WorldWideScience

Sample records for human factors safety

  1. Human factors in nuclear safety oversight

    International Nuclear Information System (INIS)

    Taylor, K.

    1989-01-01

    The mission of the nuclear safety oversight function at the Savannah River Plant is to enhance the process and nuclear safety of site facilities. One of the major goals surrounding this mission is the reduction of human error. It is for this reason that several human factors engineers are assigned to the Operations assessment Group of the Facility Safety Evaluation Section (FSES). The initial task of the human factors contingent was the design and implementation of a site wide root cause analysis program. The intent of this system is to determine the most prevalent sources of human error in facility operations and to assist in determining where the limited human factors resources should be focused. In this paper the strategy used to educate the organization about the field of human factors is described. Creating an awareness of the importance of human factors engineering in all facets of design, operation, and maintenance is considered to be an important step in reducing the rate of human error

  2. Human Factors and Safety Culture in Maritime Safety (revised

    Directory of Open Access Journals (Sweden)

    Heinz Peter Berg

    2013-09-01

    Full Text Available As in every industry at risk, the human and organizational factors constitute the main stakes for maritime safety. Furthermore, several events at sea have been used to develop appropriate risk models. The investigation on maritime accidents is, nowadays, a very important tool to identify the problems related to human factor and can support accident prevention and the improvement of maritime safety. Part of this investigation should in future also be near misses. Operation of ships is full of regulations, instructions and guidelines also addressing human factors and safety culture to enhance safety. However, even though the roots of a safety culture have been established, there are still serious barriers to the breakthrough of the safety management. One of the most common deficiencies in the case of maritime transport is the respective monitoring and documentation usually lacking of adequacy and excellence. Nonetheless, the maritime area can be exemplified from other industries where activities are ongoing to foster and enhance safety culture.

  3. Importance of human factors on nuclear installations safety

    International Nuclear Information System (INIS)

    Caruso, G.J.

    1990-01-01

    Actually, installations safety and, in particular the nuclear installations infer a strong incidence in human factors related to the design and operation of such installations. In general, the experience aims to that the most important accidents have happened as result of the components' failures combination and human failures in the operation of safety systems. Human factors in the nuclear installations may be divided into two areas: economy and human reliability. Human factors treatments for the safety evaluation of the nuclear installations allow to diagnose the weak points of man-machine interaction. (Author) [es

  4. Human factors in safety and business management.

    Science.gov (United States)

    Vogt, Joachim; Leonhardt, Jorg; Koper, Birgit; Pennig, Stefan

    2010-02-01

    Human factors in safety is concerned with all those factors that influence people and their behaviour in safety-critical situations. In aviation these are, for example, environmental factors in the cockpit, organisational factors such as shift work, human characteristics such as ability and motivation of staff. Careful consideration of human factors is necessary to improve health and safety at work by optimising the interaction of humans with their technical and social (team, supervisor) work environment. This provides considerable benefits for business by increasing efficiency and by preventing incidents/accidents. The aim of this paper is to suggest management tools for this purpose. Management tools such as balanced scorecards (BSC) are widespread instruments and also well known in aviation organisations. Only a few aviation organisations utilise management tools for human factors although they are the most important conditions in the safety management systems of aviation organisations. One reason for this is that human factors are difficult to measure and therefore also difficult to manage. Studies in other domains, such as workplace health promotion, indicate that BSC-based tools are useful for human factor management. Their mission is to develop a set of indicators that are sensitive to organisational performance and help identify driving forces as well as bottlenecks. Another tool presented in this paper is the Human Resources Performance Model (HPM). HPM facilitates the integrative assessment of human factors programmes on the basis of a systematic performance analysis of the whole system. Cause-effect relationships between system elements are defined in process models in a first step and validated empirically in a second step. Thus, a specific representation of the performance processes is developed, which ranges from individual behaviour to system performance. HPM is more analytic than BSC-based tools because HPM also asks why a certain factor is

  5. 76 FR 35130 - Pipeline Safety: Control Room Management/Human Factors

    Science.gov (United States)

    2011-06-16

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

  6. Improving Safety through Human Factors Engineering.

    Science.gov (United States)

    Siewert, Bettina; Hochman, Mary G

    2015-10-01

    Human factors engineering (HFE) focuses on the design and analysis of interactive systems that involve people, technical equipment, and work environment. HFE is informed by knowledge of human characteristics. It complements existing patient safety efforts by specifically taking into consideration that, as humans, frontline staff will inevitably make mistakes. Therefore, the systems with which they interact should be designed for the anticipation and mitigation of human errors. The goal of HFE is to optimize the interaction of humans with their work environment and technical equipment to maximize safety and efficiency. Special safeguards include usability testing, standardization of processes, and use of checklists and forcing functions. However, the effectiveness of the safety program and resiliency of the organization depend on timely reporting of all safety events independent of patient harm, including perceived potential risks, bad outcomes that occur even when proper protocols have been followed, and episodes of "improvisation" when formal guidelines are found not to exist. Therefore, an institution must adopt a robust culture of safety, where the focus is shifted from blaming individuals for errors to preventing future errors, and where barriers to speaking up-including barriers introduced by steep authority gradients-are minimized. This requires creation of formal guidelines to address safety concerns, establishment of unified teams with open communication and shared responsibility for patient safety, and education of managers and senior physicians to perceive the reporting of safety concerns as a benefit rather than a threat. © RSNA, 2015.

  7. SafetyNet. Human factors safety training on the Internet

    DEFF Research Database (Denmark)

    Hauland, G.; Pedrali, M.

    2002-01-01

    This report describes user requirements to an Internet based distance learning system of human factors training, i.e. the SafetyNet prototype, within the aviation (pilots and air traffic control), maritime and medical domains. User requirements totraining have been elicited through 19 semi...

  8. 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

  9. Human and organizational factors in nuclear safety

    International Nuclear Information System (INIS)

    Garcia, A.; Barrientos, M.; Gil, B.

    2015-01-01

    Nuclear installations are socio technical systems where human and organizational factors, in both utilities and regulators, have a significant impact on safety. Three Mile Island (TMI) accident, original of several initiatives in the human factors field, nevertheless became a lost opportunity to timely acquire lessons related to the upper tiers of the system. Nowadays, Spanish nuclear installations have integrated in their processes specialists and activities in human and organizational factors, promoted by the licensees After many years of hard work, Spanish installations have achieved a better position to face new challenges, such as those posed by Fukushima. With this experience, only technology-centered action plan would not be acceptable, turning this accident in yet another lost opportunity. (Author)

  10. Human factors and systems engineering approach to patient safety for radiotherapy.

    Science.gov (United States)

    Rivera, A Joy; Karsh, Ben-Tzion

    2008-01-01

    The traditional approach to solving patient safety problems in healthcare is to blame the last person to touch the patient. But since the publication of To Err is Human, the call has been instead to use human factors and systems engineering methods and principles to solve patient safety problems. However, an understanding of the human factors and systems engineering is lacking, and confusion remains about what it means to apply their principles. This paper provides a primer on them and their applications to patient safety.

  11. Human Factors and Systems Engineering Approach to Patient Safety for Radiotherapy

    International Nuclear Information System (INIS)

    Rivera, A. Joy; Karsh, Ben-Tzion

    2008-01-01

    The traditional approach to solving patient safety problems in healthcare is to blame the last person to touch the patient. But since the publication of To Err is Human, the call has been instead to use human factors and systems engineering methods and principles to solve patient safety problems. However, an understanding of the human factors and systems engineering is lacking, and confusion remains about what it means to apply their principles. This paper provides a primer on them and their applications to patient safety

  12. Patient safety - the role of human factors and systems engineering.

    Science.gov (United States)

    Carayon, Pascale; Wood, Kenneth E

    2010-01-01

    Patient safety is a global challenge that requires knowledge and skills in multiple areas, including human factors and systems engineering. In this chapter, numerous conceptual approaches and methods for analyzing, preventing and mitigating medical errors are described. Given the complexity of healthcare work systems and processes, we emphasize the need for increasing partnerships between the health sciences and human factors and systems engineering to improve patient safety. Those partnerships will be able to develop and implement the system redesigns that are necessary to improve healthcare work systems and processes for patient safety.

  13. Patient Safety: The Role of Human Factors and Systems Engineering

    Science.gov (United States)

    Carayon, Pascale; Wood, Kenneth E.

    2011-01-01

    Patient safety is a global challenge that requires knowledge and skills in multiple areas, including human factors and systems engineering. In this chapter, numerous conceptual approaches and methods for analyzing, preventing and mitigating medical errors are described. Given the complexity of healthcare work systems and processes, we emphasize the need for increasing partnerships between the health sciences and human factors and systems engineering to improve patient safety. Those partnerships will be able to develop and implement the system redesigns that are necessary to improve healthcare work systems and processes for patient safety. PMID:20543237

  14. 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

  15. 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)

  16. Human factors and safety in emergency medicine

    Science.gov (United States)

    Schaefer, H. G.; Helmreich, R. L.; Scheidegger, D.

    1994-01-01

    A model based on an input process and outcome conceptualisation is suggested to address safety-relevant factors in emergency medicine. As shown in other dynamic and demanding environments, human factors play a decisive role in attaining high quality service. Attitudes held by health-care providers, organisational shells and work-cultural parameters determine communication, conflict resolution and workload distribution within and between teams. These factors should be taken into account to improve outcomes such as operational integrity, job satisfaction and morale.

  17. 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

  18. Human factors in safety assessment. Safety culture assessment

    International Nuclear Information System (INIS)

    Zhang Li; Deng Zhiliang; Wang Yiqun; Huang Weigang

    1996-01-01

    This paper analyses the present conditions and problems in enterprises safety assessment, and introduces the characteristics and effects of safety culture. The authors think that safety culture must be used as a 'soul' to form the pattern of modern safety management. Furthermore, they propose that the human safety and synthetic safety management assessment in a system should be changed into safety culture assessment. Finally, the assessment indicators are discussed

  19. 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)

  20. Development of a draft of human factors safety review procedures for the Korean Next Generation Reactor

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C.

    2000-02-01

    In this study, a draft of Human Factors Engineering (HFE) Safety Review Procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE program management, human factors analyses, human factors design, and HFE verification and validation, based on section 15.1 'human factors engineering design process' and 15.2 'control room human factors engineering' of KNGR specific safety requirements and chapter 15 'human factors engineering' of KNGR safety regulatory guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system

  1. Human and organization factors: engineering operating safety into offshore structures

    International Nuclear Information System (INIS)

    Bea, Robert G.

    1998-01-01

    History indicates clearly that the safety of offshore structures is determined primarily by the humans and organizations responsible for these structures during their design, construction, operation, maintenance, and decommissioning. If the safety of offshore structures is to be preserved and improved, then attention of engineers should focus on to how to improve the reliability of the offshore structure 'system,' including the people that come into contact with the structure during its life-cycle. This article reviews and discusss concepts and engineering approaches that can be used in such efforts. Two specific human factor issues are addressed: (1) real-time management of safety during operations, and (2) development of a Safety Management Assessment System to help improve the safety of offshore structures

  2. Development of a draft of human factors safety review procedures for the Korean next generation reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-02-01

    In this study, a draft of human factors engineering (HFE) safety review procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE Program Management, Human Factors Analyses, Human Factors Design, and HFE Verification and Validation, based on Section 15.1 'Human Factors Engineering Design Process' and 15.2 'Control Room Human Factors Engineering' of KNGR Specific Safety Requirements and Chapter 15 'Human Factors Engineering' of KNGR Safety Regulatory Guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system. 8 refs., 2 figs. (Author)

  3. 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

  4. 75 FR 5536 - Pipeline Safety: Control Room Management/Human Factors, Correction

    Science.gov (United States)

    2010-02-03

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts...: Control Room Management/Human Factors, Correction AGENCY: Pipeline and Hazardous Materials Safety... following correcting amendments: PART 192--TRANSPORTATION OF NATURAL AND OTHER GAS BY PIPELINE: MINIMUM...

  5. 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.)

  6. Modelling of safety barriers including human and organisational factors to improve process safety

    DEFF Research Database (Denmark)

    Markert, Frank; Duijm, Nijs Jan; Thommesen, Jacob

    2013-01-01

    It is believed that traditional safety management needs to be improved on the aspect of preparedness for coping with expected and unexpected deviations, avoiding an overly optimistic reliance on safety systems. Remembering recent major accidents, such as the Deep Water Horizon, the Texas City....... A valuable approach is the inclusion of human and organisational factors into the simulation of the reliability of the technical system using event trees and fault trees and the concept of safety barriers. This has been demonstrated e.g. in the former European research project ARAMIS (Accidental Risk...

  7. 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

  8. National plan to enhance aviation safety through human factors improvements

    Science.gov (United States)

    Foushee, Clay

    1990-01-01

    The purpose of this section of the plan is to establish a development and implementation strategy plan for improving safety and efficiency in the Air Traffic Control (ATC) system. These improvements will be achieved through the proper applications of human factors considerations to the present and future systems. The program will have four basic goals: (1) prepare for the future system through proper hiring and training; (2) develop a controller work station team concept (managing human errors); (3) understand and address the human factors implications of negative system results; and (4) define the proper division of responsibilities and interactions between the human and the machine in ATC systems. This plan addresses six program elements which together address the overall purpose. The six program elements are: (1) determine principles of human-centered automation that will enhance aviation safety and the efficiency of the air traffic controller; (2) provide new and/or enhanced methods and techniques to measure, assess, and improve human performance in the ATC environment; (3) determine system needs and methods for information transfer between and within controller teams and between controller teams and the cockpit; (4) determine how new controller work station technology can optimally be applied and integrated to enhance safety and efficiency; (5) assess training needs and develop improved techniques and strategies for selection, training, and evaluation of controllers; and (6) develop standards, methods, and procedures for the certification and validation of human engineering in the design, testing, and implementation of any hardware or software system element which affects information flow to or from the human.

  9. [Human factors and crisis resource management: improving patient safety].

    Science.gov (United States)

    Rall, M; Oberfrank, S

    2013-10-01

    A continuing high number of patients suffer harm from medical treatment. In 60-70% of the cases the sources of harm can be attributed to the field of human factors (HFs) and teamwork; nevertheless, those topics are still neither part of medical education nor of basic and advanced training even though it has been known for many years and it has meanwhile also been demonstrated for surgical specialties that training in human factors and teamwork considerably reduces surgical mortality.Besides the medical field, the concept of crisis resource management (CRM) has already proven its worth in many other industries by improving teamwork and reducing errors in the domain of human factors. One of the best ways to learn about CRM and HFs is realistic simulation team training with well-trained instructors in CRM and HF. The educational concept of the HOTT (hand over team training) courses for trauma room training offered by the DGU integrates these elements based on the current state of science. It is time to establish such training for all medical teams in emergency medicine and operative care. Accompanying safety measures, such as the development of a positive culture of safety in every department and the use of effective critical incident reporting systems (CIRs) should be pursued.

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

    Science.gov (United States)

    2010-11-16

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

  11. Human factors and fuzzy set theory for safety analysis

    International Nuclear Information System (INIS)

    Nishiwaki, Y.

    1987-01-01

    Human reliability and performance is affected by many factors: medical, physiological and psychological, etc. The uncertainty involved in human factors may not necessarily be probabilistic, but fuzzy. Therefore, it is important to develop a theory by which both the non-probabilistic uncertainties, or fuzziness, of human factors and the probabilistic properties of machines can be treated consistently. In reality, randomness and fuzziness are sometimes mixed. From the mathematical point of view, probabilistic measures may be considered a special case of fuzzy measures. Therefore, fuzzy set theory seems to be an effective tool for analysing man-machine systems. The concept 'failure possibility' based on fuzzy sets is suggested as an approach to safety analysis and fault diagnosis of a large complex system. Fuzzy measures and fuzzy integrals are introduced and their possible applications are also discussed. (author)

  12. Missing focus on Human Factors - organizational and cognitive ergonomics - in the safety management for the petroleum industry.

    Science.gov (United States)

    Johnsen, Stig O; Kilskar, Stine Skaufel; Fossum, Knut Robert

    2017-08-01

    More attention has recently been given to Human Factors in petroleum accident investigations. The Human Factors areas examined in this article are organizational, cognitive and physical ergonomics. A key question to be explored is as follows: To what degree are the petroleum industry and safety authorities in Norway focusing on these Human Factors areas from the design phase? To investigate this, we conducted an innovative exploratory study of the development of four control centres in Norwegian oil and gas industry in collaboration between users, management and Human Factors experts. We also performed a literature survey and discussion with the professional Human Factors network in Norway. We investigated the Human Factors focus, reasons for not considering Human Factors and consequences of missing Human Factors in safety management. The results revealed an immature focus and organization of Human Factors. Expertise on organizational ergonomics and cognitive ergonomics are missing from companies and safety authorities and are poorly prioritized during the development. The easy observable part of Human Factors (i.e. physical ergonomics) is often in focus. Poor focus on Human Factors in the design process creates demanding conditions for human operators and impact safety and resilience. There is lack of non-technical skills such as communication and decision-making. New technical equipment such as Closed Circuit Television is implemented without appropriate use of Human Factors standards. Human Factors expertise should be involved as early as possible in the responsible organizations. Verification and validation of Human Factors should be improved and performed from the start, by certified Human Factors experts in collaboration with the workforce. The authorities should check-back that the regulatory framework of Human Factors is communicated, understood and followed.

  13. 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.)

  14. 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)

  15. Human Factors in Fire Safety Management and Prevention

    Directory of Open Access Journals (Sweden)

    M.A. Othuman Mydin

    2014-07-01

    Full Text Available Fire protection is the study and practice of mitigating the unwanted effects of potentially destructive fires. It involves the study of the behavior, compartmentalization, and investigation of fire and its related emergencies, as well as the research and development, production, testing and application of mitigating systems. Problems still occurred despite of the adequate fire safety systems installed. For most people in high-risk buildings, not all accidents were caused by them. They were more likely to be the victims of a fire that occurred. Besides damaging their properties and belongings, some people were burned to death for not knowing what to do if fire happens in their place. This paper will present the human factors in fire safety management and prevention system.

  16. The consideration of the humane factor is essential in safety systems

    International Nuclear Information System (INIS)

    Parisot, F.

    2010-01-01

    In most risk analysis we consider that the staff fit perfectly the tasks to do in terms of training and competence but in fact a lot of factors intervene like the level of stress of the operator, the time available to identify the trouble or to take a decision, the relevance of the procedures, or the level of coordination and communication between the members of the staff. Different methods exist to assess the human factor, most have been designed to be used in the nuclear sector for instance: THERP (Technique for Human Error Rate Prediction) or OATS (Operation Action Tree) or SHARP (Systematic Human Action Reliability Procedure). These methods apply as early as the design stage of the engineered safety systems. Virtual reality has entered these methods because it allows operators to learn by making errors since errors in virtual reality have no consequences. Learning by making errors is an efficient method to get the operator used to accidental situations and as a consequence to reduce his level of stress. Some methods incorporate human elements into system safety analysis through the definition of performance shaping factors that describe the behaviour of operators in terms of physical and psychological abilities. (A.C.)

  17. 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

  18. Infrastructural and Human Factors Affecting Safety Outcomes of Cyclists

    Directory of Open Access Journals (Sweden)

    Sergio Useche

    2018-01-01

    Full Text Available The increasing number of registered road crashes involving cyclists during the last decade and the high proportion of road crashes resulting in severe injuries and fatalities among cyclists constitutes a global issue for community health, urban development and sustainability. Nowadays, the incidence of many risk factors for road crashes of cyclists remains largely unexplained. Given the importance of this issue, the present study has been conducted with the aim of determining relationships between infrastructural, human factors and safety outcomes of cyclists. Objectives: This study aimed, first, to examine the relationship between key infrastructural and human factors present in cycling, bicycle-user characteristics and their self-reported experience with road crashes. And second, to determine whether a set of key infrastructural and human factors may predict their self-reported road crashes. Methods: For this cross-sectional study, a total of 1064 cyclists (38.8% women, 61.2% men; M = 32.8 years of age from 20 different countries across Europe, South America and North America, participated in an online survey composed of four sections: demographic data and cycling-related factors, human factors, perceptions on infrastructural factors and road crashes suffered. Results: The results of this study showed significant associations between human factors, infrastructural conditions and self-reported road crashes. Also, a logistic regression model found that self-reported road crashes of cyclists could be predicted through variables such as age, riding intensity, risky behaviours and problematic user/infrastructure interactions. Conclusions: The results of this study suggest that self-reported road crashes of cyclists are influenced by features related to the user and their interaction with infrastructural characteristics of the road.

  19. Human Factors engineering criteria and design for the Hanford Waste Vitrification Plant preliminary safety analysis report

    International Nuclear Information System (INIS)

    Wise, J.A.; Schur, A.; Stitzel, J.C.L.

    1993-09-01

    This report provides a rationale and systematic methodology for bringing Human Factors into the safety design and operations of the Hanford Waste Vitrification Plant (HWVP). Human Factors focuses on how people perform work with tools and machine systems in designed settings. When the design of machine systems and settings take into account the capabilities and limitations of the individuals who use them, human performance can be enhanced while protecting against susceptibility to human error. The inclusion of Human Factors in the safety design of the HWVP is an essential ingredient to safe operation of the facility. The HWVP is a new construction, nonreactor nuclear facility designed to process radioactive wastes held in underground storage tanks into glass logs for permanent disposal. Its design and mission offer new opposites for implementing Human Factors while requiring some means for ensuring that the Human Factors assessments are sound, comprehensive, and appropriately directed

  20. 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

  1. 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)

  2. Analysis of human factors effects on the safety of transporting radioactive waste materials: Technical report

    Energy Technology Data Exchange (ETDEWEB)

    Abkowitz, M.D.; Abkowitz, S.B.; Lepofsky, M.

    1989-04-01

    This report examines the extent of human factors effects on the safety of transporting radioactive waste materials. It is seen principally as a scoping effort, to establish whether there is a need for DOE to undertake a more formal approach to studying human factors in radioactive waste transport, and if so, logical directions for that program to follow. Human factors effects are evaluated on driving and loading/transfer operations only. Particular emphasis is placed on the driving function, examining the relationship between human error and safety as it relates to the impairment of driver performance. Although multi-modal in focus, the widespread availability of data and previous literature on truck operations resulted in a primary study focus on the trucking mode from the standpoint of policy development. In addition to the analysis of human factors accident statistics, the report provides relevant background material on several policies that have been instituted or are under consideration, directed at improving human reliability in the transport sector. On the basis of reported findings, preliminary policy areas are identified. 71 refs., 26 figs., 5 tabs.

  3. The balance between safety and productivity and its relationship with human factors and safety awareness and communication in aircraft manufacturing

    NARCIS (Netherlands)

    Karanikas, N.; Melis, Damien Jose; Kourousis, Kyriakos

    2017-01-01

    Background: This paper presents the findings of a pilot research survey which assessed the degree of balance between safety and productivity, and its relationship with awareness and communication of human factors and safety rules in the aircraft manufacturing environment. Methods: The study was

  4. Human factors and safe patient care.

    Science.gov (United States)

    Norris, Beverley

    2009-03-01

    This paper aims to introduce the topic of human factors to nursing management and to identify areas where it can be applied to patient safety. Human factors is a discipline established in most safety critical industries and uses knowledge about human behaviour in the analysis and design of complex systems, yet it is relatively new to many in healthcare. Most safety critical industries have developed tools and techniques to apply human factors to system design, and these have been reviewed together with those resources already available for use in healthcare. Models of human behaviour such as the nature and patterns of human error, information processing, decision-making and team work have clear applications to healthcare. Human factors focus on a system view of safety, and propose that safety should, where possible, be 'designed in'. Other interventions such as building defences, mitigating hazards and education and training should only be used where design solutions cannot be found. Simple human factors principles such as: designing for standardization; the involvement of users and staff in designing services and procuring equipment; understanding how errors occur; and the workarounds that staff will inevitably take are vital considerations in improving patient safety. Opportunities for the application of human factors to healthcare and improved patient safety are discussed. Some existing tools and techniques for applying human factors in nursing management are also presented.

  5. Safety of recombinant human platelet-derived growth factor-BB in Augment® Bone Graft

    Directory of Open Access Journals (Sweden)

    Luis A Solchaga

    2012-12-01

    Full Text Available This article discusses nonclinical and clinical data regarding the safety of recombinant human platelet-derived growth factor-BB as a component of the Augment® Bone Graft (Augment. Augment is a bone graft substitute intended to be used as an alternative to autologous bone graft in the fusion of hindfoot and ankle joints. Nonclinical studies included assessment of the pharmacokinetic profile of intravenously administered recombinant human platelet-derived growth factor-BB in rat and dog, effects of intravenous administration of recombinant human platelet-derived growth factor-BB in a reproductive and development toxicity study in rats, and chronic toxicity and carcinogenicity of Augment in a 12-month implantation model. These studies showed that systemic exposure was brief and clearance was rapid. No signs of toxicity, carcinogenicity, or tumor promotion were observed even with doses far exceeding the maximum clinical dose. Results of clinical trials (605 participants and commercial use of recombinant human platelet-derived growth factor-BB containing products indicate that these products are not associated with increased incidence of adverse events or cancer. The safety data presented provide evidence that recombinant human platelet-derived growth factor-BB is a safe therapeutic when used in combination products as a single administration during surgical procedures for bone repair and fusion. There is no evidence associating use of recombinant human platelet-derived growth factor-BB in Augment with chronic toxicity, carcinogenicity, or tumor promotion.

  6. Operation, Safety and Human: Critical Factors for the Success of Railway Transportation

    NARCIS (Netherlands)

    Rajabali Nejad, Mohammadreza; Martinetti, Alberto; van Dongen, Leonardus Adriana Maria

    2016-01-01

    This paper focuses on three categories of performance indicators for railway transportation: the excellence of operation, system safety and human factors. These are among the most critical indicators for delivering high quality services. This paper discusses the main issues, challenges and future

  7. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang

    2006-01-01

    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 Yonggwang Unit no. 1, 2. 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

  8. Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

    2006-01-15

    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 Yonggwang Unit no. 1, 2. 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.

  9. Probabilistic safety assessment model in consideration of human factors based on object-oriented bayesian networks

    International Nuclear Information System (INIS)

    Zhou Zhongbao; Zhou Jinglun; Sun Quan

    2007-01-01

    Effect of Human factors on system safety is increasingly serious, which is often ignored in traditional probabilistic safety assessment methods however. A new probabilistic safety assessment model based on object-oriented Bayesian networks is proposed in this paper. Human factors are integrated into the existed event sequence diagrams. Then the classes of the object-oriented Bayesian networks are constructed which are converted to latent Bayesian networks for inference. Finally, the inference results are integrated into event sequence diagrams for probabilistic safety assessment. The new method is applied to the accident of loss of coolant in a nuclear power plant. the results show that the model is not only applicable to real-time situation assessment, but also applicable to situation assessment based certain amount of information. The modeling complexity is kept down and the new method is appropriate to large complex systems due to the thoughts of object-oriented. (authors)

  10. 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

  11. 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)

  12. 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)

  13. Safety assessment of human and organizational factors in French fuel cycle facilities

    International Nuclear Information System (INIS)

    Menuet, Lise; Beauquier, Sophie

    2013-01-01

    According to the French law, each nuclear facility has to provide a safety demonstration every ten years. The assessment of this demonstration supports the decision of the French Safety Authority regarding the authorisation of operating for the ten years to come. In addition, transversal topics, which are linked with safety performance, such as safety management, management of competencies, maintenance's policy are periodically evaluated. One aspect of these assessments relates to Human and Organizational Factors (HOF) and their contribution to safety. Our communication will describe the assessment of the HOF-related part, performed by the Institute for Radioprotection and Nuclear Safety Institute (IRSN) the Technical Support Organisation of the French Safety Authority). It will focus on the methodological framework, the tools which are developed and used for assessing the integration of HOF in safety demonstration, and the main difficulties of this kind of assessment. Each situation will be illustrated by concrete examples coming from safety assessments concerning fuel cycle's plants: Areva's plants dedicated to uranium conversion, uranium enrichment, fuel manufacturing, spent fuel reprocessing, treatment facilities and CEA's laboratories dedicated to research and development and to interim spent fuel storage. The methodological framework for assessing HOF currently implements three main steps which will be precisely described: - checking that the nuclear plant has made an exhaustive analysis of the risks linked with HOF. Regarding to HOF, the Licensee safety demonstration is based on the description of the main human activities which are considered as hazardous regarding safety. These activities are accomplished with a human contribution and they require a safe realisation. - assessing the human, organisational and technical barriers that the nuclear plant have planed in order to make the operations safe, to avoid, prevent or detect an

  14. Integrated approach to knowledge acquisition and safety management of complex plants with emphasis on human factors

    International Nuclear Information System (INIS)

    Kosmowski, K.T.

    1998-01-01

    In this paper an integrated approach to the knowledge acquisition and safety management of complex industrial plants is proposed and outlined. The plant is considered within a man-technology-environment (MTE) system. The knowledge acquisition is aimed at the consequent reliability evaluation of human factor and probabilistic modeling of the plant. Properly structured initial knowledge is updated in life-time of the plant. The data and knowledge concerning the topology of safety related systems and their functions are created in a graphical CAD system and are object oriented. Safety oriented monitoring of the plant includes abnormal situations due to external and internal disturbances, failures of hard/software components and failures of human factor. The operation and safety related evidence is accumulated in special data bases. Data/knowledge bases are designed in such a way to support effectively the reliability and safety management of the plant. (author)

  15. 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

  16. 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

  17. The use of human factors methods to identify and mitigate safety issues in radiation therapy

    International Nuclear Information System (INIS)

    Chan, Alvita J.; Islam, Mohammad K.; Rosewall, Tara; Jaffray, David A.; Easty, Anthony C.; Cafazzo, Joseph A.

