailed set of applicable human factors standards be developed to stimulate a uniform and systematic concern for human factors in design considerations

Nuclear safety and human factors: the French factory of expertise

International Nuclear Information System (INIS)

Rolina, G.

2009-01-01

The French regulation of the nuclear safety is based on the maintaining of a deep technical dialogue between the nuclear safety authority, the I.R.S.N. (Institute of radiation protection and nuclear safety) and the nuclear operators. This type of risk management is called 'french coking' by the Anglo-Saxons, followers of stricter regulatory approach, more readable by the civil society. This technical dialogue is not without quality, especially in the field of human and organizational factors where it allows to improve the know how situation that stays incomplete. (N.C.)

Human factor in the process of nuclear power development

International Nuclear Information System (INIS)

Enenkl, V.

The building up of nuclear power requires the training not only of personnel but of the whole population as well. Professional workers in nuclear power facilities production and personnel operating the equipment of nuclear power plants must be on a high technical and managerial level. The important quality of such personnel is their reliability and responsibility. The human factor influences the level, quality and thereby also the service-life of the machines and equipment and their operation. The improvement of the quality of work in nuclear power production depends on upgrading the scientific and technical level of workers and personnel, their training, in-service education and the raising of the social standing. (B.H.)

Human factors design guidelines for maintainability of Department of Energy nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

1985-06-18

Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed.

Human factors design guidelines for maintainability of Department of Energy nuclear facilities

International Nuclear Information System (INIS)

Bongarra, J.P. Jr.; VanCott, H.P.; Pain, R.F.; Peterson, L.R.; Wallace, R.I.

1985-01-01

Intent of these guidelines is to provide design and design review teams of DOE nuclear facilities with human factors principles to enhance the design and aid in the inspection of DOE nuclear facilities, systems, and equipment. These guidelines are concerned with design features of DOE nuclear facilities which can potentially affect preventive and corrective maintenance of systems within DOE nuclear facilities. Maintenance includes inspecting, checking, troubleshooting, adjusting, replacing, repairing, and servicing activities. Other factors which influence maintainability such as repair and maintenance suport facilities, maintenance information, and various aspects of the environment are also addressed

Establishing a value chain for human factors in nuclear power plantcontrol room modernization

Energy Technology Data Exchange (ETDEWEB)

Joe, Jeffrey Clark [Idaho National Laboratory; Thomas, Kenneth David [Idaho National Laboratory; Boring, Ronald Laurids [Idaho National Laboratory

2015-07-01

Commercial nuclear power plants in the United States (U.S.) have operated reliably and efficiently for decades. With the life extensions of plants now being planned for operation beyond their original operating licenses, there are opportunities to achieve even greater efficiencies, while maintaining high operational reliabilities, with strategic, risk- and economically-informed, upgrades to plant systems and infrastructure. The U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) program supports the commercial nuclear industry’s modernization efforts through research and development (R&D) activities across many areas to help establish the technical and economic bases for modernization activities. The Advanced Instrumentation, Information, and Control Systems Technologies pathway is one R&D focus area for the LWRS program, and has researchers at Idaho National Laboratory working with select utility partners to use human factors and instrumentation and controls R&D to help modernize the plant’s main control room. However, some in the nuclear industry have not been as enthusiastic about using human factors R&D to inform life extension decision making. Part of the reason for this may stem from uncertainty decision-makers have regarding how human factors fits into the value chain for nuclear power plant control room modernization. This paper reviews past work that has attempted to demonstrate the value of human factors, and then describes the value chain concept, how it applies to control room modernization, and then makes a case for how and why human factors is an essential link in the modernization value chain.

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

Human factors in nuclear power plant operation

International Nuclear Information System (INIS)

Sabri, Z.A.; Husseiny, A.A.

1980-01-01

An extensive effort is being devoted to developing a comprehensive human factor program that encompasses establishment of a data base for human error prediction using past operation experience in commercial nuclear power plants. Some of the main results of such an effort are reported including data retrieval and classification systems which have been developed to assist in estimation of operator error rates. Also, statistical methods are developed to relate operator error data to reactor type, age, and specific technical design features. Results reported in this paper are based on an analysis of LER's covering a six-year period for LWR's. Developments presently include a computer data management program, statistical model, and detailed error taxonomy

Human factors review of nuclear power plant control room design. Summary report

International Nuclear Information System (INIS)

Seminara, J.L.; Gonzalez, W.R.; Parsons, S.O.

1976-11-01

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. The human factors aspects of five representative nuclear power plant control rooms were evaluated using such methods as a checklist-guided observation system, structured interviews with operators and trainers, direct observations of operator behavior, task analyses and procedure evaluation, and historical error analyses. The human factors aspects of design practices are illustrated, and many improvements in current practices are suggested. The study recommends that a detailed set of applicable human factors standards be developed to stimulate a uniform and systematic concern for human factors in design considerations

Battelle's human factors program for the US Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Shikiar, R.

1983-10-01

Battelle has been involved in a programmatic effort of technical assistance to the Division of Human Factors Safety of the NRC. This program involves the efforts of over 75 professionals engaged in over 20 projects. These projects span the areas of human factors engineering, procedures, examinations, training, staffing and qualifications, and utility management and organization. All of these bear, one way or another, on the role of operators in nuclear power plants. This programmatic effort can be viewed as part of an integrative approach to system safety

Human factors in nuclear power plants

International Nuclear Information System (INIS)

Bohr, E.; Hennig, J.; Preuss, W.; Thau, G.

1977-01-01

This report describes the results of a study on the functions of operating and maintenance personnel in nuclear power plants. Since an effective power plant design must take into systematic account the possibilities and limitations of the human element, the basic aim of the study was to identify what the human operators are required to do and how they achieve it. Information was acquired by direct observation and by interviews as well as by evaluation of written documents (e.g. incident reports, procedures manuals, work regulations) and of working conditions (e.g. equipment and workplace design). A literature search and evaluation carried out within the scope of this study has been published as a separate document. The main part of the report is devoted to discussions and conclusions on selected areas of potential improvements. The topics include control room design, factors of the physical environment including radiation, problems of maintainability, design of written documents, problems in communicating information, design and control of tasks, placement and training. A separate section deals with problems of recording human errors. (orig.) [de

The human factor in operating nuclear power plants during crisis situations

International Nuclear Information System (INIS)

Schnauder, H.; Smidt, D.

1981-10-01

Human factors in nuclear power plant operation are a main part of safety analyses. A considerable reduction in the influence of human factors has been obtained through ergonomic control room design, automation, clearly formulated operating manuals, and appropriate personnel education and training. These precautions are directed primarily at skill- and rule-based behaviour and are intended for normal operation and design accidents. In addition, one can construct an area of uncommon and very rare events where a partial failure of the safety systems is assumed. This is an area of knowledge-based behaviour. This report describes and assesses the present situation in German nuclear power plants. Recommendations for further research activity are made and, as a main result, for improvements in knowledge-based behaviour. (orig.) [de

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.

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

The need and direction of a human factors research program for the nuclear power industry

International Nuclear Information System (INIS)

Blackman, H.S.; Meyer, O.R.; Nelson, W.R.

1986-01-01

It is axiomatic that the need for a human factors program in the nuclear power industry must be based upon an examination of the process of nuclear energy production and the role that the human plays in this process. It has been pointed out by others that a large number of incidents in technology based industries can be attributed to human error, thereby demonstrating the need to understand the human in interacting with complex processes. But an emphasis upon human ''error'' is a negative approach and can be non-productive, particularly when the ''correct'' human action has not been clearly defined prior to the incident. Some industries have expended great resources in a positive attempt to maximize the performance of the human in critical roles, e.g., the man-in-space program, the commercial airlines industry, deep-sea exploration. Central to this issue of human factors in nuclear power is the question of the role that the human plays in reducing the risk of the total system. If, as in other areas of application, the nuclear industry can make substantial improvements in the performance of humans, one needs to know how much risk is really reduced

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)

A human factors data bank for French nuclear power plants

International Nuclear Information System (INIS)

Villemeur, A.; Mosneron-Dupin, F.; Bouissou, M.; Meslin, T.

1986-01-01

CONFUCIUS is a computerized data bank developed by Electricite de France to study human factors in nuclear power plants. A detailed and homogeneous grouping of described operation and maintenance errors as well as of performance times is possible with CONFUCIUS. It also incorporates a selection of statistical treatment softwares. Readily usable and modifiable, the system can easily evolve. It allows a wide range of applications (safety analysis, event analysis, training, human factors engineering, probabilistic analysis). Data derived from the analysis of significant events reported in power plants and from the analysis of simulator tests are used as inputs into this data bank

IRSN-ANCCLI partnership. Organizational and human factors in nuclear safety - April 2014

International Nuclear Information System (INIS)

Jeffroy, Francois; Garron, Joel; Mercel, Philippe; Compagnat, Gilles; Gaucher, Eric; Gaillard, Pierre; Fanchini, Henri; Jacquemont, Vincent

2013-06-01

The contributions (Power Point presentations) of this seminar first address the history of the taking into account of organizational and human factors until the Fukushima accident (history of their taking into account in nuclear safety expertise in France, history of the development of policy of organizational and human factors by an operator). The next contributions discuss the main issues regarding these factors after Fukushima: report by a work-group, work performed by the the Comite d'Orientation sur les Facteurs Sociaux, Organisationnels et Humains (Committee of orientation on social, organizational and human factors). The third session addresses the implication of stakeholders in expertise on these factors: analysis of organizational and human factors by a local information commission or by a CHSCT (committee of hygiene, safety and working conditions)

Human factor analysis and preventive countermeasures of maintenance in nuclear power plant

International Nuclear Information System (INIS)

Zhang Li; Hu Chao

2008-01-01

Based on the human error analysis theory and the characteristics of maintenance in a nuclear power plant, human factors of maintenance in NPP are divided into three different areas: human, technology, and organization, in which human refers to the individual factors, mainly including psychological quality, physiological characteristic, state of health, knowledge, skill level, and interpersonal relationship. Technology includes the maintenance technology, maintenance strategy, maintenance tool, maintenance interface, maintenance regulation, and work environment. Organization includes task arrangement, information communication, training, personnel external environment, team construction, and leadership. The analysis also reveals that the organization factors, which can indirectly influence personnel performance, are the primary initiators of human error. Based on these, some countermeasures are brought forward in order to reduce human errors. (authors)

Research and development on the human factors technologies for nuclear power plants in Korea

International Nuclear Information System (INIS)

Sim, B.S.; Lee, J.W.; Cheon, S.W.

1996-01-01

This paper introduces our research project on the development of human factors technologies for nuclear power plants in Korea. The project is divided into two sub-projects. The first sub-project is the development of human factors experimental evaluation techniques, which aims to develop the techniques for experimental design, experimental measurement and data collection/analysis, and to construct an integrated test facility (ITF) suitable for the experimental evaluation of man-machine interfaces (MMIs) at an advanced control room. The second is the development of human behavior analysis techniques, which has two research areas: one is the development of a task simulation analyzer and the other is human error case studies for nuclear power plants. (author)

Ergonomics in nuclear and human factors engineering

International Nuclear Information System (INIS)

Muench, E.; Schultheiss, G.F.

1988-01-01

The work situation including man-machine-relationships in nuclear power plants is described. The overview gives only a compact summary of some important ergonomic parameters, i.e. human body dimension, human load, human characteristics and human knowledge. (DG)

Human factors engineering measures taken by nuclear power plant owners/operators for optimisation of the man-machine interface

International Nuclear Information System (INIS)

Eisgruber, H.

1996-01-01

Both operating results and human factors studies show that man is able to meet the requirements in this working environment. Hence the degree of human reliability required by the design basis of nuclear power plants is ensured. This means: - Nuclear technology for electricity generation is justifiable from the human factors point of view. - The chief opponent is not right in saying that man is not able to cope with the risks and challenges brought about by nuclear technology applications. The human factors concept for optimisation or configuration of the man-machine systems represents an additional endeavor on the part of nuclear power plant operators within the framework of their responsibilities. Human factors analyses meet with good response by the personnel, as analysis results and clarification of causes of accident scenarios contribute to relieve the personnel (exoneration) and find ways for remedial action. (orig./DG) [de

The human factor data management system of Daya Bay Nuclear Power Station

International Nuclear Information System (INIS)

Zhang Li; Zhang Ning; Guo Jianbing; Huang Weigang; Zhu Minhong; Wang Jin

1999-12-01

The collection, analysis and quantification of human factor data are very important parts of human reliability analysis and probabilistic risk assessment. Therefore various human databases have been created. But a human data management system with the functions of data collection, classification, analysis, computation and forecast is scarcely seen at home and abroad. So the authors have developed the human data management system of Daya Bay Nuclear Power Station. The system includes three modules and four databases. The authors firstly set forth some basic problems on the human factor data, which are concerned during the development of the system. Then the structure and function of the system are described. In view of the important role of human factor databases in the system, the authors also discuss the structure problems of the data in the databases in detail

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

International Nuclear Information System (INIS)

2001-01-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.

Energy Technology Data Exchange (ETDEWEB)

OHara,J.; Higgins, J.; Brown, W.; Fink, R.

2008-02-14

This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant

Human Factors Engineering Review Model for advanced nuclear power reactors

International Nuclear Information System (INIS)

O'Hara, J.; Higgins, J.; Goodman, C.; Galletti, G.: Eckenrode, R.

1993-01-01

One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

Human factors information system

International Nuclear Information System (INIS)

Goodman, P.C.; DiPalo, C.A.

1991-01-01

Nuclear power plant safety is dependent upon human performance related to plant operations. To provide improvements in human performance, data collection and assessment play key roles. This paper reports on the Human factors Information System (HFIS) which is designed to meet the needs of the human factors specialists of the United States Nuclear Regulatory Commission. These specialists identify personnel errors and provide guidance designed to prevent such errors. HFIS is a simple and modular system designed for use on a personal computer. It is designed to contain four separate modules that provide information indicative of program or function effectiveness as well as safety-related human performance based on programmatic and performance data. These modules include the Human Factors Status module; the Regulatory Programs module; the Licensee Event Report module; and the Operator Requalification Performance module. Information form these modules can either be used separately or can be combined due to the integrated nature of the system. HFIS has the capability, therefore, to provide insights into those areas of human factors that can reduce the probability of events caused by personnel error at nuclear power plants and promote the health and safety of the public. This information system concept can be applied to other industries as well as the nuclear industry

Development of a Pilot Program for Human Factors Management in Operating Nuclear Power plants

International Nuclear Information System (INIS)

Lee, Jung-Woon; Lee, Yong-Hee; Jang, Tong-Il; Kim, Dae-Ho

2007-01-01

The human factors of operating NPPs have been reviewed as a part of Periodic Safety Reviews (PSRs). This human factors PSR covers a wide range of human factors including control room man-machine interfaces (MMIs), procedures, working conditions, qualification, training, information requirements and workload. Korea Atomic Energy Research Institute (KAERI) has performed human factors PSRs from the first PSR for Kori 1. It was determined in 2005 that for a Continuous Operation of the Korean NPPs an enhanced PSR should be performed and issues raised from the PSRs should be resolved. From the results of the PSR for Kori 1, several safety enhancement issues related to human factors were raised. KAERI is working on a resolution of some of the human factors issues for the Korea Hydro and Nuclear Power Co. (KHNP). As a part of the resolution, we are developing a human factors management program (HFMP) for Kori 1. This paper introduces the status of our development of HFMP

Basic research on human reliability in nuclear power plants

International Nuclear Information System (INIS)

Zhang Li; Deng Zhiliang

1996-10-01

Human reliability in nuclear power plants is one of key factors in nuclear safety and economic operation. According to cognitive science, behaviour theory and ergonomic and on the bases of human cognitive behaviour characteristics, performance shaping factors, human error mechanisms and organization management, the project systematically studied the human reliability in nuclear power plant systems, established the basic theory and methods for analyzing human factor accidents and suggested feasible approaches and countermeasures for precaution against human factor accidents and improving human reliability. The achievement has been applied in operation departments, management departments and scientific research institutions of nuclear power, and has produced guiding significance and practical value to design, operation and management in nuclear power plants. (11 refs.)

Human factors in maintenance: Development and research in Swedish nuclear power plants

International Nuclear Information System (INIS)

Salo, I.; Svensson, Ola

2001-11-01

The present report investigated previously completed, ongoing, and planned research and development projects focusing human factors and maintenance work carried out at Swedish nuclear power plants and SKI. In addition, needs for future research and development works were also investigated. Participants from all nuclear power plants and SKI were included in the study. Participants responded to a set of questions in an interview. The interviews also generated a list of future research and development projects

Human factors in maintenance: development and research in Swedish nuclear power plants

International Nuclear Information System (INIS)

Salo, I.; Svenson, O.

2001-11-01

The report investigated previously completed, ongoing, and planned research and development projects focusing human factors and maintenance work carried out at Swedish nuclear power plants and SKI. In addition, needs for future research and development works were also investigated. Participants from all nuclear power plants and SKI were included in the study. Participants responded to a set of questions in an interview. The interviews also generated a list of future research and development projects. (au)

Human factors in maintenance: Development and research in Swedish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Salo, I. [Lund Univ. (Sweden). Dept. of Psychology; Svensson, Ola [Stockholm Univ. (Sweden). Dept. of Psychology

2001-11-01

The present report investigated previously completed, ongoing, and planned research and development projects focusing human factors and maintenance work carried out at Swedish nuclear power plants and SKI. In addition, needs for future research and development works were also investigated. Participants from all nuclear power plants and SKI were included in the study. Participants responded to a set of questions in an interview. The interviews also generated a list of future research and development projects.

Human and social factors in the transportation of nuclear wastes

International Nuclear Information System (INIS)

Freudenburg, W.R.

1991-01-01

The main body of this report is a broad-based examination of human and social factors in the transportation of nuclear wastes. It deals with pair interested problems that, while familiar to the social science community, appear to have received little attention from the risk assessment community to data: The human and social attenuation of risk estimates, and the organizational amplification of risks. Second, given the special opportunities for learning that are presented by the recent Alaska oil spill, in particular, the Appendix to this report examines the issue of organizational foresight in the context of the Exxon oil spill

Potential human factors research relating to modern technology in nuclear power plants

International Nuclear Information System (INIS)

Ketchel, J.; Fink, R.; Hanes, L.; Williges, R.; Williges, B.

1994-01-01

This paper discusses proposed human factors research to address advanced human-machine interface technology in nuclear power plants. It relates to a current EPRI project to identify a prioritized list of specific research issues that could be assessed to improve control room and other user interface areas. The project seeks to bridge the gap between the functional requirements of advanced design initiatives and the human factors research needed to support them. It seeks to identify potential benefits to be expected, as well as potential problems that might be introduced by advanced technology. It provides an organized approach to identifying human factors research needs, information already available, and measures of performance and effectiveness that might be used to assess the value of potential improvements. Those parts of the proposed plan that are subsequently approved by EPRI management and by the utility advisory committee will provide a basis for recommending research priorities

A system engineer's Perspective on Human Errors For a more Effective Management of Human Factors in Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Yong-Hee; Jang, Tong-Il; Lee, Soo-Kil

2007-01-01

The management of human factors in nuclear power plants (NPPs) has become one of the burden factors during their operating period after the design and construction period. Almost every study on the major accidents emphasizes the prominent importance of the human errors. Regardless of the regulatory requirements such as Periodic Safety Review, the management of human factors would be a main issue to reduce the human errors and to enhance the performance of plants. However, it is not easy to find out a more effective perspective on human errors to establish the engineering implementation plan for preventing them. This paper describes a system engineer's perspectives on human errors and discusses its application to the recent study on the human error events in Korean NPPs

Human factors considerations for expert systems in the nuclear industry

International Nuclear Information System (INIS)

Nelson, W.R.

1988-01-01

This paper discusses the general human factors issues relative to the development and implementation of expert systems for the nuclear industry. It summarizes the relevant research that addresses these issues, and identifies those areas that need the most effort for success. Since much of the prominent work for the application of expert systems has focused on computerized aids for decision making in emergencies, this paper draws from this area for its examples. This area tends to highlight the issues because of the safety-critical nature of the application. The same issues, however, are relevant to other applications of expert systems in the nuclear industry as well, even though the consequences of failure may not be as dramatic

Human factor as nuclear safety element

International Nuclear Information System (INIS)

Valeca, S.C.; Preda, M.; Valeca, M.; Ana, E. M.; Popescu, D.

2008-01-01

National nuclear power system is based on western technology, it covers almost 20% from national need and could be briefly described by: - Safety and economic performances of Cernavoda NPP Unit 1; - Reduced influence on environment, population and workers; - Excellent ranking (place 4) among CANDU units from all over the world. Also, the national nuclear power system plays a major role in Romanian power policy accomplishment: - Energy safety and independence assurance; - Decrease of production of greenhouse effect gases; - Preserve the stability and adequacy of energy cost. 'Nuclear Safety' concept covers all the activities resulting from nuclear fuel cycle. By taking into account the international experience, the related activities are estimated to last around 70 years in Romania: - 10 years for site description and selection, design, manufacturing and commissioning activities; - 40 years for Nuclear Power Plant operation, maintenance and modernization activities; - 20 years for preservation and decommissioning activities. The above mentioned activities requires human resources, qualified and specialized in the following areas: - research and development; - equipment design, manufacturing and operation; - components construction and assembly, operation and maintenance. (authors)

Research on cognitive reliability model for main control room considering human factors in nuclear power plants

International Nuclear Information System (INIS)

Jiang Jianjun; Zhang Li; Wang Yiqun; Zhang Kun; Peng Yuyuan; Zhou Cheng

2012-01-01

Facing the shortcomings of the traditional cognitive factors and cognitive model, this paper presents a Bayesian networks cognitive reliability model by taking the main control room as a reference background and human factors as the key points. The model mainly analyzes the cognitive reliability affected by the human factors, and for the cognitive node and influence factors corresponding to cognitive node, a series of methods and function formulas to compute the node cognitive reliability is proposed. The model and corresponding methods can be applied to the evaluation of cognitive process for the nuclear power plant operators and have a certain significance for the prevention of safety accidents in nuclear power plants. (authors)

Lessons Learned from Human Factor Technical Support for Nuclear Power Plants

International Nuclear Information System (INIS)

Jung, Yeon Sub; Song, Tae Young

2011-01-01

NETEC is on the frontier to support Korean nuclear power plants. Requests of service are distributed through web based system. Human factor requests are occasionally posted. This paper analyzes interesting human factors requests/responses serviced, and summarizes the lesson learned. Subjects of the service include man machine interface, equipment label, procedure writing, procedure adherence, BISI, hand switch and alarm tile. Specifically the man machine interface is related to control command generated by acknowledge button, arrangement of switches. Procedure writing is about how to write contingency actions with proper numbering scheme. BISI is analyzed in view of automation level. Alarm tile is about how to handle the common alarm tile originated from local alarm boards. These topics seem to be legacies of past technology. Even though there are still human engineering discrepancies, these have been less evaluated because the topics need knowledge of other field domains

CSNI technical opinion papers no.10. The role of human and organisational factors in nuclear power plant modifications

International Nuclear Information System (INIS)

2009-01-01

Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; feedback from operating experience; and opportunities for improved plant safety, reliability or capability. However, experience has also shown that weaknesses in the design and/or implementation of modifications can present significant challenges to plant safety. They can also have a considerable impact on the commercial performance of the plant. It is therefore important that the plant modification process reflect a recognition of the potential impact of human errors and that it incorporate suitable measures to minimise the potential for such errors. In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Human and Organisational Factors organised an international workshop in 2003 to discuss the role of human and organisational performance in the nuclear plant modification process. This technical opinion paper represents the consensus of specialists in human and organisational factors (HOF) in the NEA member countries on commendable practices and approaches to dealing with nuclear plant modifications. It considers factors that should be taken into account when developing a modification process and identifies some lessons learnt from application of the process. The paper should be of particular interest of nuclear safety regulators and nuclear power plant operators. (author)

Human Resource Managements as a part of the Human Factors Management Program(HFMP) for Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, DaeHo; Lee, YongHee; Lee, JungWoon; Kim, Younggab

2007-01-01

Programs for the effective implementation and management of human factor issues in nuclear power plants (NPPs) should contain technical criteria, an establishment of a job process, and activities for job improvements and be a system through which human factors can be managed in an integrated way. Human factors to be managed should include those related to an operation of plants as well as those related to a plant design as mentioned in NUREG-0800(2004), NUREG- 0711(2004), and NUREG-0700(2002). Human factor items to be managed for an operation of plants are listed in the PSR (Periodic Safety Review) items defined in the Enforcement of Regulation of the Atomic Energy Act. They are procedures, a work management system including a shift work management, a qualification management of plant personnel, training, a work amount assessment, a MMI (Man Machine Interface), and the use of experience. Among these factors, factors related to a human resource management include work management systems and the status of a work management including shift work, a qualification management ensuring qualified workers on duty at all times, and the systems for and the status of training and education. This paper addresses the scope of a human resource management, guidelines and procedures to be developed for a human resource management, and considerations critical in the development of guidelines and procedures

A formal design verification and validation on the human factors of a computerized information system in nuclear power plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Park, Jae Chang; Cheon, Se Woo; Jung, Kwang Tae; Baek, Seung Min; Han, Seung; Park, Hee Suk; Son, Ki Chang; Kim, Jung Man; Jung Yung Woo

1999-11-01

This report describe a technical transfer under the title of ''A formal design verification and validation on the human factors of a computerized information system in nuclear power plants''. Human factors requirements for the information system designs are extracted from various regulatory and industrial standards and guidelines, and interpreted into a more specific procedures and checklists for verifying the satisfaction of those requirements. A formalized implementation plan is established for human factors verification and validation of a computerized information system in nuclear power plants. Additionally, a Computer support system, named as DIMS-web (design Issue Management System), is developed based upon web internet environment so as to enhance the implementation of the human factors activities. DIMS-Web has three maine functions: supporting requirements review, tracking design issues, and management if issues screening evaluation. DIMS-Web shows its benefits in practice through a trial application to the design review of CFMS for YGN nuclear unit 5 and 6. (author)

A formal design verification and validation on the human factors of a computerized information system in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Park, Jae Chang; Cheon, Se Woo; Jung, Kwang Tae; Baek, Seung Min; Han, Seung; Park, Hee Suk; Son, Ki Chang; Kim, Jung Man; Jung Yung Woo

1999-11-01

This report describe a technical transfer under the title of ''A formal design verification and validation on the human factors of a computerized information system in nuclear power plants''. Human factors requirements for the information system designs are extracted from various regulatory and industrial standards and guidelines, and interpreted into a more specific procedures and checklists for verifying the satisfaction of those requirements. A formalized implementation plan is established for human factors verification and validation of a computerized information system in nuclear power plants. Additionally, a Computer support system, named as DIMS-web (design Issue Management System), is developed based upon web internet environment so as to enhance the implementation of the human factors activities. DIMS-Web has three maine functions: supporting requirements review, tracking design issues, and management if issues screening evaluation. DIMS-Web shows its benefits in practice through a trial application to the design review of CFMS for YGN nuclear unit 5 and 6. (author)

A development of the Human Factors Assessment Guide for the Study of Erroneous Human Behaviors in Nuclear Power Plants

International Nuclear Information System (INIS)

Oh, Yeon Ju; Lee, Yong Hee; Jang, Tong Il; Kim, Sa Kil

2014-01-01

The aim of this paper is to describe a human factors assessment guide for the study of the erroneous characteristic of operators in nuclear power plants (NPPs). We think there are still remaining the human factors issues such as an uneasy emotion, fatigue and stress, varying mental workload situation by digital environment, and various new type of unsafe response to digital interface for better decisions, although introducing an advanced main control room. These human factors issues may not be resolved through the current human reliability assessment which evaluates the total probability of a human error occurring throughout the completion of a specific task. This paper provides an assessment guide for the human factors issues a set of experimental methodology, and presents an assessment case of measurement and analysis especially from neuro physiology approach. It would be the most objective psycho-physiological research technique on human performance for a qualitative analysis considering the safety aspects. This paper can be trial to experimental assessment of erroneous behaviors and their influencing factors, and it can be used as an index for recognition and a method to apply human factors engineering V and V, which is required as a mandatory element of human factor engineering program plan for a NPP design

A development of the Human Factors Assessment Guide for the Study of Erroneous Human Behaviors in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Oh, Yeon Ju; Lee, Yong Hee; Jang, Tong Il; Kim, Sa Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-08-15

The aim of this paper is to describe a human factors assessment guide for the study of the erroneous characteristic of operators in nuclear power plants (NPPs). We think there are still remaining the human factors issues such as an uneasy emotion, fatigue and stress, varying mental workload situation by digital environment, and various new type of unsafe response to digital interface for better decisions, although introducing an advanced main control room. These human factors issues may not be resolved through the current human reliability assessment which evaluates the total probability of a human error occurring throughout the completion of a specific task. This paper provides an assessment guide for the human factors issues a set of experimental methodology, and presents an assessment case of measurement and analysis especially from neuro physiology approach. It would be the most objective psycho-physiological research technique on human performance for a qualitative analysis considering the safety aspects. This paper can be trial to experimental assessment of erroneous behaviors and their influencing factors, and it can be used as an index for recognition and a method to apply human factors engineering V and V, which is required as a mandatory element of human factor engineering program plan for a NPP design.

Human factors analysis and design methods for nuclear waste retrieval systems. Human factors design methodology and integration plan

Energy Technology Data Exchange (ETDEWEB)

Casey, S.M.

1980-06-01

The purpose of this document is to provide an overview of the recommended activities and methods to be employed by a team of human factors engineers during the development of a nuclear waste retrieval system. This system, as it is presently conceptualized, is intended to be used for the removal of storage canisters (each canister containing a spent fuel rod assembly) located in an underground salt bed depository. This document, and the others in this series, have been developed for the purpose of implementing human factors engineering principles during the design and construction of the retrieval system facilities and equipment. The methodology presented has been structured around a basic systems development effort involving preliminary development, equipment development, personnel subsystem development, and operational test and evaluation. Within each of these phases, the recommended activities of the human engineering team have been stated, along with descriptions of the human factors engineering design techniques applicable to the specific design issues. Explicit examples of how the techniques might be used in the analysis of human tasks and equipment required in the removal of spent fuel canisters have been provided. Only those techniques having possible relevance to the design of the waste retrieval system have been reviewed. This document is intended to provide the framework for integrating human engineering with the rest of the system development effort. The activities and methodologies reviewed in this document have been discussed in the general order in which they will occur, although the time frame (the total duration of the development program in years and months) in which they should be performed has not been discussed.

Human factors analysis and design methods for nuclear waste retrieval systems. Human factors design methodology and integration plan

International Nuclear Information System (INIS)

Casey, S.M.

1980-06-01

The purpose of this document is to provide an overview of the recommended activities and methods to be employed by a team of human factors engineers during the development of a nuclear waste retrieval system. This system, as it is presently conceptualized, is intended to be used for the removal of storage canisters (each canister containing a spent fuel rod assembly) located in an underground salt bed depository. This document, and the others in this series, have been developed for the purpose of implementing human factors engineering principles during the design and construction of the retrieval system facilities and equipment. The methodology presented has been structured around a basic systems development effort involving preliminary development, equipment development, personnel subsystem development, and operational test and evaluation. Within each of these phases, the recommended activities of the human engineering team have been stated, along with descriptions of the human factors engineering design techniques applicable to the specific design issues. Explicit examples of how the techniques might be used in the analysis of human tasks and equipment required in the removal of spent fuel canisters have been provided. Only those techniques having possible relevance to the design of the waste retrieval system have been reviewed. This document is intended to provide the framework for integrating human engineering with the rest of the system development effort. The activities and methodologies reviewed in this document have been discussed in the general order in which they will occur, although the time frame (the total duration of the development program in years and months) in which they should be performed has not been discussed

Measurement and evaluation of human factor training in nuclear power plants

International Nuclear Information System (INIS)

Hamasaki, Kenichi

2006-01-01

The purpose of this study is to measure and evaluate the effectiveness of human factor training aimed at awareness and behavioral changes, conducted by electric power company for the nuclear power plant staff. As the first step, the researcher investigated recent trends in training measurement and evaluation methods in the United States. It was found that many instances of training measurement/evaluation had been reported, and that the ROI model was the mainstream method for such measurement and evaluation. However, there had been no instances reported in which the effectiveness of human factor training for plant staff had been measured. The researcher therefore developed a new questionnaire-type of effectiveness measurement/evaluation method, based on the framework of the ROI model. Two-years of research was then conducted, in which the effectiveness of a human factor training program was measured using the newly developed method. This research revealed that participants' overall satisfaction and knowledge/skill acquisition levels were high. The percentage of participants who demonstrated awareness/behavioral change after returning to the workplace increased from 50% at first measurement to 81% at second measurement. It can therefore be concluded that the effectiveness of the second training is greater than that of the first training. Use of the new effectiveness measurement/evaluation method will enable quantification of human factor training effectiveness and help improve training quality. (author)

Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

International Nuclear Information System (INIS)

Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M.

2007-01-01

The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

Energy Technology Data Exchange (ETDEWEB)

Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: grecco@ien.gov.br; luquetti@ien.gov.br; mol@ien.gov.br; paulov@ien.gov.br; tonico@ien.gov.br; fferreira@ien.gov.br; dutra@ien.gov.br

2007-07-01

The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

ACSNI study group on human factors

International Nuclear Information System (INIS)

1993-01-01

Organisational failures are now recognised as being as important as mechanical failures or individual human errors in causing major accidents such as the capsize of the Herald of Free Enterprise or the Pipa Alpha disaster. The Human Factors Study Group of the Advisory Committee on the Safety of Nuclear Installations was set up to look at the part played by human factors in nuclear risk and its reduction. The third report of the Study Group considers the role played by organisational factors and management in promoting nuclear safety. Actions to review and promote a safety culture are suggested. Three main conclusions are drawn and several recommendations made. (UK)

A Study on Human Factors in Maintenance of a Nuclear Power Plant (NPP)

International Nuclear Information System (INIS)

Park, Young Ho; Seong, Poong Hyun

2006-01-01

In human factors research, more attention has been devoted to the operation of a nuclear power plant (NPP) than to their maintenance. However, more NPP incidents are caused by inadequate maintenance rather than by faulty operation. There is a trend in NPP toward introducing digital technology into safety and non-safety systems. This lead to changes of maintenance, and support systems such as diagnosis system, augmentation system and handy terminal will be developed. In this context, it is important to identify tasks of human related to each phase of maintenance and their relation in order to apply those to maintenance. However, there are few researches of human factors in maintenance. This paper studies on framework of cognitive task analysis for developing maintenance support systems

Analysis of human factor aspects in connection with available incident reports obligatorily reported by German nuclear power plants

International Nuclear Information System (INIS)

Wilpert, B.; Freitag, M.; Miller, R.