    2010-01-01

    Background and purpose: New radiation therapy technologies can enhance the quality of treatment and reduce error. However, the treatment process has become more complex, and radiation dose is not always delivered as intended. Using human factors methods, a radiotherapy treatment delivery process was evaluated, and a redesign was undertaken to determine the effect on system safety. Material and methods: An ethnographic field study and workflow analysis was conducted to identify human factors issues of the treatment delivery process. To address specific issues, components of the user interface were redesigned through a user-centered approach. Sixteen radiation therapy students were then used to experimentally evaluate the redesigned system through a usability test to determine the effectiveness in mitigating use errors. Results: According to findings from the usability test, the redesigned system successfully reduced the error rates of two common errors (p < .04 and p < .01). It also improved the mean task completion time by 5.5% (p < .02) and achieved a higher level of user satisfaction. Conclusions: These findings demonstrated the importance and benefits of applying human factors methods in the design of radiation therapy systems. Many other opportunities still exist to improve patient safety in this area using human factors methods.

  18. 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

  19. Human Factors Evaluation of Procedures for Periodic Safety Review of Yonggwang Unit no. 1, 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

    2006-01-15

    This report describes the results of human factors assessment on the plant operating procedures as part of Periodic Safety Review(PSR) of Yonggwang Nuclear Power Plant Unit no. 1, 2. The suitability of item and appropriateness of format and structure in the key operating procedures of nuclear power plants were investigated by the review of plant operating experiences and procedure documents, field survey, and experimental assessment on some part of procedures. A checklist was used to perform this assessment and record the review results. The reviewed procedures include EOP(Emergency Operating Procedures), GOP(General Operating Procedures), AOP(Abnormal Operating Procedures), and management procedures of some technical departments. As results of the assessments, any significant problem challenging the safety was not found on the human factors in the operating procedures. However, several small items to be changed and improved were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on the operating procedure.

  20. 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)

  1. Human factors science and safety engineering : can the STAMP model serve in establishing a common language?

    NARCIS (Netherlands)

    Karanikas, Nektarios; Schwarz, M; Harfmann, J

    2017-01-01

    A symbiotic relationship between human factors and safety scientists is needed to ensure the provision of holistic solutions for problems emerging in modern socio-technical systems. System Theoretic Accident Model and Processes (STAMP) tackles both interactions and individual failures of human and

  2. Development of Human Factor Management Requirements and Human Error Classification for the Prevention of Railway Accident

    International Nuclear Information System (INIS)

    Kwak, Sang Log; Park, Chan Woo; Shin, Seung Ryoung

    2008-08-01

    Railway accident analysis results show that accidents cased by human factors are not decreasing, whereas H/W related accidents are steadily decreasing. For the efficient management of human factors, many expertise on design, conditions, safety culture and staffing are required. But current safety management activities on safety critical works are focused on training, due to the limited resource and information. In order to improve railway safety, human factors management requirements for safety critical worker and human error classification is proposed in this report. For this accident analysis, status of safety measure on human factor, safety management system on safety critical worker, current safety planning is analysis

  3. 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

  4. Human factors of safety: a few landmarks

    International Nuclear Information System (INIS)

    Mosneron Dupin, F.

    1992-06-01

    This paper discusses factors to be taken into account, and methods to be used. It concludes that more realistic and positive conceptions of Human Factors should be developed, and that Human Factors should be addressed at the very beginning of any technical project

  5. 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)

  6. Development of safety and regulatory requirements for Korean next generation reactor - Development of human factors design review guidelines (II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Lee, Hyun Chul; Cheon, Se Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25. Human Factors Engineering Program Review Model' and '26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and the characteristics of the KNGR design, and reviewing the reference documents of NURGE-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides at KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system design review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we updated the guidelines by reviewing the literature related to alarm design that published after 1994. 12 refs., 11 figs., 2 tabs. (Author)

  7. Development of safety and regulatory requirements for Korean next generation reactor - Development of human factors design review guidelines (II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Lee, Hyun Chul; Cheon, Se Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25. Human Factors Engineering Program Review Model' and '26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and the characteristics of the KNGR design, and reviewing the reference documents of NURGE-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides at KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system design review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we updated the guidelines by reviewing the literature related to alarm design that published after 1994. 12 refs., 11 figs., 2 tabs. (Author)

  8. 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

  9. The science of human factors: separating fact from fiction.

    Science.gov (United States)

    Russ, Alissa L; Fairbanks, Rollin J; Karsh, Ben-Tzion; Militello, Laura G; Saleem, Jason J; Wears, Robert L

    2013-10-01

    Interest in human factors has increased across healthcare communities and institutions as the value of human centred design in healthcare becomes increasingly clear. However, as human factors is becoming more prominent, there is growing evidence of confusion about human factors science, both anecdotally and in scientific literature. Some of the misconceptions about human factors may inadvertently create missed opportunities for healthcare improvement. The objective of this article is to describe the scientific discipline of human factors and provide common ground for partnerships between healthcare and human factors communities. The primary goal of human factors science is to promote efficiency, safety and effectiveness by improving the design of technologies, processes and work systems. As described in this article, human factors also provides insight on when training is likely (or unlikely) to be effective for improving patient safety. Finally, we outline human factors specialty areas that may be particularly relevant for improving healthcare delivery and provide examples to demonstrate their value. The human factors concepts presented in this article may foster interdisciplinary collaborations to yield new, sustainable solutions for healthcare quality and patient safety.

  10. Insight and Lessons Learned on Organizational Factors and Safety Culture from the Review of Human Error-related Events of NPPs in Korea

    International Nuclear Information System (INIS)

    Kim, Ji Tae; Lee, Dhong Hoon; Choi, Young Sung

    2014-01-01

    Event investigation is one of the key means of enhancing nuclear safety deriving effective measures and preventing recurrences. However, it is difficult to analyze organizational factors and safety culture. This paper tries to review human error-related events from perspectives of organizational factors and safety culture, and to derive insights and lessons learned in developing the regulatory infrastructure of plant oversight on safety culture

  11. Insight and Lessons Learned on Organizational Factors and Safety Culture from the Review of Human Error-related Events of NPPs in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Tae; Lee, Dhong Hoon; Choi, Young Sung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-08-15

    Event investigation is one of the key means of enhancing nuclear safety deriving effective measures and preventing recurrences. However, it is difficult to analyze organizational factors and safety culture. This paper tries to review human error-related events from perspectives of organizational factors and safety culture, and to derive insights and lessons learned in developing the regulatory infrastructure of plant oversight on safety culture.

  12. A probabilistic analysis method to evaluate the effect of human factors on plant safety

    International Nuclear Information System (INIS)

    Ujita, H.

    1987-01-01

    A method to evaluate the effect of human factors on probabilistic safety analysis (PSA) is developed. The main features of the method are as follows: 1. A time-dependent multibranch tree is constructed to treat time dependency of human error probability. 2. A sensitivity analysis is done to determine uncertainty in the PSA due to branch time of human error occurrence, human error data source, extraneous act probability, and human recovery probability. The method is applied to a large-break, loss-of-coolant accident of a boiling water reactor-5. As a result, core melt probability and risk do not depend on the number of time branches, which means that a small number of branches are sufficient. These values depend on the first branch time and the human error probability

  13. 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

  14. [Human factors in medicine].

    Science.gov (United States)

    Lazarovici, M; Trentzsch, H; Prückner, S

    2017-01-01

    The concept of human factors is commonly used in the context of patient safety and medical errors, all too often ambiguously. In actual fact, the term comprises a wide range of meanings from human-machine interfaces through human performance and limitations up to the point of working process design; however, human factors prevail as a substantial cause of error in complex systems. This article presents the full range of the term human factors from the (emergency) medical perspective. Based on the so-called Swiss cheese model by Reason, we explain the different types of error, what promotes their emergence and on which level of the model error prevention can be initiated.

  15. Meeting Human Reliability Requirements through Human Factors Design, Testing, and Modeling

    Energy Technology Data Exchange (ETDEWEB)

    R. L. Boring

    2007-06-01

    In the design of novel systems, it is important for the human factors engineer to work in parallel with the human reliability analyst to arrive at the safest achievable design that meets design team safety goals and certification or regulatory requirements. This paper introduces the System Development Safety Triptych, a checklist of considerations for the interplay of human factors and human reliability through design, testing, and modeling in product development. This paper also explores three phases of safe system development, corresponding to the conception, design, and implementation of a system.

  16. Evolution of human factors research and studies of health information technologies: the role of patient safety

    NARCIS (Netherlands)

    Beuscart-Zéphir, M. C.; Borycki, E.; Carayon, P.; Jaspers, M. W. M.; Pelayo, S.

    2013-01-01

    The objective of this survey paper is to present and explain the impact of recent regulations and patient safety initiatives (EU, US and Canada) on Human Factors (HF)/Usability studies and research focusing on Health Information Technology (HIT). The authors have selected the most prominent of these

  17. Human factors in atomic power plant

    International Nuclear Information System (INIS)

    Kawano, Ryutaro

    1997-01-01

    To ensure safety should have priority over all other things in atomic power plants. In Chernobyl accident, however, various human factors including the systems for bulb check after inspection and communication, troubles in the interface between hardwares such as warning speakers and instruments, and their operators, those in education and training for operators and those in the general management of the plant have been pointed out. Therefore, the principles and the practical measures from the aspect of human factors in atomic power plants were discussed here. The word, ''human factor'' was given a definition in terms of the direct cause and the intellectual system. An explanatory model for human factors, model SHEL constructed by The Tokyo Electric Power Co., Ltd., Inc. was presented; the four letter mean software(S), hardware(H), environment(E) and liveware(L). In the plants of the company, systemic measures for human error factors are taken now in all steps not only for design, operation and repairing but also the step for safety culture. Further, the level required for the safety against atomic power is higher in the company than those in other fields. Thus, the central principle in atomic power plants is changing from the previous views that technology is paid greater importance to a view regarding human as most importance. (M.N.)

  18. 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

  19. 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

  20. 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.

  1. The contributions of human factors on human error in Malaysia aviation maintenance industries

    Science.gov (United States)

    Padil, H.; Said, M. N.; Azizan, A.

    2018-05-01

    Aviation maintenance is a multitasking activity in which individuals perform varied tasks under constant pressure to meet deadlines as well as challenging work conditions. These situational characteristics combined with human factors can lead to various types of human related errors. The primary objective of this research is to develop a structural relationship model that incorporates human factors, organizational factors, and their impact on human errors in aviation maintenance. Towards that end, a questionnaire was developed which was administered to Malaysian aviation maintenance professionals. Structural Equation Modelling (SEM) approach was used in this study utilizing AMOS software. Results showed that there were a significant relationship of human factors on human errors and were tested in the model. Human factors had a partial effect on organizational factors while organizational factors had a direct and positive impact on human errors. It was also revealed that organizational factors contributed to human errors when coupled with human factors construct. This study has contributed to the advancement of knowledge on human factors effecting safety and has provided guidelines for improving human factors performance relating to aviation maintenance activities and could be used as a reference for improving safety performance in the Malaysian aviation maintenance companies.

  2. How to evaluate the effectiveness of safety assessment in the area of human factors?

    International Nuclear Information System (INIS)

    Rolina, G.; Moisdon, J.C.; Jeffroy, F.

    2007-01-01

    The Three Mile Island nuclear reactor accident in 1979 led to a new approach regarding safety that includes a better consideration of man and his activities. A few years later, with the set up of a group of specialists at Electricite de France and at the Institute for Radiological Protection and Nuclear Safety, a new player appeared at France's nuclear safety organisation: the assessment expert specialising in human factors (HF). The improvement of man-machine interfaces was one of the first projects undertaken by the HF experts, the majority of whom specialise in ergonomics. A review of the literature and analysis of the archives, revealed that the specialists' scope of investigation has since increased; so that organisation is also the subject of HF assessment. However, this area is not one of consensual or established knowledge; neither researchers nor specialists can agree on a model of safe organisation. What then can we say about effectiveness of HF assessment? How can we define the criteria of effectiveness of a safety assessment production system in this area? The question is the subject of original research based on collaboration between the scientific management centre (CGS) of the Ecole des Mines in Paris and the section for the study of human factors (SEFH) at IRSN. To address this question, the CGS team monitors some assessments to which SEFH contributes. In other words, it attends different meetings on framing, technical instruction, reporting, taking notes and collecting related documents (minutes of meetings,...). It carries out additional interviews with different parties involved in assessment in order to ascertain their point of view. A sample of five assessments was defined to cover a varied number of situations encountered by the team of HF experts. The type of facility, the operator and the subject concerned are some of the variables integrated for this choice

  3. Research on disaster prevention by human factor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bok Youn; Kang, Chang Hee; Kang, Sun Duck; Jo, Young Do [Korea Institute of Geology Mining and Materials, Taejon (Korea)

    1998-12-01

    Mining, by its very nature, requires workers and technology to function in an unpredictable environment that can not easily be engineered to accommodate human factors. Miners' physical and cognitive capabilities are sometimes stretched to the point that 'human error' in performance result. Mine safety researchers estimate that 50-85% of all mining injuries are due, in large part, to human error. Further research suggests that the primary causes of these errors in performance lie outside the individual and can be minimized by improvements in equipment design, work environments, work procedures and training. The human factors research is providing the science needed to determine which aspects of the mining environment can be made more worker-friendly and how miners can work more safely in environments that can not be improved. Underground mines have long been recognized as an innately hazardous and physically demanding work environment. Recently, mining is becoming a more complicated process as more sophisticated technologies are introduced. The more complicated or difficult the tasks to be performed, the more critical it is to have a systematic understanding of the humans, the technology, the environments, and how they interact. Human factors is a key component in solving most of today's mine safety and health problems. Human factors research primarily centered around solving problems in the following four areas: 1) How mining methods and equipment affect safety, 2) Evaluating the fit between miner's physical capabilities and the demands of their job, 3) Improving miner's ability to perceive and react to hazards, 4) Understanding how organizational and managerial variables influence safety. Human factor research was begun during the World war II. National Coal Board (British Coal) of Great Britain commenced ergonomics in 1969, and Bureau of Mine of United States started human factor researches in same year. Japan has very short history

  4. 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

  5. A quantitative assessment of organizational factors affecting safety using a system dynamics model

    International Nuclear Information System (INIS)

    Yoo, J. K.; Yoon, T. S.

    2003-01-01

    The purpose of this study is to develop a system dynamics model for the assessment of organizational and human factors in the nuclear power plant safety. Previous studies are classified into two major approaches. One is the engineering approach such as ergonomics and Probabilistic Safety Assessment (PSA). The other is socio-psychology one. Both have contributed to find organizational and human factors and increased nuclear safety However, since these approaches assume that the relationship among factors is independent they do not explain the interactions between factors or variables in NPP's. To overcome these restrictions, a system dynamics model, which can show causal relations between factors and quantify organizational and human factors, has been developed. Operating variables such as degree of leadership, adjustment of number of employee, and workload in each department, users can simulate various situations in nuclear power plants in the organization side. Through simulation, user can get an insight to improve safety in plants and to find managerial tools in the organization and human side

  6. Human Factors in Nuclear Reactor Accidents

    International Nuclear Information System (INIS)

    Mustafa, M.E.

    2016-01-01

    While many people would blame nature for the disaster of the “Fukushima Daiichi” accident, experts considered this accident to be also a human-induced disaster. This confirmed the importance of human errors which have been getting a growing interest in the nuclear field after the Three Mile Island accident. Personnel play an important role in design, operation, maintenance, planning, and management. The interface between machine and man is known as a human factor. In the present work, the human factors that have to be considered were discussed. The effect of the control room configuration and equipment design effect on the human behavior was also discussed. Precise reviewing of person’s qualifications and experience was focused. Insufficient training has been a major cause of human error in the nuclear field. The effective training issues were introduced. Avoiding complicated operational processes and non responsive management systems was stressed. Distinguishing between the procedures for normal and emergency operations was emphasised. It was stated that human error during maintenance and testing activities could cause a serious accident. This is because safety systems do not cover much more risk probabilities in the maintenance and testing activities like they do in the normal operation. In nuclear industry, the need for a classification and identification of human errors has been well recognised. As a result of this, human reliability must be assessed. These errors are analyzed by a probabilistic safety assessment which deals with errors in reading, listening and implementing procedures but not with cognitive errors. Much efforts must be accomplished to consider cognitive errors in the probabilistic safety assessment. The ways of collecting human factor data were surveyed. The methods for identifying safe designs, helping decision makers to predict how proposed or current policies will affect safety, and comprehensive understanding of the relationship

  7. Role of human factors in system safety

    International Nuclear Information System (INIS)

    Brooks, D. M.; Robert, C.; Graham, T.

    2008-01-01

    What happens when technology goes wrong? Three Mile Island, Chernobyl, space shuttles Challenger and Columbia, numerous airplane crashes, and other notable and newsworthy as well as many more incidents that are not reported on the news, have all been attributed to human error. Millions of dollars in fines are levied against industry under the General Duty clause for ergonomic violations, all avoidable. These incidents and situations indicate a lack of consideration for the humans in the system during the design phase. As a consequence, all of these organizations had to retrofit, had to redesign and had to pay countless dollars for medical costs, Worker's Compensation, OSHA fines and in some instances had irrecoverable damage to their public image. Human Factors, otherwise known as Engineering Psychology or Ergonomics, found its origins in loss, loss of life, loss of confidence, loss of technology, loss of property. Without loss, there would be no need for human factors. No one really 'attends' to discomfort...nor are errors attended to that have little consequence. Often it is ultimately the compilation and cumulative effects of these smaller and often ignored occurrences that lead to the bigger and more tragic incidents that make the evening news. When an incident or accident occurs, they are frequently attributed to accomplished, credible, experienced people. In reality however, the crisis was inevitable when a series of events happen such that a human is caught in the whirlwind of accident sequence. The world as known is becoming smaller and more complex. Highly technical societies have been hard at work for several centuries rebuilding the world out of cold steel that is very far removed from ancient instincts and traditions and is becoming more remote to human users. The growth of technology is more than exponential, and is virtually beyond comprehension for many people. Humans, feeling comfortable with the familiar, fulfill their propensity to implement new

  8. 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

  9. Decommissioning: Regulatory activities and identification of key organizational and human factors safety issues

    International Nuclear Information System (INIS)

    Durbin, N.E.; Melber, B.D.; Lekberg, A.

    2001-12-01

    In the late 1990's the Swedish government decided to shut down Unit 1 of the Barsebaeck nuclear power plant. This report documents some of the efforts made by the Swedish Nuclear Power Inspectorate (SKI) to address human factors and organizational issues in nuclear safety during decommissioning of a nuclear facility. This report gives a brief review of the background to the decommissioning of Barsebaeck 1 and points out key safety issues that can arise during decommissioning. The main regulatory activities that were undertaken were requirements that the plant provide special safety reports on decommissioning focusing on first, the operation of both units until closure of Unit 1 and second, the operation of Unit 2 when Unit 1 was closed. In addition, SKI identified areas that might be affected by decommissioning and called these areas out for special attention. With regard to these areas of special attention, SKI required that the plant provide monthly reports on changing and emerging issues as well as self-assessments of the areas to be addressed in the special safety reports. Ten key safety issues were identified and evaluated with regard to different stages of decommissioning and with regard to the actions taken by Barsebaeck. Some key conclusions from SKI's experience in regulating a decommissioning nuclear power plant conclude the report

  10. 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

  11. 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)

  12. A quantitative assessment of organizational factors affecting safety using a system dynamics model

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, J. K. [Systemix Company, Seoul (Korea, Republic of); Yoon, T. S. [Korea Electric Power Research Institute (Korea, Republic of)

    2003-07-01

    The purpose of this study is to develop a system dynamics model for the assessment of organizational and human factors in the nuclear power plant safety. Previous studies are classified into two major approaches. One is the engineering approach such as ergonomics and Probabilistic Safety Assessment (PSA). The other is socio-psychology one. Both have contributed to find organizational and human factors and increased nuclear safety However, since these approaches assume that the relationship among factors is independent they do not explain the interactions between factors or variables in NPP's. To overcome these restrictions, a system dynamics model, which can show causal relations between factors and quantify organizational and human factors, has been developed. Operating variables such as degree of leadership, adjustment of number of employee, and workload in each department, users can simulate various situations in nuclear power plants in the organization side. Through simulation, user can get an insight to improve safety in plants and to find managerial tools in the organization and human side.

  13. A quantitative assessment of organizational factors affecting safety using system dynamics model

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Jae Kook; Ahn, Nam Sung [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Jae, Moo Sung [Hanyang Univ., Seoul (Korea, Republic of)

    2004-02-01

    The purpose of this study is to develop a system dynamics model for the assessment of the organizational and human factors in a nuclear power plant which contribute to nuclear safety. Previous studies can be classified into two major approaches. One is the engineering approach using tools such as ergonomics and Probability Safety Assessment (PSA). The other is the socio-psychology approach. Both have contributed to find organizational and human factors and to present guidelines to lessen human error in plants. However, since these approaches assume that the relationship among factors is independent they do not explain the interactions among the factors or variables in nuclear power plants. To overcome these restrictions, a system dynamics model, which can show cause and effect relationships among factors and quantify the organizational and human factors, has been developed. Handling variables such as the degree of leadership, the number of employees, and workload in each department, users can simulate various situations in nuclear power plant organization. Through simulation, users can get insights to improve safety in plants and to find managerial tools in both organizational and human factors.

  14. A quantitative assessment of organizational factors affecting safety using system dynamics model

    International Nuclear Information System (INIS)

    Yu, Jae Kook; Ahn, Nam Sung; Jae, Moo Sung

    2004-01-01

    The purpose of this study is to develop a system dynamics model for the assessment of the organizational and human factors in a nuclear power plant which contribute to nuclear safety. Previous studies can be classified into two major approaches. One is the engineering approach using tools such as ergonomics and Probability Safety Assessment (PSA). The other is the socio-psychology approach. Both have contributed to find organizational and human factors and to present guidelines to lessen human error in plants. However, since these approaches assume that the relationship among factors is independent they do not explain the interactions among the factors or variables in nuclear power plants. To overcome these restrictions, a system dynamics model, which can show cause and effect relationships among factors and quantify the organizational and human factors, has been developed. Handling variables such as the degree of leadership, the number of employees, and workload in each department, users can simulate various situations in nuclear power plant organization. Through simulation, users can get insights to improve safety in plants and to find managerial tools in both organizational and human factors

  15. Effectiveness of human factors simulator

    International Nuclear Information System (INIS)

    Moragas, F.

    2015-01-01

    En 2011, ANAV started the exploitation of the Human Factors Simulator installed in TECNATOM Training Center located in L'Hospital de L'Infant Tarragona. AVAN's Strategic Plan includes the Action Plan for the improvement of human behavior. The plan includes improving the efficiency of the efficiency of the human factors simulator. It is proposed to improve the efficiency into two different terms: winning effectiveness in modeling behaviors, and interweaving the activities in the simulator with the actual strategy of promoting Safety culture and human behaviour. (Author)

  16. Safety and human factors impacts of introducing quality management into high-risk industries: A field study

    International Nuclear Information System (INIS)

    Chollet, M.G.; Normier, C.; Girault, M.; Tasset, D.

    2002-01-01

    The Institute for Radiological Protection and Nuclear Safety has undertaken a study for getting a better understanding, especially in terms of Safety and Human Factors, of the changes caused by the progressive deployment of the Quality Management in French high risk industries. This study is based on both theoretical elements from the human sciences and management and practical elements from the field, collected from interviews in large French industrial sites involved in integrating this management method. The results show frequent discrepancies between theory, which is very positive and production-oriented, and reality, which is more complex and subtle, ever looking for trade-offs between production requirements and safety constraints. Thus, each step forward announced in the literature may be matched by possible steps backward in terms of safety on the ground. Where, in theory, processes enable practices to be mastered, in practice they can reduce autonomy and fossilize know-how. Where theoretically continuous improvement stimulates and strengthens performances, in reality it can also generate stress and deadlock. Where theoretically personal commitment and collective responsibility work towards all-out performance, in reality they can also operate to conceal safety deviations and infringements. The assessment of Quality Management processes in the nuclear field will benefit from these results raised from theoretical review and confirmed by similar management changes. (author)

  17. Development of human factors design review guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

    1997-10-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 12 refs., 5 figs., 2 tabs.

  18. Barriers to Safety Event Reporting in an Academic Radiology Department: Authority Gradients and Other Human Factors.

    Science.gov (United States)

    Siewert, Bettina; Swedeen, Suzanne; Brook, Olga R; Eisenberg, Ronald L; Hochman, Mary

    2018-05-15

    Purpose To investigate barriers to reporting safety concerns in an academic radiology department and to evaluate the role of human factors, including authority gradients, as potential barriers to safety concern reporting. Materials and Methods In this institutional review board-approved, HIPAA-compliant retrospective study, an online questionnaire link was emailed four times to all radiology department staff members (n = 648) at a tertiary care institution. Survey questions included frequency of speaking up about safety concerns, perceived barriers to speaking up, and the annual number of safety concerns that respondents were unsuccessful in reporting. Respondents' sex, role in the department, and length of employment were recorded. Statistical analysis was performed with the Fisher exact test. Results The survey was completed by 363 of the 648 employees (56%). Of those 363 employees, 182 (50%) reported always speaking up about safety concerns, 134 (37%) reported speaking up most of the time, 36 (10%) reported speaking up sometimes, seven (2%) reported rarely speaking up, and four (1%) reported never speaking up. Thus, 50% of employees spoke up about safety concerns less than 100% of the time. The most frequently reported barriers to speaking up included high reporting threshold (69%), reluctance to challenge someone in authority (67%), fear of disrespect (53%), and lack of listening (52%). Conclusion Of employees in a large academic radiology department, 50% do not attain 100% reporting of safety events. The most common human barriers to speaking up are high reporting threshold, reluctance to challenge authority, fear of disrespect, and lack of listening, which suggests that existing authority gradients interfere with full reporting of safety concerns. © RSNA, 2018.

  19. 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

  20. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  1. Development of human factors design review guidelines

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

    1997-10-01

    The Objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, Human factors engineering program review model' and '26, Review criteria for human actors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides be ing performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we well update the guidelines by reviewing the literature related to alarm design published after 1994

  2. 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)

  3. Human and organizational biases affecting the management of safety

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu, E-mail: teemu.reiman@vtt.fi [VTT, Espoo (Finland); Rollenhagen, Carl [KTH, Stockholm (Sweden)

    2011-10-15

    Management of safety is always based on underlying models or theories of organization, human behavior and system safety. The aim of the article is to review and describe a set of potential biases in these models and theories. We will outline human and organizational biases that have an effect on the management of safety in four thematic areas: beliefs about human behavior, beliefs about organizations, beliefs about information and safety models. At worst, biases in these areas can lead to an approach where people are treated as isolated and independent actors who make (bad) decisions in a social vacuum and who pose a threat to safety. Such an approach aims at building barriers and constraints to human behavior and neglects the measures aiming at providing prerequisites and organizational conditions for people to work effectively. This reductionist view of safety management can also lead to too drastic a strong separation of so-called human factors from technical issues, undermining the holistic view of system safety. Human behavior needs to be understood in the context of people attempting (together) to make sense of themselves and their environment, and act based on perpetually incomplete information while relying on social conventions, affordances provided by the environment and the available cognitive heuristics. In addition, a move toward a positive view of the human contribution to safety is needed. Systemic safety management requires an increased understanding of various normal organizational phenomena - in this paper discussed from the point of view of biases - coupled with a systemic safety culture that encourages and endorses a holistic view of the workings and challenges of the socio-technical system in question. - Highlights: > Biases in safety management approaches are reviewed and described. > Four thematic areas are covered: human behavior, organizations, information, safety models. > The biases influence how safety management is defined, executed

  4. Human and organizational biases affecting the management of safety

    International Nuclear Information System (INIS)

    Reiman, Teemu; Rollenhagen, Carl

    2011-01-01

    Management of safety is always based on underlying models or theories of organization, human behavior and system safety. The aim of the article is to review and describe a set of potential biases in these models and theories. We will outline human and organizational biases that have an effect on the management of safety in four thematic areas: beliefs about human behavior, beliefs about organizations, beliefs about information and safety models. At worst, biases in these areas can lead to an approach where people are treated as isolated and independent actors who make (bad) decisions in a social vacuum and who pose a threat to safety. Such an approach aims at building barriers and constraints to human behavior and neglects the measures aiming at providing prerequisites and organizational conditions for people to work effectively. This reductionist view of safety management can also lead to too drastic a strong separation of so-called human factors from technical issues, undermining the holistic view of system safety. Human behavior needs to be understood in the context of people attempting (together) to make sense of themselves and their environment, and act based on perpetually incomplete information while relying on social conventions, affordances provided by the environment and the available cognitive heuristics. In addition, a move toward a positive view of the human contribution to safety is needed. Systemic safety management requires an increased understanding of various normal organizational phenomena - in this paper discussed from the point of view of biases - coupled with a systemic safety culture that encourages and endorses a holistic view of the workings and challenges of the socio-technical system in question. - Highlights: → Biases in safety management approaches are reviewed and described. → Four thematic areas are covered: human behavior, organizations, information, safety models. → The biases influence how safety management is defined

  5. The role of psychological factors in workplace safety.

    Science.gov (United States)

    Kotzé, Martina; Steyn, Leon

    2013-01-01

    Workplace safety researchers and practitioners generally agree that it is necessary to understand the psychological factors that influence people's workplace safety behaviour. Yet, the search for reliable individual differences regarding psychological factors associated with workplace safety has lead to sparse results and inconclusive findings. The aim of this study was to investigate whether there are differences between the psychological factors, cognitive ability, personality and work-wellness of employees involved in workplace incidents and accidents and/or driver vehicle accidents and those who are not. The study population (N = 279) consisted of employees employed at an electricity supply organisation in South Africa. Mann-Whitney U-test and one-way ANOVA were conducted to determine the differences in the respective psychological factors between the groups. These results showed that cognitive ability did not seem to play a role in workplace incident/accident involvement, including driver vehicle accidents, while the wellness factors burnout and sense of coherence, as well as certain personality traits, namely conscientiousness, pragmatic and gregariousness play a statistically significant role in individuals' involvement in workplace incidents/accidents/driver vehicle accidents. Safety practitioners, managers and human resource specialists should take cognisance of the role of specifically work-wellness in workplace safety behaviour, as management can influence these negative states that are often caused by continuously stressful situations, and subsequently enhance work place safety.

  6. 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)

  7. The significance of human factors in nuclear activities

    International Nuclear Information System (INIS)

    Weil, L.; Berg, H.P.

    1999-01-01

    Human factors is an aspect increasingly investigated in the last few years in efforts and programmes for enhancing the operational safety of nuclear systems. Methodology has been elaborated for analysis and evaluation of human reliability, or development of instruments supporting the decisions to be taken by the operators at the man-control room interface of nuclear installations, as well as initial approaches to introduce organisational factors which may influence the man-machine function allocation, and thus are an element of the safety culture concept. The significance of human factors in nuclear activities, as well as activities at the national and international level for optimisation of the man-machine interface and the man-organisation interface are discussed. (orig./CB) [de

  8. Human factors in waste management - potential and reality

    International Nuclear Information System (INIS)

    Thompson, J.S.

    1996-01-01

    There is enormous potential for human factors contributions in the realm of waste management. The reality, however, is very different from the potential. This is particularly true for low-level and low-level mixed-waste management. The hazards are less severe; therefore, health and safety requirements (including human factors) are not as rigorous as for high-level waste. High-level waste management presents its own unique challenges and opportunities. Waste management is strongly driven by regulatory compliance. When regulations are flexible and open to interpretation and the environment is driven so strongly by regulatory compliance, standard practice is to drop open-quotes nice to haveclose quotes features, like a human factors program, to save money for complying with other requirements. The challenge is to convince decision makers that human factors can help make operations efficient and cost-effective, as well as improving safety and complying with regulations. A human factors program should not be viewed as competing with compliance efforts; in fact, it should complement them and provide additional cost-effective means of achieving compliance with other regulations. Achieving this synergy of human factors with ongoing waste management operations requires educating program and facility managers and other technical specialists about human factors and demonstrating its value open-quotes through the back doorclose quotes on existing efforts. This paper describes ongoing projects at Los Alamos National Laboratory (LANL) in support of their waste management groups. It includes lessons learned from hazard and risk analyses, safety analysis reports, job and task analyses, operating procedure development, personnel qualification/certification program development, and facility- and job-specific training program and course development

  9. Development of human factors design review guidelines(II)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-06-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 11 refs., 2 figs., 2 tabs.

  10. Discovering Innovation at the Intersection of Undergraduate Medical Education, Human Factors, and Collaboration: The Development of a Nasogastric Tube Safety Pack.

    Science.gov (United States)

    Taylor, Natalie; Bamford, Thomas; Haindl, Cornelia; Cracknell, Alison

    2016-04-01

    Significant deficiencies exist in the knowledge and skills of medical students and residents around health care quality and safety. The theory and practice of quality and safety should be embedded into undergraduate medical practice so that health care professionals are capable of developing interventions and innovations to effectively anticipate and mitigate errors. Since 2011, Leeds Medical School in the United Kingdom has used case study examples of nasogastric (NG) tube patient safety incidents within the undergraduate patient safety curriculum. In 2012, a medical undergraduate student approached a clinician with an innovative idea after undertaking an NG tubes root cause analysis case study. Simultaneously, a separate local project demonstrated low compliance (11.6%) with the United Kingdom's National Patient Safety Agency NG tubes guideline for use of the correct method to check tube position. These separate endeavors led to interdisciplinary collaboration between a medical student, health care professionals, researchers, and industry to develop the Initial Placement Nasogastric Tube Safety Pack. Human factors engineering was used to inform pack design to allow guideline recommendations to be accessible and easy to follow. A timeline of product development, mapped against key human factors and medical device design principles used throughout the process, is presented. The safety pack has since been launched in five UK National Health Service (NHS) hospitals, and the pack has been introduced into health care professional staff training for NG tubes. A mixed-methods evaluation is currently under way in five NHS organizations.

  11. Human Reliability Analysis for Design: Using Reliability Methods for Human Factors Issues

    Energy Technology Data Exchange (ETDEWEB)

    Ronald Laurids Boring

    2010-11-01

    This paper reviews the application of human reliability analysis methods to human factors design issues. An application framework is sketched in which aspects of modeling typically found in human reliability analysis are used in a complementary fashion to the existing human factors phases of design and testing. The paper provides best achievable practices for design, testing, and modeling. Such best achievable practices may be used to evaluate and human system interface in the context of design safety certifications.

  12. Human Reliability Analysis for Design: Using Reliability Methods for Human Factors Issues

    International Nuclear Information System (INIS)

    Boring, Ronald Laurids

    2010-01-01

    This paper reviews the application of human reliability analysis methods to human factors design issues. An application framework is sketched in which aspects of modeling typically found in human reliability analysis are used in a complementary fashion to the existing human factors phases of design and testing. The paper provides best achievable practices for design, testing, and modeling. Such best achievable practices may be used to evaluate and human system interface in the context of design safety certifications.

  13. Monitoring human and organizational factors influencing common-cause failures of safety-instrumented system during the operational phase

    International Nuclear Information System (INIS)

    Rahimi, Maryam; Rausand, Marvin

    2013-01-01

    Safety-instrumented systems (SISs) are important safety barriers in many technical systems in the process industry. Reliability requirements for SISs are specified as a safety integrity level (SIL) with reference to the standard IEC 61508. The SIS reliability is often threatened by common-cause failures (CCFs), and the beta-factor model is the most commonly used model for incorporating the effects of CCFs. In the design phase, the beta-factor, β, is determined by answering a set of questions that is given in part 6 of IEC 61508. During the operational phase, there are several factors that influence β, such that the actual β differs from what was predicted in the design phase, and therefore the required reliability may not be maintained. Among the factors influencing β in the operational phase are human and organizational factors (HOFs). A number of studies within industries that require highly reliable products have shown that HOFs have significant influence on CCFs and therefore on β in the operational phase, but this has been neglected in the process industry. HOFs are difficult to predict, and susceptible to be changed during the operational phase. Without proper management, changing HOFs may cause the SIS reliability to drift out of its required value. The aim of this article is to highlight the importance of HOFs in estimation of β for SISs, and also to propose a framework to follow the HOFs effects and to manage them such that the reliability requirement can be maintained

  14. The human factor in the nuclear industry

    International Nuclear Information System (INIS)

    Colas, Armand

    1998-01-01

    After having evoked the progressive reduction and stabilization of significant incidents occurring every year in French nuclear power plants, and the challenges faced by nuclear energy (loss of public confidence, loss of competitiveness), and then outlined the importance of safety to overcome these challenges, the author comments EDF's approach to the human factor. He first highlights the importance of information and communication towards the population. He briefly discusses the meaning of human factors for the nuclear industry, sometimes perceived as the contribution people to the company's safety and performance. He comments the evolution observed in the perception of human error in different industrial or technical environments and situations, and outlines what is at stake to reduce the production of faults and organize a 'hunt for latent defects'

  15. Effectiveness of human factors simulator; Eficiencia del simulador de factores humanos

    Energy Technology Data Exchange (ETDEWEB)

    Moragas, F.

    2015-07-01

    En 2011, ANAV started the exploitation of the Human Factors Simulator installed in TECNATOM Training Center located in L'Hospital de L'Infant Tarragona. AVAN's Strategic Plan includes the Action Plan for the improvement of human behavior. The plan includes improving the efficiency of the efficiency of the human factors simulator. It is proposed to improve the efficiency into two different terms: winning effectiveness in modeling behaviors, and interweaving the activities in the simulator with the actual strategy of promoting Safety culture and human behaviour. (Author)

  16. Development of human factors design review guidelines(III)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-02-15

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

  17. Development of human factors design review guidelines(III)

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

    1999-02-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

  18. Development of human factors design review guidelines(II)

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

    1998-06-01

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

  19. Development of human factors design review guidelines(III)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-02-15

    The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

  20. Human and Organisational Safety Barriers in the Oil & Gas Industry

    International Nuclear Information System (INIS)

    Nystad, E.; Szőke, I.

    2016-01-01

    The oil & gas industry is a safety-critical industry where errors or accidents may potentially have severe consequences. Offshore oil & gas installations are complex technical systems constructed to pump hydrocarbons from below the seabed, process them and pipe them to onshore refineries. Hydrocarbon leaks may lead to major accidents or have negative environmental impacts. The industry must therefore have a strong focus on safety. Safety barriers are devices put into place to prevent or reduce the effects of unwanted incidents. Technical barriers are one type of safety barrier, e.g., blow-out preventers to prevent uncontrolled release of hydrocarbons from a well. Human operators may also have an important function in maintaining safety. These human operators are part of a larger organisation consisting of different roles and responsibilities and with different mechanisms for ensuring safety. This paper will present two research projects from the Norwegian oil & gas industry that look at the role of humans and organisations as safety barriers. The first project used questionnaire data to investigate the use of mindful safety practices (safety-promoting work practices intended to prevent or interrupt unwanted events) and what contextual factors may affect employees’ willingness to use these safety practices. Among the findings was that employees’ willingness to use mindful safety practices was affected more by factors on a group level than factors at an individual or organisational level, and that the factors may differ depending on what is the object of a practice—the employee or other persons. It was also suggested that employees’ willingness to use mindful safety practices could be an indicator used in the assessment of the safety level on oil & gas installations. The second project is related to organisational safety barriers against major accidents. This project was based on a review of recent incidents in the Norwegian oil & gas industry, as well as

  1. Human Factors in Cabin Accident Investigations

    Science.gov (United States)

    Chute, Rebecca D.; Rosekind, Mark R. (Technical Monitor)

    1996-01-01

    Human factors has become an integral part of the accident investigation protocol. However, much of the investigative process remains focussed on the flight deck, airframe, and power plant systems. As a consequence, little data has been collected regarding the human factors issues within and involving the cabin during an accident. Therefore, the possibility exists that contributing factors that lie within that domain may be overlooked. The FAA Office of Accident Investigation is sponsoring a two-day workshop on cabin safety accident investigation. This course, within the workshop, will be of two hours duration and will explore relevant areas of human factors research. Specifically, the three areas of discussion are: Information transfer and resource management, fatigue and other physical stressors, and the human/machine interface. Integration of these areas will be accomplished by providing a suggested checklist of specific cabin-related human factors questions for investigators to probe following an accident.

  2. Implementing human factors in clinical practice

    Science.gov (United States)

    Timmons, Stephen; Baxendale, Bryn; Buttery, Andrew; Miles, Giulia; Roe, Bridget; Browes, Simon

    2015-01-01

    Objectives To understand whether aviation-derived human factors training is acceptable and useful to healthcare professionals. To understand whether and how healthcare professionals have been able to implement human factors approaches to patient safety in their own area of clinical practice. Methods Qualitative, longitudinal study using semi-structured interviews and focus groups, of a multiprofessional group of UK NHS staff (from the emergency department and operating theatres) who have received aviation-derived human factors training. Results The human factors training was evaluated positively, and thought to be both acceptable and relevant to practice. However, the staff found it harder to implement what they had learned in their own clinical areas, and this was principally attributed to features of the informal organisational cultures. Conclusions In order to successfully apply human factors approaches in hospital, careful consideration needs to be given to the local context and informal culture of clinical practice. PMID:24631959

  3. The human component in the safety of complex systems

    International Nuclear Information System (INIS)

    Wahlstroem, B.

    1986-02-01

    The safety of nuclear power and other complex processes requires that human actions are carried though on time and without error. Investigations indicate that human errors are the main or an important contributing cause in more than half of the incidents which occur. This makes it important to try understand the mechanisms behind the human errors and to investigate possibilities for decreasing their likelihood. The present report presents an overview of the Nordic cooperation in the field of human factors in nuclear safety, under the LIT-programme carried out 1981-1985. The work was divided into six different projects in the following fields: human reliability in test and maintenance work; safety oriented organizations and company structures; design of information and control systems; new approaches for information presentation; experimental validation of man-machine interfaces; planning and evaluation of operator training. The research topics were selected from the findings of an earlier phase of the Nordic cooperation. The results are described in more detail in separate reports

  4. Human resource factors associated with workplace safety and health education of small manufacturing businesses in Korea.

    Science.gov (United States)

    Park, Kyoung-Ok

    2018-01-25

    Human resources (HR) are essential indicators of safety and health (SH) status, and HR can be key sources of workplace safety management such as safety and health education at work (SHEW). This study analyzed significant HR factors associated with SHEW of small manufacturing businesses in Korea. The secondary data of the 2012 Korea Occupational Safety and Health Trend Survey were used to achieve this research purpose. A total of 2,089 supervisors or managers employed in the small manufacturing businesses completed the interview survey. Survey businesses were selected by multiple stratified sampling method based on industry code, business size, and region in Korea. The survey included workplace characteristics of HR and SHEW. SHEW was significantly related to business size, occupational injury incidence in the previous year, foreign and elderly worker employment, presence of site supervisors, and presence of SH committees (p <.05). SHEW for office workers, non-office workers, and newcomers was associated with business size, presence of site supervisors, and presence of SH committees in logistic regression analysis (p <.001). Businesses with 30-49 workers conducted SHEW 3.64 times more than did businesses with 5 to fewer than 10 workers. The companies that had occupational injuries in the previous year conducted SHEW 1.68 times more than the others. The businesses that had site supervisors and committees conducted SHEW 2.30 and 2.18 times more, respectively, than others. Site supervisors and SH committees were significant HR factors that improved SHEW in small manufacturing businesses.

  5. Exploring Barriers to Medication Safety in an Ethiopian Hospital Emergency Department: A Human Factors Engineering Approach

    Directory of Open Access Journals (Sweden)

    Ephrem Abebe

    2018-02-01

    Full Text Available Objective: To describe challenges associated with the medication use process and potential medication safety hazards in an Ethiopian hospital emergency department using a human factors approach. Methods: We conducted a qualitative study employing observations and semi-structured interviews guided by the Systems Engineering Initiative for Patient Safety model of work system as an analytical framework. The study was conducted in the emergency department of a teaching hospital in Ethiopia. Study participants included resident doctors, nurses, and pharmacists. We performed content analysis of the qualitative data using accepted procedures. Results: Organizational barriers included communication failures, limited supervision and support for junior staff contributing to role ambiguity and conflict. Compliance with documentation policy was minimal. Task related barriers included frequent interruptions and work-related stress resulting from job requirements to continuously prioritize the needs of large numbers of patients and family members. Person related barriers included limited training and work experience. Work-related fatigue due to long working hours interfered with staff’s ability to document and review medication orders. Equipment breakdowns were common as were non-calibrated or poorly maintained medical devices contributing to erroneous readings. Key environment related barriers included overcrowding and frequent interruption of staff’s work. Cluttering of the work space compounded the problem by impeding efforts to locate medications, medical supplies or medical charts. Conclusions: Applying a systems based approach allows a context specific understanding of medication safety hazards in EDs from low-income countries. When developing interventions to improve medication and overall patient safety, health leaders should consider the interactions of the different factors. Conflict of Interest We declare no conflicts of interest or

  6. 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)

  7. Human factors considerations in control room modernization: Trends and personnel performance issues

    International Nuclear Information System (INIS)

    O'Hara, J.; Stubler, B.; Kramer, J.

    1997-01-01

    Advanced human-system interface (HSI) technology is being integrated into existing nuclear plants as part of plant modifications and upgrades. The result of this trend is that hybrid HSIs are created, i.e., HSIs containing a mixture of conventional (analog) and advanced (digital) technology. The purpose of the present research is to define the potential effects of hybrid HSIs on personnel performance and plant safety and to develop human factors guidance for safety reviews of them where necessary. In support of this objective, human factors topics associated with hybrid HSIs were identified. A human performance topic is an aspect of hybrid HSIs, such as a design or implementation feature, for which human performance concerns were identified. The topics were then evaluated for their potential significance to plant safety. Twelve topics were identified as potentially safety significant issues, i.e., their human performance concerns have the potential to compromise plant safety. The issues were then prioritized and a subset was selected for design review guidance development. 6 refs

  8. Organizational root causes for human factor accidents

    International Nuclear Information System (INIS)

    Dougherty, D.T.

    1997-01-01

    Accident prevention techniques and technologies have evolved significantly throughout this century from the earliest establishment of standards and procedures to the safety engineering improvements the fruits of which we enjoy today. Most of the recent prevention efforts focused on humans and defining human factor causes of accidents. This paper builds upon the remarkable successes of the past by looking beyond the human's action in accident causation to the organizational factors that put the human in the position to cause the accident. This organizational approach crosses all functions and all career fields

  9. 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

  10. 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)

  11. Human Factor on Gravelines Nuclear Power Plants

    International Nuclear Information System (INIS)

    Duboc, Gerard

    1998-01-01

    In a first part, the documents describes the commitments by EDF nuclear power plan operations to demands made by the Safety Authority regarding actions in the field of human factors (concerns expressed by the Authority, in-depth analysis, positions on different points raised by the Authority). In a second part, it presents the various actions undertaken in the Gravelines nuclear power station regarding human factors: creation of an 'operator club' (mission and objectives, methods and means, first meetings, tracking file), development of risk analysis strategy, setting up of a human factor engineering mission and example of action in case of a significant event

  12. State-of-the-art report on systematic approaches to safety management - Special Expert Group on Human and Organisational Factors (SEGHOF)

    International Nuclear Information System (INIS)

    Van den Berghe, Yves; Frischknecht, Albert; Gil, Benito; Martin, Anibal; McRobbie, Helen; Reiersen, Craig; Tasset, Daniel; Aastrand, Kaisa; Dahlgren-Persson, Kerstin; Pyy, Pekka; Mauny, Elisabeth

    2006-02-01

    There is a growing awareness of the significant contribution which human and organisational factors (HOF) make to nuclear safety. Within the HOF area, attention is increasingly focused on addressing management and organisational issues. This reflects an evolving recognition that the members of a nuclear licensee form part of a socio-technological system, and that their performance is influenced by the organisation and the culture within that organisation. A series of events across the nuclear industry and other sectors has reinforced the appreciation of the importance of robust safety management. Also, the management and organisation of nuclear installations is impacted by a number of current challenges such as deregulation, change in institutional ownership of the industry, contractorization and an ageing plant and workforce. It is in this context that the CSNI (Committee on Safety of Nuclear Installations) Special Experts' Group on Human and Organisational Factors (SEGHOF) was requested by the CNRA (Committee on Nuclear Regulatory Actions) to examine the role and influence of safety management in nuclear plant operations in 2000. A workshop on 'systematic approaches to safety management' was held in spring 2002 and this was followed by a survey in 2003-4 of relevant practices and developments across licensees and regulators. This report provides a brief explanation of the relationship between safety management and safety culture. It reinforces the need for nuclear licensees and regulators to take positive steps to ensure that licensees develop and sustain a robust safety management system as a part of their management systems as a whole. The report draws out the main findings of the workshop and presents the results of the survey in more detail. It seeks to identify current issues and areas warranting further consideration. The workshop explored the development of current organisational theories and their application to nuclear plant safety management. It

  13. The psychological background about human error and safety in NPP

    International Nuclear Information System (INIS)

    Zhang Li

    1992-01-01

    A human error is one of the factors which cause an accident in NPP. The in-situ psychological background plays an important role in inducing it. The author analyzes the structure of one's psychological background when one is at work, and gives a few examples of typical psychological background resulting in human errors. Finally it points out that the fundamental way to eliminate the unfavourable psychological background of safety production is to establish the safety culture in NPP along with its characteristics

  14. Human Factors Science: Brief History and Applications to Healthcare.

    Science.gov (United States)

    Parker, Sarah Henrickson

    2015-12-01

    This section will define the science of human factors, its origins, its impact on safety in other domains, and its impact and potential for impact on patient safety. Copyright © 2015 Mosby, Inc. All rights reserved.

  15. 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)

  16. Human factors in resuscitation teaching.

    Science.gov (United States)

    Norris, Elizabeth M; Lockey, Andrew S

    2012-04-01

    There is an increasing interest in human factors within the healthcare environment reflecting the understanding of their impact on safety. The aim of this paper is to explore how human factors might be taught on resuscitation courses, and improve course outcomes in terms of improved mortality and morbidity for patients. The delivery of human factors training is important and this review explores the work that has been delivered already and areas for future research and teaching. Medline was searched using MESH terms Resuscitation as a Major concept and Patient or Leadership as core terms. The abstracts were read and 25 full length articles reviewed. Critical incident reporting has shown four recurring problems: lack of organisation at an arrest, lack of equipment, non functioning equipment, and obstructions preventing good care. Of these, the first relates directly to the concept of human factors. Team dynamics for both team membership and leadership, management of stress, conflict and the role of debriefing are highlighted. Possible strategies for teaching them are discussed. Four strategies for improving human factors training are discussed: team dynamics (including team membership and leadership behaviour), the influence of stress, debriefing, and conflict within teams. This review illustrates how human factor training might be integrated further into life support training without jeopardising the core content and lengthening the courses. Copyright © 2011 Elsevier Ireland Ltd. All rights reserved.

  17. Human factors challenges for advanced process control

    International Nuclear Information System (INIS)

    Stubler, W.F.; O'Hara, J..M.

    1996-01-01

    New human-system interface technologies provide opportunities for improving operator and plant performance. However, if these technologies are not properly implemented, they may introduce new challenges to performance and safety. This paper reports the results from a survey of human factors considerations that arise in the implementation of advanced human-system interface technologies in process control and other complex systems. General trends were identified for several areas based on a review of technical literature and a combination of interviews and site visits with process control organizations. Human factors considerations are discussed for two of these areas, automation and controls

  18. Implementing human factors in clinical practice.

    Science.gov (United States)

    Timmons, Stephen; Baxendale, Bryn; Buttery, Andrew; Miles, Giulia; Roe, Bridget; Browes, Simon

    2015-05-01

    To understand whether aviation-derived human factors training is acceptable and useful to healthcare professionals. To understand whether and how healthcare professionals have been able to implement human factors approaches to patient safety in their own area of clinical practice. Qualitative, longitudinal study using semi-structured interviews and focus groups, of a multiprofessional group of UK NHS staff (from the emergency department and operating theatres) who have received aviation-derived human factors training. The human factors training was evaluated positively, and thought to be both acceptable and relevant to practice. However, the staff found it harder to implement what they had learned in their own clinical areas, and this was principally attributed to features of the informal organisational cultures. In order to successfully apply human factors approaches in hospital, careful consideration needs to be given to the local context and informal culture of clinical practice. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  19. The integration of Human Factors (HF) in the SAR process training course text

    International Nuclear Information System (INIS)

    Ryan, T.G.

    1995-03-01

    This text provides the technical basis for a two-day course on human factors (HF), as applied to the Safety Analysis Report (SAR) process. The overall objective of this text and course is to: provide the participant with a working knowledge of human factors-related requirements, suggestions for doing a human safety analysis applying a graded approach, and an ability to demonstrate using the results of the human safety analysis, that human factors elements as defined by DOE (human factors engineering, procedures, training, oversight, staffing, qualifications), can support wherever necessary, nuclear safety commitments in the SAR. More specifically, the objectives of the text and course are: (1) To provide the SAR preparer with general guidelines for doing HE within the context of a graded approach for the SAR; (2) To sensitize DOE facility managers and staff, safety analysts and SAR preparers, independent reviewers, and DOE reviewers and regulators, to DOE Order 5480.23 requirements for HE in the SAR; (3) To provide managers, analysts, reviewers and regulators with a working knowledge of HE concepts and techniques within the context of a graded approach for the SAR, and (4) To provide SAR managers and DOE reviewers and regulators with general guidelines for monitoring and coordinating the work of preparers of HE inputs throughout the SAR process, and for making decisions regarding the safety relevance of HE inputs to the SAR. As a ready reference for implementing the human factors requirements of DOE Order 5480.22 and DOE Standard 3009-94, this course text and accompanying two-day course are intended for all persons who are involved in the SAR

  20. The integration of Human Factors (HF) in the SAR process training course text

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, T.G.

    1995-03-01

    This text provides the technical basis for a two-day course on human factors (HF), as applied to the Safety Analysis Report (SAR) process. The overall objective of this text and course is to: provide the participant with a working knowledge of human factors-related requirements, suggestions for doing a human safety analysis applying a graded approach, and an ability to demonstrate using the results of the human safety analysis, that human factors elements as defined by DOE (human factors engineering, procedures, training, oversight, staffing, qualifications), can support wherever necessary, nuclear safety commitments in the SAR. More specifically, the objectives of the text and course are: (1) To provide the SAR preparer with general guidelines for doing HE within the context of a graded approach for the SAR; (2) To sensitize DOE facility managers and staff, safety analysts and SAR preparers, independent reviewers, and DOE reviewers and regulators, to DOE Order 5480.23 requirements for HE in the SAR; (3) To provide managers, analysts, reviewers and regulators with a working knowledge of HE concepts and techniques within the context of a graded approach for the SAR, and (4) To provide SAR managers and DOE reviewers and regulators with general guidelines for monitoring and coordinating the work of preparers of HE inputs throughout the SAR process, and for making decisions regarding the safety relevance of HE inputs to the SAR. As a ready reference for implementing the human factors requirements of DOE Order 5480.22 and DOE Standard 3009-94, this course text and accompanying two-day course are intended for all persons who are involved in the SAR.

  1. The role of engineering judgement, safety culture, and organizational factors in risk assessment

    International Nuclear Information System (INIS)

    Muzumdar, Ajit; Professor, Visiting

    1996-01-01

    This paper reviews the role of engineering judgement, safety culture, and organizational factors in risk assessment by examining the reasons for human-based error. The need for more emphasis on producing engineers with good engineering judgement is described. The progress in quantifying the role of safety culture and organizational factors in risk assessment studies is summarized

  2. US Nuclear Regulatory Commission human-factors program plan

    International Nuclear Information System (INIS)

    1983-08-01

    The purpose of the NRC Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This initial plan addresses nuclear power plants (NPP) 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, and (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-83 through FY-85 time frame

  3. 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

  4. 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.

  5. Organisational and human factors in risk management: common beliefs, deceived ideas

    International Nuclear Information System (INIS)

    2011-01-01

    The author propose critical discussions of common beliefs about the ineluctability of human error, individual ability, the validity of written procedures, good organisation, the culture of safety, the contribution of quality approaches to safety, the continuous improvement of safety, the good usage of the return on experience, the rigour and objectivity of the FOH (organisational and human factor) approach, and appealing to experts in FOHs

  6. 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

  7. 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

  8. Probabilistic Safety Assessment: An Effective Tool to Support “Systemic Approach” to Nuclear Safety and Analysis of Human and Organizational Aspects

    International Nuclear Information System (INIS)

    Kuzmina, I.

    2016-01-01

    The Probabilistic Safety Assessment (PSA) represents a comprehensive conceptual and analytical tool for quantitative evaluation of risk of undesirable consequences from nuclear facilities and drawing on qualitative insights for nuclear safety. PSA considers various technical, human, and organizational factors in an integral manner thus explicitly pursuing a true ‘systemic approach’ to safety and enabling holistic insights for further safety improvement. Human Reliability Analysis (HRA) is one of the major tasks within PSA. The poster paper provides an overview of the objectives and scope of PSA and HRA and discusses on further needs in the area of HRA. (author)

  9. 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)

  10. 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

  11. 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.

  12. Space operations and the human factor

    Science.gov (United States)

    Brody, Adam R.

    1993-10-01

    Although space flight does not put the public at high risk, billions of dollars in hardware are destroyed and the space program halted when an accident occurs. Researchers are therefore applying human-factors techniques similar to those used in the aircraft industry, albeit at a greatly reduced level, to the spacecraft environment. The intent is to reduce the likelihood of catastrophic failure. To increase safety and efficiency, space human factors researchers have simulated spacecraft docking and extravehicular activity rescue. Engineers have also studied EVA suit mobility and aids. Other basic human-factors issues that have been applied to the space environment include antropometry, biomechanics, and ergonomics. Workstation design, workload, and task analysis currently receive much attention, as do habitability and other aspects of confined environments. Much work also focuses on individual payloads, as each presents its own complexities.

  13. 14 CFR 31.25 - Factor of safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Factor of safety. 31.25 Section 31.25... STANDARDS: MANNED FREE BALLOONS Strength Requirements § 31.25 Factor of safety. (a) Except as specified in paragraphs (b) and (c) of this section, the factor of safety is 1.5. (b) A factor of safety of at least five...

  14. Human reliability analysis in probabilistic safety assessment for nuclear power plants. A Safety Practice. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1995-01-01

    Probabilistic safety assessment (PSA) is playing an increasingly important role in the safe operation of nuclear power plants throughout the world. In order to establish a consistent framework for conducting PSA studies, for promoting technology transfer of the state of the art, and for encouraging uniformity in the way PSA is carried out, the IAEA is preparing a set of publications which gives guidance on various aspects of PSA. This document presents a practical approach for incorporating human reliability analysis (HRA) into PSA. It describes the steps needed and the documentation that should be provided both to support the PSA itself and to ensure effective communication of important information arising from the studies. It also describes a framework for analysing those human actions which could affect safety and for relating such human influences to specific parts of a PSA. This Safety Practice also addresses the limitations of PSA in taking account of human factors in relation to safety and risk. Refs, figs and tabs

  15. Human factors in healthcare level two

    CERN Document Server

    Rosenorn-Lanng, Debbie

    2015-01-01

    This book builds on Human Factors in Healthcare Level One by delving deeper into the challenges of leadership, conflict resolution, and decision making that healthcare professionals currently face. It is written in an easy to understand style and includes a wealth of real-life examples of errors and patient safety issues.