1993-01-01

Goal of the present study is the analysis of human factor aspects in connection with available incident reports obligatorily reported by German nuclear power plants. Based on psychological theories and empirical studies this study develops a classification scheme which permits the identification of foci of erroneous human actions. This classification scheme is applied to a selection of human factor relevant incidents by calculating frequencies of the occurrence of human error categories. The results allow insights into human factor related problem areas. (orig.) [de

Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

International Nuclear Information System (INIS)

Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos

2009-01-01

Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: vasconv@cdtn.br, e-mail: silvaem@cdtn.br, e-mail: aclc@cdtn.br, e-mail: reissc@cdtn.br

2009-07-01

Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

Human Factors Engineering Incorporated into the Carolina Power and Light company's nuclear power plant control panel modifications

International Nuclear Information System (INIS)

Beith, D.M.; Shoemaker, E.M.; Horn, K.; Boush, D.

1988-01-01

Maintaining human factors conventions/practices that were established during the Detailed Control Design Review (DCRDR), is difficult if Human Factors Engineering (HFE) is not incorporated into the plant modification process. This paper presents the approach used at Carolina Power and Light's nuclear power plants that has successfully incorporated human factors engineering into their plant modification process. An HFE Design Guide or HFE Specification was developed which is used by the design engineers or plant engineering support groups in the preparation of plant modifications

Human factors evaluation of man-machine interface for periodic safety review of nuclear power plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang; Hwang, In Koo; Lee, Hyun Cheol; Jang, Tong Il; Ku, Jin Young; Kim, Soo Jin

2004-12-01

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Nuclear Power Plants(NPPs). As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

The contribution of nuclear training staff to human factors work in the CEGB and Nuclear Electric PLC

International Nuclear Information System (INIS)

Madden, V.J.

1990-01-01

The staff and simulators of utility's nuclear training function are being utilized in support of a wide range of human factor related activities. In addition to work on man machines interface review, operating procedures, operator support system and VDU format design and validation for the Magnox and AGR series of nuclear power plants, support is also being provided to the PWR Project Team through staff who have undergone extensive and comprehensive overseas PWR training programs. This paper discusses how recent initiatives in connection with a survey on operator stress and the possible use of psychometric testing in support of the selection of reactor desk engineers are also being supported

Human factor reliability program

International Nuclear Information System (INIS)

Knoblochova, L.

2017-01-01

The human factor's reliability program was at Slovenske elektrarne, a.s. (SE) nuclear power plants. introduced as one of the components Initiatives of Excellent Performance in 2011. The initiative's goal was to increase the reliability of both people and facilities, in response to 3 major areas of improvement - Need for improvement of the results, Troubleshooting support, Supporting the achievement of the company's goals. The human agent's reliability program is in practice included: - Tools to prevent human error; - Managerial observation and coaching; - Human factor analysis; -Quick information about the event with a human agent; -Human reliability timeline and performance indicators; - Basic, periodic and extraordinary training in human factor reliability(authors)

Potential human factors deficiencies in the design of local control stations and operator interfaces in nuclear power plants

International Nuclear Information System (INIS)

Hartley, C.S.; Levy, I.S.; Fecht, B.A.

1984-04-01

The Pacific Northwest Laboratory has completed a project to identify human factors deficiencies in safety-significant control stations outside the control room of a nuclear power plant and to determine whether NUREG-0700, Guidelines for Control Room Design Reviews, would be sufficient for reviewing those local control stations (LCSs). The project accomplished this task by first, reviewing existing data pertaining to human factors deficiencies in LCSs involved in significant safety actions; second, surveying LCSs environments and design features at several operating nuclear power plants; and third, assessing the results of that survey relative to the contents of NUREG-0700

Proceedings of the international topical meeting on advances in human factors in nuclear power systems

International Nuclear Information System (INIS)

Anon.

1986-01-01

This book presents the papers given at a conference on the human factors engineering of nuclear power plants. Topics considered at the conference included human modeling, artificial intelligence, expert systems, robotics and teleoperations, organizational issues, innovative applications, testing and evaluation, training systems technology, a modeling framework for crew decisions during reactor accident sequences, intelligent operator support systems, control algorithms for robot navigation, and personnel management

The Countermeasures against the Human Errors in Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Kwon, Ki Chun; Lee, Jung Woon; Lee, Hyun; Jang, Tong Il

2009-10-01

Due to human error, the failure of nuclear power facilities essential for the prevention of accidents and related research in ergonomics and human factors, including the long term, comprehensive measures are considered technology is urgently required. Past nuclear facilities for the hardware in terms of continuing interest over subsequent definite improvement even have brought, now a nuclear facility to engage in people-related human factors for attention by nuclear facilities, ensuring the safety of its economic and industrial aspects. The point of the improvement is urgently required. The purpose of this research, including nuclear power plants in various nuclear facilities to minimize the possibility of human error by ensuring the safety for human engineering aspects will be implemented in the medium and long term preventive measures is to establish comprehensive

The Countermeasures against the Human Errors in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Kwon, Ki Chun; Lee, Jung Woon; Lee, Hyun; Jang, Tong Il

2009-10-15

Due to human error, the failure of nuclear power facilities essential for the prevention of accidents and related research in ergonomics and human factors, including the long term, comprehensive measures are considered technology is urgently required. Past nuclear facilities for the hardware in terms of continuing interest over subsequent definite improvement even have brought, now a nuclear facility to engage in people-related human factors for attention by nuclear facilities, ensuring the safety of its economic and industrial aspects. The point of the improvement is urgently required. The purpose of this research, including nuclear power plants in various nuclear facilities to minimize the possibility of human error by ensuring the safety for human engineering aspects will be implemented in the medium and long term preventive measures is to establish comprehensive.

Human factors analysis and design methods for nuclear waste retrieval systems. Volume II. A compendium of human factors design data

International Nuclear Information System (INIS)

Casey, S.M.

1980-04-01

This document is a compilation of human factors engineering design recommendations and data, selected and organized to assist in the design of a nuclear waste retrieval system. Design guidelines from a variety of sources have been evaluated, edited, and expanded for inclusion in this document, and, where appropriate, portions of text from selected sources have been included in their entirety. A number of human factors engineering guidelines for equipment designers have been written over the past three decades, each tailored to the needs of the specific system being designed. In the case of this particular document, a review of the preliminary human operator functions involved in each phase of the retrieval process was performed, resulting in the identification of areas of design emphasis upon which this document should be based. Documents containing information and design data on each of these areas were acquired, and data and design guidelines related to the previously identified areas of emphasis were extracted and reorganized. For each system function, actions were first assigned to operator and/or machine, and the operator functions were then described. Separate lists of operator functions were developed for each of the areas of retrieval activities - survey and mapping, remining, floor flange emplacement, plug and canister overcoring, plug and canister removal and transport, and CWSRS activity. These functions and the associated man-machine interface were grouped into categories based on task similarity, and the principal topics of human factors design emphasis were extracted. These topic areas are reflected in the contents of the 12 sections of this document

Human factors estimation methods using physiological informations

International Nuclear Information System (INIS)

Takano, Ken-ichi; Yoshino, Kenji; Nakasa, Hiroyasu

1984-01-01

To enhance the operational safety in the nuclear power plant, it is necessary to decrease abnormal phenomena due to human errors. Especially, it is essential to basically understand human behaviors under the work environment for plant maintenance workers, inspectors, and operators. On the above stand point, this paper presents the results of literature survey on the present status of human factors engineering technology applicable to the nuclear power plant and also discussed the following items: (1) Application fields where the ergonomical evaluation is needed for workers safety. (2) Basic methodology for investigating the human performance. (3) Features of the physiological information analysis among various types of ergonomical techniques. (4) Necessary conditions for the application of in-situ physiological measurement to the nuclear power plant. (5) Availability of the physiological information analysis. (6) Effectiveness of the human factors engineering methodology, especially physiological information analysis in the case of application to the nuclear power plant. The above discussions lead to the demonstration of high applicability of the physiological information analysis to nuclear power plant, in order to improve the work performance. (author)

Interesting and useful applications and outcomes of the methods of assessment of the human factor and conditions of operators' work at Czech operational nuclear power plants

International Nuclear Information System (INIS)

Kubicek, Jan; Holy, Jaroslav

2009-01-01

The article gives practical examples of qualitative analysis of human factor issues and describes quantitative human reliability analysis as an approach to improvement of the Czech nuclear power plants safety level. The introductory part includes a list of selected human factor-related projects implemented (mainly for the Dukovany nuclear power plant) by human factor specialists at the Nuclear Research Institute during the last decade. Three selected examples of analysis are described in detail: systematic qualitative human factor analysis carried out within a Periodic Safety Review; predictive analysis of the consequences of a potential fusion of the existing local control rooms into larger units controlling the entire NPP operation; and the development of a combination of a new hybrid tool for semi-automatic human reliability analysis and a human factor-related knowledge database. In addition to a comprehensive description of the topics and results of analyses, some general conclusions regarding the human factor and human reliability analysis are formulated going far beyond the scope of the applications presented. (orig.)

Review of human factors R and D in the nuclear power industry

International Nuclear Information System (INIS)

Parris, H.L.

1986-01-01

The history of human factors (HF) R and D in the nuclear power industry can clearly be divided into two phases: pre- and post-Three Mile Island (TMI). Pre-TMI, most people in the industry were unfamiliar with the discipline and its contributions to military and space system designs, and the number of HF professionals involved with nuclear power could essentially be counted on the fingers of two hands. Consequently, there was little research into the improvement of plant man/machine interfaces. The picture changed dramatically in the aftermath of TMI as investigation after investigation pointed to deficiencies in the operator/control room interface, training, procedures, communications, and organizational effectiveness. This paper first outlines pre-TMI events, then examines the post-TMI scenario, and concludes with summary observations and suggestions for future efforts

Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System

Energy Technology Data Exchange (ETDEWEB)

Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

2012-08-01

The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities

Human factors survey of advanced instrumentation and controls technologies in nuclear plants

International Nuclear Information System (INIS)

Carter, R.J.

1992-01-01

A survey of advanced instrumentation and controls (I ampersand C) technologies and associated human factors issues in the US and Canadian nuclear industries was carried out by a team from Oak Ridge national laboratory to provide background for the development of regulatory policy, criteria, and guides for review of advanced I ampersand C systems as well as human engineering guidelines for evaluating these systems. The survey found those components of the US nuclear industry surveyed to be quite interested in advanced I ampersand C, but very cautious in implementing such systems in nuclear facilities and power plants. The trend in the facilities surveyed is to experiment cautiously when there is an intuitive advantage or short-term payoff. In the control room, the usual practice is direct substitution of digital and microprocessor-based instruments or systems that are functionally identical to the analog instruments or systems being replaced. The most advanced I ampersand C systems were found in the Canadian CANDU plants, where the newest plant has digital system in almost 100% of its control systems and in over 70% of its plant protection system. The hypothesis that properly 'introducing digital systems increases safety' is supported by the Canadian experience. The performance of these digital systems was achieved using an appropriate quality assurance program for the software development. The ability of digital systems to detect impending failures and initiate a fail-safe action, is a significant safety issue that should be of special interest to every US utility as well as to the US Nuclear Regulatory Commission. (orig.)

Overview of EPRI's human factors research program

International Nuclear Information System (INIS)

O'Brien, J.F.; Parris, H.L.

1981-01-01

The human factors engineering program in the Nuclear Power Division, EPRI is dedicated to the resolution of man-machine interface problems specific to the nuclear power industry. Particularly emphasis is placed on the capabilities and limitations of the people who operate and maintain the system, the tasks they must perform, and what they need to accomplish those tasks. Six human factors R and D projects are being conducted at the present time. In addition, technical consultation is being furnished to a study area, operator aids, being funded by another program area outside the human factors program area. All of these activities are summarized

The human factors and job task analysis in nuclear power plant operation

International Nuclear Information System (INIS)

Stefanescu, Petre; Mihailescu, Nicolae; Dragusin, Octavian

1999-01-01

After a long period of time, during the development of the NPP technology, where the plant hardware has been considered to be the main factor for a safe, reliable and economic operation, the industry is now changing to an adequate responsibility of plant hardware and operation. Since the human factors has been not discussed methodically so far, there is still a lack of improved classification systems for human errors as well as a lack of methods for the systematic approach in designing the operator's working system, as for instance by using the job task analysis (J.T.A.). The J.T.A. appears to be an adequate method to study the human factor in the nuclear power plant operation, enabling an easy conversion to operational improvements. While the results of the analysis of human errors tell 'what' is to be improved, the J.T.A. shows 'how' to improve, for increasing the quality of the work and the safety of the operator's working system. The paper analyses the issue of setting the task and displays four criteria used to select aspects in NPP operation which require special consideration as personal training, design of control room, content and layout of the procedure manual, or organizing the operating personnel. The results are given as three tables giving: 1- Evaluation of deficiencies in the Working System; 2- Evaluation of the Deficiencies of Operator's Disposition; 3- Evaluation of the Mental Structure of Operation

Prescribing safety, negotiating expertise. Building of nuclear safety human factors expertise

International Nuclear Information System (INIS)

Rolina, Gregory

2008-01-01

This Ph.D thesis is dedicated to a specific type of expertise, the safety of nuclear installations in the field of human and organisational factors. Empirical work is at the foundation of this thesis: the monitoring of experts 'in action', allowed a detailed reconstruction of three cases they were examining. The analysis, at the core of which lies the definition of what an efficient expertise can be, emphasizes the incompleteness of the knowledge that links together the nuclear facilities' organisational characteristics and their safety. This leads us to identify the expert's three ranges of actions (rhetorical, cognitive, operative). Defined from objectives and constraints likely to influence the expert's behaviour, those three ranges each require specific skills. A conception of expertise based on these ranges seems adaptable to other sectors and allows an enrichment of models of expertise cited in literature. Historical elements from French institutions of nuclear safety are also called upon to take into consideration some of the determinants of the expertise; its efficiency relies on the upholding of a continuous dialogue between the regulators (the experts and the control authority) and the regulated (the operators). This type of historically inherited regulation makes up a specificity of the French system of external control of nuclear risks. (author) [fr

IEEE 845 - a proposed guideline for use of human factors in design and retrofit design of nuclear power plants

International Nuclear Information System (INIS)

Schurman, D.L.

1987-01-01

This paper describes the development and content of the Institute of Electrical and Electronics Engineers (IEEE) Standard 845. This guide was developed by Working Group 7.2 of Subcommittee 7 of the Nuclear Power Engineering Committee of the Power Engineering Society of the IEEE. The guide has been approved by the Nuclear Power Engineering Committee (NPEC) and is now in the standards development and approval process. The guide is the first standards action approved by the NPEC of IEEE and is presented here to obtain wider peer response to its content. The guide provides a systematic framework for selection of human factors techniques and for the use of those techniques. The guide also provides a list of commonly used human factors techniques, along with a commentary about cost, ease of use, and other characteristics of each of the techniques. The guide is written with the project engineer and design engineer in mind. Thus, the guide attempts to provide a basis for the systematic selection of human factors techniques for various purposes and guidance regarding which of these techniques is likely to require the assistance of a human factors expert to apply

Applying human factors to the design of control centre and workstation of a nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Santos, Isaac J.A. Luquetti dos; Carvalho, Paulo V.R.; Goncalves, Gabriel de L., E-mail: luquetti@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Souza, Tamara D.M.F.; Falcao, Mariana A. [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro, RJ (Brazil). Dept. de Desenho Industrial

2013-07-01

Human factors is a body of scientific factors about human characteristics, covering biomedical, psychological and psychosocial considerations, including principles and applications in the personnel selection areas, training, job performance aid tools and human performance evaluation. Control Centre is a combination of control rooms, control suites and local control stations which are functionally related and all on the same site. Digital control room includes an arrangement of systems, equipment such as computers and communication terminals and workstations at which control and monitoring functions are conducted by operators. 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 objective of this paper is to present a specific approach for the conceptual and basic design of the control centre and workstation of a nuclear reactor used to produce radioisotope. The approach is based on human factors standards, guidelines 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 team, an initial sketch 3D of the control centre and workstation are being developed. (author)

Applying human factors to the design of control centre and workstation of a nuclear reactor

International Nuclear Information System (INIS)

Santos, Isaac J.A. Luquetti dos; Carvalho, Paulo V.R.; Goncalves, Gabriel de L.; Souza, Tamara D.M.F.; Falcao, Mariana A.

2013-01-01

Human factors is a body of scientific factors about human characteristics, covering biomedical, psychological and psychosocial considerations, including principles and applications in the personnel selection areas, training, job performance aid tools and human performance evaluation. Control Centre is a combination of control rooms, control suites and local control stations which are functionally related and all on the same site. Digital control room includes an arrangement of systems, equipment such as computers and communication terminals and workstations at which control and monitoring functions are conducted by operators. 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 objective of this paper is to present a specific approach for the conceptual and basic design of the control centre and workstation of a nuclear reactor used to produce radioisotope. The approach is based on human factors standards, guidelines 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 team, an initial sketch 3D of the control centre and workstation are being developed. (author)

A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

Energy Technology Data Exchange (ETDEWEB)

Yang, Chih Wei; Yang, Li Chen [Institute of Nuclear Energy Research, Atomic Energy Council, Longtan (China)

2014-08-15

Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective.

A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

International Nuclear Information System (INIS)

Yang, Chih Wei; Yang, Li Chen

2014-01-01

Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective

Implementation and test of proposals to integrate human factors in reporting and causal analysis in nuclear power plants

International Nuclear Information System (INIS)

Wilpert; Maimer, H.; Miller, R.; Fahlbruch, B.; Leiber, I.; Szameitat, S.; Baggen, R.; Gans, A.; Becker, G.

1998-01-01

The research project 'Implementation and Test of Proposals to integrate Human Factors in Reporting and Causal Analysis in Nuclear Power Plants' ('Implementation and Test', SR 2039/8) is based on two antecedent projects: 'Reporting System' (SR 2039/1) and 'Causal Analysis' (SR 2039/2). The project 'Implementation and Test' conducted various tests and introductory programs in cooperation with different target groups concerning the event analysis methodology 'SOL - Safety through Organizational Learning': Regulators, consultant organizations, union/works councillors and utilities. Thus, SOL was concurrently optimized and [apted for the practice in the German nuclear power industry. SOL was also validated in a German nuclear power plant using a concrete event. Results of the 'Implementation and Test' project demonstrate that SOL is fit to conduct event analyses practicably and economically with appropriate comprehensiveness and depth. SOL facilitates the identification of relevant contributing factors of events. This report concludes with various concrete proposals for the further development of the Program of the Federal Ministry of Environment, Nature Protection and Reactor Safety (BMU) and the Federal Agency of R[iation Protection (BfS) concerning 'The Contribution of Humans to Safety of Nuclear Power Plants'. (orig.) [de

Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

International Nuclear Information System (INIS)

O'Hara, J.M.; Higgins, J.; Fleger, Stephen

2011-01-01

The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

Human Factors Regulatory Research Program Plan, FY 1989--FY 1992

International Nuclear Information System (INIS)

Coffman, F.; Persensky, J.; Ryan, T.; Ramey-Smith, A.; Goodman, C.; Serig, D.; Trager, E; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC; Nuclear Regulatory Commission, Washington, DC

1989-10-01

This report describes the currently ongoing (FY 1989) and planned (FY 1989-1992) Human Factors Regulatory Research Program in the NRC Office of Nuclear Regulatory Research (RES). Examples of the influence of human factors on nuclear safety are presented, and the role of personnel is discussed. Current regulatory issues associated with human factors in the nuclear system and the purpose of the research plan are provided. The report describes the research process applied to the human factors research issues and the program activities: Personnel Performance Measurement, Personnel Subsystem, Human-System Interface. Organization and Management, and Reliability Assessment. The research being conducted within each activity is summarized along with the objectives, background information, and expected regulatory products. Budget and personnel forecasts are provided along with a summary of contractors performing some of the ongoing research. Appendices contain a chronology of human factors research at NRC, a description of the research approach, an update on human factors programs and initiatives in RES and other NRC offices, and the integration among these programs. 46 refs., 5 tabs

Analysis and prevention of human failure in nuclear power plants

International Nuclear Information System (INIS)

Liu Xinshuan

2001-01-01

Based on the performances in Daya Bay Nuclear Power Plant and the common experience from the world nuclear industry, the features and usual kinds of human failures in nuclear power plants are highlighted and the prominent factors on the personal, external and decision problems which might cause the human failures are analyzed. Effective preventive measures have been proposed respectively. Some successful human-failure-prevention practices applied in the Daya Bay Nuclear Power Plant are illustrated specifically

Overview of NRC's human factors regulatory research program

International Nuclear Information System (INIS)

Coffman, F.D. Jr.

1989-01-01

The human factors research program is divided into distinct and interrelated program activities: (1) Personnel Performance measurement, (2) Personnel Subsystem, (3) Human-System Interface, (4) Organization and Management, and (5) a group of Reliability Assessment activities. The purpose of the Personnel Performance Measurement activity is to improve the Agency's understanding of the factors influencing personnel performance and the effects on the safety of nuclear operations and maintenance by developing improvements to methods for collecting and managing personnel performance data. Personnel Subsystem research will broaden the understanding of such factors as staffing, qualifications, and training that influence human performance in the nuclear system and will develop the technical basis for regulatory guidance to reduce any adverse impact of these influences on nuclear safety. Research in the Human-System Interface activity will provide the technical basis for ensuring that the interface between the system and the human user supports safe operations and maintenance. Organization and Management research will result in the development of tools for evaluating organization and management issues within the nuclear industry. And finally, the Reliability Assessment group of activities includes multidisciplinary research that will integrate human and hardware considerations for evaluating reliability and risk in NRC licensing, inspection, and regulatory decisions

Draft revision of human factors guideline HF-010

International Nuclear Information System (INIS)

Lee, Hyun Chul; Lee, Yong Hee; Oh, In Seok; Lee, Jung Woon; Cha, Woo Chang; Lee, Dhong Ha

2003-05-01

The Application of Human Factors to the design of Man-Machine Interfaces System(MMIS) in the nuclear power plant is essential to the safety and productivity of the nuclear power plants, human factors standards and guidelines as well as human factors analysis methods and experiments are weightily used to the design application. A Korean engineering company has developed a human factors engineering guideline, so-call HF-010, and has used it for human factors design, however the revision of HF-010 is necessary owing to lack of the contents related to the advanced MMI(Man-Machine Interfaces). As the results of the reviews of HF-010, it is found out that the revision of Section 9. Computer Displays of HF-010 is urgent, thus the revision was drafted on the basis of integrated human factors design guidelines for VDT, human factors design guidelines for PMAS SPADES display, human factors design guidelines for PMAS alarm display, and human factors design guidelines for electronic displays developed by the surveillance and operation support project of KOICS. The draft revision of HF-010 Section 9 proposed in this report can be utilized for the human factors design of the advanced MMI, and the high practical usability of the draft can be kept up through the continuous revision according to the advancement of digital technology

The human factor in the design and operation of french light water nuclear power plants

International Nuclear Information System (INIS)

Gomolinski, M.

1986-10-01

The accident which occurred at Three Mile Island (TMI 2) on March 28, 1979 is considered rightfully as the outset of the approach taking the human factor explicitly into account in nuclear safety, both in the design of the plants and in their operational use. In this paper, we shall endeavour to explain how this human factor has been taken into account in France. For this purpose, in the first part, we shall define the requirements, i.e. describe the sectors in which improvements were deemed necessary. In the second part, we shall describe the structures set up both at EDF and at the CEA to handle these problems. Lastly, in the third part, we shall describe the principal actions taken or in progress [fr

The human factor in the operation of nuclear powered submarines

International Nuclear Information System (INIS)

Dambier, M.

1982-05-01

The conditions characterizing the operation of nuclear powered submarines are described and the precautionary measures suitable to reduce the incidence of human errors and their consequences are explained

Support of protective work of human error in a nuclear power plant

International Nuclear Information System (INIS)

Yoshizawa, Yuriko

1999-01-01

The nuclear power plant human factor group of the Tokyo Electric Power Co., Ltd. supports various protective work of human error conducted at the nuclear power plant. Its main researching theme are studies on human factor on operation of a nuclear power plant, and on recovery and common basic study on human factor. In addition, on a base of the obtained informations, assistance to protective work of human error conducted at the nuclear power plant as well as development for its actual use was also promoted. Especially, for actions sharing some dangerous informations, various assistances such as a proposal on actual example analytical method to effectively understand a dangerous information not facially but faithfully, construction of a data base to conveniently share such dangerous information, and practice on non-accident business survey for a hint of effective promotion of the protection work, were promoted. Here were introduced on assistance and investigation for effective sharing of the dangerous informations for various actions on protection of human error mainly conducted in nuclear power plant. (G.K.)

Human factors in the operation of nuclear power plants

International Nuclear Information System (INIS)

Swaton, E.; Neboyan, V.; Lederman, L.

1987-01-01

In large and complex interactive systems, human error can contribute substantially to system failures. At nuclear power plants, operational experience demonstrates that human error accounts for a considerable proportion of safety-related incidents. However, experience also shows that human intervention can be very effective if there is a thorough understanding of the situation in the plant. Thus, an efficient interface of man and machine is important not only to prevent human errors but also to assist the operator in coping with unforeseen events. Human reliability can be understood as a qualitative as well as a quantitative term. Qualitatively it can be described as the aim for successful human performance of activities necessary for system reliability and availability. Quantitatively, it refers to data on failure rates or error probabilities that can be used, for example, for probabilistic safety assessments

Human factors questionnaire as a tool for risk assessment

International Nuclear Information System (INIS)

Santos, Isaac J.A.L.; Grecco, Claudio H.S.; Carvalho, Paulo V.R.; Mol, Antonio C.A.; Oliveira, Mauro V.; Augusto, Silas C.

2009-01-01

The human factors engineering (HFE) as a discipline, and as a process, seeks to discover and to apply knowledge about human capabilities and limitations to system and equipment design, ensuring that the system design, human tasks and work environment are compatible with the sensory, perceptual, cognitive and physical attributes of the personnel who operates systems and equipment. Risk significance considers the magnitude of the consequences (loss of life, material damage, environmental degradation) and the frequency of occurrence of a particular adverse event. The questionnaire design was based on the following definitions: the score and the classification of the nuclear safety risk. The principal benefit of applying an approach based on the risk significance in the development of the questionnaire is to ensure the identification and evaluation of the features of the projects, related to human factors, which affect the nuclear safety risk, the human actions and the safety of the nuclear plant systems. The human factors questionnaire developed in this study will provide valuable support for risk assessment, making possible the identification of design problems that can influence the evaluation of the nuclear safety risk. (author)

Identification and Evaluation of Human Factors Issues Associated with Emerging Nuclear Plant Technology

International Nuclear Information System (INIS)

O'Hara, J.M.; Higgins, J.; Brown, William S.

2009-01-01

This study has identified human performance research issues associated with the implementation of new technology in nuclear power plants (NPPs). To identify the research issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were prioritized into four categories based on evaluations provided by 14 independent subject matter experts representing vendors, utilities, research organizations and regulators. Twenty issues were categorized into the top priority category. The study also identifies the priority of each issue and the rationale for those in the top priority category. The top priority issues were then organized into research program areas of: New Concepts of Operation using Multi-agent Teams, Human-system Interface Design, Complexity Issues in Advanced Systems, Operating Experience of New and Modernized Plants, and HFE Methods and Tools. The results can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas to support the safe operation of new NPPs.

Relationship between organizational factors, safety culture and PSA in nuclear power plant operations

International Nuclear Information System (INIS)

Joksimovich, V.; Orvis, D.D.

1997-01-01

There are four nuclear safety imperatives or ''4Ms'': machine (hardware, design, QA/QC), milieux (operating conditions, environment, natural phenomena), man (human reliability) and management (organizational and management influences). Nuclear safety evaluations as well as evolution of its most powerful tool, Probabilistic Safety Assessment (PSA), followed chronologically the 4M constituents. The nuclear industry worldwide, and the nuclear safety regulators in particular, have been preoccupied with the first M almost to the point of obsession with belated and only intuitive interest in the third and fourth M (human dimension). Human factors or economics in the nuclear industry was an afterthought. Human reliability was essentially born in the aftermath of the Three Mile Island (TMI) accident. Impact of organizational factors on nuclear safety is only in the early stages of R and D. This paper describes some of the concepts being pursued by APG to link organizational factors and safety culture to Human Reliability Analysis (HRA) and to integrate such into probabilistic safety assessment (PSA), e.g. [APG, 1993]. (author). 11 refs, 4 figs, 1 tab

HUMAN FACTORS GUIDANCE FOR CONTROL ROOM EVALUATION

International Nuclear Information System (INIS)

OHARA, J.; BROWN, W.; STUBLER, W.; HIGGINS, J.; WACHTEL, J.; PERSENSKY, J.J.

2000-01-01

The Human-System Interface Design Review Guideline (NUREG-0700, Revision 1) was developed by the US Nuclear Regulatory Commission (NRC) to provide human factors guidance as a basis for the review of advanced human-system interface technologies. The guidance consists of three components: design review procedures, human factors engineering guidelines, and a software application to provide design review support called the ''Design Review Guideline.'' Since it was published in June 1996, Rev. 1 to NUREG-0700 has been used successfully by NRC staff, contractors and nuclear industry organizations, as well as by interested organizations outside the nuclear industry. The NRC has committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool in the face of emerging and rapidly changing technology. This paper addresses the current research to update of NUREG-0700 based on the substantial work that has taken place since the publication of Revision 1

Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

International Nuclear Information System (INIS)

Garvin, L.J.

1998-01-01

This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a)

Human reliability analysis of Lingao Nuclear Power Station

International Nuclear Information System (INIS)

Zhang Li; Huang Shudong; Yang Hong; He Aiwu; Huang Xiangrui; Zheng Tao; Su Shengbing; Xi Haiying

2001-01-01

The necessity of human reliability analysis (HRA) of Lingao Nuclear Power Station are analyzed, and the method and operation procedures of HRA is briefed. One of the human factors events (HFE) is analyzed in detail and some questions of HRA are discussed. The authors present the analytical results of 61 HFEs, and make a brief introduction of HRA contribution to Lingao Nuclear Power Station

Analyzing and sense making of human factors in the Malaysian radiation and nuclear emergency planning framework

Science.gov (United States)

Hamid, A. H. A.; Rozan, M. Z. A.; Deris, S.; Ibrahim, R.; Abdullah, W. S. W.; Rahman, A. A.; Yunus, M. N. M.

2016-01-01

The evolution of current Radiation and Nuclear Emergency Planning Framework (RANEPF) simulator emphasizes on the human factors to be analyzed and interpreted according to the stakeholder's tacit and explicit knowledge. These human factor criteria are analyzed and interpreted according to the "sense making theory" and Disaster Emergency Response Management Information System (DERMIS) design premises. These criteria are corroborated by the statistical criteria. In recent findings, there were no differences of distributions among the stakeholders according to gender and organizational expertise. These criteria are incrementally accepted and agreed the research elements indicated in the respective emergency planning frameworks and simulator (i.e. 78.18 to 84.32, p-value <0.05). This paper suggested these human factors criteria in the associated analyses and theoretical perspectives to be further acomodated in the future simulator development. This development is in conjunction with the proposed hypothesis building of the process factors and responses diagram. We proposed that future work which implies the additional functionality of the simulator, as strategized, condensed and concise, comprehensive public disaster preparedness and intervention guidelines, to be a useful and efficient computer simulation.

Human factors survey of advanced instrumentation and controls

International Nuclear Information System (INIS)

Carter, R.J.

1989-01-01

A survey oriented towards identifying the human factors issues in regard to the use of advanced instrumentation and controls (I ampersand C) in the nuclear industry was conducted. A number of United States (US) and Canadian nuclear vendors and utilities were participants in the survey. Human factors items, subsumed under the categories of computer-generated displays (CGD), controls, organizational support, training, and related topics, were discussed. The survey found the industry to be concerned about the human factors issues related to the implementation of advanced I ampersand C. Fifteen potential human factors problems were identified. They include: the need for an advanced I ampersand C guideline equivalent to NUREG-0700; a role change in the control room from operator to supervisor; information overload; adequacy of existing training technology for advanced I ampersand C; and operator acceptance and trust. 11 refs., 1 tab

Human factoring administrative procedures

International Nuclear Information System (INIS)

Grider, D.A.; Sturdivant, M.H.

1991-01-01

In nonnuclear business, administrative procedures bring to mind such mundane topics as filing correspondence and scheduling vacation time. In the nuclear industry, on the other hand, administrative procedures play a vital role in assuring the safe operation of a facility. For some time now, industry focus has been on improving technical procedures. Significant efforts are under way to produce technical procedure requires that a validated technical, regulatory, and administrative basis be developed and that the technical process be established for each procedure. Producing usable technical procedures requires that procedure presentation be engineered to the same human factors principles used in control room design. The vital safety role of administrative procedures requires that they be just as sound, just a rigorously formulated, and documented as technical procedures. Procedure programs at the Tennessee Valley Authority and at Boston Edison's Pilgrim Station demonstrate that human factors engineering techniques can be applied effectively to technical procedures. With a few modifications, those same techniques can be used to produce more effective administrative procedures. Efforts are under way at the US Department of Energy Nuclear Weapons Complex and at some utilities (Boston Edison, for instance) to apply human factors engineering to administrative procedures: The techniques being adapted include the following

Nuclear pore complex protein mediated nuclear localization of dicer protein in human cells.

Directory of Open Access Journals (Sweden)

Yoshinari Ando

Full Text Available Human DICER1 protein cleaves double-stranded RNA into small sizes, a crucial step in production of single-stranded RNAs which are mediating factors of cytoplasmic RNA interference. Here, we clearly demonstrate that human DICER1 protein localizes not only to the cytoplasm but also to the nucleoplasm. We also find that human DICER1 protein associates with the NUP153 protein, one component of the nuclear pore complex. This association is detected predominantly in the cytoplasm but is also clearly distinguishable at the nuclear periphery. Additional characterization of the NUP153-DICER1 association suggests NUP153 plays a crucial role in the nuclear localization of the DICER1 protein.

Studies of safety and critical work situations in nuclear power plants: A human factors perspective

International Nuclear Information System (INIS)

Jacobsson Kecklund, L.

1998-05-01

The purpose of this thesis was to develop and apply different approaches for analyzing safety in critical work situations in real work settings in nuclear power plants, and also to identify safety enhancing measures by using the framework of interaction between human, organizational and technical subsystems. A Cognitive Psychology as well as a Stress Psychology framework was used. All studies were related to the annual outage operational state where the need for coping with many infrequent tasks, often carried out under high time pressure, puts great strain on the staff and organisation of the plant. In three studies the natural variations in the plant state, normal operation and annual outage operation, were used to explore human performance, work-related factors as well as coping and the operators' own resources and the relationship between them. In the annual outage condition high work demands, decreased sleepiness at night shift, more errors and less satisfaction with work performance quality was reported by maintenance as well as by control room operators. A relationship between high work demands and more organizational problems and reports of more frequent human errors and lower satisfactions with work performance quality was also identified in the annual outage condition. Moreover, a relationship between increased sleepiness during night shift, more frequent use of coping strategies and a higher frequency of human errors was reported. In two studies the Event and Barrier Function Model was applied to analyze the safety of barrier function systems inserted into work process sequences to protect the systems from the negative consequences of failures and errors. The model was also used to assess safety in relation to a technical and organizational change. The last study addressed changes in work performance and work-related factors in relation to a technical and organizational change of a safety significant work process involving increased automation and new

Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation.

Science.gov (United States)

Scheblanov, V Y; Sneve, M K; Bobrov, A F

2012-12-01

This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical-Biological Agency of Russia and the Norwegian Radiation Protection Authority.

The human factors specialist in nuclear control centre design

International Nuclear Information System (INIS)

Wilson, R.B.; Beattie, J.D.

The main focus at Ontario Hydro for man-machine interface design is in the design of control centres. Because the control of a nuclear generating unit is highly centralized there is an increasing need for effective information display and control layout. Control panel design innovations such as the use of CRT displays and the extended use of computerized control in the Darlington station have made it possible for Ontario Hydro to continue to have one first operator for each generating unit. The human factors specialist involved in control panel design must deal with people who know much more about the specific systems being controlled, and must become a generalist in all these systems as well. Designers have to use conceptual techniques such as task analysis, systems design, panel mock-ups, anthropometric data, and personal judgement based on experience as they design panels. They must find a balance between becoming locked into existing technology and methods, slavishly following the latest technological trends, and forgetting that real people will be using what they design

Human factors issues in fuel handling

International Nuclear Information System (INIS)

Beattie, J.D.; Iwasa-Madge, K.M.; Tucker, D.A.

1994-01-01

The staff of the Atomic Energy Control Board wish to further their understanding of human factors issues of potential concern associated with fuel handling in CANDU nuclear power stations. This study contributes to that objective by analysing the role of human performance in the overall fuel handling process at Ontario Hydro's Darlington Nuclear Generating Station, and reporting findings in several areas. A number of issues are identified in the areas of design, operating and maintenance practices, and the organizational and management environment

Review of human factors guidelines and methods

International Nuclear Information System (INIS)

Rhodes, W.; Szlapetis, I.; Hay, T.; Weihrer, S.

1995-04-01

The review examines the use of human factors guidelines and methods in high technology applications, with emphasis on application to the nuclear industry. An extensive literature review was carried out identifying over 250 applicable documents, with 30 more documents identified during interviews with experts in human factors. Surveys were sent to 15 experts, of which 11 responded. The survey results indicated guidelines used and why these were favoured. Thirty-three of the most applicable guideline documents were described in detailed annotated bibliographies. A bibliographic list containing over 280 references was prepared. Thirty guideline documents were rated for their completeness, validity, applicability and practicality. The experts survey indicated the use of specific techniques. Ten human factors methods of analysis were described in general summaries, including procedures, applications, and specific techniques. Detailed descriptions of the techniques were prepared and each technique rated for applicability and practicality. Recommendations for further study of areas of importance to human factors in the nuclear field in Canada are given. (author). 8 tabs., 2 figs

Review of human factors guidelines and methods

Energy Technology Data Exchange (ETDEWEB)

Rhodes, W; Szlapetis, I; Hay, T; Weihrer, S [Rhodes and Associates Inc., Toronto, ON (Canada)

1995-04-01

The review examines the use of human factors guidelines and methods in high technology applications, with emphasis on application to the nuclear industry. An extensive literature review was carried out identifying over 250 applicable documents, with 30 more documents identified during interviews with experts in human factors. Surveys were sent to 15 experts, of which 11 responded. The survey results indicated guidelines used and why these were favoured. Thirty-three of the most applicable guideline documents were described in detailed annotated bibliographies. A bibliographic list containing over 280 references was prepared. Thirty guideline documents were rated for their completeness, validity, applicability and practicality. The experts survey indicated the use of specific techniques. Ten human factors methods of analysis were described in general summaries, including procedures, applications, and specific techniques. Detailed descriptions of the techniques were prepared and each technique rated for applicability and practicality. Recommendations for further study of areas of importance to human factors in the nuclear field in Canada are given. (author). 8 tabs., 2 figs.

Analyzing and sense making of human factors in the Malaysian radiation and nuclear emergency planning framework

International Nuclear Information System (INIS)

Hamid, A. H. A.; Rozan, M. Z. A.; Ibrahim, R.; Deris, S.; Abdullah, W. S. W.; Yunus, M. N. M.; Rahman, A. A.

2016-01-01

The evolution of current Radiation and Nuclear Emergency Planning Framework (RANEPF) simulator emphasizes on the human factors to be analyzed and interpreted according to the stakeholder’s tacit and explicit knowledge. These human factor criteria are analyzed and interpreted according to the “sense making theory” and Disaster Emergency Response Management Information System (DERMIS) design premises. These criteria are corroborated by the statistical criteria. In recent findings, there were no differences of distributions among the stakeholders according to gender and organizational expertise. These criteria are incrementally accepted and agreed the research elements indicated in the respective emergency planning frameworks and simulator (i.e. 78.18 to 84.32, p-value <0.05). This paper suggested these human factors criteria in the associated analyses and theoretical perspectives to be further acomodated in the future simulator development. This development is in conjunction with the proposed hypothesis building of the process factors and responses diagram. We proposed that future work which implies the additional functionality of the simulator, as strategized, condensed and concise, comprehensive public disaster preparedness and intervention guidelines, to be a useful and efficient computer simulation

Analyzing and sense making of human factors in the Malaysian radiation and nuclear emergency planning framework

Energy Technology Data Exchange (ETDEWEB)

Hamid, A. H. A., E-mail: amyhamijah@gmail.com, E-mail: amyhamijah@nm.gov.my [Faculty of Computing, Universiti Teknologi Malaysia (UTM), Skudai, 81310 Johor Bahru, Johor (Malaysia); Universiti Malaysia Kelantan (UMK), Pengkalan Chepa, 16100 Kota Bharu, Kelantan (Malaysia); Rozan, M. Z. A., E-mail: drmohdzaidi@gmail.com; Ibrahim, R. [Faculty of Computing, Universiti Teknologi Malaysia (UTM), Skudai, 81310 Johor Bahru, Johor (Malaysia); Deris, S. [Universiti Malaysia Kelantan (UMK), Pengkalan Chepa, 16100 Kota Bharu, Kelantan (Malaysia); Abdullah, W. S. W.; Yunus, M. N. M. [Malaysian Nuclear Agency (NM), Bangi, 43000 Kajang, Selangor (Malaysia); Rahman, A. A. [Faculty of Medicine and Health Sciences, Universiti Putra Malaysia (UPM), 43400 Serdang, Selangor (Malaysia)

2016-01-22

The evolution of current Radiation and Nuclear Emergency Planning Framework (RANEPF) simulator emphasizes on the human factors to be analyzed and interpreted according to the stakeholder’s tacit and explicit knowledge. These human factor criteria are analyzed and interpreted according to the “sense making theory” and Disaster Emergency Response Management Information System (DERMIS) design premises. These criteria are corroborated by the statistical criteria. In recent findings, there were no differences of distributions among the stakeholders according to gender and organizational expertise. These criteria are incrementally accepted and agreed the research elements indicated in the respective emergency planning frameworks and simulator (i.e. 78.18 to 84.32, p-value <0.05). This paper suggested these human factors criteria in the associated analyses and theoretical perspectives to be further acomodated in the future simulator development. This development is in conjunction with the proposed hypothesis building of the process factors and responses diagram. We proposed that future work which implies the additional functionality of the simulator, as strategized, condensed and concise, comprehensive public disaster preparedness and intervention guidelines, to be a useful and efficient computer simulation.

Human Factors and Information Operation for a Nuclear Power Space Vehicle

International Nuclear Information System (INIS)

Trujillo, Anna C.; Brown-Van Hoozer, S. Alenka

2002-01-01

This paper describes human-interactive systems needed for a crew nuclear-enabled space mission. A synthesis of aircraft engine and nuclear power plant displays, biofeedback of sensory input, virtual control, brain mapping for control process and manipulation, and so forth are becoming viable solutions. These aspects must maintain the crew's situation awareness and performance, which entails a delicate function allocation between crew and automation. (authors)

Improved efficacy of soluble human receptor activator of nuclear factor kappa B (RANK) fusion protein by site-directed mutagenesis.

Science.gov (United States)

Son, Young Jun; Han, Jihye; Lee, Jae Yeon; Kim, HaHyung; Chun, Taehoon

2015-06-01

Soluble human receptor activator of nuclear factor kappa B fusion immunoglobulin (hRANK-Ig) has been considered as one of the therapeutic agents to treat osteoporosis or diseases associated with bone destruction by blocking the interaction between RANK and the receptor activator of nuclear factor kappa B ligand (RANKL). However, no scientific record showing critical amino acid residues within the structural interface between the human RANKL and RANK complex is yet available. In this study, we produced several mutants of hRANK-Ig by replacement of amino acid residue(s) and tested whether the mutants had increased binding affinity to human RANKL. Based on the results from flow cytometry and surface plasmon resonance analyses, the replacement of E(125) with D(125), or E(125) and C(127) with D(125) and F(127) within loop 3 of cysteine-rich domain 3 of hRANK-Ig increases binding affinity to human RANKL over the wild-type hRANK-Ig. This result may provide the first example of improvement in the efficacy of hRANK-Ig by protein engineering and may give additional information to understand a more defined structural interface between hRANK and RANKL.

Human factors in design modifications: panel alternative stop in Almaraz

International Nuclear Information System (INIS)

Roman, Y.; Bote, J.

2015-01-01

Human Factors Engineering has acquired a crucial role in the development of any design modification (DM), where every aspect relative to any interaction with the human user has to be taken into account at any stage thereof. Considering this, during the last years, Almaraz Nuclear Powe Plants has developed a program of Human Factors Engineering in order to reach the internationally recognized standards or systematic collected on NUREG 0711 Human Factors Engineering Program Review Model (NRC). One of the most important projects of this program at Almaraz Nuclear Power Plant has been the implementation of the Alternative Stop Panel and their corresponding Transfer Panels. (Author)

Nuclear human resource projection up to 2030 in KOREA

International Nuclear Information System (INIS)

Min, Byung Joo; Lee, Man Ki; Nam, Kee Yung; Jeong, Ki Ho

2011-01-01

The prospects for growth of the nuclear power industry in Korea have improved remarkably as the demand for energy increases in stride with economic development. Meanwhile, as nuclear energy development is enhanced, nuclear technology has also improved evolutionarily and innovatively in the areas of reactor design and safety measures. As nuclear technology development in Korea advances, more human resources are required. Accordingly, the need for a well-managed program of human resource development (HRD) aimed at assuring needed capacities, skills, and knowledge and maintaining valuable human resources through education and training in various nuclear-related fields has been recognized. A well-defined and object-oriented human resource development and management (HRD and M) is to be developed in order to balance between the dynamics of supply and demand of the workforce in the nuclear industry. The HRD and M schemes include a broad base of disciplines, education, sciences, and technologies within a framework of national sustainable development goals, which are generally considered to include economics, environment, and social concerns. In this study, the projection methodology considering a variety of economic, social, and environmental factors was developed. Using the developed methodology, medium- and long-term nuclear human resources projections up to 2030 were conducted in compliance with the national nuclear technology development programmes and plans

Special Experts Meeting: Identifying and Overcoming Barriers to the Effective Consideration of Human and Organizational Factors in Event Analysis and Root Cause Analysis. Nuclear Energy Agency / Working Group on Human and Organizational Factors

International Nuclear Information System (INIS)

2011-01-01

The main mission of the Nuclear Energy Agency (NEA) Working Group on Human and Organisational Factors (WGHOF) is to improve the understanding and treatment of human and organisational factors (HOF) within the nuclear industry in order to support the continued safety performance of nuclear installations and improve the effectiveness of regulatory practices in member countries. WGHOF developed a CSNI (Committee on the Safety of Nuclear Installations) Activity Proposal Sheet (CAPS) outlining the work and milestones necessary towards achieving the following objectives: - Identify barriers to analyzing and correctly identifying the Human and Organisational Factors (HOF) causes of events; - Identify barriers to implementing lessons learned from these analyses; and - Develop recommendations for overcoming these barriers to: improve the identification of HOF causes of events and support the successful implementation of appropriate corrective actions The CAPS can be found in Appendix A. The first activity under the plan was the development of a questionnaire. This was distributed to WGHOF members and their counterparts from the Working Group on Operating Experience (WGOE). The questionnaire was comprised of 20 questions based on the objectives of the CSNI Activity Proposed Sheet. The intended survey participants were licensees with previous experience conducting root cause analyses. Responses were received from 26 respondents from 11 different countries. The results of the questionnaire were analyzed to identify themes for further discussion during a specialist meeting planned for September 2009. The following themes were presented during the WGHOF meeting in March of 2009 and endorsed for further work: - Roles and Influence of Senior Management, - Skills and Knowledge of the Investigators, - Qualitative Nature of HOF, - Influence of the Regulator, - Systematic Approach to Investigation. A summary of the questionnaire responses is provided in Appendix B

Human factors issues in fuel handling

Energy Technology Data Exchange (ETDEWEB)

Beattie, J D; Iwasa-Madge, K M; Tucker, D A [Humansystems Inc., Milton, ON (Canada)

1994-12-31

The staff of the Atomic Energy Control Board wish to further their understanding of human factors issues of potential concern associated with fuel handling in CANDU nuclear power stations. This study contributes to that objective by analysing the role of human performance in the overall fuel handling process at Ontario Hydro`s Darlington Nuclear Generating Station, and reporting findings in several areas. A number of issues are identified in the areas of design, operating and maintenance practices, and the organizational and management environment. 1 fig., 4 tabs., 19 refs.

Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation

International Nuclear Information System (INIS)

Scheblanov, V Y; Bobrov, A F; Sneve, M K

2012-01-01

This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical–Biological Agency of Russia and the Norwegian Radiation Protection Authority. (paper)

Development of human factors evaluation techniques for nuclear power plants

International Nuclear Information System (INIS)

Oh, I.S.; Lee, Y.H.; Lee, J.W.; Sim, B.S.

1999-01-01

This paper describes development of an operator task simulation analyzer and human factors evaluation techniques performed recently at Korea Atomic Energy Research Institute. The first is the SACOM (Simulation Analyzer with a Cognitive Operator Model) for the assessment of task performance by simulating control room operation. The latter has two objectives: to establish a human factors experiment facility, the Integrated Test Facility (ITF), and to establish techniques for human factors experiments. (author)

Anatomy of event and human performance management in nuclear power plants

International Nuclear Information System (INIS)

Wang Jinhua

2014-01-01

This article analyzes the occurrence mechanism of events in nuclear power plants, and explains the four factors of human errors and the relations among them, then probes into the occurrence mechanism and characteristics of human errors in nuclear power plants. Moreover, the article clarifies that the principle of human performance training in nuclear power plants is all-member training, and that the implementation approach is to develop different human performance tools for different staff categories as workers, knowledge workers and supervisors, which are categorized based on characteristics of work of different staff. (author)

Nuclear human resources management in Serbia

International Nuclear Information System (INIS)

Videnovic, I.

2007-01-01

Full text: Over the past fifty years Serbia passed a way from a founder of the International Atomic Energy Agency and a country with an extensive nuclear program which was supported by the knowledgeable and experienced expert human sources, to the period followed by political and economic difficulties and major changes. They, among the other factors, caused a considerable modification in the scope of the nuclear program and a range of its activities which were diminished. Inherited nuclear infrastructure, as a legacy of the past, comprises nowadays significant and complex issues to be solved in a serious and urgent manner in the forthcoming period, what requires a high level of knowledge and sufficient and adequate human sources. Brain drain, aging workforce, absence of a well established nuclear education system and strategy and a lack of younger experts to which the experience could be transferred are, gradually, but certainly, leading to a loss of knowledge and capabilities to handle and cope with the existing requests and the ones of the future overall development of nuclear energy and its application in the peaceful purposes. To overcome this situation, an active approach and serious consideration of all the relating elements with a goal to define future directions and prospective in the nuclear human resource management in Serbia are therefore a task to be undertaken by the state without a delay and a prerequisite for a future development. (author)

Human characteristics affecting nuclear safety

International Nuclear Information System (INIS)

Skof, M.

1990-01-01

It is important to collect data about human behavior in work situation and data about work performance. On the basis of these data we can analyse human errors. Human reliability analysis gives us the input data to improve human behavior at a work place. We have tried to define those human characteristics that have impact on safe work and operation. Estimation of a work place was used for determination of important human characteristics. Performance estimations were used to define the availability of workers at a work place. To our experience it is very important to pay attention to R.A. and R.C. also in the area of human factor. Data for quality assurance in the area of human factor should be collected from selection procedure (the level of cognitive and conative abilities, the level of physical characteristics, the level of education and other personal data). Data for quality control should be collected from the periodical examinations of annual checking and evaluation of human working capacity as well as from training. For quality control of every day human performance data of staff estimation of their daily working performance and well-being should also be collected. With all these data more effective analyses of all events in nuclear power plants could be provided. Quality assurance and quality control in the area of human factor could help us to keep the optimum performance level of the plant staff and to avoid human errors. (author). 3 refs, 3 figs

Human factors engineering in nuclear plant rehabilitations

International Nuclear Information System (INIS)

Bernston, K.; Remisz, M.; Malcolm, S.

2001-01-01

There are several unique considerations when creating and maintaining a human factors program for a plant refurbishment. These consideration arise from a variety of sources, including budget and time constraints on life extension projects, working to existing plant protocols and current acceptable HFE practices, and issues relating to function and task analysis. This results in a need to streamline and carefully time HFE practices from project start up to completion. In order to perform this task adequately, a comprehensive Human Factors Engineering Program Plan should be designed and tailored to the project. Systems of planning and prioritization are essential, and the required HFE designer training needs to be established. HFE specialists need to be aware of the existing plant constraints, and he prepared to work within them when providing support. The current paper discusses these aspects in the context of major refurbishment work at CANDU stations. (author)

Human factor in the operation of the Dukovany nuclear power plant

International Nuclear Information System (INIS)

Kostiha, Frantisek; Pleskac, Frantisek

2009-01-01

The human factor, i.e. the action of man within complex technical systems, has been in the focus of the Dukovany NPP management constantly. The paper gives an overview of the plant strategy regarding human factor issues, such as training, human factor prevention methods and practices to improve the resistance of the system to human error, the use of information systems, and operational feedback from the role of the human factor and influence of the operators on the initiation, development and resulting level of severity of operational events. The method of monitoring and assessment of the quality of human performance at the Dukovany plant on an ongoing basis aimed at a constant improvement is highlighted. (orig.)

Human equation in operating a nuclear-power plant

International Nuclear Information System (INIS)

Barrett, R.S.

1982-01-01

The accident at Three Mile Island has forced the nuclear industry to acknowledge a badly neglected aspect of nuclear-power-plant safety - the human equation. The industry now appears to recognize the importance of operator selection, training, motivation, and licensing, and the need to design a system from the point of view of communication, information retrieval, record keeping, and human factors psychology. As a result, the relatively small initiatives that were begun a few years ago by the EPRI are now being greatly expanded

1981 NRC/BNL/IEEE standards workshop on human factors and nuclear safety. The man-machine interface and human reliability: an assessment and projection

International Nuclear Information System (INIS)

Hall, R.E.; Fragola, J.R.; Luckas, W.J. Jr.

1981-09-01

The role of the human in the safety of nuclear power plant operations was addressed in a meeting held in Myrtle Beach, SC in August 1981. Presentation were made on Control Room reviews, safety parameter display systems, the integration of human factors in the entire design process, and the use of automated control features. A need was shown for the development of a taxonomy or model to structure future data gathering and the need for models and data to address the issue of cognitive behavior. The primary effect of this behavior on risk was identified. Discussion sessions on the human impact on reliability, and control room design and evaluation were included

Incorporating Human Factors into design change processes - a regulator's perspective

International Nuclear Information System (INIS)

Staples, L.; McRobbie, H.

2003-01-01

Nuclear power plants in Canada must receive written approval from the Canadian Nuclear Safety Commission (CNSC) when making certain changes that are defined in their licenses. The CNSC expects the design change process to include a method for ensuring that the human-machine interface and workplace design support the safe and reliable performance of required tasks. When reviewing design changes for approval, the CNSC looks for evidence of analysis work, use of appropriate human factors design guide-lines, and verification and validation testing of the design. In addition to reviewing significant design changes, evaluations are conducted to ensure design change processes adequately address human performance. Findings from reviews and evaluations highlight the need to integrate human factors into the design change process, provide human factors training and support to engineering staff, establish processes to ensure coordination between the various groups with a vested interest in human factors, and develop more rigorous methods to validate changes to maintenance, field operations and testing interfaces. (author)

Role of human factor in safety assurance in the nuclear industry

International Nuclear Information System (INIS)

Agapov, A.M.; Mikhajlov, M.V.; Novikov, G.A.

2010-01-01

The authors discuss the issues of human resource activities in the Rosatom Corporation that aim to achieve and maintain the required levels of safety culture and qualification of personnel involved in the operations of nuclear energy sites. These activities are supported by the appropriate resources, organisational management structure and quality control system, legislation, regulations and methodological support. It is emphasized that systematic and versatile HR-related activities in the nuclear industry represent one of the key areas of production operations that assure safety and reliability of nuclear sites at all stages of their life cycle. Especially important is the assurance of high professional level of nuclear regulators. They believe that it would appear sensible, in addition to the existing system of training, to engage the mechanisms of rotation of personnel from utility organisations to regulatory authorities [ru

The development of human factors technologies -The development of human behaviour analysis techniques-

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Lee, Yong Heui; Park, Keun Ok; Chun, Se Woo; Suh, Sang Moon; Park, Jae Chang [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

In order to contribute to human error reduction through the studies on human-machine interaction in nuclear power plants, this project has objectives to develop SACOM(Simulation Analyzer with a Cognitive Operator Model) and techniques for human error analysis and application. In this year, we studied the followings: (1) Site investigation of operator tasks, (2) Development of operator task micro structure and revision of micro structure, (3) Development of knowledge representation software and SACOM prototype, (4) Development of performance assessment methodologies in task simulation and analysis of the effects of performance shaping factors. human error analysis and application techniques> (1) Classification of error shaping factors(ESFs) and development of software for ESF evaluation, (2) Analysis of human error occurrences and revision of analysis procedure, (3) Experiment for human error data collection using a compact nuclear simulator, (4) Development of a prototype data base system of the analyzed information on trip cases. 55 figs, 23 tabs, 33 refs. (Author).

The significance of the human factor in the safety of nuclear reactors: the French experience and the lessons of Three Mile Island

International Nuclear Information System (INIS)

Houze, C.; Oury, J.M.

1982-05-01

The importance of the human factor to French nuclear safety policy and the application of human fallibility as a parameter of safety analysis are described. The impact of reactor operating experience on future theoretical and practical application considerations is discussed. Particular reference is given to the lessons of Three Mile Island

Activities of nuclear human resource development in nuclear industry

International Nuclear Information System (INIS)

Tsujikura, Yonezo

2010-01-01

Since 2007, the JAIF (Japan Atomic Industrial Forum) had established the nuclear energy human resource development council to make analysis of the issue on nuclear human resource development. The author mainly contributed to develop its road map as a chairman of working group. Questionnaire survey to relevant parties on issues of nuclear human resource development had been conducted and the council identified the six relevant issues and ten recommendations. Both aspects for career design and skill-up program are necessary to develop nuclear human resource at each developing step and four respective central coordinating hubs should be linked to each sector participating in human resource development. (T. Tanaka)

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

Human factors and technology environment in multinational project: problems and solutions

International Nuclear Information System (INIS)

Jardi Besa, X.; Munoz Cervantes, A.

2012-01-01

At the onset of nuclear projects in Spain, there was an import of nuclear technology. In a second phase, there was a transfer of technology. Subsequently, there was an adaptation of the technology. In this evolution, comparable to that of other countries, were involved several countries, overcoming the difficulties of human factors involved. The current nuclear projects multinationals have a new difficulty: the different industrial technological environments. This paper will address the organizational challenges of multinational engineering projects, in the type of project and the human factors of the participating companies.

The development of human factors technologies -The development of human behaviour analysis techniques-

International Nuclear Information System (INIS)

Lee, Jung Woon; Lee, Yong Heui; Park, Keun Ok; Chun, Se Woo; Suh, Sang Moon; Park, Jae Chang

1995-07-01

In order to contribute to human error reduction through the studies on human-machine interaction in nuclear power plants, this project has objectives to develop SACOM(Simulation Analyzer with a Cognitive Operator Model) and techniques for human error analysis and application. In this year, we studied the followings: 1) Site investigation of operator tasks, 2) Development of operator task micro structure and revision of micro structure, 3) Development of knowledge representation software and SACOM prototype, 4) Development of performance assessment methodologies in task simulation and analysis of the effects of performance shaping factors. 1) Classification of error shaping factors(ESFs) and development of software for ESF evaluation, 2) Analysis of human error occurrences and revision of analysis procedure, 3) Experiment for human error data collection using a compact nuclear simulator, 4) Development of a prototype data base system of the analyzed information on trip cases. 55 figs, 23 tabs, 33 refs. (Author)

A human factors design of a nuclear plant analyzer

Energy Technology Data Exchange (ETDEWEB)

Byeon, Seung Nam; Lee, Dong Hoon; Park, Chan Woo [Kyounghee Univ., Seoul (Korea, Republic of)

2000-12-15

The project consists of four key stages as follows : based on the review of various literature, human factors design principles and processes are identified, the literature reviewed in the project includes NUREG-0700, research papers for MMI, human factors handbooks, and laboratory reports, after the design principles and processes are determined, a design checklist is developed to evaluate the user interface of NPA, the design checklist consists of seven different categories such as display screen, menu interface, form-fillin, alphanumeric characters, symbols, color, and highlighting, NPA was tested with the design checklist for conformance to the human factors design principles, the expert reviews are performed to evaluate a graphic user interface of NPA, the application of the design checklist and the subjective opinion of the expert identify the design included in the user interface of NPA, based on the thorough analysis of design defects, design guidelines are recommended to improve the user interface of NPA.

A human factors design of a nuclear plant analyzer

International Nuclear Information System (INIS)

Byeon, Seung Nam; Lee, Dong Hoon; Park, Chan Woo

2000-12-01

The project consists of four key stages as follows : based on the review of various literature, human factors design principles and processes are identified, the literature reviewed in the project includes NUREG-0700, research papers for MMI, human factors handbooks, and laboratory reports, after the design principles and processes are determined, a design checklist is developed to evaluate the user interface of NPA, the design checklist consists of seven different categories such as display screen, menu interface, form-fillin, alphanumeric characters, symbols, color, and highlighting, NPA was tested with the design checklist for conformance to the human factors design principles, the expert reviews are performed to evaluate a graphic user interface of NPA, the application of the design checklist and the subjective opinion of the expert identify the design included in the user interface of NPA, based on the thorough analysis of design defects, design guidelines are recommended to improve the user interface of NPA

Human reliability guidance - How to increase the synergies between human reliability, human factors, and system design and engineering. Phase 2: The American Point of View - Insights of how the US nuclear industry works with human reliability analysis

International Nuclear Information System (INIS)

Oxstrand, J.

2010-12-01

The main goal of this Nordic Nuclear Safety Research Council (NKS) project is to produce guidance for how to use human reliability analysis (HRA) to strengthen overall safety. The project consists of two substudies: The Nordic Point of View - A User Needs Analysis, and The American Point of View - Insights of How the US Nuclear Industry Works with HRA. The purpose of the Nordic Point of View study was a user needs analysis that aimed to survey current HRA practices in the Nordic nuclear industry, with the main focus being to connect HRA to system design. In this study, 26 Nordic (Swedish and Finnish) nuclear power plant specialists with research, practitioner, and regulatory expertise in HRA, PRA, HSI, and human performance were interviewed. This study was completed in 2009. This study concludes that HRA is an important tool when dealing with human factors in control room design or modernizations. The Nordic Point of View study showed areas where the use of HRA in the Nordic nuclear industry could be improved. To gain more knowledge about how these improvements could be made, and what improvements to focus on, the second study was conducted. The second study is focused on the American nuclear industry, which has many more years of experience with risk assessment and human reliability than the Nordic nuclear industry. Interviews were conducted to collect information to help the author understand the similarities and differences between the American and the Nordic nuclear industries, and to find data regarding the findings from the first study. The main focus of this report is to identify potential HRA improvements based on the data collected in the American Point of View survey. (Author)

Human reliability guidance - How to increase the synergies between human reliability, human factors, and system design and engineering. Phase 2: The American Point of View - Insights of how the US nuclear industry works with human reliability analysis

Energy Technology Data Exchange (ETDEWEB)

Oxstrand, J. (Vattenfall Ringhals AB, Stockholm (Sweden))

2010-12-15

The main goal of this Nordic Nuclear Safety Research Council (NKS) project is to produce guidance for how to use human reliability analysis (HRA) to strengthen overall safety. The project consists of two substudies: The Nordic Point of View - A User Needs Analysis, and The American Point of View - Insights of How the US Nuclear Industry Works with HRA. The purpose of the Nordic Point of View study was a user needs analysis that aimed to survey current HRA practices in the Nordic nuclear industry, with the main focus being to connect HRA to system design. In this study, 26 Nordic (Swedish and Finnish) nuclear power plant specialists with research, practitioner, and regulatory expertise in HRA, PRA, HSI, and human performance were interviewed. This study was completed in 2009. This study concludes that HRA is an important tool when dealing with human factors in control room design or modernizations. The Nordic Point of View study showed areas where the use of HRA in the Nordic nuclear industry could be improved. To gain more knowledge about how these improvements could be made, and what improvements to focus on, the second study was conducted. The second study is focused on the American nuclear industry, which has many more years of experience with risk assessment and human reliability than the Nordic nuclear industry. Interviews were conducted to collect information to help the author understand the similarities and differences between the American and the Nordic nuclear industries, and to find data regarding the findings from the first study. The main focus of this report is to identify potential HRA improvements based on the data collected in the American Point of View survey. (Author)

Inhibition of nuclear factor-kappa B activation decreases survival of Mycobacterium tuberculosis in human macrophages.

Directory of Open Access Journals (Sweden)

Xiyuan Bai

Full Text Available Nuclear factor-kappa B (NFκB is a ubiquitous transcription factor that mediates pro-inflammatory responses required for host control of many microbial pathogens; on the other hand, NFκB has been implicated in the pathogenesis of other inflammatory and infectious diseases. Mice with genetic disruption of the p50 subunit of NFκB are more likely to succumb to Mycobacterium tuberculosis (MTB. However, the role of NFκB in host defense in humans is not fully understood. We sought to examine the role of NFκB activation in the immune response of human macrophages to MTB. Targeted pharmacologic inhibition of NFκB activation using BAY 11-7082 (BAY, an inhibitor of IκBα kinase or an adenovirus construct with a dominant-negative IκBα significantly decreased the number of viable intracellular mycobacteria recovered from THP-1 macrophages four and eight days after infection. The results with BAY were confirmed in primary human monocyte-derived macrophages and alveolar macrophages. NFκB inhibition was associated with increased macrophage apoptosis and autophagy, which are well-established killing mechanisms of intracellular MTB. Inhibition of the executioner protease caspase-3 or of the autophagic pathway significantly abrogated the effects of BAY. We conclude that NFκB inhibition decreases viability of intracellular MTB in human macrophages via induction of apoptosis and autophagy.

An approach to human-centered design of nuclear medical equipment: the system of caption of the thyroid

International Nuclear Information System (INIS)

Santos, Isaac J.A. Luquetti; Silva, Carlos Borges da; Santana, Marcos; Carvalho, Paulo Victor R.; Oliveira, Mauro Vitor de; Mol, Antonio Carlos Mol; Grecco, Claudio Henrique; Augusto, Silas Cordeiro

2005-01-01

Technology plays an important role in modern medical centers, making health care increasingly complex, relying on complex technical equipment. This technical complexity is particularly noticeable in the nuclear medicine and can increase the risks for human error. Human error has many causes such as performance shaping factors, organizational factors and user interface design. Poorly design human system interfaces of nuclear medical equipment can increase the risks for human error. If all nuclear medical equipment had been designed with good user interfaces, incidents and accidents could be reduced as well as he time required to learn how to use the equipment. Although some manufacturers of nuclear medical equipment have already integrate human factors principles in their products, there is still a need to steer the development of nuclear medical technology toward more human-centered approach. The aim of this paper is to propose a methodology that contributes to the design, development and evaluation of nuclear medical equipment and human system interface, towards a human-centered approach. This methodology includes the ergonomic approach, based on the operator activity analysis, together with human factors standards and guidelines, questionnaires and user based testing. We describe a case study in which this methodology is being applied in evaluation of the thyroid uptake system, getting essential information and data, that ill be used in development of a new system. (author)

Analysis of human factors in incidents reported by Swiss nuclear power plants to the inspectorate

International Nuclear Information System (INIS)

Alder, H.P.; Hausmann, W.