  16. 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

  17. 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

  18. 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

  19. 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

  20. A systematic review of human factors and ergonomics (HFE)-based healthcare system redesign for quality of care and patient safety.

    Science.gov (United States)

    Xie, Anping; Carayon, Pascale

    2015-01-01

    Healthcare systems need to be redesigned to provide care that is safe, effective and efficient, and meets the multiple needs of patients. This systematic review examines how human factors and ergonomics (HFE) is applied to redesign healthcare work systems and processes and improve quality and safety of care. We identified 12 projects representing 23 studies and addressing different physical, cognitive and organisational HFE issues in a variety of healthcare systems and care settings. Some evidence exists for the effectiveness of HFE-based healthcare system redesign in improving process and outcome measures of quality and safety of care. We assessed risk of bias in 16 studies reporting the impact of HFE-based healthcare system redesign and found varying quality across studies. Future research should further assess the impact of HFE on quality and safety of care, and clearly define the mechanisms by which HFE-based system redesign can improve quality and safety of care.

  1. 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

  2. Towards Clinical Application of Neurotrophic Factors to the Auditory Nerve; Assessment of Safety and Efficacy by a Systematic Review of Neurotrophic Treatments in Humans

    NARCIS (Netherlands)

    Bezdjian, Aren; Kraaijenga, Véronique J C; Ramekers, Dyan; Versnel, Huib; Thomeer, Hans G X M; Klis, Sjaak F L; Grolman, Wilko

    2016-01-01

    Animal studies have evidenced protection of the auditory nerve by exogenous neurotrophic factors. In order to assess clinical applicability of neurotrophic treatment of the auditory nerve, the safety and efficacy of neurotrophic therapies in various human disorders were systematically reviewed.

  3. 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

  4. Development of HANARO human factors management plan and evaluation of BCS display

    International Nuclear Information System (INIS)

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

    2004-01-01

    In this study, human factors evaluation of BCS display design was performed. We adopted the suitability of design elements of BCS display as human factors evaluation measure. And, we also adopted guideline based evaluation, field survey and expert evaluation as evaluation method. The checklist was utilized for the evaluation, and the results of evaluation were well arranged in the evaluation format. We did not find out the HED (Human Engineering Discrepancy) impede safety of HANARO, except some necessary items to improve during short periods. We also provide some items of improvement for the enhancement of safety and operator's performance in the aspect of long periods. If the proposed improvement items were completely fulfilled, the more improved safety of HANARO will be secured

  5. Safety factors for neutron fluences in NPP safety assessment

    International Nuclear Information System (INIS)

    Demekhin, V.L.; Bukanov, V.N.; Il'kovich, V.V.; Pugach, A.M.

    2016-01-01

    In accordance with global practice and a number of existing regulations, the use of conservative approach is required for the calculations related to nuclear safety assessment of NPP. It implies the need to consider the determination of neutron fluence errors that is rather complicated. It is proposed to carry out the consideration by the way of multiplying the neutron fluences obtained with transport calculations by safety factors. The safety factor values are calculated by the developed technique based on the theory of errors, features of the neutron transport calculation code and the results obtained with the code. It is shown that the safety factor value is equal 1.18 with the confidence level of not less than 0.95 for the majority of VVER-1000 reactor places where neutron fluences are determined by MCPV code, and its maximum value is 1.25

  6. Requirements to amend the main influence factors on the safety culture after fukushima accident

    International Nuclear Information System (INIS)

    Farcasiu, M.; Nitoi, M.

    2015-01-01

    The paper presents a general model that provides a framework for the safety culture assessment, creating the possibility to identify factors that can significantly influence the safety culture. The main safety culture influence factors (SCIF) used by model are the following: regulatory environment, organizational environment, worker characteristics, socio-political environment, national culture, organization history, business and technological characteristics. After the analysis of the deficiencies and weaknesses of SCIFc in evolution of the Fukushima accident, some issues that may become necessities and requirements to change and improve both the safety culture and safety of the nuclear installations were highlighted. For each influence factor were identified some requirements to amend. The results will emphasize the necesity of the human - technology - organization system assessment. Hence it was demonstrated that the safety culture results from the interaction of individuals with technology and with the organization. (authors)

  7. U.S. Nuclear Regulatory Commission human factors program plan

    International Nuclear Information System (INIS)

    1986-04-01

    The purpose of the U.S. Nuclear Regulatory Commission (NRC) Human Factors Program Plan is to ensure that proper consideration is given to human factors in the design and operation of nuclear facilities. This revised plan addresses human factors issues related to the operation of nuclear power plants (NPPs). The three issues of concern are (1) the activities planned to provide the technical bases to resolve the remaining tasks related to human factors as 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 need to address the additional human factors efforts that were identified during implementation of the Action Plan; and (3) the actual fulfillment of those developmental activities specified in Revision 1 of this plan. The plan represents a systematic approach for addressing high priority human factors concerns important to NPP safety in FY 1986 through 1987

  8. 14 CFR 29.303 - Factor of safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Factor of safety. 29.303 Section 29.303... STANDARDS: TRANSPORT CATEGORY ROTORCRAFT Strength Requirements General § 29.303 Factor of safety. Unless otherwise provided, a factor of safety of 1.5 must be used. This factor applies to external and inertia...

  9. 14 CFR 27.303 - Factor of safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Factor of safety. 27.303 Section 27.303... STANDARDS: NORMAL CATEGORY ROTORCRAFT Strength Requirements General § 27.303 Factor of safety. Unless otherwise provided, a factor of safety of 1.5 must be used. This factor applies to external and inertia...

  10. Application of factor analysis in psychological diagnostics (sample: study of students’ social safety

    Directory of Open Access Journals (Sweden)

    Pavel Aleksandrovich Kislyakov

    2015-10-01

    Our recommendations for the use of factor analysis, with necessary restrictions and clear reasons of a possible ambiguity of solutions, will be useful to everyone interested in mastering an adequate mathematical tool for solving problems pertaining to the humanities, in particular, those of practical psychology. As a practical example is presented the research of the psychological factors which provide students’ social safety. With the help of the factor analysis relevant personal and professional qualities of a teacher were revealed which are the subjective factors of students’ social safety, namely: social anticipation, socio-psychological stress resistance, social tolerance, professional orientation, responsibility, communication skills.

  11. Human Factors Engineering Guidelines for Overhead Cranes

    Science.gov (United States)

    Chandler, Faith; Delgado, H. (Technical Monitor)

    2001-01-01

    This guideline provides standards for overhead crane cabs that can be applied to the design and modification of crane cabs to reduce the potential for human error due to design. This guideline serves as an aid during the development of a specification for purchases of cranes or for an engineering support request for crane design modification. It aids human factors engineers in evaluating existing cranes during accident investigations or safety reviews.

  12. Human factors, system safety, and systems engineering in the transportation of U.S. high-level waste

    International Nuclear Information System (INIS)

    Price, D.L.; Chu, S.C.

    1993-01-01

    The U.S. Nuclear Waste Technical Review Board is an independent agency charged with evaluating the technical and scientific validity of the U.S. Department of Energy's program to manage the disposal of spent fuel and defense high-level waste. The Board has continued to emphasize the importance of using a true system approach in designing the waste management system. The Board has recommended the application of basic design disciplines such as human factors, system safety, and systems engineering. A top-level system study needs to be undertaken that focuses on minimizing handling. The analysis must be well done, in a timely manner, and without the inclusion in the analysis of arbitrary and artificial constraints. (author)

  13. 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

  14. An integrated graphic–taxonomic–associative approach to analyze human factors in aviation accidents

    Directory of Open Access Journals (Sweden)

    Gong Lei

    2014-04-01

    Full Text Available Human factors are critical causes of modern aviation accidents. However, existing accident analysis methods encounter limitations in addressing aviation human factors, especially in complex accident scenarios. The existing graphic approaches are effective for describing accident mechanisms within various categories of human factors, but cannot simultaneously describe inadequate human–aircraft–environment interactions and organizational deficiencies effectively, and highly depend on analysts’ skills and experiences. Moreover, the existing methods do not emphasize latent unsafe factors outside accidents. This paper focuses on the above three limitations and proposes an integrated graphic–taxonomic–associative approach. A new graphic model named accident tree (AcciTree, with a two-mode structure and a reaction-based concept, is developed for accident modeling and safety defense identification. The AcciTree model is then integrated with the well-established human factors analysis and classification system (HFACS to enhance both reliability of the graphic part and logicality of the taxonomic part for improving completeness of analysis. An associative hazard analysis technique is further put forward to extend analysis to factors outside accidents, to form extended safety requirements for proactive accident prevention. Two crash examples, a research flight demonstrator by our team and an industrial unmanned aircraft, illustrate that the integrated approach is effective for identifying more unsafe factors and safety requirements.

  15. Regulatory perspectives on human factors validation

    International Nuclear Information System (INIS)

    Harrison, F.; Staples, L.

    2001-01-01

    Validation is an important avenue for controlling the genesis of human error, and thus managing loss, in a human-machine system. Since there are many ways in which error may intrude upon system operation, it is necessary to consider the performance-shaping factors that could introduce error and compromise system effectiveness. Validation works to this end by examining, through objective testing and measurement, the newly developed system, procedure or staffing level, in order to identify and eliminate those factors which may negatively influence human performance. It is essential that validation be done in a high-fidelity setting, in an objective and systematic manner, using appropriate measures, if meaningful results are to be obtained, In addition, inclusion of validation work in any design process can be seen as contributing to a good safety culture, since such activity allows licensees to eliminate elements which may negatively impact on human behaviour. (author)

  16. Time Based Workload Analysis Method for Safety-Related Operator Actions in Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yun Goo; Oh, Eung Se [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2016-05-15

    During the design basis event, the safety system performs safety functions to mitigate the event. The most of safety system is actuated by automatic system however, there are operator manual actions that are needed for the plant safety. These operator actions are classified as important human actions in human factors engineering design. The human factors engineering analysis and evaluation is needed for these important human actions to assure that operator successfully perform their tasks for plant safety and operational goals. The work load analysis is one of the required analysis for the important human actions.

  17. Time Based Workload Analysis Method for Safety-Related Operator Actions in Safety Analysis

    International Nuclear Information System (INIS)

    Kim, Yun Goo; Oh, Eung Se

    2016-01-01

    During the design basis event, the safety system performs safety functions to mitigate the event. The most of safety system is actuated by automatic system however, there are operator manual actions that are needed for the plant safety. These operator actions are classified as important human actions in human factors engineering design. The human factors engineering analysis and evaluation is needed for these important human actions to assure that operator successfully perform their tasks for plant safety and operational goals. The work load analysis is one of the required analysis for the important human actions.

  18. Human Factors Throughout the Life Cycle: Lessons Learned from the Shuttle Program. [Human Factors in Ground Processing

    Science.gov (United States)

    Kanki, Barbara G.

    2011-01-01

    With the ending of the Space Shuttle Program, it is critical that we not forget the Human Factors lessons we have learned over the years. At every phase of the life cycle, from manufacturing, processing and integrating vehicle and payload, to launch, flight operations, mission control and landing, hundreds of teams have worked together to achieve mission success in one of the most complex, high-risk socio-technical enterprises ever designed. Just as there was great diversity in the types of operations performed at every stage, there was a myriad of human factors that could further complicate these human systems. A single mishap or close call could point to issues at the individual level (perceptual or workload limitations, training, fatigue, human error susceptibilities), the task level (design of tools, procedures and aspects of the workplace), as well as the organizational level (appropriate resources, safety policies, information access and communication channels). While we have often had to learn through human mistakes and technological failures, we have also begun to understand how to design human systems in which individuals can excel, where tasks and procedures are not only safe but efficient, and how organizations can foster a proactive approach to managing risk and supporting human enterprises. Panelists will talk about their experiences as they relate human factors to a particular phase of the shuttle life cycle. They will conclude with a framework for tying together human factors lessons-learned into system-level risk management strategies.

  19. An investigation on factors influencing on human resources productivity

    Directory of Open Access Journals (Sweden)

    Masoumeh Seifi Divkolaii

    2014-05-01

    Full Text Available Human resources development is one of the most important components of any organization and detecting important factors influencing on human resources management plays essential role on the success of the firms. In this paper, we present an empirical investigation to determine different factors influencing productivity of human resources of Islamic Republic of Iran Broadcasting (IRIB in province of Mazandaran, Iran. The study uses analytical hierarchy process (AHP to rank 17 important factors and determines that personal characteristics were the most important factors followed by management related factors and environmental factors. In terms of personal characteristics, job satisfaction plays essential role on human resources development. In terms of managerial factors, paying attention on continuous job improvement by receiving appropriate training is the most important factor followed by welfare facilities for employees and using a system of reward/punishment in organization. Finally, in terms of environmental factors, occupational safety is number one priority followed by organizational rules and regulations.

  20. 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.

  1. 14 CFR 23.303 - Factor of safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Factor of safety. 23.303 Section 23.303... STANDARDS: NORMAL, UTILITY, ACROBATIC, AND COMMUTER CATEGORY AIRPLANES Structure General § 23.303 Factor of safety. Unless otherwise provided, a factor of safety of 1.5 must be used. ...

  2. Partial Safety Factors for Rubble Mound Breakwaters

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Burcharth, H. F.; Christiani, E.

    1995-01-01

    On the basis of the failure modes formulated in the various subtasks calibration of partial safety factors are described in this paper. The partial safety factors can be used to design breakwaters under quite different design conditions, namely probabilities of failure from 0.01 to 0.4, design...... lifetimes from 20 to 100 years and different qualities of wave data. A code of practice where safety is taken into account using partial safety factors is called a level I code. The partial safety factors are calibrated using First Order Reliability Methods (FORM, see Madsen et al. [1]) where...... in section 3. First Order Reliability Methods are described in section 4, and in section 5 it is shown how partial safety factors can be introduced and calibrated. The format of a code for design and analysis of rubble mound breakwaters is discussed in section 6. The mathematical formulation of the limit...

  3. 14 CFR 25.303 - Factor of safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Factor of safety. 25.303 Section 25.303... STANDARDS: TRANSPORT CATEGORY AIRPLANES Structure General § 25.303 Factor of safety. Unless otherwise specified, a factor of safety of 1.5 must be applied to the prescribed limit load which are considered...

  4. Development of a procedure for qualitative and quantitative evaluation of human factors as a part of probabilistic safety assessments of nuclear power plants. Part A

    International Nuclear Information System (INIS)

    Richei, A.

    1998-01-01

    The objective of this project is the development of a procedure for the qualitative and quantitative evaluation of human factors in the probabilistic safety assessment for nuclear power plants. The Human Error Rate Assessment and Optimizing System (HEROS) is introduced. The evaluation of a task with HEROS is realized in the three evaluation levels, i.e. 'Management Structure', 'Working Environment' and 'Man-Machine-Interface'. The developed expert system uses the fuzzy set theory for an assessment. For the evaluation of cognitive tasks evaluation criteria are derived also. The validation of the procedure is based on three examples, reflecting the common practice of probabilistic safety assessments and including problems, which cannot, respectively - only insufficiently - be evaluated with the established human risk analysis procedures. HERO applications give plausible and comprehensible results. (orig.) [de

  5. Practical applications of safety culture concepts in human performance advances on Russian nuclear industry

    International Nuclear Information System (INIS)

    Abramova, V.N.; Volkov, E.V.; Gordienko, O.V.; Melnitskaya, T.B.; Volkova, I.V.; Alexeev, G.A.

    2002-01-01

    Sometimes, many from negative external factors can be compensated by human psychological readiness of worker. However there would be main worse to come: some cases of personnel activity and organisational factors, some person's peculiarities (attitudes, responsibility, etc.) add considerable number of the events at NPPs. A lot of aspects of Human Factor Reliability are united in Safety Culture concept. This paper presents some results of our recently research in that area. In 'proactive approach': Unique methods for measuring maturity and satisfaction of personnel motivation: comparative analysis of the labour and safety culture motivation from attitude; organization of the socio-psychological climate and safety attitude examining monitoring at all of Russia's NPPs; working-out recommendations for managers on improving human performance are presented. Besides, ergonomic research concerning work conditions at the NPP is displayed. In 'reactive approach': Analysis of the incorrect activity cases, which led to the breaches of work of the Russian NPPs, is shown. The special method to work-up is used. It was issue, that events caused by a human error, depends not only on the worker's professional competence, but on the attitude and motivation, some professionally important psychological and psycho-physiological quality data, the functional state, the group's socio-psychological climate, etc. (author)

  6. Smart driver monitoring : when signal processing meets human factors : in the driver's seat

    NARCIS (Netherlands)

    Aghaei, A.S.; Donmez, B.; Liu, C.C.; He, D.; Liu, G.; Plataniotis, K.N.; Chen, H.Y.W.; Sojoudi, Z.

    2016-01-01

    This article provides an interdisciplinary perspective on driver monitoring systems by discussing state-of-the-art signal processing solutions in the context of road safety issues identified in human factors research. Recently, the human factors community has made significant progress in

  7. Cultural factors influencing safety need to be addressed in design and operation of technology.

    Science.gov (United States)

    Meshkati, N

    1996-10-01

    Cultural factors which influence aviation safety in aircraft design, air traffic control, and human factors training are examined. Analysis of the Avianca Flight 052 crash in New York in January, 1990, demonstrates the catastrosphic effects cultural factors can play. Cultural factors include attitude toward work and technology, organizational hierarchy, religion, and population stereotyping.

  8. Human factors analysis of U.S. Navy afloat mishaps

    OpenAIRE

    Lacy, Rex D.

    1998-01-01

    The effects of maritime mishaps, which include loss of life as well as environmental and economic considerations, are significant. It has been estimated that over 80percent of maritime accidents areat least partially attributable to human error. Human error has been extensively studied in a number of fields, particularly aviation. The present research involves application of the Human Factors Accident Classification System (HFACS), developed by the Naval Safety Center, to human error causal f...

  9. Issues for resolving adverse effects on the safety culture of human work underload and workload transitions in complex human-machine systems

    International Nuclear Information System (INIS)

    Ryan, T.G.

    1996-01-01

    A workshop was conducted whose specific purpose was to build on earlier work of the US National Research Council, US federal government agencies, and the larger human factors community to: (1) clarify human factors issues pertaining to degraded safety performance in advanced human-machine systems(e.g., nuclear production, transportation, aerospace) due to human work underload and workload transition, and (2) develop strategies for resolving these issues. The workshop affirmed that: (1) work underload and workload transition are issues that will have to be addressed by designers of advanced human-machine systems, especially those relying on automation, if cost, performance, safety, and operator acceptability are to be optimized, (2) human machine allocation models, standards and guidelines which go beyond simple capability approaches will be needed to preclude or seriously diminish the work underload and workload transition problems, and (3) the 16 workload definition, measurement, situational awareness, and trust issues identified during the workshop, need resolution if these models, standards, and guidelines are to be achieved

  10. A hierarchical factor analysis of a safety culture survey.

    Science.gov (United States)

    Frazier, Christopher B; Ludwig, Timothy D; Whitaker, Brian; Roberts, D Steve

    2013-06-01

    Recent reviews of safety culture measures have revealed a host of potential factors that could make up a safety culture (Flin, Mearns, O'Connor, & Bryden, 2000; Guldenmund, 2000). However, there is still little consensus regarding what the core factors of safety culture are. The purpose of the current research was to determine the core factors, as well as the structure of those factors that make up a safety culture, and establish which factors add meaningful value by factor analyzing a widely used safety culture survey. A 92-item survey was constructed by subject matter experts and was administered to 25,574 workers across five multi-national organizations in five different industries. Exploratory and hierarchical confirmatory factor analyses were conducted revealing four second-order factors of a Safety Culture consisting of Management Concern, Personal Responsibility for Safety, Peer Support for Safety, and Safety Management Systems. Additionally, a total of 12 first-order factors were found: three on Management Concern, three on Personal Responsibility, two on Peer Support, and four on Safety Management Systems. The resulting safety culture model addresses gaps in the literature by indentifying the core constructs which make up a safety culture. This clarification of the major factors emerging in the measurement of safety cultures should impact the industry through a more accurate description, measurement, and tracking of safety cultures to reduce loss due to injury. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  11. Human factors assessments of D and D technologies

    International Nuclear Information System (INIS)

    Carpenter, C.P.; Evans, T.T.; McCabe, B.

    2000-01-01

    On April 2, 1997, the US Secretary of Energy directed the US Assistant Secretary of Environmental Management and of Safety and Health to require field input of appropriate data to ensure that safety and health considerations were properly addressed in the Accelerating Cleanup: Focus on 2006 Plan. The US Department of Energy (DOE) field managers have committed to the Secretary that they will fully implement integrated safety management systems (ISMSs) at their respective sites by the end of fiscal year 1999. The Secretary has further directed that headquarters safety and health guidance be developed to support consistent and comprehensive project baseline summaries from the field. The Secretary has committed to institutionalizing ISMS as an integral component of the way the DOE conducts its business. The Defense Nuclear Facilities Safety Board continues to oversee and closely monitor the DOE's commitment to the safety and health of its workers. The DOE is committed to a management system approach to ensure that work is performed in a manner that protects the worker, public, and environment. The Deactivation and Decommissioning Focus Area (DDFA) is actively addressing the need to incorporate environmental safety and health (ES and H) considerations in developing technologies. The DDFA is partnered with the Operating Engineers National Hazmat Program (OENHP) to evaluate the ES and H considerations of the innovative and improved decontamination and decommissioning technologies. Part of the implementation of the ES and H work practices in the field is through a cooperative agreement between the National Energy Technology Laboratory (NETL) and the OENHP. The objective of this program is to establish an International Environmental Technology and Training Center to conduct human factors assessments and protocols on environmental technologies. The intent of the human factors assessments is to enhance the effectiveness and efficiency of the technologies and to enhance

  12. Human Factors in Space Exploration

    Science.gov (United States)

    Jones, Patricia M.; Fiedler, Edna

    2010-01-01

    The exploration of space is one of the most fascinating domains to study from a human factors perspective. Like other complex work domains such as aviation (Pritchett and Kim, 2008), air traffic management (Durso and Manning, 2008), health care (Morrow, North, and Wickens, 2006), homeland security (Cooke and Winner, 2008), and vehicle control (Lee, 2006), space exploration is a large-scale sociotechnical work domain characterized by complexity, dynamism, uncertainty, and risk in real-time operational contexts (Perrow, 1999; Woods et ai, 1994). Nearly the entire gamut of human factors issues - for example, human-automation interaction (Sheridan and Parasuraman, 2006), telerobotics, display and control design (Smith, Bennett, and Stone, 2006), usability, anthropometry (Chaffin, 2008), biomechanics (Marras and Radwin, 2006), safety engineering, emergency operations, maintenance human factors, situation awareness (Tenney and Pew, 2006), crew resource management (Salas et aI., 2006), methods for cognitive work analysis (Bisantz and Roth, 2008) and the like -- are applicable to astronauts, mission control, operational medicine, Space Shuttle manufacturing and assembly operations, and space suit designers as they are in other work domains (e.g., Bloomberg, 2003; Bos et al, 2006; Brooks and Ince, 1992; Casler and Cook, 1999; Jones, 1994; McCurdy et ai, 2006; Neerincx et aI., 2006; Olofinboba and Dorneich, 2005; Patterson, Watts-Perotti and Woods, 1999; Patterson and Woods, 2001; Seagull et ai, 2007; Sierhuis, Clancey and Sims, 2002). The human exploration of space also has unique challenges of particular interest to human factors research and practice. This chapter provides an overview of those issues and reports on sorne of the latest research results as well as the latest challenges still facing the field.

  13. 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)

  14. Overview of Recent Activities on Safety Culture and Human and Organizational Factors Carried Out at the Joint Research Centre of the European Commission

    International Nuclear Information System (INIS)

    Stručić, M.; Manna, G.

    2016-01-01

    The Institute for Energy and Transport (IET) of the Joint Research Centre (JRC) of the European Commission (EC) is since more than ten years active in the field of Safety Culture (SC) and Human and Organizational Factors (HOF). Several activities related to SC and HOF have been and are carried out in the frame of the EU Nuclear Safety Clearinghouse for Operating Experience Feedback (Clearinghouse). The Clearinghouse was established in 2008 to enhance nuclear safety through the lessons learned from NPP events, and to provide help in Operational Experience Feedback (OEF) process primarily to nuclear safety Regulatory Authorities and to their Technical Support Organizations within the EU. Additionally to these activities, during the Fukushima accident, Clearinghouse has been regularly providing reports on the status and progress of the accident to the EU Regulatory Authorities. Moreover, experts, selected from the JRC staffing, were directly engaged in the EU-wide risk and safety assessments of nuclear power plants known as “the Stress Tests”.

  15. A research framework of organizational factors on safety in the Republic of Korea

    International Nuclear Information System (INIS)

    Kwang Seok Lee

    1997-01-01

    Korean nuclear society is yet unfamiliar with the topic, 'organizational factors on safety', while having shown lots of accomplishments in the area of physical and human factors on safety. However, recent large-scale accidents in other technological areas illustrate the importance of managing organization factors on safety. Recently Korea Atomic Energy Research Institute (KAERI) started paying attention to this topic and is trying to establish a future research framework of organizational factors on safety. This paper tries to explain overall direction of the framework. Our framework, as managing organizational factors on safety, considers two kinds of areas: design of management systems, which implies a feed-forward system including organizational models; and operation of those systems, which implies a feedback system including management information and implementation systems. Our framework also considers the evolution stage of a management system. Management systems evolve from visibility stage to optimization stage. To optimize a management system, we should be able to control the system. To control the system, we should be able to see how the system is going. In addition, this paper tries to share some experience of KAERI on how organizational structure and culture affects organizational performance in R and D perspective. (author). 2 refs, 1 fig

  16. 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

  17. Human performance analysis in the frame of probabilistic safety assessment of research reactors

    International Nuclear Information System (INIS)

    Farcasiu, Mita; Nitoi, Mirela; Apostol, Minodora; Turcu, I.; Florescu, Gh.

    2005-01-01

    Full text: The analysis of operating experience has identified the importance of human performance in reliability and safety of research reactors. In Probabilistic Safety Assessment (PSA) of nuclear facilities, human performance analysis (HPA) is used in order to estimate human error contribution to the failure of system components or functions. HPA is a qualitative and quantitative analysis of human actions identified for error-likely situations or accident-prone situations. Qualitative analysis is used to identify all man-machine interfaces that can lead to an accident, types of human interactions which may mitigate or exacerbate the accident, types of human errors and performance shaping factors. Quantitative analysis is used to develop estimates of human error probability as effects of human performance in reliability and safety. The goal of this paper is to accomplish a HPA in the PSA frame for research reactors. Human error probabilities estimated as results of human actions analysis could be included in system event tree and/or system fault tree. The achieved sensitivity analyses determine human performance sensibility at systematically variations both for dependencies level between human actions and for operator stress level. The necessary information was obtained from operating experience of research reactor TRIGA from INR Pitesti. The required data were obtained from generic data bases. (authors)

  18. 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)

  19. Human actions in the pre-operational probabilistic safety analysis of Juragua Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ferro, R.

    1995-01-01

    Human error is one of the main contributors to the biggest industrial disasters that the world has suffered in the last years. Safety probabilistic analysis techniques allow to consider, in the some study, the contribution of a facility's mechanical and human components safety, this guaranteeing a move integral assessment of these two factors although the PSA study of Juragua Nuclear Power Plant is carried out at a preoperational stage which causes important information limitations fos assessment of human reliability some considerations and suppositions in order to conduct treatment of human actions this stage were adopted. The present work describes the projected targets, approach applied and results obtained from the lakes of human reliability of this study

  20. Human factors considerations in the design and evaluation of flight deck displays and controls

    Science.gov (United States)

    2013-11-01

    The objective of this effort is to have a single source document for human factors regulatory and guidance material for flight deck displays and controls, in the interest of improving aviation safety. This document identifies guidance on human factor...

  1. OECD-NEA’s New Approach to Human Aspects of Nuclear Safety

    International Nuclear Information System (INIS)

    Hah, Y.

    2016-01-01

    Fukushima Daiichi accident in 2011 in Japan has brought us new challenge to deal with “human” aspects of nuclear safety which have always been crucial elements of safety, but which often receive less attention than technical and equipment issues. The key factors that led to the accident were not only a huge tsunami following a massive earthquake, but also a variety of human failures: organizational decision-making, safety culture of the plant staff and the regulator, training to assure that operators are well prepared for a wide range of possible challenges. In order to fully understand and respond to the lessons learned from the Fukushima accident, the OECD-NEA created a new Division of Human Aspects of Nuclear Safety (HANS) which is focusing on the human issues related to nuclear safety. The Division of HANS is responsible for supporting the relevant work programmes of the NEA; fostering greater focus and building expertise in areas vital to effective nuclear safety such as safety culture, personnel training policies and practices; and safety-related public communication and stakeholder engagement. In 2014, NEA produced the Green Booklet on the Characteristics of an Effective Nuclear Regulator noting that the characteristic of “safety focus and safety culture” was one of the four fundamental principles from which all regulatory body actions should be derived. Based on this understanding, in 2015, NEA published the follow up Green Booklet, Safety Culture of an Effective Nuclear Regulatory Body, providing main principles and attributes to be benchmarked for the regulatory bodies to encourage them to enhance their effectiveness as they fulfil their mission to protect public health and safety. Many challenges exist to regulatory bodies’ safety culture which must be recognised, understood and overcome. Continuing collective efforts could help turn these challenges into opportunities to further strengthen the overall health of the safety culture of regulatory

  2. 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.