1997-01-01

197 reported incidents in Swiss Nuclear Power Plants were analyzed by a team of the Swiss Federal Nuclear Safety Inspectorate (HSK) using the OECD/NEA Incident Reporting System. The following conclusions could be drawn from this exercise. While the observed cause reported by the plant was ''technical failure'' in about 90% of the incidents, the HSK-Team identified for more than 60% of the incidents ''human factors'' as the root cause. When analyzing this root cause further it was shown that only a smaller contribution came from the side of the operators and the more important shares were caused by plant maintenance, vendors/constructors and plant management with procedural and organizational deficiencies. These findings demonstrate that root cause analysis of incidents by the IRS-Code is a most useful tool to analyze incidents and to find weak points in plant performance. (author). 5 tabs

Incorporation of human factors into design change processes - a regulator's perspective

International Nuclear Information System (INIS)

Staples, L.; McRobbie, H.

2003-01-01

Nuclear power plants in Canada must receive written approval from the Canadian Nuclear Safety Commission (CNSC) when making certain changes that are defined in their licenses. The CNSC expects the design change process to include a method for ensuring that the human-machine interface and workplace design support the safe and reliable performance of required tasks. When reviewing design changes for approval, the CNSC looks for evidence of analysis work, use of appropriate human factors design guidelines, and verification and validation testing of the design. In addition to reviewing significant design changes, evaluations are conducted to ensure design change processes adequately address human performance. Findings from reviews and evaluations highlight the need to integrate human factors into the design change process, provide human factors training and support to engineering staff, establish processes to ensure coordination between the various groups with a vested interest in human factors, and develop more rigorous methods to validate changes to maintenance, field operations and testing interfaces. (author)

Anti-Inflammatory Effect of ETAS®50 by Inhibiting Nuclear Factor-κB p65 Nuclear Import in Ultraviolet-B-Irradiated Normal Human Dermal Fibroblasts

Directory of Open Access Journals (Sweden)

Ken Shirato

2018-01-01

Full Text Available Ultraviolet (UV irradiation induces proinflammatory responses in skin cells, including dermal fibroblasts, accelerating premature skin aging (photoaging. ETAS 50, a standardized extract from the Asparagus officinalis stem, is a novel and unique functional food that suppresses proinflammatory responses of hydrogen peroxide-stimulated skin fibroblasts and interleukin- (IL- 1β-stimulated hepatocytes. To elucidate its antiphotoaging potencies, we examined whether ETAS 50 treatment after UV-B irradiation attenuates proinflammatory responses of normal human dermal fibroblasts (NHDFs. UV-B-irradiated NHDFs showed reduced levels of the cytosolic inhibitor of nuclear factor-κB α (IκBα protein and increased levels of nuclear p65 protein. The nuclear factor-κB nuclear translocation inhibitor JSH-23 abolished UV-B irradiation-induced IL-1β mRNA expression, indicating that p65 regulates transcriptional induction. ETAS 50 also markedly suppressed UV-B irradiation-induced increases in IL-1β mRNA levels. Immunofluorescence analysis revealed that ETAS 50 retained p65 in the cytosol after UV-B irradiation. Western blotting also showed that ETAS 50 suppressed the UV-B irradiation-induced increases in nuclear p65 protein. Moreover, ETAS 50 clearly suppressed UV-B irradiation-induced distribution of importin-α protein levels in the nucleus without recovering cytosolic IκBα protein levels. These results suggest that ETAS 50 exerts anti-inflammatory effects on UV-B-irradiated NHDFs by suppressing the nuclear import machinery of p65. Therefore, ETAS 50 may prevent photoaging by suppressing UV irradiation-induced proinflammatory responses of dermal fibroblasts.

Summary of Survey and Workshop Results on Areas of Research in Human Factors for the Design and Operation of New Nuclear Plant Technology - Final Report

International Nuclear Information System (INIS)

Persensky, Julius J.; Joe, Jeffrey; Richards, Robert E.; Barnes, Valerie; Gonzalez, Michelle

2012-01-01

The nuclear community is currently at a stage where existing reactor control stations are undergoing various forms of modernization, new reactors are being built in many countries with computer-based control rooms, and advanced reactors are being designed through international cooperation to support power generation for decades to come. With the introduction of advanced plants, we will see new reactor and system designs, new tools to support plant personnel, and changes to nuclear power plant (NPP) staffing configurations. The concepts of operation and maintenance for this new generation of plants are likely to be quite different from those employed in today's plants. It is important that the potential impact of these developments is evaluated and understood by prospective operators and regulators responsible for determining the acceptability of new designs to support human performance in maintaining plant safety. The introduction of new technology is viewed as having promise for improving the safe and efficient operation of NPPs. To ensure the appropriate application of technology to support human performance and plant safety, it is important to evaluate the technological advances in terms of both potential negative and positive effects. Research described in this paper can provide the technical basis to help ensure that the benefits of new technology are realized and that the potential negative effects are minimized. The impetus for the current effort grew out of a Nuclear Energy Agency, Committee on the Safety of Nuclear Installations, Working Group on Human and Organizational Factors, Technical Opinion Paper (TOP) titled, 'Research on Human Factors in New Nuclear Plant Technology' [NEA/CSNI/R(2009)7], which identified eight broad topic areas that warrant further research: 1. Operating Experience (OpEx) from New and Modernized Plants. 2. Evolving Concepts for the Operation of Nuclear Power Plants. 3. The Role of Automation and Personnel: New Concepts of Teamwork

Ultraviolet B Radiation Stimulates the Interaction between Nuclear Factor of Activated T Cells 5 (NFAT5) and Nuclear Factor-Kappa B (NF-κB) in Human Lens Epithelial Cells.

Science.gov (United States)

Chung, Inyoung; Hah, Young-Sool; Ju, SunMi; Kim, Ji-Hye; Yoo, Woong-Sun; Cho, Hee-Young; Yoo, Ji-Myong; Seo, Seong-Wook; Choi, Wan-Sung; Kim, Seong-Jae

2017-07-01

Nuclear factor-kappa B (NF-κB) has been proposed as a therapeutic target for the treatment of cataracts. The authors investigated the relationship between nuclear factor of activated T cells 5 (NFAT5) and NF-κB in ultraviolet B (UVB)-irradiated human lens epithelial (HLE) cells. Human lens epithelial B-3 (HLE-B3) cells were exposed to UVB light at a dose of 10 mJ/cm 2 and then incubated for 24 h. Cell viability was assessed by using the Cell Counting Kit-8 (CCK-8) assay. Gene expression level of NFAT5 was determined using real-time quantitative polymerase chain reaction (qPCR). Protein expression levels of NFAT5, NF-κB p65, and α-smooth muscle actin (α-SMA) and the association of NFAT5 with the NF-κB p65 subunit were measured by Western blot analysis and a co-immunoprecipitation assay, respectively. The cellular distribution of NFAT5 and NF-κB p65 was examined by triple immunofluorescence staining. At 24 h after UVB exposure, cell viability significantly decreased in a dose-dependent manner, and UVB light (15 and 20 mJ/cm 2 ) significantly increased the ROS generation. UVB irradiation increased NFAT5 mRNA and protein levels and increased phosphorylation of NF-κB in HLE-B3 cells. α-SMA protein levels were increased in the irradiated cells. In addition, NFAT5 and NF-κB translocated from the cytoplasm to the nucleus, and binding between the p65 subunit and NFAT5 was increased. Exposure to UVB radiation induces nuclear translocation and stimulates binding between NFAT5 and NF-κB proteins in HLE-B3 cells. These interactions may form part of the biochemical mechanism of cataractogenesis in UVB-irradiated HLECs.

Selection of the important performance influencing factors for the assessment of human error under accident management situations in nuclear power plants

International Nuclear Information System (INIS)

Kim, J. H.; Jung, W. J.

1999-01-01

This paper introduces the process and final results of selection of the important Performance Influencing Factors (PIFs) under emergency operation and accident management situations in nuclear power plants for use in the assessment of human errors. We collected two types of PIF taxonomies, one is the full set PIF list mainly developed for human error analysis, and the other is the PIFs for human reliability analysis (HRA) in probabilistic safety assessment (PSA). 5 PIF taxonomies among the full set PIF list and 10 PIF taxonomies among HRA methodologies (CREAM, SLIM, INTENT, were collected in this research. By reviewing and analyzing PIFs selected for HRA methodologies, the criterion could be established for the selection of appropriate PIFs under emergency operation and accident management situations. Based on this selection criteria, a new PIF taxonomy was proposed for the assessment of human error under emergency operation and accident management situations in nuclear power plants

The human elements in phenomena giving rise to nuclear accidents

International Nuclear Information System (INIS)

Carnino, A.; Raggenbass, A.

1977-01-01

In its search for a high degree of safety, the nuclear industry should take into account the human parameters, which play an important role. This role is reflected in the individual records kept on incidents and analysis of these records, as has been carried out in conventional industry, represents a first attempt to allow for this factor. The first inquiries covering the background of incidents led to a series of studies and action in respect of individual staff members: on the part of operators, education of personnel in relation to their duties (for example, simulation of reactor control) and attempts to find objective selection criteria for certain specific posts; on the part of those responsible for safety, ergonomic studies and studies on human reliability. For effective prevention of accidents it is necessary to move backwards along the causality chains and therefore to study a nuclear facility as a man-machine system in order to discover the greatest number of potential accident factors. The nuclear facility is introduced into an environment which imposes its rules, constraints and checks and a full study of the human element in safety implies that they should be taken into account. The programme of the Nuclear Safety Department of the Institute of Protection and Nuclear Safety includes not only systematic updating of incident records but also special ergonomic studies (maintenance in a radioactive environment), studies of human reliability and overall studies known as safety management studies. (author)

Identification of advanced human factors engineering analysis, design and evaluation methods

International Nuclear Information System (INIS)

Plott, C.; Ronan, A. M.; Laux, L.; Bzostek, J.; Milanski, J.; Scheff, S.

2006-01-01

NUREG-0711 Rev.2, 'Human Factors Engineering Program Review Model,' provides comprehensive guidance to the Nuclear Regulatory Commission (NRC) in assessing the human factors practices employed by license applicants for Nuclear Power Plant control room designs. As software based human-system interface (HSI) technologies supplant traditional hardware-based technologies, the NRC may encounter new HSI technologies or seemingly unconventional approaches to human factors design, analysis, and evaluation methods which NUREG-0711 does not anticipate. A comprehensive survey was performed to identify advanced human factors engineering analysis, design and evaluation methods, tools, and technologies that the NRC may encounter in near term future licensee applications. A review was conducted to identify human factors methods, tools, and technologies relevant to each review element of NUREG-0711. Additionally emerging trends in technology which have the potential to impact review elements, such as Augmented Cognition, and various wireless tools and technologies were identified. The purpose of this paper is to provide an overview of the survey results and to highlight issues that could be revised or adapted to meet with emerging trends. (authors)

Human factors in RBNK plants

International Nuclear Information System (INIS)

Demitrack, T.

1995-01-01

The Safety of RBMK nuclear power plants in the Russian Federation, The Ukraine and Lithuanian is a topic of concern to the European Union and other Western European countries. The European Commission, Sweden, Finland and Canada financed the project Safety Design Solutions and Operation of NPP with RBMK Reactors. The project examined nine issues and recommended safety improvements which will form the basis of future European Commission spending on these power plants. During its year of work, the project examined these issues: 1. Systems Engineering and progression of accidents 2. Protection System 3. Core Physics 4. External Events 5. Engineering Quality 6. Operating Experience 7. Human Factors 8. Regulatory Interface 9. Probabilistic Safety analysis Empresarios Agrupados, in collaboration with other western European firms, the Russian Federation and Lithuanian took part in two of these groups, Human Factors and Probabilistic Safety Analysis. This presentation gives a brief description of the most important aspects of human factors in RBMK plants, focusing on operations organization, training and education

Status of human factors engineering system design in Europe

International Nuclear Information System (INIS)

Ives, G.

1990-01-01

A review of the European status of human factors engineering has been carried out covering a wide scope of activities which includes psychology, cognitive science, ergonomics, design, training, procedure writing, operating, artificial intelligence and expert systems. There is an increasing awareness of the part that human factors play in major nuclear power plant accidents. The emphasis of attention in human factors is changing. In some areas there are encouraging signs of progress and development, but in other areas there is still scope for improvement

Human Factors Principles in Information Dashboard Design

Energy Technology Data Exchange (ETDEWEB)

Hugo, Jacques V.; St. Germain, Shawn

2016-06-01

When planning for control room upgrades, nuclear power plants have to deal with a multitude of engineering and operational impacts. This will inevitably include several human factors considerations, including physical ergonomics of workstations, viewing angles, lighting, seating, new communication requirements, and new concepts of operation. In helping nuclear power utilities to deal with these challenges, the Idaho National Laboratory (INL) has developed effective methods to manage the various phases of the upgrade life cycle. These methods focus on integrating human factors engineering processes with the plant’s systems engineering process, a large part of which is the development of end-state concepts for control room modernization. Such an end-state concept is a description of a set of required conditions that define the achievement of the plant’s objectives for the upgrade. Typically, the end-state concept describes the transition of a conventional control room, over time, to a facility that employs advanced digital automation technologies in a way that significantly improves system reliability, reduces human and control room-related hazards, reduces system and component obsolescence, and significantly improves operator performance. To make the various upgrade phases as concrete and as visible as possible, an end-state concept would include a set of visual representations of the control room before and after various upgrade phases to provide the context and a framework within which to consider the various options in the upgrade. This includes the various control systems, human-system interfaces to be replaced, and possible changes to operator workstations. This paper describes how this framework helps to ensure an integrated and cohesive outcome that is consistent with human factors engineering principles and also provide substantial improvement in operator performance. The paper further describes the application of this integrated approach in the

Design engineer perceptions and attitudes regarding human factors application to nuclear power plant design

International Nuclear Information System (INIS)

Ma, R.; Jones, J. M.

2006-01-01

With the renewed interest in nuclear power and the possibility of constructing new reactors within the next decade in the U.S., there are several challenges for the regulators, designers, and vendors. One challenge is to ensure that Human Factors Engineering (HFE) is involved, and correctly applied in the life-cycle design of the Nuclear Power Plant (NPP). As an important part of the effort, people would ask: 'is the system-design engineer effectively incorporating HFE in the NPPs design?' The present study examines the sagacity of Instrumentation and Control design engineers on issues relating to awareness, attitude, and application of HFE in NPP design. A questionnaire was developed and distributed, focusing on the perceptions and attitudes of the design engineers. The responses revealed that, while the participants had a relatively high positive attitude about HFE, their awareness and application of HFE were moderate. The results also showed that senior engineers applied HFE more frequently in their design work than young engineers. This study provides some preliminary results and implications for improved HFE education and application in NPP design. (authors)

Managing Human Performance to Improve Nuclear Facility Operation

International Nuclear Information System (INIS)

2013-01-01

. It describes how human performance can be managed within an overall performance improvement model. The need for IAEA involvement in this area and to address key issues highlighted in IAEA Nuclear Energy Series No. NG-G-2.1 were reinforced during the meetings of the Technical Working Group on Managing Human Resources in the Field of Nuclear Energy (TWG-MHR) in 2008 and 2010. The importance of human performance in the safe operation of any nuclear facility is no longer in doubt. The contribution of human performance to the occurrence of significant events and, consequently, to overall performance in the nuclear field has been well documented. Monitoring and continually improving human performance has now become one of the key challenges in the management of human resources for nuclear facilities. To facilitate meeting the challenge of improving human performance, a model of performance improvement is presented that provides a framework which can be used to improve individual, process and organizational performance. It is generally postulated that without human performance improvement, a safe working environment is impossible to maintain. While there are many different perspectives from which safety issues might be addressed, there are several factors significant for human performance improvement that are consistent, useful and necessary to understand. This publication is not intended as an all encompassing guide to managing human performance, but, rather, provides a summary of concepts and good practices for organizations to consider in their design of various programmes and in the performance of activities. In addition, tools that are helpful for managing human performance are discussed, and references for more detailed information on these concepts and tools are provided

Human factors review of power plant maintainability

International Nuclear Information System (INIS)

Seminara, J.L.; Parsons, S.O.; Schmidt, W.J.; Gonzalez, W.R.; Dove, L.E.

1980-10-01

Human factors engineering is an interdisciplinary science and technology concerned with shaping the design of machines, facilities, and operational environments to promote safe, efficient, and reliable performance on the part of operators and maintainers of equipment systems. The human factors aspects of five nuclear power plants and four fossil fuel plants were evaluated using such methods as a checklist guided observation system, structured interviews with maintenance personnel, direct observations of maintenance tasks, reviews of procedures, and analyses of maintenance errors or accidents by means of the critical incident technique. The study revealed a wide variety of human factors problem areas, most of which are extensively photodocumented. The study recommends that a more systematic and formal approach be adopted to ensure that future power plants are human engineered to the needs of maintenance personnel

Nuclear proteins interacting with the promoter region of the human granulocyte/macrophage colony-stimulating factor gene

International Nuclear Information System (INIS)

Shannon, M.F.; Gamble, J.R.; Vadas, M.A.

1988-01-01

The gene for human granulocyte/macrophage colony-stimulating factor (GM-CSF) is expressed in a tissue-specific as well as an activation-dependent manner. The interaction of nuclear proteins with the promoter region of the GM-CSF gene that is likely to be responsible for this pattern of GM-CSF expression was investigated. The authors show that nuclear proteins interact with DNA fragments from the GM-CSF promoter in a cell-specific manner. A region spanning two cytokine-specific sequences, cytokine 1 (CK-1, 5', GAGATTCCAC 3') and cytokine 2 (CK-2, 5' TCAGGTA 3') bound two nuclear proteins from GM-CSF-expressing cells in gel retardation assays. NF-GMb was inducible with phorbol 12-myristate 13-acetate and accompanied induction of GM-CSF message. NF-GMb was absent in cell lines not producing GM-CSF, some of which had other distinct binding proteins. NF-GMa and NF-GMb eluted from a heparin-Sepharose column at 0.3 and 0.6 M KCl, respectively. They hypothesize that the sequences CK-1 and CK-2 bind specific proteins and regulate GM-CSF transcription

Self-assessment of human performance errors in nuclear operations

International Nuclear Information System (INIS)

Chambliss, K.V.

1996-01-01

One of the most important approaches to improving nuclear safety is to have an effective self-assessment process in place, whose cornerstone is the identification and improvement of human performance errors. Experience has shown that significant events usually have had precursors of human performance errors. If these precursors are left uncorrected or not understood, the symptoms recur and result in unanticipated events of greater safety significance. The Institute of Nuclear Power Operations (INPO) has been championing the cause of promoting excellence in human performance in the nuclear industry. INPO's report, open-quotes Excellence in Human Performance,close quotes emphasizes the importance of several factors that play a role in human performance. They include individual, supervisory, and organizational behaviors; real-time feedback that results in specific behavior to produce safe and reliable performance; and proactive measures that remove obstacles from excellent human performance. Zack Pate, chief executive officer and president of INPO, in his report, open-quotes The Control Room,close quotes provides an excellent discussion of serious events in the nuclear industry since 1994 and compares them with the results from a recent study by the National Transportation Safety Board of airline accidents in the 12-yr period from 1978 to 1990 to draw some common themes that relate to human performance issues in the control room

Validation of human factor engineering integrated system

International Nuclear Information System (INIS)

Fang Zhou

2013-01-01

Apart from hundreds of thousands of human-machine interface resources, the control room of a nuclear power plant is a complex system integrated with many factors such as procedures, operators, environment, organization and management. In the design stage, these factors are considered by different organizations separately. However, whether above factors could corporate with each other well in operation and whether they have good human factors engineering (HFE) design to avoid human error, should be answered in validation of the HFE integrated system before delivery of the plant. This paper addresses the research and implementation of the ISV technology based on case study. After introduction of the background, process and methodology of ISV, the results of the test are discussed. At last, lessons learned from this research are summarized. (authors)

Annotated bibliography of human factors applications literature

International Nuclear Information System (INIS)

McCafferty, D.B.

1984-01-01

This bibliography was prepared as part of the Human Factors Technology Project, FY 1984, sponsored by the Office of Nuclear Safety, US Department of Energy. The project was conducted by Lawrence Livermore National Laboratory, with Essex Corporation as a subcontractor. The material presented here is a revision and expansion of the bibliographic material developed in FY 1982 as part of a previous Human Factors Technology Project. The previous bibliography was published September 30, 1982, as Attachment 1 to the FY 1982 Project Status Report

Annotated bibliography of human factors applications literature

Energy Technology Data Exchange (ETDEWEB)

McCafferty, D.B.

1984-09-30

This bibliography was prepared as part of the Human Factors Technology Project, FY 1984, sponsored by the Office of Nuclear Safety, US Department of Energy. The project was conducted by Lawrence Livermore National Laboratory, with Essex Corporation as a subcontractor. The material presented here is a revision and expansion of the bibliographic material developed in FY 1982 as part of a previous Human Factors Technology Project. The previous bibliography was published September 30, 1982, as Attachment 1 to the FY 1982 Project Status Report.

Development of a Field Management Standard for Improving Human Factors

International Nuclear Information System (INIS)

Yun, Young Su; Son, Il Moon; Son, Byung Chang; Kwak, Hyo Yean

2009-07-01

This project is to develop a management guideline for improving human performances as a part of the Human Factors Management System of Kori unit 1 which is managing all of human factors items such as man-machine system interfaces, work procedures, work environments, and human reliabilities in nuclear power plants. Human factors engineering includes an human factors suitability analysis and improvement of human works, an analysis of accidents by human error, an improvement of work environment, an establishment of human factors management rules and a development of human resources to manage and perform those things consistently. For assisting these human factors engineering tasks, we developed human factors management guidelines, checklists and work procedures to be used in staffing, qualification, training, and human information requirements and workload. We also provided a software tool for managing the above items. Additionally, contents and an item pool for a human factors qualifying examination and training programs were developed. A procedures improvement and a human factors V and V on the Kori unit 1 have been completed as a part of this project, too

A human factors approach to effective maintenance

International Nuclear Information System (INIS)

Penington, J.; Shakeri, S.

2006-01-01

Traditionally in the field of Human Factors within the nuclear industry, the focus has been to identify the potential for human errors in operating tasks, and develop strategies to prevent their occurrence, provide recovery mechanisms, and mitigate the consequences of error as appropriate. Past experience has demonstrated however a significant number of human errors within the nuclear industry occur during maintenance tasks. It is for this reason, and the fact that our nuclear power plants are ageing and increasingly in need of maintenance, that the industry must pay more attention to maintenance tasks. The purpose of this paper is to present a framework for effective maintenance programs, and based upon this framework discuss an approach (an audit tool) that can be used to both design such a program, and to assess existing programs. In addition, this tool can form the basis of cost benefit decisions relating to priorities for improvements to existing programs. (author)

The human factors issue in the next generation nuclear plants

International Nuclear Information System (INIS)

Noviello, L.; Bolognini, G.; Nobile, M.

1992-01-01

The national Energy Plan approved by the Italian Government in 1988, soon after the public referendum on nuclear issues held in the wake of the Chernobyl accident, requested the start of a research program to study next generation nuclear plants. These new reactors should feature some important and innovative characteristics to have a chance to be considered for future constructions, should the politicians decide the conditions for such a step are again re-established in Italy. The most important of these characteristics is certainly the fact that no evaluation nor land set a-side shall be required even in case of the most severe conceivable accident. This challenging objective should be reached through: a) the simplification of the nuclear plant as a whole b) the extensive use of passive components and/or inherent safety features in the design of the engineering safeguard systems c) a containment designed to cope with any conceivable accident sequence without releasing any major quantity of radioactive products into the environment. d) the upgrading of the man-machine interface and the introduction of computerized aids both for operational and maintenance activities. This paper deals in particular with the improvements, described in point d), that aim at greatly reducing the probability of human errors, widely recognized as one of the most important aspects to be pursued to increase nuclear plant safety. (author)

Risk management and nuclear human resources management in construction nuclear power plants in the Gulf Countries

International Nuclear Information System (INIS)

Saeed Hakami; Salim Almarmary

2009-01-01

The countries of the Gulf region have the capacity to rapidly expand their economic growth and gross domestic product (GDP). Also, one may observe that their growth rate is very high. To match this, they need a mix of energy sources for this economic growth. Nuclear power plants can have a significant role as a source of energy in the Gulf countries. Although, some of the Gulf countries signed contracts to construct nuclear power plants, they still require high a level of education as well as sufficient and adequate human resources in order to solve complex issues which may happen at nuclear power plants. The objective of this paper is to identify the complex issues that may arise at a nuclear site. Then the paper goes on to discuss how to evaluate these issues. Finally, the paper studies how to manage and control such complex issues in the work place. The advantage of highly educated people as well as sufficient and adequate human resource can increasingly protect and save human health and the natural environment from issues relating to the use of nuclear energy. There are vast theories, strategies and tools that have discussed in regards to human resources management in the nuclear industries. However, this paper chiefly provides a new risk management methodology. This methodology helps to highlight the risk factors and their consequences at nuclear sites. This paper is intended to decrease risks; to protect human health in the work place at nuclear power plants and save the environment within and beyond national borders and for future generations. It aims to increase safety from the use of nuclear energy, particularly in the Gulf countries.(Author)

Safety of modifications at nuclear power plants - the role of minor modifications and human and organisational factors

International Nuclear Information System (INIS)

2005-01-01

Operating experience repeatedly shows that changes and modifications at nuclear power plants (NPPs) may lead to safety significant events. At the same time, modifications are necessary to ensure a safe and economic functioning of the NPPs. To ensure safety in all plant configurations it is important that modification processes are given proper attention both by the utilities and the regulators. The operability, maintainability and testability of every modification should be thoroughly assessed from different points of view to ensure that no safety problems are introduced. The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) has recently addressed the issue of modifications by organising a 'Workshop on Modifications at Nuclear Power Plants Operating Experience, Safety Significance and Role of Human Factors'. This workshop was undertaken as a joint effort of the Working Group on Operating Experience (WGOE) and the Special Experts Group on Human and Organisational Factors (SEGHOF), and it was held at the OECD Headquarters in Paris on October 6 to 8, 2003. The initiative to organise the workshop was taken by the WGOE and the SEGHOF based on findings from events and incidents due to modifications at nuclear power plants in the world and weaknesses experienced in modification processes. During the workshop, the WGOE focused on the theme of 'Minor Modifications and their Safety Significance', while the SEGHOF focused on the topic 'Human and Organisational Factors in NPP Modifications'. This report is based on material collected before the workshop, the workshop proceedings, discussions of the group of experts responsible for the arrangement of the workshop, and additional material collected by a consultant. The workshop was preceded by extensive preparations, which included collection of national surveys in response to questionnaires on modifications at the NPPs. Not all of these surveys were available at the workshop, but their findings have now been included

An Evaluation of the Physical Environments of a Nuclear Power Plants for Human Factors Review in Periodic Safety Review

International Nuclear Information System (INIS)

Kim, Dae Ho; Lee, Yong Hee

2006-01-01

Currently, operation of a nuclear power plants(NPP) is highly emphasized by the integrity of the H/W and the human factors security, so the periodic safety review(PSR) is performed to NPP. The PSR activities on human factors include physical environments (illumination, noise, vibration, temperature and humidity etc). The review on these physical environments is to verify the possible affect to the human error during the operation of the man machine interface. Physical environments affect the health, job stress and job satisfaction of NPP's employees. On the ground of the reason, we need integrating the management program for the sufficient satisfaction of the regulatory basis and standards of physical environment and considering a health, a job stress and satisfaction of NPP's employees. So, this paper describes the planning of the setup procedures of physical environments and the adequate management program for the field applications in NPPs

An Evaluation of the Physical Environments of a Nuclear Power Plants for Human Factors Review in Periodic Safety Review

Energy Technology Data Exchange (ETDEWEB)

Kim, Dae Ho; Lee, Yong Hee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

2006-07-01

Currently, operation of a nuclear power plants(NPP) is highly emphasized by the integrity of the H/W and the human factors security, so the periodic safety review(PSR) is performed to NPP. The PSR activities on human factors include physical environments (illumination, noise, vibration, temperature and humidity etc). The review on these physical environments is to verify the possible affect to the human error during the operation of the man machine interface. Physical environments affect the health, job stress and job satisfaction of NPP's employees. On the ground of the reason, we need integrating the management program for the sufficient satisfaction of the regulatory basis and standards of physical environment and considering a health, a job stress and satisfaction of NPP's employees. So, this paper describes the planning of the setup procedures of physical environments and the adequate management program for the field applications in NPPs.

Supporting human performance in operations - principles for new nuclear build

International Nuclear Information System (INIS)

Lane, L.; Davey, E.

2006-01-01

Operational experience worldwide continues to demonstrate that human performance is a key factor in the ongoing safety, production, and protection of investment in operation of nuclear plants for electricity generation. Human performance in support of plant operational objectives can be influenced by a range of factors, for example: organizational culture and expectations; role assignments, training, and individual and team behaviours; and the support offered by the workplace environment, tools, and task design. This paper outlines a perspective on some of the principles that should be considered for application in the design of new nuclear build to facilitate support for human performance in plant operations. The principles identified focus on but are not limited to the tasks of shift staff, and are derived from the observations and experience of the authors who are experienced with control room operations in current plants. (author)

Supporting human performance in operations - principles for new nuclear build

Energy Technology Data Exchange (ETDEWEB)

Lane, L. [Ontario Power Generation, Darlington Nuclear Div., Bowmanville, Ontario (Canada); Davey, E. [Crew Systems Solutions, Deep River, Ontario (Canada)

2006-07-01

Operational experience worldwide continues to demonstrate that human performance is a key factor in the ongoing safety, production, and protection of investment in operation of nuclear plants for electricity generation. Human performance in support of plant operational objectives can be influenced by a range of factors, for example: organizational culture and expectations; role assignments, training, and individual and team behaviours; and the support offered by the workplace environment, tools, and task design. This paper outlines a perspective on some of the principles that should be considered for application in the design of new nuclear build to facilitate support for human performance in plant operations. The principles identified focus on but are not limited to the tasks of shift staff, and are derived from the observations and experience of the authors who are experienced with control room operations in current plants. (author)

Long-term research plan for human factors affecting safeguards at nuclear power plants. Volume 1. Summary and users' guide. Vol. 1

International Nuclear Information System (INIS)

O'Brien, J.N.; Fainberg, A.

1984-04-01

This report presents a long-term research plan for addressing human factors which can adversely affect safeguards at nuclear power plants. It was developed in order to prioritize and propose research for NRC in regulating power plant safeguards. Research efforts addressing human factors in safeguards were developed and prioritized according to the importance of human factors areas. Research was also grouped to take advantage of common research approaches and data sources where appropriate. Four main program elements emerged from the analysis, namely (1) Training and Performance Evaluation, (2) Organizational Factors, (3) Man-Machine Interface, and (4) Trustworthiness and Reliability. Within each program element, projects are proposed with results and information flowing between program elements where useful. An overall research plan was developed for a 4-year period and it would lead ultimately to regulatory activities including rulemaking, regulatory guides, and technical bases for regulatory action. The entire plan is summarized in Volume 1 of this report

Considerations of Human Factors in the Design and Operation of Research Reactors

International Nuclear Information System (INIS)

Shokr, A.M.

2015-01-01

The feedback from the severe accidents occurred at nuclear power plants showed that safety of nuclear installations does not depend only on technical matters but also on human performance. Human errors can initiate an event or can make , by intervention, the event consequences worse. Human factors are of a particular importance for research reactors since the status of these facilities change frequently and the operators have an easy access to the reactor core and to the associated experimental facilities. This paper discusses the experience with human factors and their impact on the safety of research reactors and application of technical and administrative provisions to address these factors in the design and operation phases of research reactors for continuous improvements in safety and performance of these facilities

Inhibition of human T cell leukemia virus type 2 replication by the suppressive action of class II transactivator and nuclear factor Y.

Science.gov (United States)

Tosi, Giovanna; Pilotti, Elisabetta; Mortara, Lorenzo; De Lerma Barbaro, Andrea; Casoli, Claudio; Accolla, Roberto S

2006-08-22

The master regulator of MHC-II gene transcription, class II transactivator (CIITA), acts as a potent inhibitor of human T cell leukemia virus type 2 (HTLV-2) replication by blocking the activity of the viral Tax-2 transactivator. Here, we show that this inhibitory effect takes place at the nuclear level and maps to the N-terminal 1-321 region of CIITA, where we identified a minimal domain, from positions 64-144, that is strictly required to suppress Tax-2 function. Furthermore, we show that Tax-2 specifically cooperates with cAMP response element binding protein-binding protein (CBP) and p300, but not with p300/CBP-associated factor, to enhance transcription from the viral promoter. This finding represents a unique difference with respect to Tax-1, which uses all three coactivators to transactivate the human T cell leukemia virus type 1 LTR. Direct sequestering of CBP or p300 is not the primary mechanism by which CIITA causes suppression of Tax-2. Interestingly, we found that the transcription factor nuclear factor Y, which interacts with CIITA to increase transcription of MHC-II genes, exerts a negative regulatory action on the Tax-2-mediated HTLV-2 LTR transactivation. Thus, CIITA may inhibit Tax-2 function, at least in part, through nuclear factor Y. These findings demonstrate the dual defensive role of CIITA against pathogens: it increases the antigen-presenting function for viral determinants and suppresses HTLV-2 replication in infected cells.

Human performance and reliability studies on nuclear power plant

International Nuclear Information System (INIS)

Miyaoka, S.

1988-01-01

The TMI accident in USA, the Chernobyl accident in USSR and other major accidents overseas have shown that it is necessary to investigate and research human factor problems related to operation, maintenance and others in order to increase the safety and reliability of nuclear power plants. Although a variety of countermeasures have been devised, the accidents and failures due to human factors still occur. So far, the problems related to human factors have not been fundamantally and systematically investigated. Also the data base related to this problem has not been developed. Therefore, the government and electric utility industry began the research on the prevention of the accidents caused by human errors. The basic research is carried out by the government, and the applied research is done by electric utility industry. The Central Research Institute of Electric Power Industry established the Human Factors Research Center on July 1, 1987. The research program in the Human Factors Research Center is divided into the basic research to clarity fundamental human characteristics, the systematic research to apply this information and the analytical research on human error experience. These research activities are reported. (Kako, I.)

The human factors of CRT displays for nuclear power plant control

International Nuclear Information System (INIS)

Danchak, M.M.

1984-01-01

This chapter attempts to show how the Cathode Ray Tube (CRT) can be used to effectively present information to the operator rather than just data. The capabilities of the human as a sensing and information processing subsystem are discussed with CRT displays in mind. The display system is described in terms of its hardware and functioning. The interface between the two is examined by providing substantive guidelines for the effective design of CRT displays for nuclear power plant control. Alphanumeric displays, graphic displays, and representational displays are treated. The design of CRT displays for nuclear power plant control requires an extensive knowledge of cognitive psychology, computer display systems and the process being controlled

Human and Organizational Factors

International Nuclear Information System (INIS)

Eshiett, P.B.S.

2016-01-01

The Human and Organizational Factors Approach to Industrial Safety (HOFS) consists of identifying and putting in place conditions which encourage a positive contribution from operators (individually and in a team) with regards to industrial safety. The knowledge offered by the HOFS approach makes it possible better to understand what conditions human activity and to act on the design of occupational situations and the organization, in the aim of creating the conditions for safe work. Efforts made in this area can also lead to an improvement in results in terms of the quality of production or occupational safety (incidence and seriousness rates) (Daniellou, F., et al., 2011). Research on industrial accidents shows that they rarely happen as a result of a single event, but rather emerge from the accumulation of several, often seemingly trivial, malfunctions, misunderstandings, incorrect assumptions and other issues. The nuclear community has established rigorous international safety standards and concepts to ensure the protection of people and the environment from harmful effects of ionizing radiation (IAEA, 2014). A review of major human induced disasters in a number of countries and in different industries yields insights into several of the human and organizational factors involved in their occurrence. Some of these factors relate to failures in: • Design or technology; • Training; • Decision making; • Communication; • Preparation for the unexpected; • Understanding of organizational interdependencies

HUMAN ERROR QUANTIFICATION USING PERFORMANCE SHAPING FACTORS IN THE SPAR-H METHOD

Energy Technology Data Exchange (ETDEWEB)

Harold S. Blackman; David I. Gertman; Ronald L. Boring

2008-09-01

This paper describes a cognitively based human reliability analysis (HRA) quantification technique for estimating the human error probabilities (HEPs) associated with operator and crew actions at nuclear power plants. The method described here, Standardized Plant Analysis Risk-Human Reliability Analysis (SPAR-H) method, was developed to aid in characterizing and quantifying human performance at nuclear power plants. The intent was to develop a defensible method that would consider all factors that may influence performance. In the SPAR-H approach, calculation of HEP rates is especially straightforward, starting with pre-defined nominal error rates for cognitive vs. action-oriented tasks, and incorporating performance shaping factor multipliers upon those nominal error rates.

A Review on the Regulatory Strategy of Human Factors Engineering Consideration in Pakistan Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Sohail, Sabir [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Choi, Seong Nam [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

In this paper, the legal and regulatory infrastructure available in Pakistan for HFE requirements is assessed, and the methodology for strengthening of legal infrastructure is presented. The regulatory strategy on evaluation of HFE consideration should provide reviewers with guidance on review process. Therefore, the suggested methodology is based on preparation of guidance documents such as checklist, working procedures, S and Gs etc.; incorporation of PRM elements in regulatory system; and finally the development of PRM implementation criteria. Altogether, the scheme provide the enhancement in regulatory infrastructure and also the effective and efficient review process. The Three Mile Island (TMI) accident brought the general consensus among the nuclear community on the integration of human factors engineering (HFE) principles in all phases of nuclear power. This notion has further strengthened after the recent Fukushima nuclear accident. Much effort has been put over to incorporate the lesson learned and continuous technical evolution on HFE to device different standards. The total of 174 ergonomics standards are alone identified by Dul et al. (2004) published by International Organization for Standardization (ISO) and the European Committee for Standardization (CEN) and number of standards and HFE guidelines (S and Gs) are also published by organizations like Institute for Electrical and Electronics Engineering (IEEE), International Electrotechnical Commission (IEC), International Atomic Energy Agency (IAEA), United States Nuclear Regulatory Commission (USNRC), etc. The ambition of effective review on HFE integration in nuclear facility might be accomplished through the development of methodology for systematic implementation of S and Gs. Such kind of methodology would also be beneficial for strengthening the regulatory framework and practices for countries new in the nuclear arena and with small scale nuclear program. The objective of paper is to review the

A Recent Revisit Study on the Human Error Events of Nuclear Facilities in Korea

International Nuclear Information System (INIS)

Lee, Y.-H.

2016-01-01

After Fukushima accident we have launched two new projects in Korea. One is for the development of the countermeasures for human errors in nuclear facilities, and the other is for the safety culture of nuclear power plant itself. There had happened several succeeding events that turned out to be the typical flags of the human and organizational factor issues for the safety of the other socio-technical systems as well as nuclear power plants in Korea. The second safety culture project was an ambitious development to establish an infra system utilising system dynamics, business process modeling and big-data techniques to provide effective and efficient information basis to various interest parties related to the nuclear power plants. However the project has been drastically cancelled last year without any further discussion on the original issues raised before in Korea. It may come not only from the conflicting perspectives among the different approaches to nuclear safety culture but also from the misunderstandings on the human factors for the nuclear safety.

Human factors and security in the nuclear and radioactive facilities in Cuba

International Nuclear Information System (INIS)

Ferro Fernandez, R.; Guillen Campos, A.; Ilizastegui Perez, F.

1998-01-01

Considering the wide and multidisciplinary character the topics related with the human factors and the security one believes in the one in CNSN a group gives human factors that has carried out some works in several addresses such form that can be integrated the knowledge and experience in an unique objective to reduce the incidence the human factors in the security starting from a fundamentally preventive work. The present work picks up the main results the developed work

Extraction of human factors issues caused by application of the advanced HSI technology and development of human factor issue management system

Energy Technology Data Exchange (ETDEWEB)

Suh, Sang Moon; Lee, Jung Woon; Park, Jae Chang; Oh, In Seok [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-01-01

A comprehensive literature survey was performed in this study to collect human performance issues related to the advanced HSI design features. The literature from not only nuclear industry but also other industries was collected and reviewed. The issues were categorized into the following advanced HSI design features: devices characteristics, levels of automation, information design and management, display management, computerized controls, alarm systems, computerized procedures, staffing and crew coordination, and operator support systems. The classified issues were described with the description framework. Then, the relationship of issues to HSI design process such as human factors analyses, human factors design, and human factors verification and validation was investigated. Finally, the issue management system of server-client environment was developed using Microsoft's Active Server Page technology and Access 97. (author). 18 refs., 6 figs.

Organizational factors and reoccurrence protection on the JCO nuclear critical accident

International Nuclear Information System (INIS)

Takano, Kenichi

2000-01-01

A nuclear critical accident formed at a nuclear fuel conversion factory in Tokai-mura on September, 1999 became gradually clear not to be a simple human error formed at a level of workmen but to be an organizational error or accident relating to various organizational factors. As a nuclear power facility adopts a depth protection system fundamentally, a large accident with serious danger would not form only by a single trouble and a human error and unless some factors overlaps. By reviewing recent serious accidents and troubles, all of them seem to have a keyword of 'organizational factor'. In the JCO accident, there are some organizational factors such as a climate deviating from a manual, insufficient and loose check against change of procedure, reduction of operators from a reason of profit priority, attitude on priority of working efficiency, and so forth, which are partially common to the Chernobyl accident. Recently, accidents and troubles impossible to make them a cause of simple human error by a person but to have to say an organizational error, have increased. This trend seems to depend upon not only complication and scale-up of technology system but also graduate change of social and management systems operating them. Therefore, it seems to be necessary to introduce a concept of depth protection (multiple protection) in order to keep its reliability and safety when complicating and scaling-up of system. (G.K.)

Organizational factors and nuclear power plant safety

International Nuclear Information System (INIS)

Haber, S.B.

1995-01-01

There are many organizations in our society that depend on human performance to avoid incidents involving significant adverse consequences. As our culture and technology have become more sophisticated, the management of risk on a broad basis has become more and more critical. The safe operation of military facilities, chemical plants, airlines, and mass transit, to name a few, are substantially dependent on the performance of the organizations that operate those facilities. The nuclear power industry has, within the past 15 years, increased the attention given to the influence of human performance in the safe operation of nuclear power plants (NPP). While NPPs have been designed through engineering disciplines to intercept and mitigate events that could cause adverse consequences, it has been clear from various safety-related incidents that human performance also plays a dominant role in preventing accidents. Initial efforts following the 1979 Three Mile Island incident focused primarily on ergonomic factors (e.g., the best design of control rooms for maximum performance). Greater attention was subsequently directed towards cognitive processes involved in the use of NPP decision support systems and decision making in general, personnel functions such as selection systems, and the influence of work scheduling and planning on employees' performance. Although each of these approaches has contributed to increasing the safety of NPPS, during the last few years, there has been a growing awareness that particular attention must be paid to how organizational processes affect NPP personnel performance, and thus, plant safety. The direct importance of organizational factors on safety performance in the NPP has been well-documented in the reports on the Three Mile Island and Chernobyl accidents as well as numerous other events, especially as evaluated by the U.S. Nuclear Regulatory Commission (NRC)

Research on the NPP human factors engineering operating experience review

International Nuclear Information System (INIS)

Ren Xiangchen; Miao Hongxing; Ning Zhonghe

2006-01-01

This paper addresses the importance of the human factors engineering (HFE) for the design of nuclear power plant (NPP), especially for the design of human-machine interface in the NPP. It also summarizes the scope and content of the NPP HFE. The function, scope, content and process of the NPP human factors engineering operating experience review (OER) are mainly focused on, and significantly discussed. Finally, it briefly introduces the situation of the studies on the OER in China. (authors)

Human factors affecting the performance of inspection personnel in nuclear power plants: Final report

International Nuclear Information System (INIS)

Karimi, S.S.

1988-12-01

This study investigates the problem of poor performance among nuclear power plant inspection personnel both in training and in the field. First, a systems perspective is employed to explore the psychological processes and relevant human factors that may be associated with workers' inadequate performance. Second, two separate yet related approaches are used to clarify the definition of competence: (1) a theory-based (or ''top-down'') approach, in which effective performance is construed as a product of a skillful, motivated person interacting with a responsive environment; and (2) an empirical (or ''bottom-up'') approach, in which key persons and context characteristics are generated based on the opinions of experts in the industry. Using a series of semi-structured interviews, two empirical studies were conducted in the latter approach. Overall, the results of both studies converged with the theoretical analysis emphasizing (1) the reciprocal and dynamic interplay of contextual and motivational factors influencing performance, and (2) the salient role of supervisory practices in terms of support, cooperation, and efficiency in contributing to the outcome of performance. 53 refs., 14 figs., 7 tabs

The development and evaluation of human factors guidelines for the review of advanced human-system interfaces

International Nuclear Information System (INIS)

O'Hara, J.M.

1992-01-01

Advanced control rooms for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are approximately 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

Human factors and technology environment in multinational project: problems and solutions; Factores humanos y entorno tecnologico en proyectos multinacionales: dificultades y soluciones

Energy Technology Data Exchange (ETDEWEB)

Jardi Besa, X.; Munoz Cervantes, A.

2012-07-01

At the onset of nuclear projects in Spain, there was an import of nuclear technology. In a second phase, there was a transfer of technology. Subsequently, there was an adaptation of the technology. In this evolution, comparable to that of other countries, were involved several countries, overcoming the difficulties of human factors involved. The current nuclear projects multinationals have a new difficulty: the different industrial technological environments. This paper will address the organizational challenges of multinational engineering projects, in the type of project and the human factors of the participating companies.

Nuclear factor-kappaB activation correlates with better prognosis and Akt activation in human gastric cancer.

Science.gov (United States)

Lee, Byung Lan; Lee, Hye Seung; Jung, Jieun; Cho, Sung Jin; Chung, Hee-Yong; Kim, Woo Ho; Jin, Young-Woo; Kim, Chong Soon; Nam, Seon Young

2005-04-01

Because the biological significance of constitutive nuclear factor-kappaB (NF-kappaB) activation in human gastric cancer is unclear, we undertook this study to clarify the regulatory mechanism of NF-kappaB activation and its clinical significance. Immunohistochemistry for NF-kappaB/RelA was done on 290 human gastric carcinoma specimens placed on tissue array slides. The correlations between NF-kappaB activation and clinicopathologic features, prognosis, Akt activation, tumor suppressor gene expression, or Bcl-2 expression were analyzed. We also did luciferase reporter assay, Western blot analysis, and reverse transcription-PCR using the SNU-216 human gastric cancer cell line transduced with retroviral vectors containing constitutively active Akt or the NF-kappaB repressor mutant of IkappaBalpha. Nuclear expression of RelA was found in 18% of the gastric carcinomas and was higher in early-stage pathologic tumor-node-metastasis (P = 0.019). A negative correlation was observed between NF-kappaB activation and lymphatic invasion (P = 0.034) and a positive correlation between NF-kappaB activation and overall survival rate of gastric cancer patients (P = 0.0228). In addition, NF-kappaB activation was positively correlated with pAkt (P = 0.047), p16 (P = 0.004), adenomatous polyposis coli (P Smad4 (P = 0.002), and kangai 1 (P Akt. NF-kappaB activation was frequently observed in early-stage gastric carcinoma and was significantly correlated with better prognosis and Akt activation. These findings suggest that NF-kappaB activation is a valuable prognostic variable in gastric carcinoma.

Investigations on human error hazards in recent unintended trip events of Korean nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Sa Kil; Jang, Tong Il; Lee, Yong Hee; Shin, Kwang Hyeon [KAERI, Daejeon (Korea, Republic of)

2012-10-15

According to the Operational Performance Information System (OPIS) which has been operated to improve the public understanding by the KINS (Korea Institute of Nuclear Safety), unintended trip events by mainly human errors counted up to 38 cases (18.7%) from 2000 to 2011. Although the Nuclear Power Plant (NPP) industry in Korea has been making efforts to reduce the human errors which have largely contributed to trip events, the human error rate might keep increasing. Interestingly, digital based I and C systems is the one of the reduction factors of unintended reactor trips. Human errors, however, have occurred due to the digital based I and C systems because those systems require new or changed behaviors to the NPP operators. Therefore, it is necessary that the investigations of human errors consider a new methodology to find not only tangible behavior but also intangible behavior such as organizational behaviors. In this study we investigated human errors to find latent factors such as decisions and conditions in the all of the unintended reactor trip events during last dozen years. To find them, we applied the HFACS (Human Factors Analysis and Classification System) which is a commonly utilized tool for investigating human contributions to aviation accidents under a widespread evaluation scheme. The objective of this study is to find latent factors behind of human errors in nuclear reactor trip events. Therefore, a method to investigate unintended trip events by human errors and the results will be discussed in more detail.

Investigations on human error hazards in recent unintended trip events of Korean nuclear power plants

International Nuclear Information System (INIS)

Kim, Sa Kil; Jang, Tong Il; Lee, Yong Hee; Shin, Kwang Hyeon

2012-01-01

According to the Operational Performance Information System (OPIS) which has been operated to improve the public understanding by the KINS (Korea Institute of Nuclear Safety), unintended trip events by mainly human errors counted up to 38 cases (18.7%) from 2000 to 2011. Although the Nuclear Power Plant (NPP) industry in Korea has been making efforts to reduce the human errors which have largely contributed to trip events, the human error rate might keep increasing. Interestingly, digital based I and C systems is the one of the reduction factors of unintended reactor trips. Human errors, however, have occurred due to the digital based I and C systems because those systems require new or changed behaviors to the NPP operators. Therefore, it is necessary that the investigations of human errors consider a new methodology to find not only tangible behavior but also intangible behavior such as organizational behaviors. In this study we investigated human errors to find latent factors such as decisions and conditions in the all of the unintended reactor trip events during last dozen years. To find them, we applied the HFACS (Human Factors Analysis and Classification System) which is a commonly utilized tool for investigating human contributions to aviation accidents under a widespread evaluation scheme. The objective of this study is to find latent factors behind of human errors in nuclear reactor trip events. Therefore, a method to investigate unintended trip events by human errors and the results will be discussed in more detail

A task analysis-linked approach for integrating the human factor in reliability assessments of nuclear power plants

International Nuclear Information System (INIS)

Ryan, T.G.

1988-01-01

This paper describes an emerging Task Analysis-Linked Evaluation Technique (TALENT) for assessing the contributions of human error to nuclear power plant systems unreliability and risk. Techniques such as TALENT are emerging as a recognition that human error is a primary contributor to plant safety, however, it has been a peripheral consideration to data in plant reliability evaluations. TALENT also recognizes that involvement of persons with behavioral science expertise is required to support plant reliability and risk analyses. A number of state-of-knowledge human reliability analysis tools are also discussed which support the TALENT process. The core of TALENT is comprised of task, timeline and interface analysis data which provide the technology base for event and fault tree development, serve as criteria for selecting and evaluating performance shaping factors, and which provide a basis for auditing TALENT results. Finally, programs and case studies used to refine the TALENT process are described along with future research needs in the area. (author)

Human capital in nuclear industry

International Nuclear Information System (INIS)

Anon.

2010-01-01

On June 7, 2010, as part of the Atomexpo 2010 exhibition, a round-table discussion took place on the topic Human capital in the nuclear industry: challenges and solutions. The article summarizes reports made during the meeting. Tatiana Kozhevnikova, deputy director general of the Rosatom Corporation, made a report about the strategy and best human resource management practices in member companies of the Corporation. She briefly described the state of the human capital in the Russian nuclear industry and outlined the key provisions of the human resource management strategy. Attendees to the round-table discussion elaborated further on the key statements of the report. The discussion has given an evidence that the Russian nuclear industry is giving an enormous importance to human resource management and is firmly intended on successfully tacking the issues associated with the provision of sufficient staff for the industry's safe and efficient development [ru

Modelling human factor with Petri nets

International Nuclear Information System (INIS)

Bedreaga, Luminita; Constantinescu, Cristina; Guzun, Basarab

2007-01-01

The human contribution to risk and safety of nuclear power plant operation can be best understood, assessed and quantified using tools to evaluate human reliability. Human reliability analysis becomes an important part of every probabilistic safety assessment and it is used to demonstrate that nuclear power plants designed with different safety levels are prepared to cope with severe accidents. Human reliability analysis in context of probabilistic safety assessment consists in: identifying human-system interactions important to safety; quantifying probabilities appropriate with these interactions. Nowadays, the complex system functions can be modelled using special techniques centred either on states space adequate to system or on events appropriate to the system. Knowing that complex system model consists in evaluating the likelihood of success, in other words, in evaluating the possible value for that system being in some state, the inductive methods which are based on the system states can be applied also for human reliability modelling. Thus, switching to the system states taking into account the human interactions, the underlying basis of the Petri nets can be successfully applied and the likelihoods appropriate to these states can also derived. The paper presents the manner to assess the human reliability quantification using Petri nets approach. The example processed in the paper is from human reliability documentation without a detailed human factor analysis (qualitative). The obtained results by these two kinds of methods are in good agreement. (authors)

Efforts for nuclear energy human resource development by industry-government-academic sectors cooperation. Nuclear Energy Human Resource Development Council Report

International Nuclear Information System (INIS)

Yamamoto, Shinji

2009-01-01

The report consists of eighteen sections such as the present conditions of nuclear energy, decreasing students in the department of technology and decreasing numbers of nuclear-related subjects, The Nuclear Energy Human Resources Development Program (HRD Program), The Nuclear Energy Human Resources Development Council (HRD Council), the industry-academia partnership for human resource development, the present situation of new graduates in the nuclear field, new workers of nuclear industry, the conditions of technical experts in the nuclear energy industry, long-range forecast of human resource, increasing international efforts, nuclear energy human resources development road map, three points for HRD, six basic subjects for HRD, the specific efforts of the industrial, governmental and academic sectors, promoting a better understanding of nuclear energy and supporting job hunting and employment, students to play an active part in the world, and support of the elementary and secondary schools. Change of numbers of nuclear-related subjects of seven universities, change of number of new graduates in nuclear field of various companies from 1985 to 2006, number of people employed by nuclear industries from 1998 to 2007, number of technical experts in the electric companies and the mining and manufacturing industries and forecast of number of technical experts in total nuclear industries are illustrated. (S.Y.)

Human factors engineering in the design of colour-graphic displays

International Nuclear Information System (INIS)

Fenton, E.F.

1985-01-01

The operator interface for Ontario Hydro's Darlington Nuclear Generating Station will rely extensively on the use of coloured graphic display formats. These are used for the presentation of both control and monitoring information. The displays are organized in a hierarchical relationship and a simple interactive selection method using light pens has been implemented. The application of human factors engineering principles has been a major factor in all aspects of the design. This paper describes the system and the human factors engineering function

Nuclear power in human medicine

International Nuclear Information System (INIS)

Kuczera, Bernhard

2012-01-01

The public widely associate nuclear power with the megawatt dimensions of nuclear power plants in which nuclear power is released and used for electricity production. While this use of nuclear power for electricity generation is rejected by part of the population adopting the polemic attitude of ''opting out of nuclear,'' the application of nuclear power in medicine is generally accepted. The appreciative, positive term used in this case is nuclear medicine. Both areas, nuclear medicine and environmentally friendly nuclear electricity production, can be traced back to one common origin, i.e. the ''Atoms for Peace'' speech by U.S. President Eisenhower to the U.N. Plenary Assembly on December 8, 1953. The methods of examination and treatment in nuclear medicine are illustrated in a few examples from the perspective of a nuclear engineer. Nuclear medicine is a medical discipline dealing with the use of radionuclides in humans for medical purposes. This is based on 2 principles, namely that the human organism is unable to distinguish among different isotopes in metabolic processes, and the radioactive substances are employed in amounts so small that metabolic processes will not be influenced. As in classical medicine, the application of these principles serves two complementary purposes: diagnosis and therapy. (orig.)

Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

International Nuclear Information System (INIS)

1997-05-01

In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

Investigation of the factors disguising radiation effects on the human body

International Nuclear Information System (INIS)

Korzeneva, I.B.; Styazhkina, T.V.; Dubrova, Y.E.; Malinina, T.V.; Prokhorovskaya, V.D.; Kholod, O.N.

1998-01-01

Herein we have studied the effects of some hereditary and environmental factors on children's states of health. The factors under investigation, along with radiation, also impact the immunological status and human adaptivity, thus disguising hazardous radiation effects. The state-of-health criterion we have chosen are children's liability to a wide range of intrinsic diseases through the first three years of life. The analysis involved 626 children (326 male and 300 female) who's parents and grandparents lived in the vicinity of the Russian Federal Nuclear Centre (RFNC), a large-scale nuclear facility. Our results should preferably be taken into consideration when projecting radiation effects on the human body. (author)

Human factors review of power plant maintainability. Final report

International Nuclear Information System (INIS)

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

1981-02-01

Human factors engineering is an interdisciplinary science and technology concerned with shaping the design of machines, facilities, and operational environments to promote safe, efficient, and reliable performance on the part of operators and maintainers of equipment systems. The human factors aspects of five nuclear power plants and four fossil fuel plants were evaluated using such methods as a check list guided observation system, structured interviews with maintenance personnel, direct observation of maintenance tasks, reviews of procedures, and analyses of maintenance errors or accidents by means of the critical incident technique. The study revealed a wide variety of human factors problem areas, most of which are extensively photodocumented. The study recommends that a more systematic and formal approach to ensure that future power plants are human engineered to the needs of maintenance personnel

Evidence for site-specific occupancy of the mitochondrial genome by nuclear transcription factors.

Directory of Open Access Journals (Sweden)

Georgi K Marinov

Full Text Available Mitochondria contain their own circular genome, with mitochondria-specific transcription and replication systems and corresponding regulatory proteins. All of these proteins are encoded in the nuclear genome and are post-translationally imported into mitochondria. In addition, several nuclear transcription factors have been reported to act in mitochondria, but there has been no comprehensive mapping of their occupancy patterns and it is not clear how many other factors may also be found in mitochondria. Here we address these questions by using ChIP-seq data from the ENCODE, mouseENCODE and modENCODE consortia for 151 human, 31 mouse and 35 C. elegans factors. We identified 8 human and 3 mouse transcription factors with strong localized enrichment over the mitochondrial genome that was usually associated with the corresponding recognition sequence motif. Notably, these sites of occupancy are often the sites with highest ChIP-seq signal intensity within both the nuclear and mitochondrial genomes and are thus best explained as true binding events to mitochondrial DNA, which exist in high copy number in each cell. We corroborated these findings by immunocytochemical staining evidence for mitochondrial localization. However, we were unable to find clear evidence for mitochondrial binding in ENCODE and other publicly available ChIP-seq data for most factors previously reported to localize there. As the first global analysis of nuclear transcription factors binding in mitochondria, this work opens the door to future studies that probe the functional significance of the phenomenon.

HAMMLAB 2000 for human factor's studies

International Nuclear Information System (INIS)

Kvalem, J.

1999-01-01

The simulator-based Halden Man-Machine Laboratory (HAMMLAB) has, since its establishment in 1983, been the main vehicle for the human-machine systems research at the OECD Halden Reactor Project. The human factors programme relies upon HAMMLAB for performing experimental studies, but the laboratory is also utilised when evaluating computerised operator support systems, and for experimentation with advanced control room prototypes. The increased focus on experimentation as part of the research programme at the Halden Project, has led to a discussion whether today's laboratory will meet the demands of the future. A pre-project concluded with the need for a new laboratory, with extended simulation capabilities. Based upon these considerations, the HAMMLAB 2000 project was initiated with the goal of making HAMMLAB a global centre of excellence for the study of human-technology interaction in the management and control of industrial processes. This paper will focus on human factors studies to be performed in the new laboratory, and which requirements this will bring upon the laboratory infrastructure and simulation capabilities. The aim of the human factors research at the Halden Project is to provide knowledge which can be used by member organisations to enhance safety and efficiency in the operation of nuclear power plants by utilising research about the capabilities and limitations of the human operator in a control room environment. (author)

Human factors perspective on the reliability of NDT in nuclear applications

International Nuclear Information System (INIS)

Bertovic, Marija; Mueller, Christina; Fahlbruch, Babette

2013-01-01

A series of research studies have been conducted over the course of five years venturing into the fields of in-service inspections (ISI) in nuclear power plants (NPPs) and inspection of manufactured components to be used for permanent nuclear waste disposal. This paper will provide an overview of four research studies, present selected experimental results and suggest ways for optimization of the NDT process, procedures, and training. The experimental results have shown that time pressure and mental workload negatively influence the quality of the manual inspection performance. Noticeable were influences of the organization of the working schedule, communication, procedures, supervision, and demonstration task. Customized Failure Mode and Effects Analysis (FMEA) was used to identify potential human risks, arising during acquisition and evaluation of NDT data. Several preventive measures were suggested and furthermore discussed, with respect to problems that could arise from their application. Experimental results show that implementing human redundancy in critical tasks, such as defect identification, as well as using an automated aid (software) to help operators in decision making about the existence and size of defects, could lead to other kinds of problems, namely social loafing and automation bias that might affect the reliability of NDT in an undesired manner. Shifting focus from the operator, as the main source of errors, to the organization, as the underlying source, is a recommended approach to ensure safety. (orig.) [de

Human factors reliability benchmark exercise: a review

International Nuclear Information System (INIS)

Humphreys, P.

1990-01-01

The Human Factors Reliability Benchmark Exercise has addressed the issues of identification, analysis, representation and quantification of Human Error in order to identify the strengths and weaknesses of available techniques. Using a German PWR nuclear powerplant as the basis for the studies, fifteen teams undertook evaluations of a routine functional Test and Maintenance procedure plus an analysis of human actions during an operational transient. The techniques employed by the teams are discussed and reviewed on a comparative basis. The qualitative assessments performed by each team compare well, but at the quantification stage there is much less agreement. (author)

The human factor in operation and maintenance of complex high-reliability systems

International Nuclear Information System (INIS)

Ryan, T.G.

1989-01-01

Human factors issues in probabilistic risk assessment (PRAs) of complex high-reliability systems are addressed. These PRAs influence system operation and technical support programs such as maintainability, test, and surveillance. Using the U.S. commercial nuclear power industry as the setting, the paper addresses the manner in which PRAs currently treat human performance, the state of quantification methods and source data for analyzing human performance, and the role of human factors specialist in the analysis. The paper concludes with a presentation of TALENT, an emerging concept for fully integrating broad-based human factors expertise into the PRA process, is presented. 47 refs

Human factors design, verification, and validation for two types of control room upgrades at a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Boring, Laurids Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-10-01

This paper describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of a new plant process computer (PPC) and turbine control system (TCS) at a representative nuclear power plant. This paper reviews ways to take a human-system interface (HSI) specification and use it when migrating legacy PPC displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then undergo an integrated system validation (ISV) in a full scope control room training simulator. Following the successful demonstration of operator performance with the systems during the ISV, the new system is implemented at the plant, first in the training simulator and then in the main control room.

Human factors design, verification, and validation for two types of control room upgrades at a nuclear power plant

International Nuclear Information System (INIS)

Boring, Laurids Ronald

2014-01-01

This paper describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of a new plant process computer (PPC) and turbine control system (TCS) at a representative nuclear power plant. This paper reviews ways to take a human-system interface (HSI) specification and use it when migrating legacy PPC displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then undergo an integrated system validation (ISV) in a full scope control room training simulator. Following the successful demonstration of operator performance with the systems during the ISV, the new system is implemented at the plant, first in the training simulator and then in the main control room.

The human factors and the safety of experimentation reactors

International Nuclear Information System (INIS)

Jeffroy, F.; Delaporte-Normier, M.L.

2007-01-01

Inside IRSN (Institute for Radiological protection and Nuclear Safety), the mission of the Human Factors Group is to assess the way operators of nuclear installations take into account the risks related to human activities. In the last few years, IRSN has been involved in the safety analysis of different installations where Cea develops research programs, in particular experimental reactors. The first part of this article presents the methodology used by IRSN to evaluate how operators take into account risks related to human activities. This methodology is made up of 4 steps: 1) the identification of the human activities that convey a risk for the installation nuclear safety (safety-sensitive activities), for instance in the case of the Masurca reactor, it has been shown that errors made during the manufacturing of fuel tubes can lead to a criticality accident; 2) listing all the dispositions or arrangements taken to make human safety-sensitive activities more reliable; 3) checking the efficiency of such dispositions or arrangements; and 4) assessing the ability of the operators to generate the adequate dispositions or arrangements. The second part highlights the necessity to develop inside these research installations an organisation that facilitates cooperation between experimenters and operators

Negative transcriptional regulation of mitochondrial transcription factor A (TFAM) by nuclear TFAM

International Nuclear Information System (INIS)

Lee, Eun Jin; Kang, Young Cheol; Park, Wook-Ha; Jeong, Jae Hoon; Pak, Youngmi Kim

2014-01-01

Highlights: • TFAM localizes in nuclei and mitochondria of neuronal cells. • Nuclear TFAM does not bind the Tfam promoter. • Nuclear TFAM reduced the Tfam promoter activity via suppressing NRF-1 activity. • A novel self-negative feedback regulation of Tfam gene expression is explored. • FAM may play different roles depending on its subcellular localizations. - Abstract: The nuclear DNA-encoded mitochondrial transcription factor A (TFAM) is synthesized in cytoplasm and transported into mitochondria. TFAM enhances both transcription and replication of mitochondrial DNA. It is unclear, however, whether TFAM plays a role in regulating nuclear gene expression. Here, we demonstrated that TFAM was localized to the nucleus and mitochondria by immunostaining, subcellular fractionation, and TFAM-green fluorescent protein hybrid protein studies. In HT22 hippocampal neuronal cells, human TFAM (hTFAM) overexpression suppressed human Tfam promoter-mediated luciferase activity in a dose-dependent manner. The mitochondria targeting sequence-deficient hTFAM also repressed Tfam promoter activity to the same degree as hTFAM. It indicated that nuclear hTFAM suppressed Tfam expression without modulating mitochondrial activity. The repression required for nuclear respiratory factor-1 (NRF-1), but hTFAM did not bind to the NRF-1 binding site of its promoter. TFAM was co-immunoprecipitated with NRF-1. Taken together, we suggest that nuclear TFAM down-regulate its own gene expression as a NRF-1 repressor, showing that TFAM may play different roles depending on its subcellular localizations

Understanding human and organisational factors - Nuclear safety and at-risk organisations

International Nuclear Information System (INIS)

Bernard, Benoit

2014-01-01

This book addresses human and organisational factors which are present at different moments of the lifetime of an at-risk installation (from design to dismantling). At-risk organisations are considered as firstly human systems, and the objective is then to highlight individual and collective mechanisms in these organisations. Several questions are addressed, notably the origins of at-risk behaviour, and the reasons of the repetition of errors by these organisations. A first chapter, while referring to examples, addresses the human dimension of safety: human and organisational factors as obstacles, normal accidents (Three Mile Island), accidents in high-reliability organisations (Chernobyl), identification of root causes (Tokai-mura), and social-technical approach to safety (Fukushima). By also referring to examples, the second chapter addresses how to analyse at-risk organisations: individual behaviours (case of naval and air transport accidents), team coordination (a fire, the Challenger accident), and organisational regulation (organisations forms and routines, explosion of BP Texas City, explosion of Columbia)

Human factors engineering program review model

International Nuclear Information System (INIS)

1994-07-01

The staff of the Nuclear Regulatory Commission is performing nuclear power plant design certification reviews based on a design process plan that describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification and an acceptable implemented design. There are two principal reasons for this approach. First, the initial design certification applications submitted for staff review did not include detailed design information. Second, since human performance literature and industry experiences have shown that many significant human factors issues arise early in the design process, review of the design process activities and results is important to the evaluation of an overall design. However, current regulations and guidance documents do not address the criteria for design process review. Therefore, the HFE Program Review Model (HFE PRM) was developed as a basis for performing design certification reviews that include design process evaluations as well as review of the final design. A central tenet of the HFE PRM is that the HFE aspects of the plant should be developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The HFE PRM consists of ten component elements. Each element in divided into four sections: Background, Objective, Applicant Submittals, and Review Criteria. This report describes the development of the HFE PRM and gives a detailed description of each HFE review element

Critical survey of research on human factors and the man-machine interaction

International Nuclear Information System (INIS)

Watson, L.A.