  3. Human factors research in Central Research Institute of Electric Power Industry creation of safety culture

    International Nuclear Information System (INIS)

    Horie, Yasuo

    2002-01-01

    To prevent accident of nuclear power plant, Human Factors Center was built in the Central Research Institute of Electric Power Industry in July 1987. It developed an evaluation method of human error cases and an application method of human factors information. Now it continues analysis and application of human factors information, development of training/work support tools and research/experiment of human behavior. Japan-Human Performance Evaluation System (J-HPES) was developed as an analytical system for analysis and evaluation of human factors related to the trouble and for using the result as the common property by storage the analytical results. J-HPES has a standard procedure consisted of collecting and analyzing data and proposing the countermeasures. The analytical results are arranged by 4 kinds of charts by putting into the form of a diagram. Moreover, it tries to find the causes with indirect and potential causes. Two kinds of materials, Caution Report and Human Factors Precept by means of Illustrations, are published. People can gain access to HFC database by URL http://criepi.denken.or.jp/CRIEPI/HFC/DB. To prevent these accidents, creation of human factors culture has been required. Five kinds of teaching materials and the training method are developed. (S.Y.)

  4. The Analysis of the Contribution of Human Factors to the In-Flight Loss of Control Accidents

    Science.gov (United States)

    Ancel, Ersin; Shih, Ann T.

    2012-01-01

    In-flight loss of control (LOC) is currently the leading cause of fatal accidents based on various commercial aircraft accident statistics. As the Next Generation Air Transportation System (NextGen) emerges, new contributing factors leading to LOC are anticipated. The NASA Aviation Safety Program (AvSP), along with other aviation agencies and communities are actively developing safety products to mitigate the LOC risk. This paper discusses the approach used to construct a generic integrated LOC accident framework (LOCAF) model based on a detailed review of LOC accidents over the past two decades. The LOCAF model is comprised of causal factors from the domain of human factors, aircraft system component failures, and atmospheric environment. The multiple interdependent causal factors are expressed in an Object-Oriented Bayesian belief network. In addition to predicting the likelihood of LOC accident occurrence, the system-level integrated LOCAF model is able to evaluate the impact of new safety technology products developed in AvSP. This provides valuable information to decision makers in strategizing NASA's aviation safety technology portfolio. The focus of this paper is on the analysis of human causal factors in the model, including the contributions from flight crew and maintenance workers. The Human Factors Analysis and Classification System (HFACS) taxonomy was used to develop human related causal factors. The preliminary results from the baseline LOCAF model are also presented.

  5. 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

  6. 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

  7. 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)

  8. Incorporating Hofstede’ National Culture in Human Factor Analysis and Classification System (HFACS: Cases of Indonesian Aviation Safety

    Directory of Open Access Journals (Sweden)

    Pratama Gradiyan Budi

    2018-01-01

    Full Text Available National culture plays an important role in the application of ergonomics and safety. This research examined role of national culture in accident analysis of Indonesian aviation using framework of Human Factors Analysis and Classification System (HFACS. 53 Indonesian aviation accidents during year of 2001-2012 were analyzed using the HFACS framework by authors and were validated to 14 air-transport experts in Indonesia. National culture is viewed with Hofstede’ lens of national culture. Result shows that high collectivistic, low uncertainty avoidance, high power distance, and masculinity dimension which are characteristics of Indonesian culture, play an important role in Indonesian aviation accident and should be incorporated within HFACS. Result is discussed in relation with HFACS and Indonesian aviation accident analysis.

  9. 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)

  10. Human factors experts beginning to focus on organizational factors in safety.

    Science.gov (United States)

    Westrum, R

    1996-10-01

    The role of organizational culture in aviation safety is explored. Information flow is used to demonstrate three ranges of climate within an organization. Organizations may be pathological in which information is hidden, bureaucratic in which information is ignored, or generative in which information is actively sought. The effects of organizational change on personnel are explored with emphasis on mergers between air carriers. The relationship between safety measures and economic pressures is discussed.

  11. Organizational factors in nuclear safety

    International Nuclear Information System (INIS)

    Wilpert, Bernhard

    2000-01-01

    The overall picture of factors which contributed to the event presents a panorama of a NPP where organizational and managerial characteristics were intricately intertwined and emerged as crucial for a general deterioration of the plant's capabilities to continually correct its deficiencies and optimize its operations. In the following author shall attempt to first cover various important efforts to modeling organizational factors relevant to safety. The second part of my presentation will offer an attempt towards an integrative model. The third part concludes with an agenda for research and practice. Most of the twelve different approaches above attempt to consider safety relevant organizational factors by way of pragmatic classifications. Together with their sub-categories we can count close to 160 different factors on various levels of abstraction. This is tantamount to say that most approaches lack systematic theoretical underpinnings. Thus then arises the question whether we need to develop a generic model, which promises to encompass these three major approaches altogether. Practical issues emerge particularly in the domain of organizational development, i.e. the goal oriented efforts to change the structures and the functioning of nuclear operations in such a way that the desired outputs in terms safety and reliability result in a sustained fashion. Again, these practical concerns are intimately related to developments and advances in theory and methodology. Only a close cooperation among scientists from various disciplines and of practitioners holds the promise of adequately understanding and use of organizational factors in future improving the safety record of nuclear industry worldwide. (S.Y.)

  12. The Design of Transportation Equipment in Terms of Human Capabilities. The Role of Engineering Psychology in Transport Safety.

    Science.gov (United States)

    McFarland, Ross A.

    Human factors engineering is considered with regard to the design of safety factors for aviation and highway transportation equipment. Current trends and problem areas are identified for jet air transportation and for highway transportation. Suggested solutions to transportation safety problems are developed by applying the techniques of human…

  13. Human factors and safety issues associated with actinide retrieval from spent light water reactor fuel assemblies

    International Nuclear Information System (INIS)

    Spelt, P.F.

    1992-01-01

    A major problem in environmental restoration and waste management is the disposition of used fuel assemblies from the many light water reactors in the United States, which present a radiation hazard to those whose job is to dispose of them, with a similar threat to the general environment associated with long-term storage in fuel repositories around the country. Actinides resident in the fuel pins as a result of their use in reactor cores constitute a significant component of this hazard. Recently, the Department of Energy has initiated an Actinide Recycle Program to study the feasibility of using pyrochemical (molten salt) processes to recover actinides from the spent fuel assemblies of commercial reactors. This project concerns the application of robotics technology to the operation and maintenance functions of a plant whose objective is to recover actinides from spent fuel assemblies, and to dispose of the resulting hardware and chemical components from this process. Such a procedure involves a number of safety and human factors issues. The purpose of the project is to explore the use of robotics and artificial intelligence to facilitate accomplishment of the program goals while maintaining the safety of the humans doing the work and the integrity of the environment. This project will result in a graphic simulation on a Silicon Graphics workstation as a proof of principle demonstration of the feasibility of using robotics along with an intelligent operator interface. A major component of the operator-system interface is a hybrid artificial intelligence system developed at Oak Ridge National Laboratory, which combines artificial neural networks and an expert system into a hybrid, self-improving computer-based system interface. 10 refs

  14. Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

    Energy Technology Data Exchange (ETDEWEB)

    O`Hara, J.M.; Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J. [Carlow International Inc., Falls Church, VA (United States)

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

  15. Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

    International Nuclear Information System (INIS)

    O'Hara, J.M.; Brown, W.S.; Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J.

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use

  16. Human Factor Modelling in the Risk Assessment of Port Manoeuvers

    Directory of Open Access Journals (Sweden)

    Teresa Abramowicz-Gerigk

    2015-09-01

    Full Text Available The documentation of human factor influence on the scenario development in maritime accidents compared with expert methods is commonly used as a basis in the process of setting up safety regulations and instructions. The new accidents and near misses show the necessity for further studies in determining the human factor influence on both risk acceptance criteria and development of risk control options for the manoeuvers in restricted waters. The paper presents the model of human error probability proposed for the assessment of ship masters and marine pilots' error decision and its influence on the risk of port manoeuvres.

  17. 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

  18. Human factors paradigm and customer care perceptions.

    Science.gov (United States)

    Clarke, Colin; Eales-Reynolds, Lesley-Jane

    2015-01-01

    The purpose of this paper is to examine if customer care (CC) can be directly linked to patient safety through a human factors (HF) framework. Data from an online questionnaire, completed by a convenience healthcare worker sample (n=373), was interrogated using thematic analysis within Vincent et al.'s (1998) HF theoretical framework. This proposes seven areas affecting patient safety: institutional context, organisation and management, work environment, team factors, individual, task and patient. Analysis identified responses addressing all framework areas. Responses (597) principally focused on work environment 40.7 per cent (n=243), organisation and management 28.8 per cent (n=172). Nevertheless, reference to other framework areas were clearly visible within the data: teams 10.2 per cent (n=61), individual 6.7 per cent (n=40), patients 6.0 per cent (n=36), tasks 4.2 per cent (n=24) and institution 3.5 per cent (n=21). Findings demonstrate congruence between CC perceptions and patient safety within a HF framework. The questionnaire requested participants to identify barriers to rather than CC enablers. Although this was at a single site complex organisation, it was similar to those throughout the NHS and other international health systems. CC can be viewed as consonant with patient safety rather than the potentially dangerous consumerisation stance, which could ultimately compromise patient safety. This work provides an original perspective on the link between CC and patient safety and has the potential to re-focus healthcare perceptions.

  19. Safety of PEGylated recombinant human full-length coagulation factor VIII (BAX 855) in the overall context of PEG and PEG conjugates.

    Science.gov (United States)

    Stidl, R; Fuchs, S; Bossard, M; Siekmann, J; Turecek, P L; Putz, M

    2016-01-01

    BAX 855 is a PEGylated human full-length recombinant factor VIII (rFVIII) based on licensed rFVIII (ADVATE). The applied PEGylation technology has been optimized to retain functionality of the FVIII molecule, improve its pharmacokinetic properties and allow less frequent injections while maintaining efficacy. The aim of this study was to confirm that the excellent safety profile of ADVATE remains unchanged after PEGylation. Non-clinical safety studies with BAX 855 and its respective unbound polyethylene glycol (PEG) were conducted in several species. The distribution of a single dose of radiolabelled BAX 855 was further investigated in rats. Publically available safety data on PEG alone and PEGylated biomolecules were summarized and reviewed for specific safety findings attributable to PEG or PEGylated biopharmaceuticals. Safety pharmacology studies in rabbits and macaques and repeated dose toxicity studies in rats and macaques identified no safety issues. Results of a distribution study in rats administered radiolabelled BAX 855 showed that radioactivity was completely excreted; urine was the major elimination route. A 28-day study in rats dosed with the unbound PEG constituent (PEG2ru20KCOOH) of BAX 855 showed no adverse or non-adverse effects. Safety data for PEG and PEG-protein conjugates indicate no safety concerns associated with PEG at clinically relevant dose levels. Although vacuolation of certain cell types has been reported in mammals, no such vacuolation was observed with BAX 855 or with the unbound PEG constituent. Non-clinical safety evaluation of PEG and BAX 855 identified no safety signals; the compound is now in clinical development for the treatment of patients with haemophilia A. © 2015 Baxalta Innovations GmbH. Haemophilia Published by John Wiley & Sons Ltd.

  20. 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

  1. Accidents and human factors

    International Nuclear Information System (INIS)

    Nishiwaki, Y.; Kawai, H.; Morishima, H.; Terano, T.; Sugeno, M.

    1984-01-01

    When the TMI accident occurred it was 4 a.m., an hour when the error potential of the operators would have been very high. The frequency of car and train accidents in Japan is also highest between 4 a.m. and 6 a.m. The error potential may be classified into five phases corresponding to the electroencephalogramic pattern (EEG). At phase 0, when the delta wave appears, a person is unconscious and in deep sleep; at phase I, when the theta wave appears, he is very tired, sleepy and subnormal; at phase II, when the alpha wave appears, he is normal, relaxed and passive; at phase III, when the beta wave appears, he is normal, clear-minded and active; at phase IV, when the strong beta or epileptic wave appears, he is hypernormal, excited and incapable of normal judgement. Should an accident occur at phase II, the brain condition may jump to phase IV. At this phase the error or accident potential is maximum. The response of the human brain to different types of noises and signals may vary somewhat for different individuals and for different groups of people. Therefore, the possibility that such differences in brain functions may influence the mental structure would be worthy of consideration in human factors and in the design of man-machine systems. Human reliability and performance would be affected by many factors: medical, physiological and psychological, etc. The uncertainty involved in human factors may not necessarily be probabilistic, but fuzzy. Therefore, it would be important to develop a theory by which both non-probabilistic uncertainties, or fuzziness, of human factors and the probabilistic properties of machines can be treated consistently. From the mathematical point of view, probabilistic measure is considered a special case of fuzzy measure. Therefore, fuzzy set theory seems to be an effective tool for analysing man-machine systems. To minimize human error and the possibility of accidents, new safety systems should not only back up man and make up for his

  2. Effects of botropase on clotting factors in healthy human volunteers

    Directory of Open Access Journals (Sweden)

    Ashok K Shenoy

    2014-01-01

    Full Text Available Objective: To evaluate the effects of botropase on various clotting factors in human volunteers. Materials and Methods: It was a prospective open label study conducted on human healthy volunteers. After the baseline screening, subjects fulfilling inclusion criteria were enrolled. On the study day, 1 ml of botropase was administered intravenously and after an hour same dose of botropase (1 ml was given by intramuscular (IM route. The efficacy and safety parameters were monitored up to 72 h from the time of intravenous (IV administration. Results: A total of 15 volunteers, belonging to 24-35 years of age were included in the study. Botropase significantly reduced the plasma level of fibrinogen and fibrin degradation products after 5 min of IV administration (P < 0.05. In addition, factor X was observed to reduce constantly by botropase administration suggesting enhanced turnover between 5 and 20 min of IV administration. Although botropase reduced clotting and bleeding time in all the volunteers, the data remains to be statistically insignificant. Conclusion: Present study demonstrated the safety and efficacy of botropase in human healthy volunteers. The study has shown that it is a factor X activator and reduces effectively clotting and bleeding time.

  3. Leadership and Management for Safety. General Safety Requirements

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factor, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations (registrants and licensees) and other organizations concerned with facilities and activities that give rise to radiation risks

  4. General safety considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

  5. General safety considerations

    International Nuclear Information System (INIS)

    2001-01-01

    This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

  6. General safety considerations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-09-01

    This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

  7. General safety considerations

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

  8. An Evaluation of the Effects of Human Factors and Ergonomics on Health Care and Patient Safety Practices: A Systematic Review

    Science.gov (United States)

    Zhang, Longhao; Zhao, Pujing; Chen, Ying; Zhang, Mingming

    2015-01-01

    Background From the viewpoint of human factors and ergonomics (HFE), errors often occur because of the mismatch between the system, technique and characteristics of the human body. HFE is a scientific discipline concerned with understanding interactions between human behavior, system design and safety. Objective To evaluate the effectiveness of HFE interventions in improving health care workers’ outcomes and patient safety and to assess the quality of the available evidence. Methods We searched databases, including MEDLINE, EMBASE, BIOSIS Previews and the CBM (Chinese BioMedical Literature Database), for articles published from 1996 to Mar.2015. The quality assessment tool was based on the risk of bias criteria developed by the Cochrane Effective Practice and Organization of Care (EPOC) Group. The interventions of the included studies were categorized into four relevant domains, as defined by the International Ergonomics Association. Results For this descriptive study, we identified 8, 949 studies based on our initial search. Finally, 28 studies with 3,227 participants were included. Among the 28 included studies, 20 studies were controlled studies, two of which were randomized controlled trials. The other eight studies were before/after surveys, without controls. Most of the studies were of moderate or low quality. Five broad categories of outcomes were identified in this study: 1) medical errors or patient safety, 2) health care workers’ quality of working life (e.g. reduced fatigue, discomfort, workload, pain and injury), 3) user performance (e.g., efficiency or accuracy), 4) health care workers’ attitudes towards the interventions(e.g., satisfaction and preference), and 5) economic evaluations. Conclusion The results showed that the interventions positively affected the outcomes of health care workers. Few studies considered the financial merits of these interventions. Most of the included studies were of moderate quality. This review highlights the need

  9. 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)

  10. 2016 Annual Meeting of the German Human Factors and Ergonomics Society

    CERN Document Server

    Duckwitz, Sönke; Flemisch, Frank; Frenz, Martin; Kuz, Sinem; Mertens, Alexander; Mütze-Niewöhner, Susanne

    2017-01-01

    These proceedings summarize the best papers in each research area represented at the 2016 Annual Meeting of the German Human Factors and Ergonomics Society, held at Institute of Industrial Engineering and Ergonomics of RWTH Aachen University from March 2-4. The meeting featured more than 200 presentations and 36 posters reflecting the diversity of subject matter in the field of human and industrial engineering. This volume addresses human factors and safety specialists, industrial engineers, work and organizational psychologists, occupational medicines as well as production planners and design engineers.

  11. 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

  12. Human factors

    International Nuclear Information System (INIS)

    Brown, G.J.

    1991-01-01

    Recent reactor accidents have spurred the major review, described here, of the contribution of operator personnel to safety in Scottish Nuclear Power Stations. The review aims to identify factors leading to the Chernobyl accident and take preventative measures to avoid possible recurrence. Scottish Nuclear power stations aim to remove the operator from a position where failure to take correct action could lead to a safety hazard. Instead operators concentrate on routine and breakdown maintenance and measures are taken to minimize the probability of operator error. The review concluded that most safety procedures were satisfactory but safety analysis supported by good design practices may offer a significant reduction in the risk of operator error. (UK)

  13. 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

  14. Applying Human Factors during the SIS Life Cycle

    International Nuclear Information System (INIS)

    Avery, K.

    2010-01-01

    Safety Instrumented Systems (SIS) are widely used in U.S. Department of Energy's (DOE) nonreactor nuclear facilities for safety-critical applications. Although use of the SIS technology and computer-based digital controls, can improve performance and safety, it potentially introduces additional complexities, such as failure modes that are not readily detectable. Either automated actions or manual (operator) actions may be required to complete the safety instrumented function to place the process in a safe state or mitigate a hazard in response to an alarm or indication. DOE will issue a new standard, Application of Safety Instrumented Systems Used at DOE Nonreactor Nuclear Facilities, to provide guidance for the design, procurement, installation, testing, maintenance, operation, and quality assurance of SIS used in safety significant functions at DOE nonreactor nuclear facilities. The DOE standard focuses on utilizing the process industry consensus standard, American National Standards Institute/ International Society of Automation (ANSI/ISA) 84.00.01, Functional Safety: Safety Instrumented Systems for the Process Industry Sector, to support reliable SIS design throughout the DOE complex. SIS design must take into account human-machine interfaces and their limitations and follow good human factors engineering (HFE) practices. HFE encompasses many diverse areas (e.g., information display, user-system interaction, alarm management, operator response, control room design, and system maintainability), which affect all aspects of system development and modification. This paper presents how the HFE processes and principles apply throughout the SIS life cycle to support the design and use of SIS at DOE nonreactor nuclear facilities.

  15. Double Shell Tank (DST) Human Factors Study

    International Nuclear Information System (INIS)

    CHAFFEE, G.A.

    1994-01-01

    This report documents the data collection and analyses that were performed in development of material to be used in the Human Factors chapter for the upgrade to the Safety Analysis Report (SAR) for the Double-Shell Tank Farms (DSTF). This study was conducted to collect the data that is necessary to prepare the Human Factors chapter for the upgrade of the SAR for the DSTF. Requirements for the HF chapter of the SAR generally dictate that the facility management describe how the consideration of operator capabilities and limitations and operating experience are used in ensuring the safe and effective operation of the facility. Additionally, analysis to indicate the contribution of human error to the safety basis accidents or events must be reported. Since the DSTF is a mature operating facility and the requirement to prepare a HF chapter is new, it was not expected that the consideration of HF principles would be an explicit part of DSTF operations. It can be expected, however, that the programs that guide the daily operations at the DSTF contain provisions for the consideration of the needs of their operating personnel and lessons learned from prior experience. Consideration of both the SAR requirements and the nature of the DSTF operations led to the following objectives being defined for the study: (1) to identify the programs at the OSTF where human performance may be considered; (2) to describe how HF principles and operating experience are used to ensure safe and reliable human performance at the DSTF; (3) to describe how HF principles and operating experience are considered as modifications or improvements are made at the DSTF; and (4) to perform task analysis sufficient to understand the potential for human error in OSTF operations

  16. 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

  17. 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

  18. 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.

  19. General safety aspects

    International Nuclear Information System (INIS)

    1998-01-01

    In this part next aspects are described: (1) Priority to safety; (2) Financial and human resources;; (3) Human factor; (4) Operator's quality assurance system; (5) Safety assessment and Verification; (6) Radiation protection and (7) Emergency preparedness

  20. 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)

  1. A human factors framework and study of the effect of nursing workload on patient safety and employee quality of working life.

    Science.gov (United States)

    Holden, Richard J; Scanlon, Matthew C; Patel, Neal R; Kaushal, Rainu; Escoto, Kamisha Hamilton; Brown, Roger L; Alper, Samuel J; Arnold, Judi M; Shalaby, Theresa M; Murkowski, Kathleen; Karsh, Ben-Tzion

    2011-01-01

    Nursing workload is increasingly thought to contribute to both nurses' quality of working life and quality/safety of care. Prior studies lack a coherent model for conceptualising and measuring the effects of workload in healthcare. In contrast, we conceptualised a human factors model for workload specifying workload at three distinct levels of analysis and having multiple nurse and patient outcomes. To test this model, we analysed results from a cross-sectional survey of a volunteer sample of nurses in six units of two academic tertiary care paediatric hospitals. Workload measures were generally correlated with outcomes of interest. A multivariate structural model revealed that: the unit-level measure of staffing adequacy was significantly related to job dissatisfaction (path loading=0.31) and burnout (path loading=0.45); the task-level measure of mental workload related to interruptions, divided attention, and being rushed was associated with burnout (path loading=0.25) and medication error likelihood (path loading=1.04). Job-level workload was not uniquely and significantly associated with any outcomes. The human factors engineering model of nursing workload was supported by data from two paediatric hospitals. The findings provided a novel insight into specific ways that different types of workload could affect nurse and patient outcomes. These findings suggest further research and yield a number of human factors design suggestions.

  2. Organizational factors influencing improvements in safety

    International Nuclear Information System (INIS)

    Marcus, A.; Nichols, M.L.; Olson, J.; Osborn, R.; Thurber, J.

    1992-01-01

    Research reported here seeks to identify the key organizational factors that influence safety-related performance indicators in nuclear power plants over time. It builds upon organizational factors identified in NUREG/CR-5437, and begins to develop a theory of safety-related performance and performance improvement based on economic and behavioral theories of the firm. Central to the theory are concepts of past performance, problem recognition, resource availability, resource allocation, and business strategies that focus attention. Variables which reflect those concepts are combined in statistical models and tested for their ability to explain scrams, safety system actuations, significant events, safety system failures, radiation exposure, and critical hours. Results show the performance indicators differ with respect to the sets of variables which serve as the best predictors of future performance, and past performance is the most consistent predictor of future performance

  3. An Empirical Analysis of Human Performance and Nuclear Safety Culture

    International Nuclear Information System (INIS)

    Jeffrey Joe; Larry G. Blackwood

    2006-01-01

    The purpose of this analysis, which was conducted for the US Nuclear Regulatory Commission (NRC), was to test whether an empirical connection exists between human performance and nuclear power plant safety culture. This was accomplished through analyzing the relationship between a measure of human performance and a plant's Safety Conscious Work Environment (SCWE). SCWE is an important component of safety culture the NRC has developed, but it is not synonymous with it. SCWE is an environment in which employees are encouraged to raise safety concerns both to their own management and to the NRC without fear of harassment, intimidation, retaliation, or discrimination. Because the relationship between human performance and allegations is intuitively reciprocal and both relationship directions need exploration, two series of analyses were performed. First, human performance data could be indicative of safety culture, so regression analyses were performed using human performance data to predict SCWE. It also is likely that safety culture contributes to human performance issues at a plant, so a second set of regressions were performed using allegations to predict HFIS results

  4. Human factors engineering checklists for application in the SAR process

    International Nuclear Information System (INIS)

    Overlin, T.K.; Romero, H.A.; Ryan, T.G.

    1995-03-01

    This technical report was produced to assist the preparers and reviewers of the human factors portions of the SAR in completing their assigned tasks regarding analysis and/or review of completed analyses. The checklists, which are the main body of the report, and the subsequent tables, were developed to assist analysts in generating the needed analysis data to complete the human engineering analysis for the SAR. The technical report provides a series of 19 human factors engineering (HFE) checklists which support the safety analyses of the US Department of Energy's (DOE) reactor and nonreactor facilities and activities. The results generated using these checklists and in the preparation of the concluding analyses provide the technical basis for preparing the human factors chapter, and subsequent inputs to other chapters, required by DOE as a part of the safety analysis reports (SARs). This document is divided into four main sections. The first part explains the origin of the checklists, the sources utilized, and other information pertaining to the purpose and scope of the report. The second part, subdivided into 19 sections, is the checklists themselves. The third section is the glossary which defines terms that could either be unfamiliar or have specific meanings within the context of these checklists. The final section is the subject index in which the glossary terms are referenced back to the specific checklist and page the term is encountered

  5. Human reliability analysis methods for probabilistic safety assessment

    International Nuclear Information System (INIS)

    Pyy, P.

    2000-11-01

    Human reliability analysis (HRA) of a probabilistic safety assessment (PSA) includes identifying human actions from safety point of view, modelling the most important of them in PSA models, and assessing their probabilities. As manifested by many incidents and studies, human actions may have both positive and negative effect on safety and economy. Human reliability analysis is one of the areas of probabilistic safety assessment (PSA) that has direct applications outside the nuclear industry. The thesis focuses upon developments in human reliability analysis methods and data. The aim is to support PSA by extending the applicability of HRA. The thesis consists of six publications and a summary. The summary includes general considerations and a discussion about human actions in the nuclear power plant (NPP) environment. A condensed discussion about the results of the attached publications is then given, including new development in methods and data. At the end of the summary part, the contribution of the publications to good practice in HRA is presented. In the publications, studies based on the collection of data on maintenance-related failures, simulator runs and expert judgement are presented in order to extend the human reliability analysis database. Furthermore, methodological frameworks are presented to perform a comprehensive HRA, including shutdown conditions, to study reliability of decision making, and to study the effects of wrong human actions. In the last publication, an interdisciplinary approach to analysing human decision making is presented. The publications also include practical applications of the presented methodological frameworks. (orig.)

  6. [Surgeons can learn from pilots: human factors in surgery].

    Science.gov (United States)

    Sockeel, P; Chatelain, E; Massoure, M-P; David, P; Chapellier, X; Buffat, S

    2009-06-01

    Human factors (HF) study is mandatory to get air transport pilot licences. In aviation, crew resource management (CRM) and declaration of adverse events (feedback) result in improving of air safety. Air missions and surgical procedures have similarities. Bridging the gap is tempting, despite severe warnings against simplistic adaptation. Putting HF theory into surgical practice: how to? Educational principles derived from CRM improve professional attitudes of a team. We propose to translate concepts of CRM to clinical teams. CRM training applying in surgery could allow the work environment to be restructured to reduce human error. Feedback: in aviation, the Bureau of Flight Safety deals with investigations for air events. Pilots, air traffic controllers can anonymously declare nuisance, resulting in a feedback for the whole air force. Adverse events are analysed. Usually, multilevel problems are found, rather than the only responsibility of the last operator. Understanding the mechanisms of human failure finally improves safety. In surgery, CRM and feedback would probably be helpful. Anyway, it requires time; people have to change their mind. Nevertheless people such as fighter pilots, who were very unwilling at the beginning, now consider HF as a cornerstone for security. But it is difficult to estimate the extent of HF-related morbidity and mortality. We propose as a first step to consider CRM and feedback in surgical procedure. HF deals with the mechanisms of human errors and the ways to improve safety and probably improve the surgical team's efficacy.

  7. Quantification of human reliability in probabilistic safety assessment

    International Nuclear Information System (INIS)

    Hirschberg, S.; Dankg, Vinh N.