1984-01-01

A case is developed for placing a high priority on research into human factors in the nuclear power industry. This is based essentially on the fact that human error is a significant factor in plant reliability and the assurance of safety. Control of human error can therefore produce benefits in the reduction of both operational costs and public risk. Descriptions are given of activities initiated by the Commission of the European Communities in conjunction with institutes within the Member States. These include: a comprehensive survey and analysis of current relevant work; considerations of classification schemes for human factors activities; the use of simulators for human factors research; and a proposed European collaborative research programme. (author)

Improvements of the Regulatory Framework for Nuclear Installations in the Areas of Human and Organizational Factors and Safety Culture

International Nuclear Information System (INIS)

Tronea, M.; Ciurea, C.

2016-01-01

The paper presents the development of regulatory requirements in the area of human and organizational factors taking account of the lessons learned from major accidents in the nuclear industry and in particular of the factors that contributed to the Fukushima Daiichi accident and the improvement of the regulatory oversight of nuclear safety culture. New requirements have been elaborated by the National Commission for Nuclear Activities Control (CNCAN) on the nuclear safety policy of licencees for nuclear installations, on independent nuclear safety oversight, on safety conscious work environment and on the assessment of nuclear safety culture. The regulatory process for the oversight of nuclear safety culture within licencees’ organizations operating nuclear installations and the associated procedure and guidelines, based on the IAEA Safety Standards, have been developed in 2010-2011. CNCAN has used the 37 IAEA attributes for a strong safety culture, grouped into five areas corresponding to safety culture characteristics, as the basis for its regulatory guidelines providing support to the reviewers and inspectors, in their routine activities, for recognising and gathering information relevant to safety culture. The safety culture oversight process, procedure and guidelines are in process of being reviewed and revised to improve their effectiveness and to align with the current international practices, using lessons learned from the Fukushima Daiichi accident. Starting with July 2014, Romania has a National Strategy for Nuclear Safety and Security, which includes strategic objectives, associated directions for action and concrete actions for promoting nuclear safety culture in all the organizations in the nuclear sector. The progress with the implementation of this strategy with regard to nuclear safety culture is described in the paper. CNCAN started to define its own organizational culture model and identifying the elements that promote and support safety

Modeling for climate change in the aspect of nuclear energy priority: Nuclear power energy-based convergence social-humanity analysis

Energy Technology Data Exchange (ETDEWEB)

Woo, Tae Ho [Systemix Global Co. Ltd., Seoul, (Korea, Republic of)

2015-05-15

Following the industry expansion, the energy consumptions have increased steeply, which have produced the global warming in our lives by carbon production energies. This climate change has provoked significant natural disasters which have damaged to social as well economic matters. Considering the non-carbon production which is the major factor of global warming, nuclear energy is a newly spotlighted source as the green energy source. The climate change factor is affected by the carbon productions made by humans. Then, the nuclear energy increasing rate with the climate change factor affects to the temperature change which is expressed by annual anomaly. Fig. 6 is the protocol for climate change investigation incorporated with the nuclear industry where the climate factor like the temperature is an important index to find out the priority of nuclear energy. The increased environmental pollutions can give the expanding of nuclear energy due to the carbon gas of fossil fuels. This study showed the effectiveness of the nuclear energy by the simulations. The seasonal climate disaster like the very cold winter and very hot summer can increase the necessity of nuclear energy development which could appeal to the general public persons as well as the politicians. So, it is important for the nuclear energy manager to make people understand the importance of the nuclear energy comparing to the oil or coal fuels. The regeneration energy has been considered as the alternative source.

Human factors review of CFMS displays for Ulchin Nuclear Power Unit 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Baek, Seung Min; Kim, Jung Taek; Park, Jae Chang; Lee, Jung Woon; Oh, In Suk; Lee, Joon Whan; Jung, Kwang Tae; Cha, Hye Young [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-11-01

This report describes the human factors review of CFMS displays for Ulchin 3 and 4 by the following four subjects; At first, by reviewing issues regarding the design process of present CFMS, human factors engineering program plan (HFEPP) and human factors verification and validation plan Were proposed to accomplish the completeness of design word; Secondly, researches and developments were integrated into the review results at the point of suitability of CFMS design concept and basic function; For the third, availability and suitability were assessed according to human factors evaluation criteria on the CFMS display design, and overall effectiveness was also evaluated in parts; For the fourth, recommendations were made to human factors problems in accordance with their importance and an implementation plan was suggested for the resolution of problems. 54 refs., 34 tabs., 42 figs. (author)

Human factors estimation methods in nuclear power plant

International Nuclear Information System (INIS)

Takano, Kenichi; Yoshino, Kenji; Nagasaka, Akihiko; Ishii, Keichiro; Nakasa, Hiroyasu

1985-01-01

To improve the operational and maintenance work reliability, it is neccessary for workers to maintain his performance always at high level, that leads to decreasing mistaken judgements and operations. This paper inuolves the development and evaluation of ''Multi-Purpose Physiological Information Measurement system'' to estimate human performance and conditions with a highly fixed quantity. The following itemes is mentioned : (1) Most suitable physiological informations are selected to measure worker' performance in nuclear power plant with none-disturbance, ambulatory, continual, and multi channel measurement. (2) Relatively important physiological informations are measured with the real-time monitoring functions. (electrocardiogram, respirometric functions and EMG (electromyogram) pulse rete). (3) It is made to optimize the measurement condition and analysing methods in the use of a noise-cut function and a D.C. drift cutting method. (4) As a example, it is clear that, when the different weight is loaded to the arm and make it strech-bend motion, the EMG signal is measured and analysed by this system, the analysed EMG pulse rate and maximum amplitude is related to the arm loaded weight. (author)

Bringing organizational factors to the fore of human error management

International Nuclear Information System (INIS)

Embrey, D.

1991-01-01

Human performance problems account for more than half of all significant events at nuclear power plants, even when these did not necessarily lead to severe accidents. In dealing with the management of human error, both technical and organizational factors need to be taken into account. Most important, a long-term commitment from senior management is needed. (author)

Future for nuclear data research. Human resources

International Nuclear Information System (INIS)

Baba, Mamoru

2006-01-01

A comment is given on the problem of human resources to support the future nuclear data activity which will be indispensable for advanced utilization of nuclear energy and radiations. Emphasis is put in the importance of the functional organization among the nuclear data center (JAEA), industries and universities for provision of human resources. (author)

The Security of Russia's Nuclear Arsenal: The Human Factor

International Nuclear Information System (INIS)

Ball, D.Y.

1999-01-01

Assertions by the Russian military that all of their nuclear weapons are secure against theft and that nuclear units within the military are somehow insulated from the problems plaguing the Russian military should not be accepted uncritically. Accordingly, we should not give unwarranted credence to the pronouncements of military figures like Cal.-Gen. Igor Valynkin, Chief of the Defense Ministry's 12th Main Directorate, which oversees the country's nuclear arsenal. He contends that ''Russian nuclear weapons are under reliable supervision'' and that ''talk about the unreliability of our control over nuclear weapons has only one pragmatic goal--to convince international society that the country is incapable of maintaining nuclear safety and to introduce international oversight over those weapons, as it is done, for example, in Iraq.'' While the comparison to Iraq is preposterous, many analysts might agree with Valynkin's sanguine appraisal of the security of Russia's nuclear weapons. In contrast, I argue that the numerous difficulties confronting the military as a whole should cause concern in the West over the security of the Russian nuclear arsenal

Analysis of operational events by ATHEANA framework for human factor modelling

International Nuclear Information System (INIS)

Bedreaga, Luminita; Constntinescu, Cristina; Doca, Cezar; Guzun, Basarab

2007-01-01

In the area of human reliability assessment, the experts recognise the fact that the current methods have not represented correctly the role of human in prevention, initiating and mitigating the accidents in nuclear power plants. The nature of this deficiency appears because the current methods used in modelling of human factor have not taken into account the human performance and reliability such as it has been observed in the operational events. ATHEANA - A Technique for Human Error ANAlysis - is a new methodology for human analysis that has included the specific data of operational events and also psychological models for human behaviour. This method has included new elements such as the unsafe action and error mechanisms. In this paper we present the application of ATHEANA framework in the analysis of operational events that appeared in different nuclear power plants during 1979-2002. The analysis of operational events has consisted of: - identification of the unsafe actions; - including the unsafe actions into a category, omission ar commission; - establishing the type of error corresponding to the unsafe action: slip, lapse, mistake and circumvention; - establishing the influence of performance by shaping the factors and some corrective actions. (authors)

Proceedings of the CSNI WGOE/SEGHOF workshop on modifications at nuclear power plants - Operating experience, safety significance and the role of human factors and organisation

International Nuclear Information System (INIS)

2004-01-01

Operating experience repeatedly shows that changes and modifications at nuclear power plants (NPPs) may lead to safety significant events. At the same time, modifications are necessary to ensure a safe and economic functioning of the NPPs. To ensure the continuing safety of NPPs it is important that processes for change and modification are given proper attention both by the NPPs and the regulators. The operability, maintainability and testability of every modification should be thoroughly assessed from different points of view to ensure that no safety problems are introduced. The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) addressed the issue of modifications at a 'Workshop on Modifications at Nuclear Power Plants - Operating Experience, Safety Significance and Role of Human Factors' held at the OECD headquarters in Paris on October 6 to 8, 2003. This workshop was undertaken as a joint effort of the Working Group on Operating Experience (WGOE) and the Special Experts Group on Human and Organisational Factors (SEGHOF). During the workshop, WGOE focused on the theme of 'Minor Modifications and their Safety Significance', while SEGHOF focused on the topic 'Human and Organisational Factors in NPP Modifications'. The workshop was attended by 55 experts from the industry, regulators and technical support organizations in 15 countries. The workshop programme consisted of plenary and parallel sessions for presentations and discussions. One important part of the workshop was to discuss findings of the WGOE and SEGHOF surveys of utility and regulatory experience from modifications at the NPPs. Modifications at the NPPs are controlled by written procedures. The process varies depending on the type of the modification. Large modifications generally lead to fewer problems, because the projects are given both a great deal of attention and resources. In contrast, minor modifications seem to represent a generic challenge because they are less likely to be

Human factors considerations for reliability and safety

International Nuclear Information System (INIS)

Carnino, A.

1985-01-01

Human factors in many industries have become an important issue, since the last few years. They should be considered during the whole life time of a plant: design, fabrication and construction, licensing, operation. Improvements have been performed in the field of man-machine interface such as procedures, control room lay-out, operator aids, training. In order to meet the needs of reliability and probabilistic risk studies, quantification of human errors has been developed but needs still improvements in the field of cognitive behaviour, diagnosis and representation errors. Data banks to support these quantifications are still in a development stage. This applies to nuclear power plants and several examples are given to illustrate the above ideas. In conclusion, human factors field is in a very quickly evolving process but the tendency is still to adapt the man to the machines whilst the reverse would be desirable

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

Humanity can survive a nuclear war

International Nuclear Information System (INIS)

Greene, J.C.

1985-01-01

In this paper, the author expresses his belief that while a nuclear war would be a horrendous experience, the United States could still survive and ultimately recover. The author describes what the United States would be like two weeks after a full-scale attack against major military targets and population centers. He says about one half of the population will survive but their lifestyles will be drastically different. Although water distribution systems could be damaged and water service interrupted, analysis has shown that in most cases enough drinking water would be available. Food would also not be a serious complicating factor. With the right precautions, there is no intrinsic reason why life-support requirements for the survivors of a nuclear attack should not be met. The author also discusses how epidemics and diseases could be avoided. He also explains why the genetic effects of radiation are misunderstood and why a nuclear war would not cause sufficient mutations to threaten the survival of the society. The author concludes that the argument that a nuclear war could eliminate the human species or bring an end to civilization as we know it has not stood up to the light of objective and scientific examination

Human factors: A major issue in plant aging

International Nuclear Information System (INIS)

Widrig, R.D.

1985-01-01

Humans play a significant role in the effects of aging on safe and reliable operation of nuclear power plants. These human issues may be more important than the issues of materials and component degradation with age. Human actions can accelerate or decelerate physical aging of a plant. And an aging plant can have a significant negative impact on staff quality and performance. The purpose of this paper is to provide some insights into the nature of these human factors issues and their relationship to plant aging. An early awareness of these issues facilitates timely action to at least mitigate these problems before they become insurmountable

Verification and validation of human factors issues in control room design and upgrades

Energy Technology Data Exchange (ETDEWEB)

Green, M.; Collier, S. [Inst. for Energiteknikk, Halden (Norway). OECD Halden Reactor Project

1999-12-01

Systems, facilities and equipment are periodically updated during a power plant's lifetime. This has human factors implications, especially if the central control room is involved. Human factors work may therefore be required. There is an extensive literature on human factors itself, but not so much on how it is verified and validated. Therefore, HRP and the Swedish Nuclear Power Inspectorate commissioned a study. The objective was to review the literature and establish a knowledge base on verification and validation (V and V) of human factors issues. The report first discusses verification and validation as applied to human factors work. It describes a design process and the typical human factors topics involved. It then presents a generic method for V and V of human factors. This is built on a review of standards, guidelines and other references given in an annotated bibliography. The method is illustrated by application to some human factors topics.

Verification and validation of human factors issues in control room design and upgrades

International Nuclear Information System (INIS)

Green, M.; Collier, S.

1999-12-01

Systems, facilities and equipment are periodically updated during a power plant's lifetime. This has human factors implications, especially if the central control room is involved. Human factors work may therefore be required. There is an extensive literature on human factors itself, but not so much on how it is verified and validated. Therefore, HRP and the Swedish Nuclear Power Inspectorate commissioned a study. The objective was to review the literature and establish a knowledge base on verification and validation (V and V) of human factors issues. The report first discusses verification and validation as applied to human factors work. It describes a design process and the typical human factors topics involved. It then presents a generic method for V and V of human factors. This is built on a review of standards, guidelines and other references given in an annotated bibliography. The method is illustrated by application to some human factors topics

Human-machine interactions: The human element of expert systems for the nuclear industry

International Nuclear Information System (INIS)

Nelson, W.R.

1989-01-01

This paper will begin with a brief history of the development of expert systems in the nuclear industry. This discussion will serve to provide the reader with an understanding of how the field of artificial intelligence (AI) applications in the nuclear industry has developed. Next, this paper will discuss the general human factors issues relative to the development and implementation of expert systems for the nuclear industry. It will summarize the relevant research that addresses these issues and identify those areas that need the most effort for success. Since much of the prominent work for the application of expert systems has focused on computerized aids for decisionmaking in emergencies, this paper will draw from this area for its examples. This area tends to highlight the issues because of the safety-critical nature of the application. The same issues, however, are relevant to other applications of expert systems in the nuclear industry as well, even though the consequences of failure may not be as dramatic. (orig./GL)

The Toll-like receptor 1/2 agonists Pam(3) CSK(4) and human β-defensin-3 differentially induce interleukin-10 and nuclear factor-κB signalling patterns in human monocytes.

Science.gov (United States)

Funderburg, Nicholas T; Jadlowsky, Julie K; Lederman, Michael M; Feng, Zhimin; Weinberg, Aaron; Sieg, Scott F

2011-10-01

Human β-defensin 3 (hBD-3) activates antigen-presenting cells through Toll-like receptors (TLRs) 1/2. Several TLR1/2 agonists have been identified but little is known about how they might differentially affect cellular activation. We compared the effects of hBD-3 with those of another TLR1/2 agonist, Pam(3) CSK(4) , in human monocytes. Monocytes incubated with hBD-3 or Pam(3) CSK(4) produced interleukin-6 (IL-6), IL-8 and IL-1β, but only Pam(3) CSK(4) induced IL-10. The IL-10 induction by Pam(3) CSK(4) caused down-modulation of the co-stimulatory molecule, CD86, whereas CD86 expression was increased in monocytes exposed to hBD-3. Assessment of signalling pathways linked to IL-10 induction indicated that mitogen-activated protein kinases were activated similarly by hBD-3 or Pam(3) CSK(4) , whereas the non-canonical nuclear factor-κB pathway was only induced by Pam(3) CSK(4) . Our data suggest that the lack of non-canonical nuclear factor-κB signalling by hBD-3 could contribute to the failure of this TLR agonist to induce production of the anti-inflammatory cytokine, IL-10, in human monocytes. © 2011 The Authors. Immunology © 2011 Blackwell Publishing Ltd.

The proposed human factors engineering program plan for man-machine interface system design of the next generation NPP in Korea

International Nuclear Information System (INIS)

Oh, I.S.; Lee, H.C.; Seo, S.M.; Cheon, S.W.; Park, K.O.; Lee, J.W.; Sim, B.S.

1994-01-01

Human factors application to nuclear power plant (NPP) design, especially, to man-machine interface system (MMIS) design becomes an important issue among the licensing requirements. Recently, the nuclear regulatory bodies require the evidence of systematic human factors application to the MMIS design. Human Factors Engineering Program Plan (HFEPP), as a basis and central one among the human factors application by the MMIS designers. This paper describes the framework of HFEPP for the MMIS design of next generation NPP (NG-NPP) in Korea. This framework provides an integral plan and some bases of the systematic application of human factors to the MMIS design, and consists of purpose and scope, codes and standards, human factors organization, human factors tasks, engineering control methodology, human factors documentations, and milestones. The proposed HFEPP is a top level document to define and describe human factors tasks, based on each step of MMIS design process, in view point of how, what, when and by whom to be performed. (author). 11 refs, 1 fig

The importance of the human factor in a physical protection system

International Nuclear Information System (INIS)

Silva, A.; Rocha, A.

2002-01-01

Full text: A complete physical protection system gathers three elements: equipment's, guards and procedures. The integration of these three elements will guarantee the efficiency of the overall PPS in such a way that it can meet the objectives that were defined during its project: clear and precise procedures will rule the relation between the technical factor (equipments/ hardware and software) and the human factor (guards). The technical factor is easily adapted ad upgraded to continue meet the objectives of the PPS; however, the human factor presents some resistance, internal and external, concerning the performance of its function within the overall PPS. The objective of this paper is to show the importance of the human factor as an integrant part of the PPS of a nuclear facility. 1. Good relationship between guards and other employees in a facility; 2. the knowledge and acceptance of rules and procedures; 3. and the awareness of the needing to implement security measures, as well as the cooperation with these measures to avoid unauthorized nuclear material removal from the facility or sabotage with consequent radioactive release will guarantee the success of the human factor within the overall PPS. In countries where there is no recent record of terrorist activities, as in Brazil's case, these three key factors are particularly critical, once the concept of security culture is not present in those people's way of life. The target public of this survey are the employees, including the guards of the security force, of the CNAAA - Central Nuclear Almirante Alvaro Alberto - consisting of Angra 1 and Angra 2 nuclear power plants. The tools used to came up with the conclusions of this work were two different kinds of questionnaires: a) one of the questionnaires was answered by the guards of the security force concerning their feelings or impressions about other employees' knowledge, acceptance and cooperation of/with the security measures applied on site, and their

The place of human-factors in the work of the Atomic Energy Control Board

International Nuclear Information System (INIS)

Barkow, B.

1982-01-01

The AECB do not effectively regulate human factors in nuclear power plants since they have no staff trained to do so. Two new positions are recommended and their activities are outlined. Special problems are identified in the certification of personnel, management information control, and in accommodating human factors to AECB style

Technological Advances, Human Performance, and the Operation of Nuclear Facilities

Science.gov (United States)

Corrado, Jonathan K.

Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

Human factors evaluation of remote afterloading brachytherapy. Supporting analyses of human-system interfaces, procedures and practices, training and organizational practices and policies. Volume 3

International Nuclear Information System (INIS)

Callan, J.R.; Kelly, R.T.; Quinn, M.L.

1995-07-01

A human factors project on the use of nuclear by-product material to treat cancer using remotely operated afterloaders was undertaken by the Nuclear Regulatory Commission. The purpose of the project was to identify factors that contribute to human error in the system for remote afterloading brachytherapy (RAB). This report documents the findings from the second, third, fourth, and fifth phases of the project, which involved detailed analyses of four major aspects of the RAB system linked to human error: human-system interfaces; procedures and practices; training practices and policies; and organizational practices and policies, respectively. Findings based on these analyses provided factual and conceptual support for the final phase of this project, which identified factors leading to human error in RAB. The impact of those factors on RAB performance was then evaluated and prioritized in terms of safety significance, and alternative approaches for resolving safety significant problems were identified and evaluated

Human factors evaluation of remote afterloading brachytherapy. Supporting analyses of human-system interfaces, procedures and practices, training and organizational practices and policies. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Callan, J.R.; Kelly, R.T.; Quinn, M.L. [Pacific Science & Engineering Group, San Diego, CA (United States)] [and others

1995-07-01

A human factors project on the use of nuclear by-product material to treat cancer using remotely operated afterloaders was undertaken by the Nuclear Regulatory Commission. The purpose of the project was to identify factors that contribute to human error in the system for remote afterloading brachytherapy (RAB). This report documents the findings from the second, third, fourth, and fifth phases of the project, which involved detailed analyses of four major aspects of the RAB system linked to human error: human-system interfaces; procedures and practices; training practices and policies; and organizational practices and policies, respectively. Findings based on these analyses provided factual and conceptual support for the final phase of this project, which identified factors leading to human error in RAB. The impact of those factors on RAB performance was then evaluated and prioritized in terms of safety significance, and alternative approaches for resolving safety significant problems were identified and evaluated.

The nuclear envelopathies and human diseases

Directory of Open Access Journals (Sweden)

Jeang Kuan-Teh

2009-10-01

Full Text Available Abstract The nuclear envelope (NE consists of two membrane layers that segregate the nuclear from the cytoplasmic contents. Recent progress in our understanding of nuclear-lamina associated diseases has revealed intriguing connections between the envelope components and nuclear processes. Here, we review the functions of the nuclear envelope in chromosome organization, gene expression, DNA repair and cell cycle progression, and correlate deficiencies in envelope function with human pathologies.

Human factors activities in teleoperator development at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Draper, J.V.; Herndon, J.N.

1986-01-01

The Consolidated Fuel Reprocessing Program (CFRP) at the Oak Ridge National Laboratory is developing advanced teleoperator systems for maintenance of future nuclear reprocessing facilities. Remote maintenance systems developed by the CFRP emphasize man-in-the-loop teleoperation. Consequently, human factors issues which affect teleoperator performance must be addressed. This papers surveys research and development activities carried out by the human factors group within the Remote Control Engineering Task of the CFRP

A human error probability estimate methodology based on fuzzy inference and expert judgment on nuclear plants

International Nuclear Information System (INIS)

Nascimento, C.S. do; Mesquita, R.N. de

2009-01-01

Recent studies point human error as an important factor for many industrial and nuclear accidents: Three Mile Island (1979), Bhopal (1984), Chernobyl and Challenger (1986) are classical examples. Human contribution to these accidents may be better understood and analyzed by using Human Reliability Analysis (HRA), which has being taken as an essential part on Probabilistic Safety Analysis (PSA) of nuclear plants. Both HRA and PSA depend on Human Error Probability (HEP) for a quantitative analysis. These probabilities are extremely affected by the Performance Shaping Factors (PSF), which has a direct effect on human behavior and thus shape HEP according with specific environment conditions and personal individual characteristics which are responsible for these actions. This PSF dependence raises a great problem on data availability as turn these scarcely existent database too much generic or too much specific. Besides this, most of nuclear plants do not keep historical records of human error occurrences. Therefore, in order to overcome this occasional data shortage, a methodology based on Fuzzy Inference and expert judgment was employed in this paper in order to determine human error occurrence probabilities and to evaluate PSF's on performed actions by operators in a nuclear power plant (IEA-R1 nuclear reactor). Obtained HEP values were compared with reference tabled data used on current literature in order to show method coherence and valid approach. This comparison leads to a conclusion that this work results are able to be employed both on HRA and PSA enabling efficient prospection of plant safety conditions, operational procedures and local working conditions potential improvements (author)

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

Preparation of the requirements for the safety regulation related to human and organizational factors

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The outline of the project in the current fiscal year is to investigate and analyze issues associated with Human and Organizational Factors involved in incidents of nuclear facilities, and to study and develop evaluation methods of these countermeasures. The guideline to evaluate licensee's safety culture and root cause analysis (RCA) had been developed for further improving safety on nuclear power plants at 2007. These guidelines have been used at regulatory inspection since that time. Based on experience of using these existing guidelines, some activities for improving guidelines are now under investigation; these are selecting candidate quantitative indicators for safety culture evaluation and researching good practices for RCA issues. JNES implemented human factor analysis about 18 domestic events including the Fukushima Dai-ichi nuclear power plant accident. (author)

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.

A study on the human factors of nuclear power plants man-machine interface

International Nuclear Information System (INIS)

Shin, Hyun Kook; Lee, Jeong Woon; Lee, Yong Hee; Oh, In Suk; Park, Geun Ok

1991-01-01

Approaches of the MMIS design were analysed in this project. Both systems approach and experimental approach were studied. In addition, guidelines for the design of MMI are discussed. The methodology of experimental approach studied in this project can be useful for establishing experimental criteria on MMI design items. The framework of a computer code was developed by utilizing function-based task analysis and procedure information requirements. This can be further developed as a tool useful for the verification and validation of MMI designs. A test facility was designed in compliance with the purpose of experimental approach by considering specific conditions and factors inherent in nuclear power plants. Test facility can be used for conducting experiments which provide detailed human performance and characteristics data at the low level of systems approach. An experimental study was performed to obtain a range of illumination levels suitable for the operation in VDU-based control rooms. Existing design guidelines were tested by this experimental study. A conceptual design of MMIS was developed in accordance with the established MMIS design approach and was evaluated through the comparison to other advanced control room designs. (Author)

Sensitivity evaluation of human factors for reliability of the containment spray system

International Nuclear Information System (INIS)

Tsujimura, Yasuhiro; Suzuki, Eiji

1988-01-01

Evaluation of the human reliability is one of the most difficult problems that deal with the safety and reliability of large systems, especially of the Engineered Safety Features (ESF) of the nuclear power plant. Influences of human factors on the reliability of the Containment Spray System in the ESF were estimated by using the FTA method in this paper. As a result, the adequacy of the system structure and the effects of human factors on variations of the design of the system structure were explained. (author)

Human Factors Engineering and Ergonomics Analysis for the Canister Storage Building (CSB) Results and Findings

International Nuclear Information System (INIS)

GARVIN, L.J.

1999-01-01

The purpose for this supplemental report is to follow-up and update the information in SNF-3907, Human Factors Engineering (HFE) Analysis: Results and Findings. This supplemental report responds to applicable U.S. Department of Energy Safety Analysis Report review team comments and questions. This Human Factors Engineering and Ergonomics (HFE/Erg) analysis was conducted from April 1999 to July 1999; SNF-3907 was based on analyses accomplished in October 1998. The HFE/Erg findings presented in this report and SNF-3907, along with the results of HNF-3553, Spent Nuclear Fuel Project, Final Safety Analysis Report. Annex A, ''Canister Storage Building Final Safety Analysis Report,'' Chapter A3.0, ''Hazards and Accidents Analyses,'' provide the technical basis for preparing or updating HNF-3553, Annex A, Chapter A13.0, ''Human Factors Engineering.'' The findings presented in this report allow the HNF-3553 Chapter 13.0, ''Human Factors,'' to respond fully to the HFE requirements established in DOE Order 5480.23, Nuclear Safety Analysis Reports

Human Factors Engineering and Ergonomics Analysis for the Canister Storage Building (CSB): Results and Findings

International Nuclear Information System (INIS)

GARVIN, L.J.

1999-01-01

The purpose for this supplemental report is to follow-up and update the information in SNF-3907, Human Factors Engineering (HFE) Analysis: Results and Findings. This supplemental report responds to applicable U.S. Department of Energy Safety Analysis Report review team comments and questions. This Human Factors Engineering and Ergonomics (HFE/Erg) analysis was conducted from April 1999 to July 1999; SNF-3907 was based on analyses accomplished in October 1998. The HFE/Erg findings presented in this report and SNF-3907, along with the results of HNF-3553, Spent Nuclear Fuel Project, Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report,'' Chapter A3.0, ''Hazards and Accidents Analyses,'' provide the technical basis for preparing or updating HNF-3553. Annex A, Chaptex A13.0, ''Human Factors Engineering.'' The findings presented in this report allow the HNF-3553 Chapter 13.0, ''Human Factors,'' to respond fully to the HFE requirements established in DOE Order 5480.23, Nuclear Safety Analysis Reports

Some recent human performance issues at U.S. nuclear plants

International Nuclear Information System (INIS)

Kauffman, John V.

1998-01-01

Some recent events at U.S. operating nuclear power plants revealed interesting human performance issues. Events discussed in this paper are: (1) a September 1996 event at Clinton, (2) a February 1997 event at Zion 1, and (3) March 1997 operator failures of 'in-house' examinations at LaSalle. The specific human performance weaknesses exhibited in these events, some underlying organizational or institutional issues and factors which influenced operators and their management, and implications regarding regulatory oversight are discussed. (author)

IAEA Nuclear Security Human Resource Development Program

International Nuclear Information System (INIS)

Braunegger-Guelich, A.

2009-01-01

The IAEA is at the forefront of international efforts to strengthen the world's nuclear security framework. The current Nuclear Security Plan for 2006-2009 was approved by the IAEA Board of Governors in September 2005. This Plan has three main points of focus: needs assessment, prevention, detection and response. Its overall objective is to achieve improved worldwide security of nuclear and other radioactive material in use, storage and transport, and of their associated facilities. This will be achieved, in particular, through the provision of guidelines and recommendations, human resource development, nuclear security advisory services and assistance for the implementation of the framework in States, upon request. The presentation provides an overview of the IAEA nuclear security human resource development program that is divided into two parts: training and education. Whereas the training program focuses on filling gaps between the actual performance of personnel working in the area of nuclear security and the required competencies and skills needed to meet the international requirements and recommendations described in UN and IAEA documents relating to nuclear security, the Educational Program in Nuclear Security aims at developing nuclear security experts and specialists, at fostering a nuclear security culture and at establishing in this way sustainable knowledge in this field within a State. The presentation also elaborates on the nuclear security computer based learning component and provides insights into the use of human resource development as a tool in achieving the IAEA's long term goal of improving sustainable nuclear security in States. (author)

A sample application of nuclear power human resources model

International Nuclear Information System (INIS)

Gurgen, A.; Ergun, S.

2016-01-01

One of the most important issues for a new comer country initializing the nuclear power plant projects is to have both quantitative and qualitative models for the human resources development. For the quantitative model of human resources development for Turkey, “Nuclear Power Human Resources (NPHR) Model” developed by the Los Alamos National Laboratory was used to determine the number of people that will be required from different professional or occupational fields in the planning of human resources for Akkuyu, Sinop and the third nuclear power plant projects. The number of people required for different professions for the Nuclear Energy Project Implementation Department, the regulatory authority, project companies, construction, nuclear power plants and the academy were calculated. In this study, a sample application of the human resources model is presented. The results of the first tries to calculate the human resources needs of Turkey were obtained. Keywords: Human Resources Development, New Comer Country, NPHR Model

The human factor in high-tech plant operation

Energy Technology Data Exchange (ETDEWEB)

Grassani, E

1988-02-01

The article develops a series of considerations on reliability standards applied to operators of technologically complex industrial installations. From research conducted within the field of cognitive psychology, significant indications are emerging relative to professional training within industry, as well as to the functional and human interface characteristics of automated control systems. Recent tragic incidents (Three Mile Island nuclear power plant, Bopal methyl isocynate storage, Mexico City petroleum tank farm and Chernobylsk-4 reactor) have evidenced the greater weight that should be given to human factors in plant safety and reliability assessments and planning.

Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

Energy Technology Data Exchange (ETDEWEB)

Vasconcelos, Vanderley de; Soares, Wellington Antonio; Marques, Raíssa Oliveira; Silva Júnior, Silvério Ferreira da; Raso, Amanda Laureano, E-mail: vasconv@cdtn.br, E-mail: soaresw@cdtn.br, E-mail: raissaomarques@gmail.com, E-mail: silvasf@cdtn.br, E-mail: amandaraso@hotmail.com [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. NDI is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI methods are reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components. Among these can be highlighted Failure Modes and Effects Analysis (FMEA) and THERP (Technique for Human Error Rate Prediction). The application of these techniques is illustrated in an example of qualitative and quantitative studies to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues. (author)

Human reliability in non-destructive inspections of nuclear power plant components: modeling and analysis

International Nuclear Information System (INIS)

Vasconcelos, Vanderley de; Soares, Wellington Antonio; Marques, Raíssa Oliveira; Silva Júnior, Silvério Ferreira da; Raso, Amanda Laureano

2017-01-01

Non-destructive inspection (NDI) is one of the key elements in ensuring quality of engineering systems and their safe use. NDI is a very complex task, during which the inspectors have to rely on their sensory, perceptual, cognitive, and motor skills. It requires high vigilance once it is often carried out on large components, over a long period of time, and in hostile environments and restriction of workplace. A successful NDI requires careful planning, choice of appropriate NDI methods and inspection procedures, as well as qualified and trained inspection personnel. A failure of NDI to detect critical defects in safety-related components of nuclear power plants, for instance, may lead to catastrophic consequences for workers, public and environment. Therefore, ensuring that NDI methods are reliable and capable of detecting all critical defects is of utmost importance. Despite increased use of automation in NDI, human inspectors, and thus human factors, still play an important role in NDI reliability. Human reliability is the probability of humans conducting specific tasks with satisfactory performance. Many techniques are suitable for modeling and analyzing human reliability in NDI of nuclear power plant components. Among these can be highlighted Failure Modes and Effects Analysis (FMEA) and THERP (Technique for Human Error Rate Prediction). The application of these techniques is illustrated in an example of qualitative and quantitative studies to improve typical NDI of pipe segments of a core cooling system of a nuclear power plant, through acting on human factors issues. (author)

AMPK activation represses the human gene promoter of the cardiac isoform of acetyl-CoA carboxylase: Role of nuclear respiratory factor-1

Energy Technology Data Exchange (ETDEWEB)

Adam, Tasneem; Opie, Lionel H. [Hatter Cardiovascular Research Institute, Faculty of Health Sciences, University of Cape Town, Observatory 7925 (South Africa); Essop, M. Faadiel, E-mail: mfessop@sun.ac.za [Cardio-Metabolic Research Group (CMRG), Department of Physiological Sciences, Stellenbosch University, Stellenbosch 7600 (South Africa)

2010-07-30

Research highlights: {yields} AMPK inhibits acetyl-CoA carboxylase beta gene promoter activity. {yields} Nuclear respiratory factor-1 inhibits acetyl-CoA carboxylase beta promoter activity. {yields} AMPK regulates acetyl-CoA carboxylase beta at transcriptional level. -- Abstract: The cardiac-enriched isoform of acetyl-CoA carboxylase (ACC{beta}) produces malonyl-CoA, a potent inhibitor of carnitine palmitoyltransferase-1. AMPK inhibits ACC{beta} activity, lowering malonyl-CoA levels and promoting mitochondrial fatty acid {beta}-oxidation. Previously, AMPK increased promoter binding of nuclear respiratory factor-1 (NRF-1), a pivotal transcriptional modulator controlling gene expression of mitochondrial proteins. We therefore hypothesized that NRF-1 inhibits myocardial ACC{beta} promoter activity via AMPK activation. A human ACC{beta} promoter-luciferase construct was transiently transfected into neonatal cardiomyocytes {+-} a NRF-1 expression construct. NRF-1 overexpression decreased ACC{beta} gene promoter activity by 71 {+-} 4.6% (p < 0.001 vs. control). Transfections with 5'-end serial promoter deletions revealed that NRF-1-mediated repression of ACC{beta} was abolished with a pPII{beta}-18/+65-Luc deletion construct. AMPK activation dose-dependently reduced ACC{beta} promoter activity, while NRF-1 addition did not further decrease it. We also investigated NRF-1 inhibition in the presence of upstream stimulatory factor 1 (USF1), a known transactivator of the human ACC{beta} gene promoter. Here NRF-1 blunted USF1-dependent induction of ACC{beta} promoter activity by 58 {+-} 7.5% (p < 0.001 vs. control), reversed with a dominant negative NRF-1 construct. NRF-1 also suppressed endogenous USF1 transcriptional activity by 55 {+-} 6.2% (p < 0.001 vs. control). This study demonstrates that NRF-1 is a novel transcriptional inhibitor of the human ACC{beta} gene promoter in the mammalian heart. Our data extends AMPK regulation of ACC{beta} to the transcriptional level.

Protective effect of nuclear factor E2-related factor 2 on inflammatory cytokine response to brominated diphenyl ether-47 in the HTR-8/SVneo human first trimester extravillous trophoblast cell line.

Science.gov (United States)

Park, Hae-Ryung; Loch-Caruso, Rita

2014-11-15

Polybrominated diphenyl ethers (PBDEs) are widely used flame retardants, and BDE-47 is a prevalent PBDE congener detected in human tissues. Exposure to PBDEs has been linked to adverse pregnancy outcomes in humans. Although the underlying mechanisms of adverse birth outcomes are poorly understood, critical roles for oxidative stress and inflammation are implicated. The present study investigated antioxidant responses in a human extravillous trophoblast cell line, HTR-8/SVneo, and examined the role of nuclear factor E2-related factor 2 (Nrf2), an antioxidative transcription factor, in BDE-47-induced inflammatory responses in the cells. Treatment of HTR-8/SVneo cells with 5, 10, 15, and 20μM BDE-47 for 24h increased intracellular glutathione (GSH) levels compared to solvent control. Treatment of HTR-8/SVneo cells with 20μM BDE-47 for 24h induced the antioxidant response element (ARE) activity, indicating Nrf2 transactivation by BDE-47 treatment, and resulted in differential expression of redox-sensitive genes compared to solvent control. Pretreatment with tert-butyl hydroquinone (tBHQ) or sulforaphane, known Nrf2 inducers, reduced BDE-47-stimulated IL-6 release with increased ARE reporter activity, reduced nuclear factor kappa B (NF-κB) reporter activity, increased GSH production, and stimulated expression of antioxidant genes compared to non-Nrf2 inducer pretreated groups, suggesting that Nrf2 may play a protective role against BDE-47-mediated inflammatory responses in HTR-8/SVneo cells. These results suggest that Nrf2 activation significantly attenuated BDE-47-induced IL-6 release by augmentation of cellular antioxidative system via upregulation of Nrf2 signaling pathways, and that Nrf2 induction may be a potential therapeutic target to reduce adverse pregnancy outcomes associated with toxicant-induced oxidative stress and inflammation. Copyright © 2014 Elsevier Inc. All rights reserved.

Identification of a putative nuclear export signal motif in human NANOG homeobox domain

International Nuclear Information System (INIS)

Park, Sung-Won; Do, Hyun-Jin; Huh, Sun-Hyung; Sung, Boreum; Uhm, Sang-Jun; Song, Hyuk; Kim, Nam-Hyung; Kim, Jae-Hwan

2012-01-01

Highlights: ► We found the putative nuclear export signal motif within human NANOG homeodomain. ► Leucine-rich residues are important for human NANOG homeodomain nuclear export. ► CRM1-specific inhibitor LMB blocked the potent human NANOG NES-mediated nuclear export. -- Abstract: NANOG is a homeobox-containing transcription factor that plays an important role in pluripotent stem cells and tumorigenic cells. To understand how nuclear localization of human NANOG is regulated, the NANOG sequence was examined and a leucine-rich nuclear export signal (NES) motif ( 125 MQELSNILNL 134 ) was found in the homeodomain (HD). To functionally validate the putative NES motif, deletion and site-directed mutants were fused to an EGFP expression vector and transfected into COS-7 cells, and the localization of the proteins was examined. While hNANOG HD exclusively localized to the nucleus, a mutant with both NLSs deleted and only the putative NES motif contained (hNANOG HD-ΔNLSs) was predominantly cytoplasmic, as observed by nucleo/cytoplasmic fractionation and Western blot analysis as well as confocal microscopy. Furthermore, site-directed mutagenesis of the putative NES motif in a partial hNANOG HD only containing either one of the two NLS motifs led to localization in the nucleus, suggesting that the NES motif may play a functional role in nuclear export. Furthermore, CRM1-specific nuclear export inhibitor LMB blocked the hNANOG potent NES-mediated export, suggesting that the leucine-rich motif may function in CRM1-mediated nuclear export of hNANOG. Collectively, a NES motif is present in the hNANOG HD and may be functionally involved in CRM1-mediated nuclear export pathway.

Status of human factors research program in Central Research Institute of Electric Power Industry

International Nuclear Information System (INIS)

Kabetani, Tetsuji

1989-01-01

The Human Factors Research Center was established within CRIEPI on July 1, 1987 as its research efforts to reduce human error during operation and maintenance at Japanese nuclear power plants. The Research Program has seven subjects, composed of the original subjects that include the human behavior monitoring method, and the subjects requested by the Federation of Electric Power Companies that include the establishment of techniques of analysing and evaluating information on human error. Some results of the activity are applied in nuclear power plants. We plan to obtain good results to apply to plants, and to improve the results already obtained. (author)

Establishing the Appropriate Attributes in Current Human Reliability Assessment Techniques for Nuclear Safety

International Nuclear Information System (INIS)

Bowie, Jane; Munley, Gary; Dang, Vinh; Wreathall, John; Bye, Andreas; Cooper, Susan; Marble, Julie; Peters, Sean; Xing, Jing; Fauchille, Veronique; Fiset, Jean Yves; Haage, Monica; Johanson, Gunnar; Jung, Won Dae; Kim, Jaewhan; Lee, Seung Jung; Kubicek, Jan; Le Bot, Pierre; Pesme, Helene; Preischl, Wolfgang; Salway, Alice; Amri, Abdallah; Lamarre, Greg; White, Andrew; )

2015-03-01

This report presents the results of a joint task of the Working Groups on Risk Assessment (WGRISK) and on Human and Organisational Factors (WGHOF) of the OECD/NEA CSNI, to identify desirable attributes of Human Reliability Assessment (HRA) methods, and to evaluate a range of HRA methods used in OECD member countries against those attributes. The purpose of this project is to provide information that will support regulators and operators of nuclear facilities when making judgements about the appropriateness of HRA methods for conducting assessments in support of Probabilistic Safety Assessments (PSA). The task was performed by an international team of Human Factors, HRA and PSA experts from a broad range of OECD member countries. As in other reviews of HRA methods, the study did not set out to recommend or promote the use of any particular HRA method. Rather the study aims to identify the strengths and limitations of commonly used and developing methods to aid those responsible for production of HRAs in selecting appropriate tools for specific HRA applications. The study also aims to assist regulators when making judgements on the appropriateness of the application of an HRA technique within nuclear-related probabilistic safety assessments. The report is aimed at practitioners in the field of human reliability assessment, human factors, and risk assessment more generally

Factors affecting nuclear development

International Nuclear Information System (INIS)

Stevens, G.H.; Girouard, P.

1995-01-01

Among the factors affecting nuclear development, some depend more or less on public authorities, but many are out of public authorities control (foreign policies, market and deregulation, socials and environmental impacts, public opinion). As far as possible, the following study tries to identify those factors. (D.L.). 2 photos

Nuclear Factor-kappaB in Autoimmunity: Man and Mouse.

Science.gov (United States)

Miraghazadeh, Bahar; Cook, Matthew C

2018-01-01

NF-κB (nuclear factor-kappa B) is a transcription complex crucial for host defense mediated by innate and adaptive immunity, where canonical NF-κB signaling, mediated by nuclear translocation of RelA, c-Rel, and p50, is important for immune cell activation, differentiation, and survival. Non-canonical signaling mediated by nuclear translocation of p52 and RelB contributes to lymphocyte maturation and survival and is also crucial for lymphoid organogenesis. We outline NF-κB signaling and regulation, then summarize important molecular contributions of NF-κB to mechanisms of self-tolerance. We relate these mechanisms to autoimmune phenotypes described in what is now a substantial catalog of immune defects conferred by mutations in NF-κB pathways in mouse models. Finally, we describe Mendelian autoimmune syndromes arising from human NF-κB mutations, and speculate on implications for understanding sporadic autoimmune disease.

Nuclear Factor kappa B is required for the production of infectious human herpesvirus 8 virions

Directory of Open Access Journals (Sweden)

Negin N Blattman

2014-04-01

Full Text Available Human herpesvirus 8 (HHV8 infection leads to potent activation of nuclear factor kappa B (NFB in primary and transformed cells. We used recombinant HHV8 (rKSHV.219 expressing green fluorescent protein under the constitutive cellular promoter elongation factor 2 and red fluorescent protein under an early HHV8 lytic gene promoter T1.1, to monitor replication during infection of human foreskin fibroblasts (HF, noting changes in NFB activity. In primary HF, NFB levels do not affect HHV8 ability to establish infection or maintain latency. Furthermore, there was no effect on the percent of cells undergoing reactivation from latency, and there were similar numbers of released and cell associated HHV8 viral particles following reactivation in the presence of inhibitors. Reactivation of HHV8 in latently infected HF in the presence of NFB inhibitors resulted in production of viral particles that did not efficiently establish infection, due to deficiencies in binding and/or entry into normally permissive cells. Exogenous expression of glycoprotein M, an envelope protein involved in viral binding and entry was able to partially overcome the deficiency induced by NFB inhibitors. Our data indicate that in primary cells, NFB is not required for infection, establishment of latency, or entry into the lytic cycle, but is required for the expression of virion associated genes involved in the initial steps of virion infectivity. These studies suggest that strategies to inhibit NFB may prevent HHV8 spread and should be considered as a potential therapeutic target for preventing HHV8 associated diseases.

Human factors estimation method in nuclear power plants

International Nuclear Information System (INIS)

Takano, Kenichi; Yoshino, Kenji; Nagasaka, Akihiko

1987-01-01

It is need for improving a NPS reliability to prevent human-errors of operators in a control room. Especially, the time error or omission error may be often caused by a exceed of the mental work load. Therefore, in order to decrease such kinds of human errors, not only the planning of an equipment and a console is well considered about proper level of mental work load but also the exceeded mental work load must be let down by trainning etc. This paper present measurement techniques of the mental work load by physiological informations and the relation between the error rate and mental work load on the basis of the experiment by various modeled tasks. Following results are obtained. (1) TSF, the indicator of the mental work load, is well correlated to the subsidary task reaction time. Therefore it is able to estimate the TSF by subsidary tasks if the task was loaded instanteniously with main task. (2) The relation between the TSF and GSR pulses rate has a 0.81 correlation factor except the case of a parallel processing task. Because we can evaluate the mental work load by the measurement of the GSR pulses rate if the task was processed by a single channel. But if uses GSR, the atomospheric condition is kept constant and the arousal level must be at the well stage. (3) The human error is greatly increase when the TSF exceed above 60 %, that values are almost agreed to the tolerance limit of the TTS methods. (author)

Power peaking nuclear reliability factors

International Nuclear Information System (INIS)

Hassan, H.A.; Pegram, J.W.; Mays, C.W.; Romano, J.J.; Woods, J.J.; Warren, H.D.

1977-11-01

The Calculational Nuclear Reliability Factor (CNRF) assigned to the limiting power density calculated in reactor design has been determined. The CNRF is presented as a function of the relative power density of the fuel assembly and its radial local. In addition, the Measurement Nuclear Reliability Factor (MNRF) for the measured peak hot pellet power in the core has been evaluated. This MNRF is also presented as a function of the relative power density and radial local within the fuel assembly

The contribution of human factors to accidents in the offshore oil industry

International Nuclear Information System (INIS)

Gordon, Rachael P.E.

1998-01-01

Accidents such as the Piper Alpha disaster illustrate that the performance of a highly complex socio-technical system, is dependent upon the interaction of technical, human, social, organisational, managerial and environmental factors and that these factors can be important co-contributors that could potentially lead to a catastrophic event. The purpose of this article is to give readers an overview of how human factors contribute to accidents in the offshore oil industry. An introduction to human errors and how they relate to human factors in general terms is given. From here the article discusses some of the human factors which were found to influence safety in other industries and describes the human factors codes used in accident reporting forms in the aviation, nuclear and marine industries. Analysis of 25 accident reporting forms from offshore oil companies in the UK sector of the North Sea was undertaken in relation to the human factors. Suggestions on how these accident reporting forms could be improved are given. Finally, this article describes the methods by which accidents can be reduced by focusing on the human factors, such as feedback from accident reporting in the oil industry, auditing of unsafe acts and auditing of latent failures

Human factors and nuclear space technology in long-term exploration

International Nuclear Information System (INIS)

Brown-VanHoozer, S.A.; VanHoozer, W.R.

2000-01-01

Allocation of manual versus automated tasks for operation and maintenance of nuclear power systems in space will be crucial at the onset and at the return of a space flight. Such factors as space adaptation syndrome (SAS), a temporary space motion sickness that has affected 40 to 50% of crew members on past space flights, can result in lost effort ranging from a few hours to a full day. This could have a significant impact on manual performance where high levels of execution are likely to be required in the very early stages of the mission. Other considerations involving higher-level behavioral phenomena such as interpersonal and group processes, individual belief systems, social and motivational factors, and (subjective) cognitive function have received little attention; nevertheless these will be essential elements for success in long-term exploration. Understanding that long-term space flight missions may create groups that become unique societies distinct unto themselves will test current ethical, moral, and social belief systems, requiring one to examine the amalgamation as well as organizational structures for the safety and balance of the crew

Investigation of human system interface design in nuclear power plant

International Nuclear Information System (INIS)

Feng Yan; Zhang Yunbo; Wang Zhongqiu

2012-01-01

The paper introduces the importance of HFE in designing nuclear power plant, and introduces briefly the content and scope of HFE, discusses human system interface design of new built nuclear power plants. This paper also describes human system interface design of foreign nuclear power plant, and describes in detail human system interface design of domestic nuclear power plant. (authors)

Nuclear Factor Erythroid 2 Regulates Human HSC Self-Renewal and T Cell Differentiation by Preventing NOTCH1 Activation.

Science.gov (United States)

Di Tullio, Alessandro; Passaro, Diana; Rouault-Pierre, Kevin; Purewal, Sukhveer; Bonnet, Dominique

2017-07-11

Nuclear factor erythroid-derived 2 (NF-E2) has been associated with megakaryocyte maturation and platelet production. Recently, an increased in NF-E2 activity has been implicated in myeloproliferative neoplasms. Here, we investigate the role of NF-E2 in normal human hematopoiesis. Knockdown of NF-E2 in the hematopoietic stem and progenitor cells (HSPCs) not only reduced the formation of megakaryocytes but also drastically impaired hematopoietic stem cell activity, decreasing human engraftment in immunodeficient (NSG) mice. This phenotype is likely to be related to both increased cell proliferation (p21-mediated) and reduced Notch1 protein expression, which favors HSPC differentiation over self-renewal. Strikingly, although NF-E2 silencing in HSPCs did not affect their myeloid and B cell differentiation in vivo, it almost abrogated T cell production in primary hosts, as confirmed by in vitro studies. This effect is at least partly due to Notch1 downregulation in NF-E2-silenced HSPCs. Together these data reveal that NF-E2 is an important driver of human hematopoietic stem cell maintenance and T lineage differentiation. Copyright © 2017 The Author(s). Published by Elsevier Inc. All rights reserved.

Nuclear Factor Erythroid 2 Regulates Human HSC Self-Renewal and T Cell Differentiation by Preventing NOTCH1 Activation

Directory of Open Access Journals (Sweden)

Alessandro Di Tullio

2017-07-01

Full Text Available Nuclear factor erythroid-derived 2 (NF-E2 has been associated with megakaryocyte maturation and platelet production. Recently, an increased in NF-E2 activity has been implicated in myeloproliferative neoplasms. Here, we investigate the role of NF-E2 in normal human hematopoiesis. Knockdown of NF-E2 in the hematopoietic stem and progenitor cells (HSPCs not only reduced the formation of megakaryocytes but also drastically impaired hematopoietic stem cell activity, decreasing human engraftment in immunodeficient (NSG mice. This phenotype is likely to be related to both increased cell proliferation (p21-mediated and reduced Notch1 protein expression, which favors HSPC differentiation over self-renewal. Strikingly, although NF-E2 silencing in HSPCs did not affect their myeloid and B cell differentiation in vivo, it almost abrogated T cell production in primary hosts, as confirmed by in vitro studies. This effect is at least partly due to Notch1 downregulation in NF-E2-silenced HSPCs. Together these data reveal that NF-E2 is an important driver of human hematopoietic stem cell maintenance and T lineage differentiation.

Human errors and work performance in a nuclear power plant control room: associations with work-related factors and behavioral coping

International Nuclear Information System (INIS)

Kecklund, Lena Jacobsson; Svenson, Ola

1997-01-01

The present study investigated the relationships between the operator's appraisal of his own work situation and the quality of his own work performance as well as self-reported errors in a nuclear power plant control room. In all, 98 control room operators from two nuclear power units filled out a questionnaire and several diaries during two operational conditions, annual outage and normal operation. As expected, the operators reported higher work demands in annual outage as compared to normal operation. In response to the increased demands, the operators reported that they used coping strategies such as increased effort, decreased aspiration level for work performance quality and increased use of delegation of tasks to others. This way of coping does not reflect less positive motivation for the work during the outage period. Instead, the operators maintain the same positive motivation for their work, and succeed in being more alert during morning and night shifts. However, the operators feel less satisfied with their work result. The operators also perceive the risk of making minor errors as increasing during outage. The decreased level of satisfaction with work result during outage is a fact despite the lowering of aspiration level for work performance quality during outage. In order to decrease relative frequencies for minor errors, special attention should be given to reduce work demands, such as time pressure and memory demands. In order to decrease misinterpretation errors special attention should be given to organizational factors such as planning and shift turnovers in addition to training. In summary, the outage period seems to be a significantly more vulnerable window in the management of a nuclear power plant than the normal power production state. Thus, an increased focus on the outage period and human factors issues, addressing the synergetic effects or work demands, organizational factors and coping resources is an important area for improvement of

Human factors engineering design review acceptance criteria for the safety parameter display

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

This report contains human factors engineering design review acceptance criteria developed by the Human Factors Engineering Branch (HFEB) of the Nuclear Regulatory Commission (NRC) to use in evaluating designs of the Safety Parameter Display System (SPDS). These criteria were developed in response to the functional design criteria for the SPDS defined in NUREG-0696, Functional Criteria for Emergency Response Facilities. The purpose of this report is to identify design review acceptance criteria for the SPDS installed in the control room of a nuclear power plant. Use of computer driven cathode ray tube (CRT) displays is anticipated. General acceptance criteria for displays of plant safety status information by the SPDS are developed. In addition, specific SPDS review criteria corresponding to the SPDS functional criteria specified in NUREG-0696 are established

Human Factors Engineering and Ergonomics Analysis for the Canister Storage Building (CSB) Results and Findings

Energy Technology Data Exchange (ETDEWEB)

GARVIN, L.J.

1999-09-20

The purpose for this supplemental report is to follow-up and update the information in SNF-3907, Human Factors Engineering (HFE) Analysis: Results and Findings. This supplemental report responds to applicable U.S. Department of Energy Safety Analysis Report review team comments and questions. This Human Factors Engineering and Ergonomics (HFE/Erg) analysis was conducted from April 1999 to July 1999; SNF-3907 was based on analyses accomplished in October 1998. The HFE/Erg findings presented in this report and SNF-3907, along with the results of HNF-3553, Spent Nuclear Fuel Project, Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report,'' Chapter A3.0, ''Hazards and Accidents Analyses,'' provide the technical basis for preparing or updating HNF-3553. Annex A, Chaptex A13.0, ''Human Factors Engineering.'' The findings presented in this report allow the HNF-3553 Chapter 13.0, ''Human Factors,'' to respond fully to the HFE requirements established in DOE Order 5480.23, Nuclear Safety Analysis Reports.

The human cap-binding complex is functionally connected to the nuclear RNA exosome

DEFF Research Database (Denmark)

Andersen, Peter Refsing; Domanski, Michal; Kristiansen, Maiken Søndergaard

2013-01-01

Nuclear processing and quality control of eukaryotic RNA is mediated by the RNA exosome, which is regulated by accessory factors. However, the mechanism of exosome recruitment to its ribonucleoprotein (RNP) targets remains poorly understood. Here we report a physical link between the human exosome...... and the cap-binding complex (CBC). The CBC associates with the ARS2 protein to form CBC-ARS2 (CBCA) and then further connects, together with the ZC3H18 protein, to the nuclear exosome targeting (NEXT) complex, thus forming CBC-NEXT (CBCN). RNA immunoprecipitation using CBCN factors as well as the analysis...

Nuclear data and human society

International Nuclear Information System (INIS)

Fuketa, Toyojiro

2002-01-01

Necessity and significance of nuclear data activities are discussed with background of the world typical aspects at the end of the 20th century. We have to overcome the worldwide adverse wind to nuclear power production with a view to preserving global environment including natural resources and climate. The nuclear data activities should be promoted further to achieve more and more wide comprehension and integrity of evaluated nuclear databases. The comprehensive evaluated nuclear databases which link microscopic world to macroscopic world may be of use to link science and technology with perception of the public, and to link science and technology with the other fields of learning, hence of use to coordinate and integrate natural, human, and social sciences. (author)

Nuclear accidents and safety measures of domestic nuclear power plants

International Nuclear Information System (INIS)

Song Zurong; Che Shuwei; Pan Xiang

2012-01-01

Based on the design standards for the safety of nuclear and radiation in nuclear power plants, the three accidents in the history of nuclear power are analyzed. And the main factors for these accidents are found out, that is, human factors and unpredicted natural calamity. By combining the design and operation parameters of domestic nuclear plants, the same accidents are studied and some necessary preventive schemes are put forward. In the security operation technology of domestic nuclear power plants nowadays, accidents caused by human factors can by prevented completely. But the safety standards have to be reconsidered for the unpredicted neutral disasters. How to reduce the hazard of nuclear radiation and leakage to the level that can be accepted by the government and public when accidents occur under extreme conditions during construction and operation of nuclear power plants must be considered adequately. (authors)

Human factors evaluation of remote afterloading brachytherapy. Volume 2, Function and task analysis

Energy Technology Data Exchange (ETDEWEB)

Callan, J.R.; Gwynne, J.W. III; Kelly, T.T.; Muckler, F.A. [Pacific Science and Engineering Group, San Diego, CA (United States); Saunders, W.M.; Lepage, R.P.; Chin, E. [University of California San Diego Medical Center, CA (United States). Div. of Radiation Oncology; Schoenfeld, I.; Serig, D.I. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology

1995-05-01

A human factors project on the use of nuclear by-product material to treat cancer using remotely operated afterloaders was undertaken by the Nuclear Regulatory Commission. The purpose of the project was to identify factors that contribute to human error in the system for remote afterloading brachytherapy (RAB). This report documents the findings from the first phase of the project, which involved an extensive function and task analysis of RAB. This analysis identified the functions and tasks in RAB, made preliminary estimates of the likelihood of human error in each task, and determined the skills needed to perform each RAB task. The findings of the function and task analysis served as the foundation for the remainder of the project, which evaluated four major aspects of the RAB system linked to human error: human-system interfaces; procedures and practices; training and qualifications of RAB staff; and organizational practices and policies. At its completion, the project identified and prioritized areas for recommended NRC and industry attention based on all of the evaluations and analyses.

Human factors evaluation of remote afterloading brachytherapy. Volume 2, Function and task analysis

International Nuclear Information System (INIS)

Callan, J.R.; Gwynne, J.W. III; Kelly, T.T.; Muckler, F.A.; Saunders, W.M.; Lepage, R.P.; Chin, E.; Schoenfeld, I.; Serig, D.I.

1995-05-01

A human factors project on the use of nuclear by-product material to treat cancer using remotely operated afterloaders was undertaken by the Nuclear Regulatory Commission. The purpose of the project was to identify factors that contribute to human error in the system for remote afterloading brachytherapy (RAB). This report documents the findings from the first phase of the project, which involved an extensive function and task analysis of RAB. This analysis identified the functions and tasks in RAB, made preliminary estimates of the likelihood of human error in each task, and determined the skills needed to perform each RAB task. The findings of the function and task analysis served as the foundation for the remainder of the project, which evaluated four major aspects of the RAB system linked to human error: human-system interfaces; procedures and practices; training and qualifications of RAB staff; and organizational practices and policies. At its completion, the project identified and prioritized areas for recommended NRC and industry attention based on all of the evaluations and analyses

Considering the human factors contribution to the risk in the design choices

International Nuclear Information System (INIS)

Papin, B.

2004-01-01

Abstract: With the increasing reliability of the modern technological systems, the human contribution to the global risk in the operation of industrial systems is becoming more and more significant: in the nuclear reactor operation for example, a recent PSA estimation of this contribution is about 25% of the risk of core melting, all situations considered. This urges the designers of future plants to consider the minimization of this Human Factor (HF) contribution, at the very early stage of their design: the experience feedback shows that this is indeed at this stage that the fundamental design options, impacting the most the human reliability in operation, are fixed. The problem is that at these early design stages, it is also quite impossible to apply formal human reliability methods to support this HF optimisation, while the precise operating conditions of the plant are not yet known in enough details. In this paper, another approach of the HF evaluation during the design, based on the functional and operational complexity assessment, is proposed. As an illustration, this approach is used to compare various concepts of nuclear reactors from the point of view of the Human Factor relevance. (authors)

Human factor engineering analysis for computerized human machine interface design issues

International Nuclear Information System (INIS)

Wang Zhifang; Gu Pengfei; Zhang Jianbo

2010-01-01

The application of digital I and C technology in nuclear power plants is a significant improvement in terms of functional performances and flexibility, and it also poses a challenge to operation safety. Most of the new NPPs under construction are adopting advanced control room design which utilizes the computerized human machine interface (HMI) as the main operating means. Thus, it greatly changes the way the operators interact with the plant. This paper introduces the main challenges brought out by computerized technology on the human factor engineering aspect and addresses the main issues to be dealt with in the computerized HMI design process. Based on a operator task-resources-cognitive model, it states that the root cause of human errors is the mismatch between resources demand and their supply. And a task-oriented HMI design principle is discussed. (authors)

The human factor in nuclear reactor operation

International Nuclear Information System (INIS)

Bertron, L.

1982-05-01

The principal operating characteristics of nuclear power plants are summarized. A description of major hazards relating to operator fallibility in normal and abnormal operating conditions is followed by a specific analysis of control room hazards, shift organization and selection and training of management personnel

Training department's role in human factor analysis during post-trip reviews

International Nuclear Information System (INIS)

Goodman, D.

1987-01-01

Provide training is a frequent corrective action specified in a post-trip review report. This corrective action is most often decided upon by technical and operational staff, not training staff, without a detailed analysis of whether training can resolve the immediate problem or enhance employees' future performance. A more specific human factor or performance problem analysis would often reveal that training cannot impact or resolve the concern to avoid future occurrences. This human factor analysis is similar to Thomas Gilbert's Behavior Engineering Model (Human Competence, McGraw-Hill, 1978) or Robert Mager's/Peter Pipe's Performance Analysis (Analyzing Performance Problems, Pitman Learning, 1984). At Palo Verde Nuclear Generating Station, training analysts participate in post-trip reviews in order to conduct or provide input to this type of human factor and performance problem analysis. Their goal is to keep provide training out of corrective action statements unless training can in fact impact or resolve the problem. The analysts follow a plant specific logic diagram to identify human factors and to identify whether changes to the environment or to the person would best resolve the concern

Implication of human factors in terms of safety

International Nuclear Information System (INIS)

Furuta, Kazuo

2001-01-01

A critical accident of JCO occurred on September 30, 1999 gave a large impact not only to common society but also to nuclear energy field. This accident occurred by direct reason perfectly out of forecasting of the participants of nuclear energy, where a company made up a guideline violating from business allowance and safety rule and workmen also operated under a procedure out of the guideline. After the accident, a number of countermeasures on equipments, rules, and regulations were carried out, but discussion on software such as their operating methods, concrete regulation on business and authority of operators, and training of specialists seems to be much late. Safety is a problem on a complex system, containing not only hardware but also software such as human, organization, society, and so on. Then, here was discussed on a problem directly faced by conventional safety, engineering centering at hardware through thinking of a problem on human factors. (G.K.)

Company culture and human factor

International Nuclear Information System (INIS)

Rerucha, F.

1999-01-01

Human beings constitute an important factor for smooth operation and fulfilment of special safety requirements in the workplace environment of a nuclear power station. It is therefore important to carry out investigations and continual checks in order to prevent routine complacency of the employees, not only for their respective tasks but also with regard to the structure of the plant. Frantisek Rerucha reports on the investigation of procedural approaches, the methods thereby involved and the results obtained in the nuclear power station Dukovany. The investigation came to the conclusion that communication and information problems exist in many areas. The company goals are communicated inadequately, especially on the lower and middle levels, with the result that employees do not always comply exactly with the directives. On the other hand, the employees are often overstressed with additional, often useless, information. However, willingness to communicate is mostly absent, and the employees have a feeling that personal relationships in general tend to be unsatisfactory in the nuclear power station. Management personnel is experienced as highly qualified experts without qualifications for leadership. But the study came to the conclusion that communication on the operative sector functions very well, by virtue of a well-established personal network. (orig.) [de

Analysis of Human Error Types and Performance Shaping Factors in the Next Generation Main Control Room

International Nuclear Information System (INIS)

Sin, Y. C.; Jung, Y. S.; Kim, K. H.; Kim, J. H.

2008-04-01

Main control room of nuclear power plants has been computerized and digitalized in new and modernized plants, as information and digital technologies make great progresses and become mature. Survey on human factors engineering issues in advanced MCRs: Model-based approach, Literature survey-based approach. Analysis of human error types and performance shaping factors is analysis of three human errors. The results of project can be used for task analysis, evaluation of human error probabilities, and analysis of performance shaping factors in the HRA analysis

Nuclear Human Resources Development Program using Educational Core Simulator

International Nuclear Information System (INIS)

Choi, Yu Sun; Hong, Soon Kwan

2015-01-01

KHNP-CRI(Korea Hydro and Nuclear Power Co.-Central Research Institute) has redesigned the existing Core Simulator(CoSi) used as a sort of training tools for reactor engineers in operating nuclear power plant to support Nuclear Human Resources Development (NHRD) Program focusing on the nuclear department of Dalat university in Vietnam. This program has been supported by MOTIE in Korea and cooperated with KNA(Korea Nuclear Association for International Cooperation) and HYU(Hanyang University) for enhancing the nuclear human resources of potential country in consideration with Korean Nuclear Power Plant as a next candidate energy sources. KHNP-CRI has provided Edu-CoSi to Dalat University in Vietnam in order to support Nuclear Human Resources Development Program in Vietnam. Job Qualification Certificates Program in KHNP is utilized to design a training course for Vietnamese faculty and student of Dalat University. Successfully, knowhow on lecturing the ZPPT performance, training and maintaining Edu-CoSi hardware are transferred by several training courses which KHNP-CRI provides

Nuclear Human Resources Development Program using Educational Core Simulator

Energy Technology Data Exchange (ETDEWEB)

Choi, Yu Sun; Hong, Soon Kwan [KHNP-CRI, Daejeon (Korea, Republic of)

2015-10-15

KHNP-CRI(Korea Hydro and Nuclear Power Co.-Central Research Institute) has redesigned the existing Core Simulator(CoSi) used as a sort of training tools for reactor engineers in operating nuclear power plant to support Nuclear Human Resources Development (NHRD) Program focusing on the nuclear department of Dalat university in Vietnam. This program has been supported by MOTIE in Korea and cooperated with KNA(Korea Nuclear Association for International Cooperation) and HYU(Hanyang University) for enhancing the nuclear human resources of potential country in consideration with Korean Nuclear Power Plant as a next candidate energy sources. KHNP-CRI has provided Edu-CoSi to Dalat University in Vietnam in order to support Nuclear Human Resources Development Program in Vietnam. Job Qualification Certificates Program in KHNP is utilized to design a training course for Vietnamese faculty and student of Dalat University. Successfully, knowhow on lecturing the ZPPT performance, training and maintaining Edu-CoSi hardware are transferred by several training courses which KHNP-CRI provides.