    1996-01-01

    Human performance may substantially influence the reliability and safety of complex technical systems. For this reason, Human Reliability Analysis (HRA) constitutes an important part of Probabilistic Safety Assessment (PSAs) or Quantitative Risk Analyses (QRAs). The results of these studies as well as analyses of past accidents and incidents clearly demonstrate the importance of human interactions. The contribution of human errors to the core damage frequency (CDF), as estimated in the Swedish nuclear PSAs, are between 15 and 88%. A survey of the FRAs in the Swiss PSAs shows that also for the Swiss nuclear power plants the estimated HE contributions are substantial (49% of the CDF due to internal events in the case of Beznau and 70% in the case of Muehleberg; for the total CDF, including external events, 25% respectively 20%). Similar results can be extracted from the PSAs carried out for French, German, and US plants. In PSAs or QRAs, the adequate treatment of the human interactions with the system is a key to the understanding of accident sequences and their relative importance to overall risk. The main objectives of HRA are: first, to ensure that the key human interactions are systematically identified and incorporated into the safety analysis in a traceable manner, and second, to quantify the probabilities of their success and failure. Adopting a structured and systematic approach to the assessment of human performance makes it possible to provide greater confidence that the safety and availability of human-machine systems is not unduly jeopardized by human performance problems. Section 2 discusses the different types of human interactions analysed in PSAs. More generally, the section presents how HRA fits in the overall safety analysis, that is, how the human interactions to be quantified are identified. Section 3 addresses the methods for quantification. Section 4 concludes the paper by presenting some recommendations and pointing out the limitations of the

  8. Defining safety culture and the nexus between safety goals and safety culture. 3. A Methodology for Identifying Deficiencies in Safety Culture

    International Nuclear Information System (INIS)

    Apostolakis, George; Weil, Rick

    2001-01-01

    At present, the drivers of performance problems at nuclear power plants (NPPs) are organizational in nature. Organizational deficiencies and other 'latent' conditions cause human errors, resulting in incidents that impact the performance of NPPs. Therefore, the human reliability community, regulators, and others concerned with NPP safety express the view that safety culture and organizational factors play an important role in plant safety. However, we have yet to identify one complete set of organizational factors, establish links between deficient safety culture and performance, or develop adequate tools to measure safety culture. This paper will contribute to the resolution of these issues. Safety culture is not a single factor but rather is a collection of several distinct factors. This paper asserts that in order to pro-actively manage safety culture at NPPs, leading indicators and appropriate measurements must be identified and developed. Central to this effort are the identification of the distinct factors comprising safety culture and the relationships between those factors and performance. We have identified several factors important to safety culture. We have developed a methodology that is a combination of traditional root-cause analysis and theories of human error, most notably Reason's theory of accident causation. In addition to this methodology's usefulness in identifying deficiencies in safety culture, it could also be used as a starting point to identify leading indicators of deteriorating safety performance. We have identified six organizational factors as being important: communication, formalization, goal prioritization, problem identification, roles and responsibilities, and technical knowledge. In addition, we have found that certain organizational factors, although pervasive throughout the organization, have a much greater influence on the successful outcome of particular tasks of work processes, rather than being equally important to all

  9. Human factors reliability benchmark exercise, report of the SRD participation

    International Nuclear Information System (INIS)

    Waters, Trevor

    1988-01-01

    Within the scope of the Human Factors Reliability Benchmark Exercise, organised by the Joint Research Centre, Ispra, Italy, the Safety and Reliability Directorate (SRD) team has performed analysis of human factors in two different activities - a routine test and a non-routine operational transient. For both activities, an 'FMEA-like' task, potential errors, and the factors which affect performance. For analysis of the non-routine activity, which involved a significant amount of cognitive processing, such as diagnosis and decision making, a new approach for qualitative analysis has been developed. Modelling has been performed using both event trees and fault trees and examples are provided. Human error probabilities were estimated using the methods Absolute Probability Judgement (APJ), Human Cognitive Reliability Method (HCR), Human Error and Assessment and Reduction Technique (HEART), Success-Likelihood Index Method (SLIM), Technica Empiriza Stima Eurori Operatori (TESEO), and Technique for Human Error Rate Prediction (THERP). A discussion is provided of the lessons learnt in the course of the exercise and unresolved difficulties in the assessment of human reliability. (author)

  10. THE FUTURE OF PASSENGER AIR TRANSPORT – VERY LARGE AIRCRAFT AND OUT KEY HUMAN FACTORS AFFECTING THE OPERATION AND SAFETY OF PASSENGER AIR TRANSPORT

    Directory of Open Access Journals (Sweden)

    Petra Skolilova

    2017-12-01

    Full Text Available The article outlines some human factors affecting the operation and safety of passenger air transport given the massive increase in the use of the VLA. Decrease of the impact of the CO2 world emissions is one of the key goals for the new aircraft design. The main wave is going to reduce the burned fuel. Therefore, the eco-efficiency engines combined with reasonable economic operation of the aircraft are very important from an aviation perspective. The prediction for the year 2030 says that about 90% of people, which will use long-haul flights to fly between big cities. So, the A380 was designed exactly for this time period, with a focus on the right capacity, right operating cost and right fuel burn per seat. There is no aircraft today with better fuel burn combined with eco-efficiency per seat, than the A380. The very large aircrafts (VLAs are the future of the commercial passenger aviation. Operating cost versus safety or CO2 emissions versus increasing automation inside the new generation aircraft. Almost 80% of the world aircraft accidents are caused by human error based on wrong action, reaction or final decision of pilots, the catastrophic failures of aircraft systems, or air traffic control errors are not so frequent. So, we are at the beginning of a new age in passenger aviation and the role of the human factor is more important than ever.

  11. Influence of topical human epidermal growth factor on postkeratoplasty re-epithelialisation

    NARCIS (Netherlands)

    M.M. Dellaert; T.A. Casey; S. Wiffen; J. Gordon (Jocelynne); P. Johnson (Jürgen); A.J. Geerards (Annette); W.J. Rijneveld (Wilhelmina); L. Remeijer (Lies); W.H. Beekhuis (Houdijn); P.G.H. Mulder (Paul)

    1997-01-01

    textabstractAIM: To test the efficacy and safety of recombinant human epidermal growth factor (hEGF) on corneal re-epithelialisation following penetrating keratoplasty. METHODS: A prospective, randomised, placebo controlled study was carried out in which patients were

  12. 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.

  13. Human reliability in probabilistic safety assessments

    International Nuclear Information System (INIS)

    Nunez Mendez, J.

    1989-01-01

    Nowadays a growing interest in medioambiental aspects is detected in our country. It implies an assessment of the risk involved in the industrial processess and installations in order to determine if those are into the acceptable limits. In these safety assessments, among which PSA (Probabilistic Safety Assessments), can be pointed out the role played by the human being in the system is one of the more relevant subjects. (This relevance has been demostrated in the accidents happenned). However in Spain there aren't manuals specifically dedicated to asses the human contribution to risk in the frame of PSAs. This report aims to improve this situation providing: a) a theoretical background to help the reader in the understanding of the nature of the human error, b) a guide to carry out a Human Reliability Analysis and c) a selected overwiev of the techniques and methodologies currently applied in this area. (Author)

  14. Towards Clinical Application of Neurotrophic Factors to the Auditory Nerve; Assessment of Safety and Efficacy by a Systematic Review of Neurotrophic Treatments in Humans

    Directory of Open Access Journals (Sweden)

    Aren Bezdjian

    2016-11-01

    Full Text Available Animal studies have evidenced protection of the auditory nerve by exogenous neurotrophic factors. In order to assess clinical applicability of neurotrophic treatment of the auditory nerve, the safety and efficacy of neurotrophic therapies in various human disorders were systematically reviewed. Outcomes of our literature search included disorder, neurotrophic factor, administration route, therapeutic outcome, and adverse event. From 2103 articles retrieved, 20 randomized controlled trials including 3974 patients were selected. Amyotrophic lateral sclerosis (53% was the most frequently reported indication for neurotrophic therapy followed by diabetic polyneuropathy (28%. Ciliary neurotrophic factor (50%, nerve growth factor (24% and insulin-like growth factor (21% were most often used. Injection site reaction was a frequently occurring adverse event (61% followed by asthenia (24% and gastrointestinal disturbances (20%. Eighteen out of 20 trials deemed neurotrophic therapy to be safe, and six out of 17 studies concluded the neurotrophic therapy to be effective. Positive outcomes were generally small or contradicted by other studies. Most non-neurodegenerative diseases treated by targeted deliveries of neurotrophic factors were considered safe and effective. Hence, since local delivery to the cochlea is feasible, translation from animal studies to human trials in treating auditory nerve degeneration seems promising.

  15. Leadership and Management for Safety. General Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  16. Leadership and Management for Safety. General Safety Requirements (Chinese Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  17. Leadership and Management for Safety. General Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  18. Leadership and Management for Safety. General Safety Requirements (Spanish Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    his Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  19. 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

  20. Human Reliability in Probabilistic Safety Assessments

    International Nuclear Information System (INIS)

    Nunez Mendez, J.

    1989-01-01

    Nowadays a growing interest in environmental aspects is detected in our country. It implies an assessment of the risk involved in the industrial processes and installations in order to determine if those are into the acceptable limits. In these safety assessments, among which PSA (Probabilistic Safety Assessments), can be pointed out the role played by the human being in the system is one of the more relevant subjects (This relevance has been demonstrated in the accidents happened) . However, in Spain there aren't manuals specifically dedicated to asses the human contribution to risk in the frame of PSAs. This report aims to improve this situation providing: a) a theoretical background to help the reader in the understanding of the nature of the human error, b) a quid to carry out a Human Reliability Analysis and c) a selected overview of the techniques and methodologies currently applied in this area. (Author) 20 refs

  1. Human factors evaluation of remote afterloading brachytherapy: Human error and critical tasks in remote afterloading brachytherapy and approaches for improved system performance. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-01

    Remote Afterloading Brachytherapy (RAB) is a medical process used in the treatment of cancer. RAB uses a computer-controlled device to remotely insert and remove radioactive sources close to a target (or tumor) in the body. Some RAB problems affecting the radiation dose to the patient have been reported and attributed to human error. To determine the root cause of human error in the RAB system, a human factors team visited 23 RAB treatment sites in the US The team observed RAB treatment planning and delivery, interviewed RAB personnel, and performed walk-throughs, during which staff demonstrated the procedures and practices used in performing RAB tasks. Factors leading to human error in the RAB system were identified. The impact of those factors on the performance of RAB was then evaluated and prioritized in terms of safety significance. Finally, the project identified and evaluated alternative approaches for resolving the safety significant problems related to human error.

  2. Human factors evaluation of remote afterloading brachytherapy: Human error and critical tasks in remote afterloading brachytherapy and approaches for improved system performance. Volume 1

    International Nuclear Information System (INIS)

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

    1995-05-01

    Remote Afterloading Brachytherapy (RAB) is a medical process used in the treatment of cancer. RAB uses a computer-controlled device to remotely insert and remove radioactive sources close to a target (or tumor) in the body. Some RAB problems affecting the radiation dose to the patient have been reported and attributed to human error. To determine the root cause of human error in the RAB system, a human factors team visited 23 RAB treatment sites in the US The team observed RAB treatment planning and delivery, interviewed RAB personnel, and performed walk-throughs, during which staff demonstrated the procedures and practices used in performing RAB tasks. Factors leading to human error in the RAB system were identified. The impact of those factors on the performance of RAB was then evaluated and prioritized in terms of safety significance. Finally, the project identified and evaluated alternative approaches for resolving the safety significant problems related to human error

  3. Intraarticular Sprifermin (Recombinant Human Fibroblast Growth Factor 18) in Knee Osteoarthritis

    DEFF Research Database (Denmark)

    Lohmander, L. S.; Hellot, S.; Dreher, D.

    2014-01-01

    Objective. To evaluate the efficacy and safety of intraarticular sprifermin (recombinant human fibroblast growth factor 18) in the treatment of symptomatic knee osteoarthritis (OA). Methods. The study was a randomized, double-blind, placebo-controlled, proof-of-concept trial. Intraarticular sprif...

  4. 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

  5. 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.

  6. Human factors engineering checklists for application in the SAR process

    Energy Technology Data Exchange (ETDEWEB)

    Overlin, T.K.; Romero, H.A.; Ryan, T.G.

    1995-03-01

    This technical report was produced to assist the preparers and reviewers of the human factors portions of the SAR in completing their assigned tasks regarding analysis and/or review of completed analyses. The checklists, which are the main body of the report, and the subsequent tables, were developed to assist analysts in generating the needed analysis data to complete the human engineering analysis for the SAR. The technical report provides a series of 19 human factors engineering (HFE) checklists which support the safety analyses of the US Department of Energy`s (DOE) reactor and nonreactor facilities and activities. The results generated using these checklists and in the preparation of the concluding analyses provide the technical basis for preparing the human factors chapter, and subsequent inputs to other chapters, required by DOE as a part of the safety analysis reports (SARs). This document is divided into four main sections. The first part explains the origin of the checklists, the sources utilized, and other information pertaining to the purpose and scope of the report. The second part, subdivided into 19 sections, is the checklists themselves. The third section is the glossary which defines terms that could either be unfamiliar or have specific meanings within the context of these checklists. The final section is the subject index in which the glossary terms are referenced back to the specific checklist and page the term is encountered.

  7. 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

  8. Some Challenges in the Design of Human-Automation Interaction for Safety-Critical Systems

    Science.gov (United States)

    Feary, Michael S.; Roth, Emilie

    2014-01-01

    Increasing amounts of automation are being introduced to safety-critical domains. While the introduction of automation has led to an overall increase in reliability and improved safety, it has also introduced a class of failure modes, and new challenges in risk assessment for the new systems, particularly in the assessment of rare events resulting from complex inter-related factors. Designing successful human-automation systems is challenging, and the challenges go beyond good interface development (e.g., Roth, Malin, & Schreckenghost 1997; Christoffersen & Woods, 2002). Human-automation design is particularly challenging when the underlying automation technology generates behavior that is difficult for the user to anticipate or understand. These challenges have been recognized in several safety-critical domains, and have resulted in increased efforts to develop training, procedures, regulations and guidance material (CAST, 2008, IAEA, 2001, FAA, 2013, ICAO, 2012). This paper points to the continuing need for new methods to describe and characterize the operational environment within which new automation concepts are being presented. We will describe challenges to the successful development and evaluation of human-automation systems in safety-critical domains, and describe some approaches that could be used to address these challenges. We will draw from experience with the aviation, spaceflight and nuclear power domains.

  9. The contribution of human factors to risks from radioactive material transport

    International Nuclear Information System (INIS)

    Blenkin, J.J.; Ridsdale, E.; Wilkinson, H.L.

    1998-01-01

    The use of probabilistic risk assessment to assess the safety of radioactive material transport operations is well accepted. However, quantitative risk assessment of radioactive material transport operations have generally not explicitly considered human factors in estimating risks. Given the high profile of human factors as the root cause of many serious transport incidents omission of an explicit consideration of human factors in a risk assessment could lead to assessments losing credibility. In addition, scrutiny of radioactive material transport incident databases reveals a large number of operational incidents and minor accidents that would have been avoided if more attention had been paid to human factors aspects, and provides examples of instances where improvements have been achieved. This paper examines the areas of radioactive material transport risk assessments (both qualitative and quantitative) which could be strengthened by further examination of the impact of human errors. It is concluded that a more complete and detailed understanding of the effects of human factors on the risks from radioactive material transport operations has been obtained. Quality assurance has a key part to play in ensuring that packages are correctly manufactured and prepared for transport. Risk assessments of radioactive material transport operations can be strengthened by concentrating on the key human factors effects. (authors)

  10. Organizational factors affecting safety implementation in food companies in Thailand.

    Science.gov (United States)

    Chinda, Thanwadee

    2014-01-01

    Thai food industry employs a massive number of skilled and unskilled workers. This may result in an industry with high incidences and accident rates. To improve safety and reduce the accident figures, this paper investigates factors influencing safety implementation in small, medium, and large food companies in Thailand. Five factors, i.e., management commitment, stakeholders' role, safety information and communication, supportive environment, and risk, are found important in helping to improve safety implementation. The statistical analyses also reveal that small, medium, and large food companies hold similar opinions on the risk factor, but bear different perceptions on the other 4 factors. It is also found that to improve safety implementation, the perceptions of safety goals, communication, feedback, safety resources, and supervision should be aligned in small, medium, and large companies.

  11. Safety Metrics for Human-Computer Controlled Systems

    Science.gov (United States)

    Leveson, Nancy G; Hatanaka, Iwao

    2000-01-01

    The rapid growth of computer technology and innovation has played a significant role in the rise of computer automation of human tasks in modem production systems across all industries. Although the rationale for automation has been to eliminate "human error" or to relieve humans from manual repetitive tasks, various computer-related hazards and accidents have emerged as a direct result of increased system complexity attributed to computer automation. The risk assessment techniques utilized for electromechanical systems are not suitable for today's software-intensive systems or complex human-computer controlled systems.This thesis will propose a new systemic model-based framework for analyzing risk in safety-critical systems where both computers and humans are controlling safety-critical functions. A new systems accident model will be developed based upon modem systems theory and human cognitive processes to better characterize system accidents, the role of human operators, and the influence of software in its direct control of significant system functions Better risk assessments will then be achievable through the application of this new framework to complex human-computer controlled systems.

  12. 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

  13. 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.

  14. Safety Psychology Applicating on Coal Mine Safety Management Based on Information System

    Science.gov (United States)

    Hou, Baoyue; Chen, Fei

    In recent years, with the increase of intensity of coal mining, a great number of major accidents happen frequently, the reason mostly due to human factors, but human's unsafely behavior are affected by insecurity mental control. In order to reduce accidents, and to improve safety management, with the help of application security psychology, we analyse the cause of insecurity psychological factors from human perception, from personality development, from motivation incentive, from reward and punishment mechanism, and from security aspects of mental training , and put forward countermeasures to promote coal mine safety production,and to provide information for coal mining to improve the level of safety management.

  15. Automating the Human Factors Engineering and Evaluation Processes

    International Nuclear Information System (INIS)

    Mastromonico, C.

    2002-01-01

    The Westinghouse Savannah River Company (WSRC) has developed a software tool for automating the Human Factors Engineering (HFE) design review, analysis, and evaluation processes. The tool provides a consistent, cost effective, graded, user-friendly approach for evaluating process control system Human System Interface (HSI) specifications, designs, and existing implementations. The initial set of HFE design guidelines, used in the tool, was obtained from NUREG- 0700. Each guideline was analyzed and classified according to its significance (general concept vs. supporting detail), the HSI technology (computer based vs. non-computer based), and the HSI safety function (safety vs. non-safety). Approximately 10 percent of the guidelines were determined to be redundant or obsolete and were discarded. The remaining guidelines were arranged in a Microsoft Access relational database, and a Microsoft Visual Basic user interface was provided to facilitate the HFE design review. The tool also provides the capability to add new criteria to accommodate advances in HSI technology and incorporate lessons learned. Summary reports produced by the tool can be easily ported to Microsoft Word and other popular PC office applications. An IBM compatible PC with Microsoft Windows 95 or higher is required to run the application

  16. Determination of engineering safety factor -routine in Hungary (a methodology for the normal operation local power engineering safety factors)

    International Nuclear Information System (INIS)

    Szecsenyi, Z.; Korpas, L.; Bona, G.; Kereszturi, A.

    2010-01-01

    From the late nineties Paks Nuclear Power Plant-in collaboration with KFKI Atomic Energy Research Institute (KFKI AEKI)- is developing a system for determining the normal operation local power engineering safety factors. The system is based on a Monte Carlo sampling of the uncertain model input parameters. Additionally, the comparison of the calculation to the in-core measurements plays essential role for determining some important input parameters. By using new fuel types and the corresponding more recent detailed technological data, the applied method is being improved from time to time. Presently, the actually used and authorized engineering safety factors at Paks NPP are determined by using this method. In the paper, the system.s main properties are described (not going beyond the possible extent). The main points are as follows:-Mathematical definition of the engineering safety factor;-Sources of the uncertainties;-Input error propagation method constituting the basis of the system;-Flow-chart of the subsequent steps of the determination Finally, in the paper the engineering safety factors values of some selected parameters are presented as examples for demonstration of the capability of the method. (Authors)

  17. New engineering safety factors for Loviisa NPP core calculations

    Energy Technology Data Exchange (ETDEWEB)

    Kuopanportti, Jaakko; Saarinen, Simo; Lahtinen, Tuukka; Ekstroem, Karoliina [Fortum Power and Heat Ltd., Fortum (Finland)

    2017-09-15

    In Loviisa NPP, there are two limiting thermal margins called the enthalpy rise margin and the linear heat rate margin that are monitored during normal operation. Engineering safety factors are applied in determination of both of these factors. The factors take into account the effect of various manufacturing tolerances, impact of the irradiation and simulation uncertainties on the local heat rate and on the enthalpy of the coolant. The engineering factors were re-evaluated during 2015 and the factors were approved by the Finnish radiation and nuclear safety authority in 2016. The re-evaluation was performed by considering all of the identified phenomena that affect the local heat rate or the enthalpy of the coolant. This paper summarizes the work that was performed during the re-evaluation of the engineering safety factors and presents the results for each uncertainty component. The new engineering safety factors are 1.115 for the linear heat rate and 1.100 for the enthalpy rise margin when the old factors were 1.12 and 1.16, respectively. The new factors improve the fuel economy by about 1%.

  18. 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)

  19. 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

  20. Color-coding and human factors engineering to improve patient safety characteristics of paper-based emergency department clinical documentation.

    Science.gov (United States)

    Kobayashi, Leo; Boss, Robert M; Gibbs, Frantz J; Goldlust, Eric; Hennedy, Michelle M; Monti, James E; Siegel, Nathan A

    2011-01-01

    Investigators studied an emergency department (ED) physical chart system and identified inconsistent, small font labeling; a single-color scheme; and an absence of human factors engineering (HFE) cues. A case study and description of the methodology with which surrogate measures of chart-related patient safety were studied and subsequently used to reduce latent hazards are presented. Medical records present a challenge to patient safety in EDs. Application of HFE can improve specific aspects of existing medical chart organization systems as they pertain to patient safety in acute care environments. During 10 random audits over 5 consecutive days (573 data points), 56 (9.8%) chart binders (range 0.0-23%) were found to be either misplaced or improperly positioned relative to other chart binders; 12 (21%) were in the critical care area. HFE principles were applied to develop an experimental chart binder system with alternating color-based chart groupings, simple and prominent identifiers, and embedded visual cues. Post-intervention audits revealed significant reductions in chart binder location problems overall (p < 0.01), for Urgent Care A and B pods (6.4% to 1.2%; p < 0.05), Fast Track C pod (19.3% to 0.0%; p < 0.05) and Behavioral/Substance Abuse D pod (15.7% to 0.0%; p < 0.05) areas of the ED. The critical care room area did not display an improvement (11.4% to 13.2%; p = 0.40). Application of HFE methods may aid the development, assessment, and modification of acute care clinical environments through evidence-based design methodologies and contribute to safe patient care delivery.

  1. On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors

    Energy Technology Data Exchange (ETDEWEB)

    Sousa, A.L., E-mail: alsousa@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Ribeiro, A.C.O., E-mail: antonio.ribeiro@bayer.com [Bayer Crop Science Brasil S.A., Belford Roxo, RJ (Brazil); Duarte, J.P., E-mail: julianapduarte@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Departamento de Engenharia Nuclear; Frutuoso e Melo, P.F., E-mail: frutuoso@nuclear.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COOPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear

    2013-07-01

    Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)

  2. On applying safety archetypes to the Fukushima accident to identify nonlinear influencing factors

    International Nuclear Information System (INIS)

    Sousa, A.L.; Ribeiro, A.C.O.; Duarte, J.P.; Frutuoso e Melo, P.F.

    2013-01-01

    Nuclear power plants are typically characterized as high reliable organizations. In other words, they are organizations defined as relatively error free over a long period of time. Another relevant characteristic of the nuclear industry is that safety efforts are credited to design. However, major accidents, like the Fukushima accident, have shown that new tools are needed to identify latent deficiencies and help improve their safety level. Safety archetypes proposed elsewhere (e. g., safety issues stalled in the face of technological advances and eroding safety) consonant with International Atomic Energy Agency (IAEA) efforts are used to examine different aspects of accidents in a systemic perspective of the interaction between individuals, technology and organizational factors. Safety archetypes can help consider nonlinear interactions. Effects are rarely proportional to causes and what happens locally in a system (near the current operating point) often does not apply to distant regions (other system states), so that one has to consider the so-called nonlinear interactions. This is the case, for instance, with human probability failure estimates and safety level identification. In this paper, we discuss the Fukushima accident in order to show how archetypes can highlight nonlinear interactions of factors that influenced it and how to maintain safety levels in order to prevent other accidents. The initial evaluation of the set of archetypes suggested in the literature showed that at least four of them are applicable to the Fukushima accident, as is inferred from official reports on the accident. These are: complacency (that is, the effects of complacency on safety), decreased safety awareness, fixing on symptoms and not the real causes and eroding safety. (author)

  3. 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

  4. 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

  5. The PIANC Safety Factor System for Breakwaters

    DEFF Research Database (Denmark)

    Burcharth, H. F.

    2000-01-01

    The paper presents a summary of the recommendations for implementation of safety in breakwater designs given by the PIANC PTC IT Working Group No 12 on Analysis of Rubble Mound Breakwaters with Vertical and Inclined Concrete Walls. The working groups developed for the most important failure modes...... a system of partial safety factors which facilitate design to any target safety level....

  6. 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

  7. 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

  8. Analysis of factors influencing safety management for metro construction in China.

    Science.gov (United States)

    Yu, Q Z; Ding, L Y; Zhou, C; Luo, H B

    2014-07-01

    With the rapid development of urbanization in China, the number and size of metro construction projects are increasing quickly. At the same time, and increasing number of accidents in metro construction make it a disturbing focus of social attention. In order to improve safety management in metro construction, an investigation of the participants' perspectives on safety factors in China metro construction has been conducted to identify the key safety factors, and their ranking consistency among the main participants, including clients, consultants, designers, contractors and supervisors. The result of factor analysis indicates that there are five key factors which influence the safety of metro construction including safety attitude, construction site safety, government supervision, market restrictions and task unpredictability. In addition, ANOVA and Spearman rank correlation coefficients were performed to test the consistency of the means rating and the ranking of safety factors. The results indicated that the main participants have significant disagreement about the importance of safety factors on more than half of the items. Suggestions and recommendations on practical countermeasures to improve metro construction safety management in China are proposed. Copyright © 2013 Elsevier Ltd. All rights reserved.

  9. 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

  10. Human-factors engineering control-room design review/audit: Waterford 3 SES Generating Station, Louisiana Power and Light Company

    International Nuclear Information System (INIS)

    Savage, J.W.

    1983-01-01

    A human factors engineering design review/audit of the Waterford-3 control room was performed at the site on May 10 through May 13, 1982. The report was prepared on the basis of the HFEB's review of the applicant's Preliminary Human Engineering Discrepancy (PHED) report and the human factors engineering design review performed at the site. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. The review team was assisted by consultants from Lawrence Livermore National Laboratory (University of California), Livermore, California

  11. Does the concept of safety culture help or hinder systems thinking in safety?

    Science.gov (United States)

    Reiman, Teemu; Rollenhagen, Carl

    2014-07-01

    The concept of safety culture has become established in safety management applications in all major safety-critical domains. The idea that safety culture somehow represents a "systemic view" on safety is seldom explicitly spoken out, but nevertheless seem to linger behind many safety culture discourses. However, in this paper we argue that the "new" contribution to safety management from safety culture never really became integrated with classical engineering principles and concepts. This integration would have been necessary for the development of a more genuine systems-oriented view on safety; e.g. a conception of safety in which human, technological, organisational and cultural factors are understood as mutually interacting elements. Without of this integration, researchers and the users of the various tools and methods associated with safety culture have sometimes fostered a belief that "safety culture" in fact represents such a systemic view about safety. This belief is, however, not backed up by theoretical or empirical evidence. It is true that safety culture, at least in some sense, represents a holistic term-a totality of factors that include human, organisational and technological aspects. However, the departure for such safety culture models is still human and organisational factors rather than technology (or safety) itself. The aim of this paper is to critically review the various uses of the concept of safety culture as representing a systemic view on safety. The article will take a look at the concepts of culture and safety culture based on previous studies, and outlines in more detail the theoretical challenges in safety culture as a systems concept. The paper also presents recommendations on how to make safety culture more systemic. Copyright © 2013 Elsevier Ltd. All rights reserved.

  12. 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)

  13. 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

  14. Using the Human Systems Simulation Laboratory at Idaho National Laboratory for Safety Focused Research

    Energy Technology Data Exchange (ETDEWEB)

    Joe, Jeffrey .C; Boring, Ronald L.

    2016-07-01

    Under the United States (U.S.) Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program, researchers at Idaho National Laboratory (INL) have been using the Human Systems Simulation Laboratory (HSSL) to conduct critical safety focused Human Factors research and development (R&D) for the nuclear industry. The LWRS program has the overall objective to develop the scientific basis to extend existing nuclear power plant (NPP) operating life beyond the current 60-year licensing period and to ensure their long-term reliability, productivity, safety, and security. One focus area for LWRS is the NPP main control room (MCR), because many of the instrumentation and control (I&C) system technologies installed in the MCR, while highly reliable and safe, are now difficult to replace and are therefore limiting the operating life of the NPP. This paper describes how INL researchers use the HSSL to conduct Human Factors R&D on modernizing or upgrading these I&C systems in a step-wise manner, and how the HSSL has addressed a significant gap in how to upgrade systems and technologies that are built to last, and therefore require careful integration of analog and new advanced digital technologies.

  15. mathematical models for prediction of safety factors for a simply

    African Journals Online (AJOL)

    HOD

    Keywords: reliability, code calibration, load factor, safety factor, design, steel beam. 1. INTRODUCTION ... safety factors for the design of a simply supported steel beam using regression .... 5 design criteria for a solid timber portal frame.

  16. An analysis on human factor issues in criticality accident at a uranium processing plant

    International Nuclear Information System (INIS)

    Sasou, Kunihide; Goda, Hidenori; Hirotsu, Yuko

    2000-01-01

    This report analyses latent factors of a human behavior directly contributing to the criticality accident. It is pouring some 16 kg-U with an enrichment of 18.8% into the precipitation tank. It is the fact that the direct cause of this accident is the workers' unsafe act. However, the authors find lots of latent factors relating to the production-biased company's policy, the poor climate for safety in the work place, the inadequate safety management and the unsuitable equipment. This accident was caused by many organizational factors. This paper also discusses lessons learned from this accident. (author)

  17. A broader consideration of human factor to enhance sustainable building design.

    Science.gov (United States)

    Attaianese, Erminia

    2012-01-01

    The link between ergonomic/human factor and sustainability seems to be clearly evidenced mainly in relation to social dimension of sustainability, in order to contribute to assure corporate social responsibility and global value creation. But the will to establish an equilibrated connection among used resources in human activities, supported by the sustainability perspective, evidences that the contribution of ergonomics/human factors can be effectively enlarged to other aspects, especially in relation to building design. In fact a sustainable building is meant to be a building that contributes, through its characteristics and attribute, to a sustainable development by assuring, in the same time, a decrease of resources use and environmental impact and an increase of health, safety and comfort of the occupants. The purpose of this paper is to analyze in a broader sense the contribution of ergonomic/human factor to design of sustainable building, focusing how ergonomics principles, methodology and techniques can improve building design, enhancing its sustainability performance during all phases of building lifecycle.

  18. 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

  19. MedWatch Safety Alerts for Human Medical Products

    Data.gov (United States)

    U.S. Department of Health & Human Services — MedWatch alerts provide timely new safety information on human drugs, medical devices, vaccines and other biologics, dietary supplements, and cosmetics. The alerts...

  20. Failure and factors of safety in piping system design

    International Nuclear Information System (INIS)

    Antaki, G.A.

    1993-01-01

    An important body of test and performance data on the behavior of piping systems has led to an ongoing reassessment of the code stress allowables and their safety margin. The codes stress allowables, and their factors of safety, are developed from limits on the incipient yield (for ductile materials), or incipient rupture (for brittle materials), of a test specimen loaded in simple tension. In this paper, we examine the failure theories introduced in the B31 and ASME III codes for piping and their inherent approximations compared to textbook failure theories. We summarize the evolution of factors of safety in ASME and B31 and point out that, for piping systems, it is appropriate to reconsider the concept and definition of factors of safety

  1. Investigational new drug safety reporting requirements for human drug and biological products and safety reporting requirements for bioavailability and bioequivalence studies in humans. Final rule.

    Science.gov (United States)

    2010-09-29

    The Food and Drug Administration (FDA) is amending its regulations governing safety reporting requirements for human drug and biological products subject to an investigational new drug application (IND). The final rule codifies the agency's expectations for timely review, evaluation, and submission of relevant and useful safety information and implements internationally harmonized definitions and reporting standards. The revisions will improve the utility of IND safety reports, reduce the number of reports that do not contribute in a meaningful way to the developing safety profile of the drug, expedite FDA's review of critical safety information, better protect human subjects enrolled in clinical trials, subject bioavailability and bioequivalence studies to safety reporting requirements, promote a consistent approach to safety reporting internationally, and enable the agency to better protect and promote public health.

  2. The performance shaping factors influence analysis on the human reliability for NPP operation

    International Nuclear Information System (INIS)

    Farcasiu, M.; Nitoi, M.; Apostol, M.; Florescu, G.

    2008-01-01

    The Human Reliability Analysis (HRA) is an important step in Probabilistic Safety Assessment (PSA) studies and offers an advisability for concrete improvement of the man - machine - organization interfaces, reliability and safety. The goals of this analysis are to obtain sufficient details in order to understand and document all-important factors that affect human performance. The purpose of this paper is to estimate the human errors probabilities in view of the negative or positive effect of the human performance shaping factors (PSFs) for the mitigation of the initiating events which could occur in Nuclear Power Plant (NPP). Using THERP and SPAR-H methods, an analysis model of PSFs influence on the human reliability is performed. This model is applied to more important activities, that are necessary to mitigate 'one steam generator tube failure' event at Cernavoda NPP. The results are joint human error probabilities (JHEP) values estimated for the following situations: without regarding to PSFs influence; with PSFs in specific conditions; with PSFs which could have only positive influence and with PSFs which could have only negative influence. In addition, PSFs with negative influence were identified and using the DOE method, the necessary activities for changing negative influence were assigned. (authors)

  3. Design and management of production systems: Integration of human factors and ergonomics

    DEFF Research Database (Denmark)

    Jensen, Per Langå; Broberg, Ole; Hasle, Peter

    2006-01-01

    Integration of ergonomics, human factors and occupational health and safety into design and management of pro-duction systems has for years been the major strategy for professional within the field. The traditional approach based on establishing ergonomic criteria’s to be integrated into other...

  4. Human and organisational factors in the reliability of non-destructive testing (NOT)

    International Nuclear Information System (INIS)

    Norros, L.

    1998-01-01

    Non-destructive testing used in in-service inspections can be seen as a complicated activity system including three mutually related sub-activities: (1) definition of inspection programs and necessary resources, (2) carrying out diagnostic inspections, and (3) interpretation of the results from the view of plant safety and corrective measures. Various studies to investigate and measure the NDT performance have produced disappointing result. No clear correlations between single human factors and performance have been identified even though general agreement exists concerning the significance of human factors to the reliability of testing. Another incentive for our studies has been to test and evaluate the applicability of the international results in the Finnish circumstances. Three successive studies have thus been carried out on the human and organisational factors in non-destructive testing. (author)

  5. International Conference on Human and Organizational Aspects of Assuring Nuclear Safety. Exploring 30 years of Safety Culture. Programme and Abstracts

    International Nuclear Information System (INIS)

    2016-01-01

    Thirty years ago, the International Nuclear Safety Advisory Group concluded, in its investigation of the Chernobyl accident, that one of the key lessons to be learned from that accident was the importance of a strong safety culture to maintain safe operations. Almost five years have now passed since the accident at the Fukushima Daiichi nuclear power plant, and the need to implement a systemic approach to safety that takes into account the complex and dynamic sociotechnical systems comprising nuclear infrastructure is one of the main lessons emerging from investigations. This conference will allow an international audience to take a step back and reflect upon the knowledge accumulated in the areas of human and organizational factors (HOF), safety culture and leadership for safety over the past 30 years. The objectives of the conference are to: • Review the experience gained with regard to HOF, safety culture and leadership for safety; • Share and gather experiences related to current developments, approaches, methods and research in the areas of HOF, safety culture and leadership for safety; and • Identify the future needs for building organizational resilience capabilities in order to further strengthen defence in depth for nuclear facilities and activities. The special focus of the conference will be on safety culture and the past 30 years of developments in this area.

  6. The Safety of Melatonin in Humans

    DEFF Research Database (Denmark)

    Andersen, Lars Peter Holst; Gögenür, Ismayil; Rosenberg, Jacob

    2016-01-01

    Exogenous melatonin has been investigated as treatment for a number of medical and surgical diseases, demonstrating encouraging results. The aim of this review was to present and evaluate the literature concerning the possible adverse effects and safety of exogenous melatonin in humans. Furthermore...... been reported. No studies have indicated that exogenous melatonin should induce any serious adverse effects. Similarly, randomized clinical studies indicate that long-term melatonin treatment causes only mild adverse effects comparable to placebo. Long-term safety of melatonin in children...

  7. Hazard Management Dealt by Safety Professionals in Colleges: The Impact of Individual Factors

    Directory of Open Access Journals (Sweden)

    Tsung-Chih Wu

    2016-12-01

    Full Text Available Identifying, evaluating, and controlling workplace hazards are important functions of safety professionals (SPs. The purpose of this study was to investigate the content and frequency of hazard management dealt by safety professionals in colleges. The authors also explored the effects of organizational factors/individual factors on SPs’ perception of frequency of hazard management. The researchers conducted survey research to achieve the objective of this study. The researchers mailed questionnaires to 200 SPs in colleges after simple random sampling, then received a total of 144 valid responses (response rate = 72%. Exploratory factor analysis indicated that the hazard management scale (HMS extracted five factors, including physical hazards, biological hazards, social and psychological hazards, ergonomic hazards, and chemical hazards. Moreover, the top 10 hazards that the survey results identified that safety professionals were most likely to deal with (in order of most to least frequent were: organic solvents, illumination, other chemicals, machinery and equipment, fire and explosion, electricity, noise, specific chemicals, human error, and lifting/carrying. Finally, the results of one-way multivariate analysis of variance (MANOVA indicated there were four individual factors that impacted the perceived frequency of hazard management which were of statistical and practical significance: job tenure in the college of employment, type of certification, gender, and overall job tenure. SPs within colleges and industries can now discuss plans revolving around these five areas instead of having to deal with all of the separate hazards.

  8. Applying Petri nets in modelling the human factor

    International Nuclear Information System (INIS)

    Bedreaga, Luminita; Constntinescu, Cristina; Guzun, Basarab

    2007-01-01

    Usually, in the reliability analysis performed for complex systems, we determine the success probability to work with other performance indices, i.e. the likelihood associated with a given state. The possible values assigned to system states can be derived using inductive methods. If one wants to calculate the probability to occur a particular event in the system, then deductive methods should be applied. In the particular case of the human reliability analysis, as part of probabilistic safety analysis, the international regulatory commission have developed specific guides and procedures to perform such assessments. The paper presents the modality to obtain the human reliability quantification using the Petri nets approach. This is an efficient means to assess reliability systems because of their specific features. The examples showed in the paper are from human reliability documentation without a detailed human factor analysis (qualitative). We present human action modelling using event trees and Petri nets approach. The obtained results by these two kinds of methods are in good concordance. (authors)

  9. 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.

  10. 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

  11. PSA methodology including new design, operational and safety factors, 'Level of recognition of phenomena with a presumed dominant influence upon operational safety' (failures of conventional as well as non-conventional passive components, dependent failures, influence of operator, fires and external threats, digital control, organizational factors)

    International Nuclear Information System (INIS)

    Jirsa, P.

    2001-10-01

    The document represents a specific type of discussion of existing methodologies for the creation and application of probabilistic safety assessment (PSA) in light of the EUR document summarizing requirements placed by Western European NPP operators on the future design of nuclear power plants. A partial goal of this discussion consists in mapping, from the PSA point of view, those selected design, operational and/or safety factors of future NPPs that may be entirely new or, at least, newly addressed. Therefore, the terms of reference for this stage were formulated as follows: Assess current level of knowledge and procedures in the analysis of factors and phenomena with a dominant influence upon operational safety of new generation reactors, especially in the following areas: (1) Phenomenology of failure types and mechanisms and reliability of conventional passive safety system components; (2) Phenomenology of failure types and mechanisms and reliability of non-conventional passive components of newly designed safety systems; (3) Phenomenology of types and mechanisms of dependent failures; (4) Human factor role in new generation reactors and its effect upon safety; (5) Fire safety and other external threats to new nuclear installations; (6) Reliability of the digital systems of the I and C system and their effect upon safety; and (7) Organizational factors in new nuclear installations. (P.A.)

  12. A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sunghyun; Kim, Namyeong; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

    2015-10-15

    In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant.

  13. A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments

    International Nuclear Information System (INIS)

    Park, Sunghyun; Kim, Namyeong; Jae, Moosung

    2015-01-01

    In order to incorporate organizational factors into PSA, a methodology needs to be developed. Using the AHP to weigh organizational factors as well as the SLIM to rate those factors, a methodology is introduced in this study. The safety issues related to nuclear safety culture have occurred increasingly. The quantification tool has to be developed in order to include the organizational factor into Probabilistic Safety Assessments. In this study, the state-of-the-art for the organizational evaluation methodologies has been surveyed. This study includes the research for organizational factors, maintenance process, maintenance process analysis models, a quantitative methodology using Analytic Hierarchy Process, Success Likelihood Index Methodology. The purpose of this study is to develop a methodology to incorporate the safety culture into PSA for obtaining more objective risk than before. The organizational factor considered in nuclear safety culture might affect the potential risk of human error and hardware-failure. The safety culture impact index to monitor the plant safety culture can be assessed by applying the developed methodology into a nuclear power plant

  14. Human-factors engineering control-room design review/audit report: Byron Generating Station, Commonwealth Edison Company

    International Nuclear Information System (INIS)

    Savage, J.W.

    1983-01-01

    A human factors engineering design review/audit of the Byron Unit 1 control room was performed at the site on November 17 through November 19, 1981. This review was accomplished using the Unit 2 control room appropriately mocked-up to reflect design changes already committed to be incorporated in Unit 1. The report was prepared on the basis of the HFEB's audit of the applicant's Preliminary Design Assessment report and the human factors engineering design review performed at the site. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. The review team was assisted by consultants from BioTechnology, Inc. (Falls Church, Virginia), and from Lawrence Livermore National Laboratory (University of California), Livermore, California

  15. Development of the Human Error Management Criteria and the Job Aptitude Evaluation Criteria for Rail Safety Personnel

    Energy Technology Data Exchange (ETDEWEB)

    Koo, In Soo; Seo, Sang Mun; Park, Geun Ok (and others)

    2008-08-15

    It has been estimated that up to 90% of all workplace accidents have human error as a cause. Human error has been widely recognized as a key factor in almost all the highly publicized accidents, including Daegu subway fire of February 18, 2003 killed 198 people and injured 147. Because most human behavior is 'unintentional', carried out automatically, root causes of human error should be carefully investigated and regulated by a legal authority. The final goal of this study is to set up some regulatory guidance that are supposed to be used by the korean rail organizations related to safety managements and the contents are : - to develop the regulatory guidance for managing human error, - to develop the regulatory guidance for managing qualifications of rail drivers - to develop the regulatory guidance for evaluating the aptitude of the safety-related personnel.

  16. Development of the Human Error Management Criteria and the Job Aptitude Evaluation Criteria for Rail Safety Personnel

    International Nuclear Information System (INIS)

    Koo, In Soo; Seo, Sang Mun; Park, Geun Ok

    2008-08-01

    It has been estimated that up to 90% of all workplace accidents have human error as a cause. Human error has been widely recognized as a key factor in almost all the highly publicized accidents, including Daegu subway fire of February 18, 2003 killed 198 people and injured 147. Because most human behavior is 'unintentional', carried out automatically, root causes of human error should be carefully investigated and regulated by a legal authority. The final goal of this study is to set up some regulatory guidance that are supposed to be used by the korean rail organizations related to safety managements and the contents are : - to develop the regulatory guidance for managing human error, - to develop the regulatory guidance for managing qualifications of rail drivers - to develop the regulatory guidance for evaluating the aptitude of the safety-related personnel

  17. 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)

  18. Estimation of Partial Safety Factors and Target Failure Probability Based on Cost Optimization of Rubble Mound Breakwaters

    DEFF Research Database (Denmark)

    Kim, Seung-Woo; Suh, Kyung-Duck; Burcharth, Hans F.

    2010-01-01

    The breakwaters are designed by considering the cost optimization because a human risk is seldom considered. Most breakwaters, however, were constructed without considering the cost optimization. In this study, the optimum return period, target failure probability and the partial safety factors...

  19. Development of advanced methods and related software for human reliability evaluation within probabilistic safety analyses

    International Nuclear Information System (INIS)

    Kosmowski, K.T.; Mertens, J.; Degen, G.; Reer, B.

    1994-06-01

    Human Reliability Analysis (HRA) is an important part of Probabilistic Safety Analysis (PSA). The first part of this report consists of an overview of types of human behaviour and human error including the effect of significant performance shaping factors on human reliability. Particularly with regard to safety assessments for nuclear power plants a lot of HRA methods have been developed. The most important of these methods are presented and discussed in the report, together with techniques for incorporating HRA into PSA and with models of operator cognitive behaviour. Based on existing HRA methods the concept of a software system is described. For the development of this system the utilization of modern programming tools is proposed; the essential goal is the effective application of HRA methods. A possible integration of computeraided HRA within PSA is discussed. The features of Expert System Technology and examples of applications (PSA, HRA) are presented in four appendices. (orig.) [de

  20. Development of a procedure for qualitative and quantitative evaluation of human factors as a part of probabilistic safety assessments of nuclear power plants. Part B. Technical documentation

    International Nuclear Information System (INIS)

    Richei, A.

    1998-01-01

    As international studies have shown, accidents in plants are increasingly caused by combinations of technical failures and human errors. Therefore careful investigations of man-machine-interactions to determine human reliability are gaining importance worldwide. Regarding nuclear power plants such investigations are usually carried out within the scope of probabilistic safety assessments. A great number of procedures to evaluate human factors has been developed up to now. However, none of them is able to take into account the whole spectrum of requirements - as for instance transferability of date to other plants, analysis of weak points, and evaluation of cognitive tasks - for a complete and reliable probabilistic safety assessment. Based on an advanced model for a man-machine-system, the Human Error Rate Assessment and Optimizing System (HEROS) and a corresponding expert system of the same name are introduced. This expert system enables the quantification of human error probabilities for plant operator actions on the one hand and is also capable of providing quantitative statements regarding the optimization of man-machine-system in terms of human error probability minimization on the other one. Three relevant evaluation levels, i.e. 'Management Structure', 'Working Environment' and 'Man-Machine-Interface', are derived from a model of the man-machine-system. Linguistic variables are assigned to all performance shaping factors at these levels. These variables are used to establish a rule-based expert system. The knowledge bases of this system are represented by rules. Processing of these rules is carried out by means of the fuzzy set theory, after provision of relevant data for a particular personal action to be evaluated. This procedure enables a simple and effective use of ergonomic studies as the relevant database, which is also transferable to other plants with any design. The expert system consist in total of 16 rule bases in which all ascertainable and

  1. Fall Protection Characteristics of Safety Belts and Human Impact Tolerance.

    Science.gov (United States)

    Hino, Yasumichi; Ohdo, Katsutoshi; Takahashi, Hiroki

    2014-08-23

    Many fatal accidents due to falls from heights have occurred at construction sites not only in Japan but also in other countries. This study aims to determine the fall prevention performance of two types of safety belts: a body belt 1) , which has been used for more than 40 yr in the Japanese construction industry as a general type of safety equipment for fall accident prevention, and a full harness 2, 3) , which has been used in many other countries. To determine human tolerance for impact trauma, this study discusses features of safety belts with reference 4-9) to relevant studies in the medical science, automobile crash safety, and aircrew safety. For this purpose, simple drop tests were carried out in a virtual workplace to measure impact load, head acceleration, and posture in the experiments, the Hybrid-III pedestrian model 10) was used as a human dummy. Hybrid-III is typically employed in official automobile crash tests (New Car Assessment Program: NCAP) and is currently recognized as a model that faithfully reproduces dynamic responses. Experimental results shows that safety performance strongly depends on both the variety of safety belts used and the shock absorbers attached onto lanyards. These findings indicate that fall prevention equipment, such as safety belts, lanyards, and shock absorbers, must be improved to reduce impact injuries to the human head and body during falls.

  2. 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

  3. NAS Human Factors Safety Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — This laboratory conducts an integrated program of research on the relationship of factors concerning individuals, work groups, and organizations as employees perform...

  4. Partial Safety Factors and Target Reliability Level in Danish Structural Codes

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Hansen, J. O.; Nielsen, T. A.

    2001-01-01

    The partial safety factors in the newly revised Danish structural codes have been derived using a reliability-based calibration. The calibrated partial safety factors result in the same average reliability level as in the previous codes, but a much more uniform reliability level has been obtained....... The paper describes the code format, the stochastic models and the resulting optimised partial safety factors....

  5. Human factors engineering applications to the cask design activities of the Civilian Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    Lake, W.H.; Peck, M. III

    1993-01-01

    The use of human factors engineering (HFE) in the design and use of spent fuel casks being developed for the Department of Energy's Civilian Radioactive Waste Management Program is addressed. The safety functions of cask systems are presented as background for HFE considerations. Because spent fuel casks are passive safety devices they could be subject to latent system failures due to human error. It is concluded that HFE should focus on operations and verifications tests, but should begin, to the extent possible, at the beginning of cask design. Use of HFE during design could serve to eliminate or preclude opportunity for human error

  6. Factors Contribute to Safety Culture in the Manufacturing Industry in Malaysia

    OpenAIRE

    Ong Choon Hee

    2014-01-01

    The purpose of this paper is to explain the role of safety culture in the manufacturing industry in Malaysia and identify factors contribute to safety culture. It is suggested in this study that leadership support, management commitment and safety management system are important factors that contribute to safety culture. This study also provides theoretical implications to guide future research and offers practical implications to the managers in the development of safety culture. Given that ...

  7. The human factors engineering approach to biomedical informatics projects: state of the art, results, benefits and challenges.

    Science.gov (United States)

    Beuscart-Zéphir, M-C; Elkin, Peter; Pelayo, Sylvia; Beuscart, Regis

    2007-01-01

    The objective of this paper is to define a comprehensible overview of the Human Factors approach to biomedical informatics applications for healthcare. The overview starts with a presentation of the necessity of a proper management of Human factors for Healthcare IT projects to avoid unusable products and unsafe work situations. The first section is dedicated to definitions of the Human Factors Engineering (HFE) main concepts. The second section describes a functional model of an HFE lifecycle adapted for healthcare work situations. The third section provides an overview of existing HF and usability methods for healthcare products and presents a selection of interesting results. The last section discusses the benefits and limitations of the HFE approach. Literature review based on Pubmed and conference proceedings in the field of Medical Informatics coupled with a review of other databases and conference proceedings in the field of Ergonomics focused on papers addressing healthcare work and system design. Usability studies performed on healthcare applications have uncovered unacceptable usability flaws that make the systems error prone, thus endangering the patient safety. Moreover, in many cases, the procurement and the implementation process simply forget about human factors: following only technological considerations, they issue potentially dangerous and always unpleasant work situations. But when properly applied to IT projects, the HFE approach proves efficient when seeking to improve patient safety, users' satisfaction and adoption of the products. We recommend that the HFE methodology should be applied to most informatics and systems development projects, and the usability of the products should be systematically checked before permitting their release and implementation. This requires the development of Centers specialized in Human Factors for Healthcare and Patient safety in each Country/Region.

  8. Aviation Safety: Modeling and Analyzing Complex Interactions between Humans and Automated Systems

    Science.gov (United States)

    Rungta, Neha; Brat, Guillaume; Clancey, William J.; Linde, Charlotte; Raimondi, Franco; Seah, Chin; Shafto, Michael

    2013-01-01

    The on-going transformation from the current US Air Traffic System (ATS) to the Next Generation Air Traffic System (NextGen) will force the introduction of new automated systems and most likely will cause automation to migrate from ground to air. This will yield new function allocations between humans and automation and therefore change the roles and responsibilities in the ATS. Yet, safety in NextGen is required to be at least as good as in the current system. We therefore need techniques to evaluate the safety of the interactions between humans and automation. We think that current human factor studies and simulation-based techniques will fall short in front of the ATS complexity, and that we need to add more automated techniques to simulations, such as model checking, which offers exhaustive coverage of the non-deterministic behaviors in nominal and off-nominal scenarios. In this work, we present a verification approach based both on simulations and on model checking for evaluating the roles and responsibilities of humans and automation. Models are created using Brahms (a multi-agent framework) and we show that the traditional Brahms simulations can be integrated with automated exploration techniques based on model checking, thus offering a complete exploration of the behavioral space of the scenario. Our formal analysis supports the notion of beliefs and probabilities to reason about human behavior. We demonstrate the technique with the Ueberligen accident since it exemplifies authority problems when receiving conflicting advices from human and automated systems.

  9. 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

  10. 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

  11. Assessment of the factors with significant influence on safety culture

    International Nuclear Information System (INIS)

    Farcasiu, M.; Nitoi, M.

    2013-01-01

    In this paper, a qualitative and a quantitative evaluation of the factors with significant impact on safety culture were performed. These techniques were established and applied in accordance with IAEA standards. In order to show the applicability and opportunity of the methodology a specific case study was prepared: safety culture evaluation for INR Pitesti. The qualitative evaluation was performed using specific developed questionnaires. Through analysis of the completed questionnaires was established the development stage of safety culture at INR. The quantitative evaluation was performed using a guide to rate the influence factors. For each factor was identified the influence (negative or positive) and ranking score was estimated using scoring criteria. The results have emphasized safety culture stages. The paper demonstrates the fact that using both quantitative and qualitative assessment techniques, a practical value of the safety culture concept is given. (authors)

  12. [Role of some psycho-physiological factors on driving safety].

    Science.gov (United States)

    Bergomi, M; Vivoli, G; Rovesti, S; Bussetti, P; Ferrari, A; Vivoli, R

    2010-01-01

    Within a research project on the role played by human factors on road accidents, the aim of the present study is to evaluate, in young adults, the relationships between driver behaviour and personality factors as well as to assess the neuroendocrine correlates of psychological and behavioural factors investigated. Another aim is to estimate in what measure the performance levels are affected by demographic, psychological and chronobiological variables. It has been found a positive relation between highway code violations, extroversion trait of personality and Sensation Seeking scores, so confirming that this component of personality can affect risky behaviour. Furthermore the subjects more oriented to morningness chronotype were found to be prone to adopt safe driving behaviour. Regarding the relations of the neuroendocrine parameters and driving behaviour a positive correlation was observed between dopamine levels and frequency of driving violations while a negative relationship was found between adrenaline levels and frequency of driving errors. In conclusion the identification of psycho-physiological variables related to driving risky behaviour might be a useful instrument to design traffic safety programs tailored to high risk subjects.

  13. Analysis of Aviation Safety Reporting System Incident Data Associated with the Technical Challenges of the System-Wide Safety and Assurance Technologies Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2015-01-01

    The Aviation Safety Program (AvSP) System-Wide Safety and Assurance Technologies (SSAT) Project asked the AvSP Systems and Portfolio Analysis Team to identify SSAT-related trends. SSAT had four technical challenges: advance safety assurance to enable deployment of NextGen systems; automated discovery of precursors to aviation safety incidents; increasing safety of human-automation interaction by incorporating human performance, and prognostic algorithm design for safety assurance. This report reviews incident data from the NASA Aviation Safety Reporting System (ASRS) for system-component-failure- or-malfunction- (SCFM-) related and human-factor-related incidents for commercial or cargo air carriers (Part 121), commuter airlines (Part 135), and general aviation (Part 91). The data was analyzed by Federal Aviation Regulations (FAR) part, phase of flight, SCFM category, human factor category, and a variety of anomalies and results. There were 38 894 SCFM-related incidents and 83 478 human-factorrelated incidents analyzed between January 1993 and April 2011.

  14. 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)

  15. Immunogenicity and safety of human papillomavirus (HPV) vaccination in Asian populations from six countries : a meta-analysis

    NARCIS (Netherlands)

    Setiawan, Didik; Luttjeboer, Jos; Pouwels, Koen B.; Wilschut, Jan C.; Postma, Maarten J.

    Cervical cancer is a serious public-health problem in Asian countries. Since human papillomavirus (HPV) infection is the main risk factor for cervical cancer, HPV vaccination is considered a promising strategy to prevent cervical cancer. However, comprehensive immunogenicity and safety information

  16. Structural Design Requirements and Factors of Safety for Spaceflight Hardware: For Human Spaceflight. Revision A

    Science.gov (United States)

    Bernstein, Karen S.; Kujala, Rod; Fogt, Vince; Romine, Paul

    2011-01-01

    This document establishes the structural requirements for human-rated spaceflight hardware including launch vehicles, spacecraft and payloads. These requirements are applicable to Government Furnished Equipment activities as well as all related contractor, subcontractor and commercial efforts. These requirements are not imposed on systems other than human-rated spacecraft, such as ground test articles, but may be tailored for use in specific cases where it is prudent to do so such as for personnel safety or when assets are at risk. The requirements in this document are focused on design rather than verification. Implementation of the requirements is expected to be described in a Structural Verification Plan (SVP), which should describe the verification of each structural item for the applicable requirements. The SVP may also document unique verifications that meet or exceed these requirements with NASA Technical Authority approval.

  17. On the electrical safety of dielectric elastomer actuators in proximity to the human body

    Science.gov (United States)

    Pourazadi, S.; Shagerdmootaab, A.; Chan, H.; Moallem, M.; Menon, C.

    2017-11-01

    Novel devices based on the use of dielectric elastomer actuators (DEA) have been proposed for a large variety of different applications. In many of these applications, DEAs are envisioned to be in direct or close proximity to the human body. Since DEAs usually require high voltage for their actuation, the safety of individuals operating or using these devices should be ensured. In this paper, safety standards based on safe limits for electrical discharge are investigated. Flat and cylindrical DEA configurations, which are generally considered as the building blocks for the design of DEA-based systems, are investigated in detail. Relevant elements and factors that affect the electrical discharge of DEA devices are analyzed and guidelines to design DEA-based devices that are not of harm for humans are provided. The performed analyses are experimentally validated using flat DEA samples. The safety requirements that should be considered when wrapping DEAs around the body (specifically the legs) are also briefly investigated to provide a practical example of interest for the biomedical community.

  18. Critical human-factors issues in nuclear-power regulation and a recommended comprehensive human-factors long-range plan. Critical discussion of human factors areas of concern

    International Nuclear Information System (INIS)

    Hopkins, C.O.; Snyder, H.L.; Price, H.E.; Hornick, R.J.; Mackie, R.R.; Smillie, R.J.; Sugarman, R.C.

    1982-08-01

    This comprehensive long-range human factors plan for nuclear reactor regulation was developed by a Study Group of the Human Factors Society, Inc. This Study Group was selected by the Executive Council of the Society to provide a balanced, experienced human factors perspective to the applications of human factors scientific and engineering knowledge to nuclear power generation. The report is presented in three volumes. Volume 1 contains an Executive Summary of the 18-month effort and its conclusions. Volume 2 summarizes all known nuclear-related human factors activities, evaluates these activities wherever adequate information is available, and describes the recommended long-range (10-year) plan for human factors in regulation. Volume 3 elaborates upon each of the human factors issues and areas of recommended human factors involvement contained in the plan, and discusses the logic that led to the recommendations

  19. 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

  20. Human failure and industrial safety. The human factor in technology and organisation

    International Nuclear Information System (INIS)

    Semmer, N.

    1999-01-01

    Human failure is not the opposite of successful human action gut follows the same principles. The manner in which humans acquire and process information is influenced by cognitive, social and motivational aspects. Further, human failure generally means a failure of the whole system man/technology/organisation. If serious consequences are to be avoided, the logic of failures must be analyzed in the context of this system, and human staff should be trained in managing failures and not just avoiding them [de

  1. Advances in human factors and ergonomics in healthcare

    CERN Document Server

    Duffy, Vincent G

    2010-01-01

    Based on recent research, this book discusses how to improve quality, safety, efficiency, and effectiveness in patient care through the application of human factors and ergonomics principles. It provides guidance for those involved with the design and application of systems and devices for effective and safe healthcare delivery from both a patient and staff perspective. Its huge range of chapters covers everything from the proper design of bed rails to the most efficient design of operating rooms, from the development of quality products to the rating of staff patient interaction. It considers

  2. Overview of Human Factors and Habitability at NASA

    Science.gov (United States)

    Connolly, Janis; Arch, M.; Kaiser, Mary

    2009-01-01

    This slide presentation reviews the ongoing work on human factors and habitability in the development of the Constellation Program. The focus of the work is on how equipment, spacecraft design, tools, procedures and nutrition be used to improve the health, safety and efficiency of the crewmembers. There are slides showing the components of the Constellation Program, and the conceptual designs of the Orion Crew module, the lunar lander, (i.e., Altair) the microgravity EVA suit, and the lunar surface EVA suit, the lunar rover, and the lunar surface system infrastructure.