Improving human reliability through better nuclear power plant system design. Final report

International Nuclear Information System (INIS)

Golay, Michael W.

1998-01-01

Increasing task complexity is claimed to be responsible for causing human operating errors, while a significant number of system failures are due to operating errors. An experimental study reported here was conducted to isolate varying task complexity as an important factor affecting human performance quality. Earlier work concerning problems of nuclear power plants has shown that human capability declined when dealing with increasing system complexity. The goal of this study was to investigate further the relationship between human operator performance quality and the complexity of tasks served to human operators. This was done by using a simple, interactive, dynamic and generalizable computer model to simulate the behavior of a human-operated dynamic fluid system. Twenty-two human subjects participated

Surface sensitivity of nuclear-knock-out form factors

International Nuclear Information System (INIS)

Fratamico, G.

1984-01-01

A numerical calculation has been performed to investigate the sensitivity of nuclear-knock-out form factors to nuclear-surface behaviour of bound-state wave functions. The result of our investigation suggests that one can extract the bound-state behaviour at the surface from experimental information on nuclear-knock-out form factors

An examination of human factors in external beam radiation therapy: Findings and implications

International Nuclear Information System (INIS)

Henriksen, K.; Kaye, R.D.; Jones, R.E. Jr.; Morisseau, D.S.; Persensky, J.J.

1994-01-01

To better understand the contributing factors to human error in external beam radiation therapy, the US Nuclear Regulatory Commission has undertaken a series of human factors evaluations. A team of human factors specialists, assisted by a panel of radiation oncologists, medical physicists, and radiation technologists, conducted visits to 24 radiation oncology departments at community hospitals, university centers, and free-standing clinics. A function and task analysis was initially performed to guide subsequent evaluations in the areas of human-system interfaces, procedures, training and qualifications, and organizational policies and practices. Representative findings and implications for improvement are discussed within the context of a dynamic model which holds that misadministration likely results from the unanticipated interaction of several necessary but singly insufficient conditions

Development of human resources for Indian nuclear power programme

International Nuclear Information System (INIS)

Grover, R.B.; Puri, R.R.

2013-01-01

The continuing research and development on nuclear technology by research establishments in the country and maturing of Indian industry have brought the nuclear energy programme in India to a stage where it is poised to take a quantum leap forward. The vision of expansion of nuclear power also requires a well-structured specialized human resource development programme. This paper discusses the requirements of the human resource development programme for nuclear energy, the challenges in the way of its realization, its national and international status and traces the history of nuclear education in the country. It brings out the linkage of human resource development programme with the nuclear energy programme in the country. It also describes the initiatives by the university system in the area of nuclear education and support provided by the Department of Atomic Energy to the university system by way of extra-mural funding and by providing access to research facilities. (author)

Protective effect of nuclear factor E2-related factor 2 on inflammatory cytokine response to brominated diphenyl ether-47 in the HTR-8/SVneo human first trimester extravillous trophoblast cell line

International Nuclear Information System (INIS)

Park, Hae-Ryung; Loch-Caruso, Rita

2014-01-01

Polybrominated diphenyl ethers (PBDEs) are widely used flame retardants, and BDE-47 is a prevalent PBDE congener detected in human tissues. Exposure to PBDEs has been linked to adverse pregnancy outcomes in humans. Although the underlying mechanisms of adverse birth outcomes are poorly understood, critical roles for oxidative stress and inflammation are implicated. The present study investigated antioxidant responses in a human extravillous trophoblast cell line, HTR-8/SVneo, and examined the role of nuclear factor E2-related factor 2 (Nrf2), an antioxidative transcription factor, in BDE-47-induced inflammatory responses in the cells. Treatment of HTR-8/SVneo cells with 5, 10, 15, and 20 μM BDE-47 for 24 h increased intracellular glutathione (GSH) levels compared to solvent control. Treatment of HTR-8/SVneo cells with 20 μM BDE-47 for 24 h induced the antioxidant response element (ARE) activity, indicating Nrf2 transactivation by BDE-47 treatment, and resulted in differential expression of redox-sensitive genes compared to solvent control. Pretreatment with tert-butyl hydroquinone (tBHQ) or sulforaphane, known Nrf2 inducers, reduced BDE-47-stimulated IL-6 release with increased ARE reporter activity, reduced nuclear factor kappa B (NF-κB) reporter activity, increased GSH production, and stimulated expression of antioxidant genes compared to non-Nrf2 inducer pretreated groups, suggesting that Nrf2 may play a protective role against BDE-47-mediated inflammatory responses in HTR-8/SVneo cells. These results suggest that Nrf2 activation significantly attenuated BDE-47-induced IL-6 release by augmentation of cellular antioxidative system via upregulation of Nrf2 signaling pathways, and that Nrf2 induction may be a potential therapeutic target to reduce adverse pregnancy outcomes associated with toxicant-induced oxidative stress and inflammation. - Highlights: • BDE-47 stimulated ARE reporter activity and GSH production. • BDE-47 resulted in differential

Protective effect of nuclear factor E2-related factor 2 on inflammatory cytokine response to brominated diphenyl ether-47 in the HTR-8/SVneo human first trimester extravillous trophoblast cell line

Energy Technology Data Exchange (ETDEWEB)

Park, Hae-Ryung, E-mail: heaven@umich.edu; Loch-Caruso, Rita

2014-11-15

Polybrominated diphenyl ethers (PBDEs) are widely used flame retardants, and BDE-47 is a prevalent PBDE congener detected in human tissues. Exposure to PBDEs has been linked to adverse pregnancy outcomes in humans. Although the underlying mechanisms of adverse birth outcomes are poorly understood, critical roles for oxidative stress and inflammation are implicated. The present study investigated antioxidant responses in a human extravillous trophoblast cell line, HTR-8/SVneo, and examined the role of nuclear factor E2-related factor 2 (Nrf2), an antioxidative transcription factor, in BDE-47-induced inflammatory responses in the cells. Treatment of HTR-8/SVneo cells with 5, 10, 15, and 20 μM BDE-47 for 24 h increased intracellular glutathione (GSH) levels compared to solvent control. Treatment of HTR-8/SVneo cells with 20 μM BDE-47 for 24 h induced the antioxidant response element (ARE) activity, indicating Nrf2 transactivation by BDE-47 treatment, and resulted in differential expression of redox-sensitive genes compared to solvent control. Pretreatment with tert-butyl hydroquinone (tBHQ) or sulforaphane, known Nrf2 inducers, reduced BDE-47-stimulated IL-6 release with increased ARE reporter activity, reduced nuclear factor kappa B (NF-κB) reporter activity, increased GSH production, and stimulated expression of antioxidant genes compared to non-Nrf2 inducer pretreated groups, suggesting that Nrf2 may play a protective role against BDE-47-mediated inflammatory responses in HTR-8/SVneo cells. These results suggest that Nrf2 activation significantly attenuated BDE-47-induced IL-6 release by augmentation of cellular antioxidative system via upregulation of Nrf2 signaling pathways, and that Nrf2 induction may be a potential therapeutic target to reduce adverse pregnancy outcomes associated with toxicant-induced oxidative stress and inflammation. - Highlights: • BDE-47 stimulated ARE reporter activity and GSH production. • BDE-47 resulted in differential

Human factors in training

International Nuclear Information System (INIS)

Dutton, J.W.; Brown, W.R.

1981-01-01

The Human Factors concept is a focused effort directed at those activities which require human involvement. Training is, by its nature, an activity totally dependent on the Human Factor. This paper identifies several concerns significant to training situations and discusses how Human Factor awareness can increase the quality of learning. Psychology in the training arena is applied Human Factors. Training is a method of communication represented by sender, medium, and receiver. Two-thirds of this communications model involves the human element directly

Humanity cannot survive a nuclear war

International Nuclear Information System (INIS)

Ehrlich, P.R.

1985-01-01

The author documents the unprecedented disaster that a nuclear war would wreak. He and his colleagues conclude that a nuclear war may mean the end of the human species. The environment that will confront most human beings and other organisms after a thermonuclear holocaust will be so altered, and so malign, that extreme and widespread damage to living systems is inevitable. It is, for example, entirely possible that the biological impacts of a war, apart from those resulting directly from a blast, fire, and prompt radiation, could result in the end of civilization in the Northern Hemisphere. The author's primary task in this paper is to give some technical background to explain why numerous biologists, especially ecologists, are convinced that decision-makers in many nations vastly underrate the potential risks of nuclear war

About role of human factors in the building of physical protection system

International Nuclear Information System (INIS)

Ivanov, P.

2001-01-01

In our opinion, our contribution to the fight against the illicit turnover has to be focused on ensuring the safe keeping and integrity of nuclear material and radiation sources and on creating powerful and highly efficient physical protection systems. A special role in establishing the physical protection system (at all levels) pertains to the human factor. The nuclear energy sector security (as well as of other national industry sectors) is based on the people: developers, personnel, different level management responsible for decision-making process, the representative of regulatory, controlling and legal structures, and therefore, in general, the role of the human factor can be considered to be significant. After having analyzed, even in a general way, the status of the affairs we can see: 1) the stage of designing and development of facilities is actually completed; 2) the existing concept of protection does not meet current requirements of the physical protection; 3) the next period is the operation when it is necessary to adapt with using capabilities available to the today requirements and to establish conditions under which the human factor could compensate technical backwardness; 4) the final stage is the ChNPP decommissioning, the Object Shelter problem. It is obvious that the ChNPP decommissioning process will increase acuteness of the problem related to the physical protection of this facility. The operative situation while being formed during the physical protection ensuring, first of all, is affected by the following factors: 1) political factors: changes in the geopolitical situation caused by fundamental changes, formation of a national state based on a principle of democracy and law, etc.; 2) social and economic factors: difficulties originated during the period of transition towards the market economy, decrease in the standard of living; increase in the crime rate and criminalization of social relations and others; 3) spiritual wealth and cultural

Human factors: a major issue in plant aging

International Nuclear Information System (INIS)

Widrig, R.D.

1985-07-01

Human factors issues will be of great significance in the safe and reliable operation of aging nuclear power plants, and they may be more important than materials/component-type issues. Human actions can accelerate or decelerate te physical aging process. And an aging plant can have significant negative implications on staff performance and actions. Some examples include difficulties in attracting and retaining good managers, financial decisions based on a short and uncertain remaining plant life, difficulties in replacing retiring staff, increased maintenance complexity, and increased burden on training. These problems can be dealt with more effectively by early recognition and a well conceived mitigation effort

The recovery factors analysis of the human errors for research reactors

International Nuclear Information System (INIS)

Farcasiu, M.; Nitoi, M.; Apostol, M.; Turcu, I.; Florescu, Ghe.

2006-01-01

The results of many Probabilistic Safety Assessment (PSA) studies show a very significant contribution of human errors to systems unavailability of the nuclear installations. The treatment of human interactions is considered one of the major limitations in the context of PSA. To identify those human actions that can have an effect on system reliability or availability applying the Human Reliability Analysis (HRA) is necessary. The recovery factors analysis of the human action is an important step in HRA. This paper presents how can be reduced the human errors probabilities (HEP) using those elements that have the capacity to recovery human error. The recovery factors modeling is marked to identify error likelihood situations or situations that conduct at development of the accident. This analysis is realized by THERP method. The necessary information was obtained from the operating experience of the research reactor TRIGA of the INR Pitesti. The required data were obtained from generic databases. (authors)

Managing human resources in the field of nuclear energy

International Nuclear Information System (INIS)

2009-01-01

The nuclear field, comprising industry, government authorities, regulators, R and D organizations and educational institutions, relies heavily on a specialized, highly trained and motivated workforce for its sustainability. An ageing workforce, declining student enrolment and the resultant risk of losing accumulated nuclear knowledge and experience for expanding or newly established nuclear programmes are all serious challenges that influence the management of human resources (HR) in the nuclear field. The management of human resources requires particular attention in the field of nuclear energy, both because of the high standards of performance expected in this field and the considerable time needed to develop such specialists. The peaceful uses of nuclear energy were primarily developed during the second half of the twentieth century. The nuclear field is now at a mature stage of development, with those who were pioneers in the field having retired and their responsibilities handed over to subsequent generations. For those aspects of the nuclear field related to nuclear power, a great deal of effort has been devoted to managing and continuing to improve the safety and operational performance of existing facilities. However, indications are that the next decades may see considerable expansion to meet increasing energy needs, while responding to concerns about the environment, including global warming. Thus, in the nuclear field, those Member States with existing nuclear power programmes may be forced to replace a large part of their current workforce, while also attracting, recruiting and preparing a fresh workforce for the new facilities being planned. At the same time, those who will be initiating nuclear power programmes, or other peaceful applications, will be developing HR for their programmes. In the past, the development of human resources in the nuclear field has depended on considerable support from organizations in the country of origin of the technology

How to Cope with the Rare Human Error Events Involved with organizational Factors in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Sa Kil; Luo, Meiling; Lee, Yong Hee [Korea Atomic Research Institute, Daejeon (Korea, Republic of)

2014-10-15

The current human error guidelines (e.g. US DOD handbooks, US NRC Guidelines) are representative tools to prevent human errors. These tools, however, have limits that they do not adapt all operating situations and circumstances such as design base events. In other words, these tools are only adapted foreseeable standardized operating situations and circumstances. In this study, our research team proposed an evidence-based approach such as UK's safety case to coping with the rare human error events such as TMI, Chernobyl, Fukushima accidents. These accidents are representative events involved with rare human errors. Our research team defined the 'rare human errors' as the follow three characterized events; Extremely low frequency Extremely high complicated structure Extremely serious damage of human life and property A safety case is a structured argument, supported by evidence, intended to justify that a system is acceptably safe. The definition by UK defense standard 00-56 issue 4 states that such an evidence-based approach can be contrast with a prescriptive approach to safety certification, which require safety to be justified using a prescribed process. Safety managements and safety regulatory activities based on safety case are effective to control organizational factors in terms of integrated safety management. Especially safety issues relevant with public acceptance are useful to provide practical evidences to the public reasonably. European Union including UK has developed the concept of engineered safety management system to deal with public acceptance using the safety case. In Korea nuclear industry, the Korean Atomic Research Institute has firstly performed a basic research to adapt the safety case in the field of radioactive waste according to the IAEA SSG-23(KAERI/TR-4497, 4531). Excepting the radioactive waste, there is no try to adapt the safety case yet. Most incidents and accidents involved human during operating NPPs have a tendency

How to Cope with the Rare Human Error Events Involved with organizational Factors in Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Sa Kil; Luo, Meiling; Lee, Yong Hee

2014-01-01

The current human error guidelines (e.g. US DOD handbooks, US NRC Guidelines) are representative tools to prevent human errors. These tools, however, have limits that they do not adapt all operating situations and circumstances such as design base events. In other words, these tools are only adapted foreseeable standardized operating situations and circumstances. In this study, our research team proposed an evidence-based approach such as UK's safety case to coping with the rare human error events such as TMI, Chernobyl, Fukushima accidents. These accidents are representative events involved with rare human errors. Our research team defined the 'rare human errors' as the follow three characterized events; Extremely low frequency Extremely high complicated structure Extremely serious damage of human life and property A safety case is a structured argument, supported by evidence, intended to justify that a system is acceptably safe. The definition by UK defense standard 00-56 issue 4 states that such an evidence-based approach can be contrast with a prescriptive approach to safety certification, which require safety to be justified using a prescribed process. Safety managements and safety regulatory activities based on safety case are effective to control organizational factors in terms of integrated safety management. Especially safety issues relevant with public acceptance are useful to provide practical evidences to the public reasonably. European Union including UK has developed the concept of engineered safety management system to deal with public acceptance using the safety case. In Korea nuclear industry, the Korean Atomic Research Institute has firstly performed a basic research to adapt the safety case in the field of radioactive waste according to the IAEA SSG-23(KAERI/TR-4497, 4531). Excepting the radioactive waste, there is no try to adapt the safety case yet. Most incidents and accidents involved human during operating NPPs have a tendency

What factors facilitate regulatory competence in supervising the safety of nuclear technology?

International Nuclear Information System (INIS)

Mishar, Marina

2012-01-01

The proposed utilization of nuclear energy for electricity generation as the alternative energy source requires Atomic Energy Licensing Board (AELB), the Malaysian nuclear regulatory body taking key role in supervising the safety of the program. This study looked into factors influencing the competency of current AELB human resource as technical competency has been identified as one of the main contributors to the success of a civil nuclear power program. The four quadrant competency model developed by International Atomic Energy Agency was utilized as the required competency. A comprehensive study on 81 personnel from five states in different geographic regions of the country were carried out to investigate the impact of six factors related to competency (educational level, years of working experience, trainings attended, participation in technical committees, numbers of technical papers written and number of technical presentation presented) on four dependent measures in the areas of regulatory competency (legal basis, technical disciplines, regulatory practices and personal and interpersonal effectiveness). Multiple regression (method enter) identified factors that had significant contribution to level of competency while stepwise regression resulted in identifying predictors to enhance competencies. Results were mixed but each of the independent factors is a predictor to different competencies. This study had identified the best predictors that could significantly contribute to the enhancement of regulatory. (author)

Future perspectives of human resources in nuclear technology - The Korean case

International Nuclear Information System (INIS)

Min, B.J.

2007-01-01

. Experience shows that training without continued application and without long term commitment of a coordinated core of participants and programmes, is virtually worthless. HRD management must be a dynamic process that includes not only basic education and specific training but also looks to other spin-off learning/industries and to basic inputs/learning as part of the process. Comprehensive HRD and M policy and strategies for nuclear energy is one of the essential and priority issues for long-term nuclear energy development. Since a nuclear power programme cannot exist in a vacuum, future HRD and M schemes for nuclear energy should include a broad base of disciplines, sciences and technologies, perhaps within a framework of national sustainable development goals, generally considered to include economics, environment and social concerns. Within this context, areas of interest would include technical performance, nuclear science and engineering, as well as matters related to the economic performance of new nuclear generating capacities compared to alternatives (standards, economics, finance, liability, risks, internalization of externalities), environmental protection (emissions, wastes, decommissioning), social and political issues, energy demand and supply, inter generational concerns about long-lived wastes and resource depletion, supply security considerations, and innovation. The medium and long term nuclear human resources projections to be developed here for the Republic of Korea up to 2030 are not predictions but rather scenarios of plausible ranges of future nuclear human resource requirements based on nuclear power generation projections reflecting a variety of economic, social and environmental driving factors. Both the LOW and HIGH projections are derived from Input-Output analysis based on a review of national nuclear technology development programmes and plans. (author)

Current status and issues of nuclear human resource development/General activities of Japan nuclear human resource development network

International Nuclear Information System (INIS)

Murakami, Hiroyuki; Hino, Sadami; Tsuru, Hisanori

2013-01-01

The Japan Nuclear Human Resource Development Network (JN-HRD Net) was established in November 2010 with the aim of developing a framework for mutual cooperation and information sharing among nuclear-related organizations. Although the tasks and goals of developing human resources in the nuclear field have been shifted since the accident at the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi Nuclear Power Plant, the necessity of fostering capable personnel in this field stays unchanged and the importance of our network activities has further emphasized. The meeting of JN-HRD Net was held on the 5th of February 2013, where its activities by each field were reported and views and opinions were actively exchanged between more than 90 participants. This paper briefly describes current status and issues of JN-HRD Net and its general activities conducted by the JN-HRD Net secretariat. (J.P.N.)

Human survival depends on nuclear power

International Nuclear Information System (INIS)

Gilbertson, J.

1977-01-01

Both the Wall Street Journal and the New York Times published feature articles Dec. 1 advertising a report by the U.S. government's General Accounting Office as evidence that the breeder reactor component of this nation's nuclear energy program was properly on its way to the scrap heap. According to the author, these and similar press accounts are intended to further legitimize the widely believed (and totally false) notion that increased plutonium use and nuclear fission generally represent a danger to humanity. Purposefully ignored in such accounts, he says, is the evidence that the elimination of plutonium as a nuclear fuel will mean the demise of the entire U.S. nuclear power industry and ultimately the human race itself. At stake in the short term, in addition to the breeder reactor program, is the well-established use of light water reactors for generating electricity, since these must, within a matter of years, be fueled with plutonium. The attack is also directed at the more advanced, more capital-intensive nuclear fusion technology, since the elimination of fission programs will wipe out the trained cadre force of engineers, scientists, technicians, and skilled workers needed to develop fusion power. The growth of fission power over the next two decades is absolutely necessary for the transition to a full fusion-based economy, according to Mr. Gilbertson. Only nuclear fusion has the inherent capability of transforming industry to the necessary higher mode of production and output, as well as providing a limitless source of usable power in several forms, thus insuring the survival of the human race beyond this century. Fission power and conventional fossil power must be expanded and possibly even exhausted during this transition in order to guarantee the achievement of this goal, he says

Human factors assessment in PRA using task analysis linked evaluation technique (TALENT)

International Nuclear Information System (INIS)

Wells, J.E.; Banks, W.W.

1990-01-01

Human error is a primary contributor to risk in complex high-reliability systems. A 1985 U.S. Nuclear Regulatory Commission (USNRC) study of licensee event reports (LERs) suggests that upwards of 65% of commercial nuclear system failures involve human error. Since then, the USNRC has initiated research to fully and properly integrate human errors into the probabilistic risk assessment (PRA) process. The resulting implementation procedure is known as the Task Analysis Linked Evaluation Technique (TALENT). As indicated, TALENT is a broad-based method for integrating human factors expertise into the PRA process. This process achieves results which: (1) provide more realistic estimates of the impact of human performance on nuclear power safety, (2) can be fully audited, (3) provide a firm technical base for equipment-centered and personnel-centered retrofit/redesign of plants enabling them to meet internally and externally imposed safety standards, and (4) yield human and hardware data capable of supporting inquiries into human performance issues that transcend the individual plant. The TALENT procedure is being field-tested to verify its effectiveness and utility. The objectives of the field-test are to examine (1) the operability of the process, (2) its acceptability to the users, and (3) its usefulness for achieving measurable improvements in the credibility of the analysis. The field-test will provide the information needed to enhance the TALENT process

Nuclear medicine - factors influencing the choice and use of radionuclides in diagnosis and therapy

International Nuclear Information System (INIS)

Anon.

1983-01-01

This report addresses the many factors which influence the choice of the proper radiopharmaceutical drug product for the diagnosis or treatment of a specific disease or condition in a human subject. The Report examines the historical factors that influence the choice of radionuclides, the factors that influence the localization of radionuclides in tissues, the factors that influence the choice of instruments, and include an evaluation of the nuclear medicine procedures that could be selected and their clinical usefulness. In examining these factors the desirable characteristics of the radiopharmaceutical drug products of the measurement systems are identified. The methods of dose determination and the assumptions used in determination of dose are developed. There is also a section on radiation effects. A chapter on guidelines for procedures in nuclear medicine and some general and specific recommendations for protection of patients conclude the body of the text

Nuclear Accidents: Consequences for Human, Society and Energy Sector

Directory of Open Access Journals (Sweden)

L. A. Bolshov

2016-01-01

Full Text Available The article examines radiation and hygienic regulations with regard to the elimination of consequences of the Chernobyl NPP accident in the context of relationships with other aspects, primarily socio-economic and political factors. This experience is reasonable to take into account when defining criteria in other regulatory fields, for example, in radioactive waste classification and remediation of areas. The article presents an analysis of joint features and peculiarities of nuclear accidents in the industry and energy sectors. It is noted that the scale of global consequences of the Chernobyl NPP accident is defined by the large-scale release of radioactivity into the environment, as well as an affiliation of the nuclear installation with the energy sector. Large-scale radiation accidents affect the most diverse spheres of human activities, what, in its turn, evokes the reverse reaction from the society and its institutions, including involvement of political means of settlement. If the latter is seeing for criteria that are scientifically justified and feasible, then the preconditions for minimizing socio-economic impacts are created. In other cases, political decisions, such as nuclear units’ shutdown and phasing out of nuclear energy, appear to be an economic price which society, as a whole and a single industry sector, pay to compensate the negative public response. The article describes fundamental changes in approaches to ensure nuclear and radiation safety that occurred after the Chernobyl NPP accident. Multiple and negative consequences of the Chernobyl accident for human and society are balanced to some extent by a higher level of operational safety, emergency preparedness, and life-cycle safety. The article indicates that harmonization and ensuring consistency of regulations that involve different aspects of nuclear and radiation safety are important to implement practical solutions to the nuclear legacy problems. The

Hepatocyte nuclear factor 4A improves hepatic differentiation of immortalized adult human hepatocytes and improves liver function and survival.

Science.gov (United States)

Hang, Hua-Lian; Liu, Xin-Yu; Wang, Hai-Tian; Xu, Ning; Bian, Jian-Min; Zhang, Jian-Jun; Xia, Lei; Xia, Qiang

2017-11-15

Immortalized human hepatocytes (IHH) could provide an unlimited supply of hepatocytes, but insufficient differentiation and phenotypic instability restrict their clinical application. This study aimed to determine the role of hepatocyte nuclear factor 4A (HNF4A) in hepatic differentiation of IHH, and whether encapsulation of IHH overexpressing HNF4A could improve liver function and survival in rats with acute liver failure (ALF). Primary human hepatocytes were transduced with lentivirus-mediated catalytic subunit of human telomerase reverse transcriptase (hTERT) to establish IHH. Cells were analyzed for telomerase activity, proliferative capacity, hepatocyte markers, and tumorigenicity (c-myc) expression. Hepatocyte markers, hepatocellular functions, and morphology were studied in the HNF4A-overexpressing IHH. Hepatocyte markers and karyotype analysis were completed in the primary hepatocytes using shRNA knockdown of HNF4A. Nuclear translocation of β-catenin was assessed. Rat models of ALF were treated with encapsulated IHH or HNF4A-overexpressing IHH. A HNF4A-positive IHH line was established, which was non-tumorigenic and conserved properties of primary hepatocytes. HNF4A overexpression significantly enhanced mRNA levels of genes related to hepatic differentiation in IHH. Urea levels were increased by the overexpression of HNF4A, as measured 24h after ammonium chloride addition, similar to that of primary hepatocytes. Chromosomal abnormalities were observed in primary hepatocytes transfected with HNF4A shRNA. HNF4α overexpression could significantly promote β-catenin activation. Transplantation of HNF4A overexpressing IHH resulted in better liver function and survival of rats with ALF compared with IHH. HNF4A improved hepatic differentiation of IHH. Transplantation of HNF4A-overexpressing IHH could improve the liver function and survival in a rat model of ALF. Copyright © 2017 Elsevier Inc. All rights reserved.

Summary of project to develop handbook of human reliability analysis for nuclear power plant operations

International Nuclear Information System (INIS)

Swain, A.D.

1978-01-01

For the past two years Alan Swain and Henry E. Guttmann, of the Statistics, Computing, and Human Factors Division, Sandia Laboratories, have been developing a handbook to aid qualified persons to evaluate the effect of human error on the availability of engineered safety systems and features in nuclear power plants. The handbook includes a mathematical model, procedures, derived human failure data, and principles of human behavior and ergonomics. The handbook is expanding the human error analyses which were presented in WASH--1400. The work, under the sponsorship of Probabilistic Analysis Staff, NRC Office of Nuclear Regulatory Research (Dr. M.C. Cullingford, NRC Program Manager), is about half completed. An outline of the handbook contents is given in copies of vugraphs (attached), followed by copies of human performance model abstractors (also attached). A first draft of the handbook is scheduled for NRC review by July 1, 1979

Human factors engineering report for the cold vacuum drying facility

Energy Technology Data Exchange (ETDEWEB)

IMKER, F.W.

1999-06-30

The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF.

Human factors engineering report for the cold vacuum drying facility

International Nuclear Information System (INIS)

IMKER, F.W.

1999-01-01

The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF

Diesel exhaust particulate extracts inhibit transcription of nuclear respiratory factor-1 and cell viability in human umbilical vein endothelial cells

Energy Technology Data Exchange (ETDEWEB)

Mattingly, Kathleen A.; Klinge, Carolyn M. [University of Louisville School of Medicine, Department of Biochemistry and Molecular Biology, Center for Genetics and Molecular Medicine, Louisville, KY (United States)

2012-04-15

Endothelial dysfunction precedes cardiovascular disease and is accompanied by mitochondrial dysfunction. Here we tested the hypothesis that diesel exhaust particulate extracts (DEPEs), prepared from a truck run at different speeds and engine loads, would inhibit genomic estrogen receptor activation of nuclear respiratory factor-1 (NRF-1) transcription in human umbilical vein endothelial cells (HUVECs). Additionally, we examined how DEPEs affect NRF-1-regulated TFAM expression and, in turn, Tfam-regulated mtDNA-encoded cytochrome c oxidase subunit I (COI, MTCO1) and NADH dehydrogenase subunit I (NDI) expression as well as cell proliferation and viability. We report that 17{beta}-estradiol (E{sub 2}), 4-hydroxytamoxifen (4-OHT), and raloxifene increased NRF-1 transcription in HUVECs in an ER-dependent manner. DEPEs inhibited NRF-1 transcription, and this suppression was not ablated by concomitant treatment with E{sub 2}, 4-OHT, or raloxifene, indicating that the effect was not due to inhibition of ER activity. While E{sub 2} increased HUVEC proliferation and viability, DEPEs inhibited viability but not proliferation. Resveratrol increased NRF-1 transcription in an ER-dependent manner in HUVECs, and ablated DEPE inhibition of basal NRF-1 expression. Given that NRF-1 is a key nuclear transcription factor regulating genes involved in mitochondrial activity and biogenesis, these data suggest that DEPEs may adversely affect mitochondrial function leading to endothelial dysfunction and resveratrol may block these effects. (orig.)

Draft audit report, human factors engineering control room design review: Saint Lucie Nuclear Power Plant, Unit No. 2

International Nuclear Information System (INIS)

Peterson, L.R.; Lappa, D.A.; Moore, J.W.

1981-01-01

A human factors engineering preliminary design review of the Saint Lucie Unit 2 control room was performed at the site on August 3 through August 7, 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 review team included human factors consultants from BioTechnology, Inc., Falls Church, Virginia, and from Lawrence Livermore National Laboratory (University of California), Livermore, California

An Empirical Study on Human Performance according to the Physical Environment (Potential Human Error Hazard) in Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Ar Ryum; Jang, In Seok; Seong, Proong Hyun

2014-01-01

The management of the physical environment for safety is more effective than a nuclear industry. Despite the physical environment such as lighting, noise satisfy with management standards, it can be background factors may cause human error and affect human performance. Because the consequence of extremely human error and human performance is high according to the physical environment, requirement standard could be covered with specific criteria. Particularly, in order to avoid human errors caused by an extremely low or rapidly-changing intensity illumination and masking effect such as power disconnection, plans for better visual environment and better function performances should be made as a careful study on efficient ways to manage and continue the better conditions is conducted

Ergonomics in the licensing and evaluation of nuclear reactors control room; A ergonomia no licenciamento e na avaliacao de salas de controle de reatores nucleares

Energy Technology Data Exchange (ETDEWEB)

Santos, Isaac Jose Antonio Luquetti dos [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Vidal, Mario Cesar Rodriguez [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia de Producao

2002-07-01

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)

Roadmap for human resources for expanded Indian nuclear industry

International Nuclear Information System (INIS)

Singh, R.K.; Srinivasan, G.R.; Goyal, O.P.

2011-01-01

This paper deals with detailed requirement of human resources for all phases of nuclear power plant, for the manufacturing sector and the probable roadmap for achieving India's target. The accident in Fukushima has brought out that only nuclear power that avoids being a threat to the health and safety of the population and the environmental will be acceptable to the society and for this to be achieved human resources could be a single major contributor. India has ambitious plan of achieving 20,000MW by 2020 and 63,000MW by 2050. It is felt out of the three resources men, material and money; the critical shortage would be human resources both in quality and quantity. As per IAEA report (Publication of 2008 edition of energy, electricity and nuclear power estimates for the period of 2030), nuclear capacity must grow to at least 1.8 times current capacity by 2030 if global temperature rises are to be kept at 2°C. Objective of recruiting and training human resources for Indian Industry can be as follows: a) For catering domestic market. b) For catering international market later on for nuclear industries outside India. As India will be an important future international player. The above would require a multiplication of human resources by nearly seven times. In addition it has to be wholesome covering all levels and all skills and all disciplines and stages covering the whole nuclear cycle including regulators. Human resources are required for design and engineering, construction, commissioning, operation, manufacturing and for support services. The manpower for these has to be trained to achieve high quality of nuclear standards. Presently Indian Department of Atomic Energy(DAE) runs several training schools giving one year Post Graduate, tailor made courses. This needs to be multiplied by Joint efforts. Training should be on 'SAT (Systematic Approach to Training)' methodology to ensure focussed, specific, needed to culminate in safe, reliable and viable operation of

Roadmap for human resources for expanded Indian nuclear industry

Energy Technology Data Exchange (ETDEWEB)

Singh, R.K. [Bhabha Atomic Research Centre, Mumbai (India); Indian Nuclear Society (India); Srinivasan, G.R.; Goyal, O.P. [Bhabha Atomic Research Centre, Mumbai (India)

2011-07-01