  3. Representation of human behaviour in probabilistic safety analysis

    International Nuclear Information System (INIS)

    Whittingham, R.B.

    1991-01-01

    This paper provides an overview of the representation of human behaviour in probabilistic safety assessment. Human performance problems which may result in errors leading to accidents are considered in terms of methods of identification using task analysis, screening analysis of critical errors, representation and quantification of human errors in fault trees and event trees and error reduction measures. (author) figs., tabs., 43 refs

  4. Design of Vertical Wall Caisson Breakwaters using Partial Safety Factors

    DEFF Research Database (Denmark)

    Burcharth, H. F.; Sørensen, John Dalsgaard

    1999-01-01

    The paper presents a new system for implementation of target reliability in caisson breakwater designs by means of partial safety factors. The development of the system is explained, and tables of partial safety factors are presented for important overall stability failure modes related to caisson...

  5. IMPROVING CONTROL ROOM DESIGN AND OPERATIONS BASED ON HUMAN FACTORS ANALYSES OR HOW MUCH HUMAN FACTORS UPGRADE IS ENOUGH ?

    Energy Technology Data Exchange (ETDEWEB)

    HIGGINS,J.C.; OHARA,J.M.; ALMEIDA,P.

    2002-09-19

    THE JOSE CABRERA NUCLEAR POWER PLANT IS A ONE LOOP WESTINGHOUSE PRESSURIZED WATER REACTOR. IN THE CONTROL ROOM, THE DISPLAYS AND CONTROLS USED BY OPERATORS FOR THE EMERGENCY OPERATING PROCEDURES ARE DISTRIBUTED ON FRONT AND BACK PANELS. THIS CONFIGURATION CONTRIBUTED TO RISK IN THE PROBABILISTIC SAFETY ASSESSMENT WHERE IMPORTANT OPERATOR ACTIONS ARE REQUIRED. THIS STUDY WAS UNDERTAKEN TO EVALUATE THE IMPACT OF THE DESIGN ON CREW PERFORMANCE AND PLANT SAFETY AND TO DEVELOP DESIGN IMPROVEMENTS.FIVE POTENTIAL EFFECTS WERE IDENTIFIED. THEN NUREG-0711 [1], PROGRAMMATIC, HUMAN FACTORS, ANALYSES WERE CONDUCTED TO SYSTEMATICALLY EVALUATE THE CR-LA YOUT TO DETERMINE IF THERE WAS EVIDENCE OF THE POTENTIAL EFFECTS. THESE ANALYSES INCLUDED OPERATING EXPERIENCE REVIEW, PSA REVIEW, TASK ANALYSES, AND WALKTHROUGH SIMULATIONS. BASED ON THE RESULTS OF THESE ANALYSES, A VARIETY OF CONTROL ROOM MODIFICATIONS WERE IDENTIFIED. FROM THE ALTERNATIVES, A SELECTION WAS MADE THAT PROVIDED A REASONABLEBALANCE BE TWEEN PERFORMANCE, RISK AND ECONOMICS, AND MODIFICATIONS WERE MADE TO THE PLANT.

  6. EFFECTIVENESS AND SAFETY OF RECOMBINANT HUMAN GRANULOCYTIC COLONY-STIMULATING FACTOR IN TREATMENT OF GRANULOCYTOPENIA DEVELOPED DURING IMMUNOSUPPRESSIVE THERAPY IN PATIENTS WITH JUVENILE RHEUMATOID ARTHRITIS

    Directory of Open Access Journals (Sweden)

    E.I. Alexeeva

    2010-01-01

    Full Text Available Treatment of patients with severe clinical course of juvenile rheumatoid arthritis (JRA is difficult problem. During the last years genetically engineered biological drugs are used equally with traditional immunosuppressive agents in treatment of severe forms of juvenile arthritis. High effectiveness of these drugs can be accompanied with development of unfavorable effects, for example, febrile neutropenia. The article presents results of a study of effectiveness and safety of recombinant human granulocytic colony-stimulating factor — filgrastim (Leucostim — in treatment of granulocytopenia developed during immunosuppressive therapy in 16 patients with JRA. It was shown that administration of filgrastim arrests leucopenia in 100% of patients and granulocytopenia — in 93% of patients in 24 hours after first injection. High effectiveness of drug was combined with good tolerability and safety.Key words: children, treatment, granulocytopenia, filgrastim, juvenile rheumatoid arthritis.(Voprosy sovremennoi pediatrii — Current Pediatrics. – 2010;9(4:94-100

  7. Analysis of 'human element related trip case book in Korean NPPs' using organizational factors

    International Nuclear Information System (INIS)

    Kim, S. Y.; Kim, Y. I.; Lee, Y. S.; Kim, C. S.; Jung, C. H.; Jung, W. D.

    2002-01-01

    There have been no studies appling organizational factors to data analysis in Korean NPPs. In this paper, data in 'human element related trip case book in Korean NPPs' are analyzed and categorized by the 20 organizational factors of NRC-BNL according to the cause of reactor trip. These inform us how organizational factors affected on the safety of Korean NPPs. Consequently important organizational factor are identified through which it is known that NPP organization would have a tendency

  8. Design for human factors (DfHF): a grounded theory for integrating human factors into production design processes.

    Science.gov (United States)

    Village, Judy; Searcy, Cory; Salustri, Filipo; Patrick Neumann, W

    2015-01-01

    The 'design for human factors' grounded theory explains 'how' human factors (HF) went from a reactive, after-injury programme in safety, to being proactively integrated into each step of the production design process. In this longitudinal case study collaboration with engineers and HF Specialists in a large electronics manufacturer, qualitative data (e.g. meetings, interviews, observations and reflections) were analysed using a grounded theory methodology. The central tenet in the theory is that when HF Specialists acclimated to the engineering process, language and tools, and strategically aligned HF to the design and business goals of the organisation, HF became a means to improve business performance. This led to engineers 'pulling' HF Specialists onto their team. HF targets were adopted into engineering tools to communicate HF concerns quantitatively, drive continuous improvement, visibly demonstrate change and lead to benchmarking. Senior management held engineers accountable for HF as a key performance indicator, thus integrating HF into the production design process. Practitioner Summary: Research and practice lack explanations about how HF can be integrated early in design of production systems. This three-year case study and the theory derived demonstrate how ergonomists changed their focus to align with design and business goals to integrate HF into the design process.

  9. A review of human factors principles for the design and implementation of medication safety alerts in clinical information systems.

    Science.gov (United States)

    Phansalkar, Shobha; Edworthy, Judy; Hellier, Elizabeth; Seger, Diane L; Schedlbauer, Angela; Avery, Anthony J; Bates, David W

    2010-01-01

    The objective of this review is to describe the implementation of human factors principles for the design of alerts in clinical information systems. First, we conduct a review of alarm systems to identify human factors principles that are employed in the design and implementation of alerts. Second, we review the medical informatics literature to provide examples of the implementation of human factors principles in current clinical information systems using alerts to provide medication decision support. Last, we suggest actionable recommendations for delivering effective clinical decision support using alerts. A review of studies from the medical informatics literature suggests that many basic human factors principles are not followed, possibly contributing to the lack of acceptance of alerts in clinical information systems. We evaluate the limitations of current alerting philosophies and provide recommendations for improving acceptance of alerts by incorporating human factors principles in their design.

  10. Safety testing of monoclonal antibodies in non-human primates: Case studies highlighting their impact on human risk assessment.

    Science.gov (United States)

    Brennan, Frank R; Cavagnaro, Joy; McKeever, Kathleen; Ryan, Patricia C; Schutten, Melissa M; Vahle, John; Weinbauer, Gerhard F; Marrer-Berger, Estelle; Black, Lauren E

    2018-01-01

    Monoclonal antibodies (mAbs) are improving the quality of life for patients suffering from serious diseases due to their high specificity for their target and low potential for off-target toxicity. The toxicity of mAbs is primarily driven by their pharmacological activity, and therefore safety testing of these drugs prior to clinical testing is performed in species in which the mAb binds and engages the target to a similar extent to that anticipated in humans. For highly human-specific mAbs, this testing often requires the use of non-human primates (NHPs) as relevant species. It has been argued that the value of these NHP studies is limited because most of the adverse events can be predicted from the knowledge of the target, data from transgenic rodents or target-deficient humans, and other sources. However, many of the mAbs currently in development target novel pathways and may comprise novel scaffolds with multi-functional domains; hence, the pharmacological effects and potential safety risks are less predictable. Here, we present a total of 18 case studies, including some of these novel mAbs, with the aim of interrogating the value of NHP safety studies in human risk assessment. These studies have identified mAb candidate molecules and pharmacological pathways with severe safety risks, leading to candidate or target program termination, as well as highlighting that some pathways with theoretical safety concerns are amenable to safe modulation by mAbs. NHP studies have also informed the rational design of safer drug candidates suitable for human testing and informed human clinical trial design (route, dose and regimen, patient inclusion and exclusion criteria and safety monitoring), further protecting the safety of clinical trial participants.

  11. A study on the critical factors of human error in civil aviation: An early warning management perspective in Bangladesh

    Directory of Open Access Journals (Sweden)

    Md. Salah Uddin Rajib

    2015-01-01

    Full Text Available The safety of civil aviation will be more secured if the errors in all the facets can be reduced. Like the other industrial sectors, human resource is one of the most complex and sensitive resources for the civil aviation. The error of human resources can cause fatal disasters. In these days, a good volume of researches have been conducted on the disaster of civil aviation. The researchers have identified the causes of the civil aviation disasters from various perspectives. They identified the areas where more concern is needed to reduce the disastrous impacts. This paper aims to find out the critical factors of human error in civil aviation in a developing country (Bangladesh as it is accepted that human error is one of main causes of civil aviation disasters. The paper reviews the previous research to find out the critical factors conceptually. Fuzzy analytical hierarchy process (FAHP has been used to find out the critical factors systematically. Analyses indicate that the concentration on precondition for unsafe acts (including sub-factors is required to ensure the aviation safety.

  12. Human factors in network security

    OpenAIRE

    Jones, Francis B.

    1991-01-01

    Human factors, such as ethics and education, are important factors in network information security. This thesis determines which human factors have significant influence on network security. Those factors are examined in relation to current security devices and procedures. Methods are introduced to evaluate security effectiveness by incorporating the appropriate human factors into network security controls

  13. INPO Perspectives and Activities to Enhance Supplier Human Performance and Safety Culture

    International Nuclear Information System (INIS)

    Duncan, R. J.

    2016-01-01

    Within their own organizations, utilities have made significant improvements in human performance and safety culture, supported by a strong community of practice through INPO and WANO. In recent years, utilities have been making increasing use of suppliers for design, construction, inspection and maintenance services in support of their NPPs. Many of these suppliers do not have the benefit of being members of a community of practice when it comes to human performance and safety culture. To help the supplier community make improvements similar to what the utilities have achieved, INPO has recently expanded its Supplier Participant program to address the issue of human performance and safety culture in the supplier community. The intent of this paper will be to share the INPO’s perspectives and activities in helping suppliers of services and products to NPPs enhance their human performance and safety culture. (author)

  14. 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)

  15. 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)

  16. Twenty-third water reactor safety information meeting: Volume 2, Human factors research; Advanced I and C hardware and software; Severe accident research; Probabilistic risk assessment topics; Individual plant examination: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1996-03-01

    This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 2, present topics in human factors research, advanced instrumentation and control hardware and software, severe accident research, probabilistic risk assessment, and individual plant examination. Individual papers have been cataloged separately.

  17. A human error taxonomy for analysing healthcare incident reports: assessing reporting culture and its effects on safety perfomance

    DEFF Research Database (Denmark)

    Itoh, Kenji; Omata, N.; Andersen, Henning Boje

    2009-01-01

    The present paper reports on a human error taxonomy system developed for healthcare risk management and on its application to evaluating safety performance and reporting culture. The taxonomy comprises dimensions for classifying errors, for performance-shaping factors, and for the maturity...

  18. The Tchernobyl enigma or: the human factors in severe accidents

    International Nuclear Information System (INIS)

    Llory, M.

    1988-01-01

    Using the analysis of many documents published after the Tchernobyl accident, we attempt to distinguish the main human factors aspects in severe accidents that come out, and the causes the most frequently quoted to ''explain'' it. But the Tchernobyl accident keeps its ''enigmatic'' feature, like any other accident. The need to make a deeper investigation concerning safety leads to look for various research paths that go beyond the usual normative positions, based on a too much mechanistic model of man. It is to the functioning of groups in work situations that we suggest to devote part of the research and thinking effort. We attempt to show briefly how two theories, the theory of ''groupthink'' and the theory of ''trade defensive ideologies'', can throw a light on the problem of human factors in nuclear power plants [fr

  19. Safety culture' is integrating 'human' into risk assessment

    International Nuclear Information System (INIS)

    Sugimoto, Taiji

    2014-01-01

    Significance of Fukushima nuclear power accident requested reconsideration of safety standards, of which we had usually no doubt. Risk assessment standard (JIS B 9702), Which was used for repetition of database preparation and cumulative assessment, defined allowable risk and residual risk. However, work site and immediate assessment was indispensable beside such assessment so as to ensure safety. Risk of casualties was absolutely not acceptable in principle and judgments to approve allowable risk needed accountability, which was reminded by safety culture proposed by IAEA and also identified by investigation of organizational cause of Columbia accident. Actor of safety culture would be organization and individual, and mainly individual. Realization of safety culture was conducted by personnel having moral consciousness and firm sense of mission in the course of jobs and working daily with sweat pouring. Safety engineering/technology should have framework integrating human as such totality. (T. Tanaka)

  20. Reliability Analysis and Calibration of Partial Safety Factors for Redundant Structures

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard

    1998-01-01

    Redundancy is important to include in the design and analysis of structural systems. In most codes of practice redundancy is not directly taken into account. In the paper various definitions of a deterministic and reliability based redundancy measure are reviewed. It is described how reundancy can...... be included in the safety system and how partial safety factors can be calibrated. An example is presented illustrating how redundancy is taken into account in the safety system in e.g. the Danish codes. The example shows how partial safety factors can be calibrated to comply with the safety level...

  1. Applications of human factors engineering to LNG release prevention and control

    Energy Technology Data Exchange (ETDEWEB)

    Shikiar, R.; Rankin, W.L.; Rideout, T.B.

    1982-06-01

    The results of an investigation of human factors engineering and human reliability applications to LNG release prevention and control are reported. The report includes a discussion of possible human error contributions to previous LNG accidents and incidents, and a discussion of generic HF considerations for peakshaving plants. More specific recommendations for improving HF practices at peakshaving plants are offered based on visits to six facilities. The HF aspects of the recently promulgated DOT regulations are reviewed, and recommendations are made concerning how these regulations can be implemented utilizing standard HF practices. Finally, the integration of HF considerations into overall system safety is illustrated by a presentation of human error probabilities applicable to LNG operations and by an expanded fault tree analysis which explicitly recognizes man-machine interfaces.

  2. Thermal reactor safety

    International Nuclear Information System (INIS)

    1980-06-01

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport

  3. Thermal reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  4. Understanding safety and production risks in rail engineering planning and protection.

    Science.gov (United States)

    Wilson, John R; Ryan, Brendan; Schock, Alex; Ferreira, Pedro; Smith, Stuart; Pitsopoulos, Julia

    2009-07-01

    Much of the published human factors work on risk is to do with safety and within this is concerned with prediction and analysis of human error and with human reliability assessment. Less has been published on human factors contributions to understanding and managing project, business, engineering and other forms of risk and still less jointly assessing risk to do with broad issues of 'safety' and broad issues of 'production' or 'performance'. This paper contains a general commentary on human factors and assessment of risk of various kinds, in the context of the aims of ergonomics and concerns about being too risk averse. The paper then describes a specific project, in rail engineering, where the notion of a human factors case has been employed to analyse engineering functions and related human factors issues. A human factors issues register for potential system disturbances has been developed, prior to a human factors risk assessment, which jointly covers safety and production (engineering delivery) concerns. The paper concludes with a commentary on the potential relevance of a resilience engineering perspective to understanding rail engineering systems risk. Design, planning and management of complex systems will increasingly have to address the issue of making trade-offs between safety and production, and ergonomics should be central to this. The paper addresses the relevant issues and does so in an under-published domain - rail systems engineering work.

  5. Establishing a culture for patient safety - the role of education.

    Science.gov (United States)

    Milligan, Frank J

    2007-02-01

    This paper argues that the process of making significant moves towards a patient safety culture requires changes in healthcare education. Improvements in patient safety are a shared international priority as too many errors and other forms of unnecessary harm are currently occurring in the process of caring for and treating patients. A description of the patient safety agenda is given followed by a brief analysis of human factors theory and its use in other safety critical industries, most notably aviation. The all too common problem of drug administration errors is used to illustrate the relevance of human factors theory to healthcare education with specific mention made of the Human Factors Analysis and Classification System (HFACS).

  6. Analysis of the safety and pharmacodynamics of human fibrinogen concentrate in animals

    International Nuclear Information System (INIS)

    Beyerle, Andrea; Nolte, Marc W.; Solomon, Cristina; Herzog, Eva; Dickneite, Gerhard

    2014-01-01

    Fibrinogen, a soluble 340 kDa plasma glycoprotein, is critical in achieving and maintaining hemostasis. Reduced fibrinogen levels are associated with an increased risk of bleeding and recent research has investigated the efficacy of fibrinogen concentrate for controlling perioperative bleeding. European guidelines on the management of perioperative bleeding recommend the use of fibrinogen concentrate if significant bleeding is accompanied by plasma fibrinogen levels less than 1.5–2.0 g/l. Plasma-derived human fibrinogen concentrate has been available for therapeutic use since 1956. The overall aim of the comprehensive series of non-clinical investigations presented was to evaluate i) the pharmacodynamic and pharmacokinetic characteristics and ii) the safety and tolerability profile of human fibrinogen concentrate Haemocomplettan P® (RiaSTAP®). Pharmacodynamic characteristics were assessed in rabbits, pharmacokinetic parameters were determined in rabbits and rats and a safety pharmacology study was performed in beagle dogs. Additional toxicology tests included: single-dose toxicity tests in mice and rats; local tolerance tests in rabbits; and neoantigenicity tests in rabbits and guinea pigs following the introduction of pasteurization in the manufacturing process. Human fibrinogen concentrate was shown to be pharmacodynamically active in rabbits and dogs and well tolerated, with no adverse events and no influence on circulation, respiration or hematological parameters in rabbits, mice, rats and dogs. In these non-clinical investigations, human fibrinogen concentrate showed a good safety profile. This data adds to the safety information available to date, strengthening the current body of knowledge regarding this hemostatic agent. - Highlights: • A comprehensive series of pre-clinical investigations of human fibrinogen concentrate. • Human fibrinogen concentrate was shown to be pharmacodynamically active. • Human fibrinogen concentrate was well tolerated

  7. Analysis of the safety and pharmacodynamics of human fibrinogen concentrate in animals

    Energy Technology Data Exchange (ETDEWEB)

    Beyerle, Andrea, E-mail: andrea.beyerle@cslbehring.com [CSL Behring GmbH, Preclinical Research and Development, Marburg (Germany); Nolte, Marc W. [CSL Behring GmbH, Preclinical Research and Development, Marburg (Germany); Solomon, Cristina [CSL Behring GmbH, Medical Affairs, Marburg (Germany); Department of Anaesthesiology, Perioperative Medicine and General Intensive Care, Paracelsus Medical University, Salzburg (Austria); Herzog, Eva; Dickneite, Gerhard [CSL Behring GmbH, Preclinical Research and Development, Marburg (Germany)

    2014-10-01

    Fibrinogen, a soluble 340 kDa plasma glycoprotein, is critical in achieving and maintaining hemostasis. Reduced fibrinogen levels are associated with an increased risk of bleeding and recent research has investigated the efficacy of fibrinogen concentrate for controlling perioperative bleeding. European guidelines on the management of perioperative bleeding recommend the use of fibrinogen concentrate if significant bleeding is accompanied by plasma fibrinogen levels less than 1.5–2.0 g/l. Plasma-derived human fibrinogen concentrate has been available for therapeutic use since 1956. The overall aim of the comprehensive series of non-clinical investigations presented was to evaluate i) the pharmacodynamic and pharmacokinetic characteristics and ii) the safety and tolerability profile of human fibrinogen concentrate Haemocomplettan P® (RiaSTAP®). Pharmacodynamic characteristics were assessed in rabbits, pharmacokinetic parameters were determined in rabbits and rats and a safety pharmacology study was performed in beagle dogs. Additional toxicology tests included: single-dose toxicity tests in mice and rats; local tolerance tests in rabbits; and neoantigenicity tests in rabbits and guinea pigs following the introduction of pasteurization in the manufacturing process. Human fibrinogen concentrate was shown to be pharmacodynamically active in rabbits and dogs and well tolerated, with no adverse events and no influence on circulation, respiration or hematological parameters in rabbits, mice, rats and dogs. In these non-clinical investigations, human fibrinogen concentrate showed a good safety profile. This data adds to the safety information available to date, strengthening the current body of knowledge regarding this hemostatic agent. - Highlights: • A comprehensive series of pre-clinical investigations of human fibrinogen concentrate. • Human fibrinogen concentrate was shown to be pharmacodynamically active. • Human fibrinogen concentrate was well tolerated

  8. Study of human factors, and its basic aspects focusing the IEA-R1 research reactor operators, aiming at the prevention of accidents caused by human failures

    International Nuclear Information System (INIS)

    Martins, Maria da Penha Sanches

    2008-01-01

    This work presents a study of human factors and possible human failure reasons that can cause incidents, accidents and workers exposition, associated to risks intrinsic to the profession. The objective is to contribute with the operators of IEA-R1 reactor located at IPEN CNEN/S P. Accidents in the technological field, including the nuclear, have shown that the causes are much more connected to human failure than to system and equipment failures, what has led the regulatory bodies to consider studies on human failure. The research proposed in this work is quantitative/qualitative and also descriptive. Two questionnaires were used to collect data. The first of them was elaborated from the safety culture attributes which are described by the International Atomic Energy Agency - IAEA. The second considered individual and situational factors composing categories that could affect people in the work area. A carefully selected transcription of the theoretical basis according to the study of human factors was used. The methodology demonstrated a good reliability degree. Results lead to mediate factors which need direct actions concerning the needs of the group and of the individual. This research shows that it is necessary to have a really effective unit of planning and organization, not only to the physical and psychological health issues but also to the safety in the work. (author)

  9. Measuring Safety Culture on Ships Using Safety Climate: A Study among Indian Officers

    Directory of Open Access Journals (Sweden)

    Yogendra Bhattacharya

    2015-12-01

    Full Text Available Workplace safety continues to be an area of concern in the maritime industry due to the international nature of the operations. The effectiveness of extensive legislation to manage shipboard safety remains in doubt. The focus must therefore shift towards the human element - seafarers and their perceptions of safety. The study aims to understand the alignment that exists between safety culture and safety climate on board ships as perceived by seafarers. The underlying factors of safety climate were identified using factor analysis which isolated seven factors - Support on Safety, Organizational Support, Resource Availability, Work Environment, Job Demands, ‘Just’ Culture, and Safety Compliance. The perception of safety level of seafarers was found to be low indicating the existence of misalignments between safety culture values and the actual safety climate. The study also reveals that the safety perceptions of officers employed directly by ship owners and those by managers do not differ significantly, nor do they differ between senior and junior officers. A shift in perspective towards how seafarers themselves feel towards safety might provide more effective solutions – instead of relying on regulations - and indeed aid in reducing incidents on board. This paper details practical suggestions on how to identify the factors that contribute towards a better safety climate on board ships.

  10. Incident factor as a learning aspect to enhance safety culture in the experimental fuel element installation of PTBN - BATAN

    International Nuclear Information System (INIS)

    Heri Hardiyanti; Agus Sartono; Bambang Herutomo; AS Latief

    2013-01-01

    The safety of a nuclear facility depends not only on the fulfillment of all technical requirements, but also on the role of non-technical aspects. The primary causation of incidents or accidents in a nuclear facility is human error which is non-technical. Therefore, in order to enhance safety, efforts from the technical aspects are as important as efforts to deal with the human factor which can be done through the application of safety culture in the facility. Incidents that took place in the Experimental Fuel Element Installation (EFEI) of PTBN - BATAN from 2011 to 2012 were caused by aging instruments and human error. In order to prevent accidents and to enhance safety, non-technical efforts that were done in the EFEI were, interalia, the obligations on all personnel to attend the pre-lab briefing, to prepare a work proposal, to compose a HIRADC (hazard identification, risk assessment, and determining control) document, to utilize self protection devices, to perform a routine maintenance, and to practice safe behavior. All personnel were involved in all those efforts. Safety is the first priority and can always be improved in the facility. A strong commitment of and cooperation between the top management and the staff are needed. (author)

  11. A review of human factors principles for the design and implementation of medication safety alerts in clinical information systems

    OpenAIRE

    Phansalkar, Shobha; Edworthy, Judy; Hellier, Elizabeth; Seger, Diane L; Schedlbauer, Angela; Avery, Anthony J; Bates, David W

    2010-01-01

    The objective of this review is to describe the implementation of human factors principles for the design of alerts in clinical information systems. First, we conduct a review of alarm systems to identify human factors principles that are employed in the design and implementation of alerts. Second, we review the medical informatics literature to provide examples of the implementation of human factors principles in current clinical information systems using alerts to provide medication decisio...

  12. Human factors guides

    International Nuclear Information System (INIS)

    Penington, J.

    1995-10-01

    This document presents human factors guides, which have been developed in order to provide licensees of the AECB with advice as to how to address human factors issues within the design and assessment process. This documents presents the results of a three part study undertaken to develop three guides which are enclosed in this document as Parts B, C and D. As part of the study human factors standards, guidelines, handbooks and other texts were researched, to define those which would be most useful to the users of the guides and for the production of the guides themselves. Detailed specifications were then produced to outline the proposed contents and format of the three guides. (author). 100 refs., 3 tabs., 11 figs

  13. Human factors guides

    Energy Technology Data Exchange (ETDEWEB)

    Penington, J [PHF Services Inc., (Canada)

    1995-10-01

    This document presents human factors guides, which have been developed in order to provide licensees of the AECB with advice as to how to address human factors issues within the design and assessment process. This documents presents the results of a three part study undertaken to develop three guides which are enclosed in this document as Parts B, C and D. As part of the study human factors standards, guidelines, handbooks and other texts were researched, to define those which would be most useful to the users of the guides and for the production of the guides themselves. Detailed specifications were then produced to outline the proposed contents and format of the three guides. (author). 100 refs., 3 tabs., 11 figs.

  14. 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.)

  15. Regulatory Oversight of Safety Culture in Finland: A Systemic Approach to Safety

    International Nuclear Information System (INIS)

    Oedewald, P.; Väisäsvaara, J.

    2016-01-01

    In Finland the Radiation and Nuclear Safety Authority STUK specifies detailed regulatory requirements for good safety culture. Both the requirements and the practical safety culture oversight activities reflect a systemic approach to safety: the interconnections between the technical, human and organizational factors receive special attention. The conference paper aims to show how the oversight of safety culture can be integrated into everyday oversight activities. The paper also emphasises that the scope of the safety culture oversight is not specific safety culture activities of the licencees, but rather the overall functioning of the licence holder or the new build project organization from safety point of view. The regulatory approach towards human and organizational factors and safety culture has evolved throughout the years of nuclear energy production in Finland. Especially the recent new build projects have highlighted the need to systematically pay attention to the non-technical aspects of safety as it has become obvious how the HOF issues can affect the design processes and quality of construction work. Current regulatory guides include a set of safety culture related requirements. The requirements are binding to the licence holders and they set both generic and specific demands on the licencee to understand, monitor and to develop safety culture of their own organization but also that of their supplier network. The requirements set for the licence holders has facilitated the need to develop the regulator’s safety culture oversight practices towards a proactive and systemic approach.

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

    International Nuclear Information System (INIS)

    Ivanov, P.

    2002-01-01

    Full text: A special role in establishing the physical protection system (at all levels) pertains to the human factor. It is necessary to specify a place of this matter within the overall security system. 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 rote of the human factor can be considered to be significant. The operative situation while being formed during the physical protection ensuring, first of all, is affected by the following factors: political, social and economic, spiritual wealth and cultural factors and etc. In addition, a new problem suddenly appeared related to the safety and security of the energy complex, that is: uncontrolled processes such as: non-payment, debts on salary for several month period; all this factors effect negatively the level of safety and security. In this clear, that in such a difficult situation the role of an individual is increasing. Ignorance of the above factors or their non-objective (incomplete, partial ignorance) accounting (consideration) finally can lead to the negative and irremediable consequences. Thus, the content and the extent of the security of a society, in general, and every person, in particular, directly depend on the functioning of all society's structure, and, first of all, on the economic, social, political and legal structures. As a result, the physical protection system acquires a complex or comprehensive structure and I shall describe its specifics in the paper. (author)

  17. Enhancing Road Safety Behaviour Using a Psychological and Spiritual Approaches

    Directory of Open Access Journals (Sweden)

    Ghous Mohd Tarmizi

    2017-01-01

    Full Text Available Main causes of accident is due to driver itself that is influenced by their bad attitude while driving. Human attitude is closely related to the human psychology. Apart from that, spiritual aspect also influence human attitude. Hence, this study carried out to improve driver safety using a new approach through psychology and spiritual factors. Objectives of this study are to identify then analyze factors of psychological and spiritual that contribute towards safety driving. A self-administered questionnaire were distributed among 256 respondents from various type of background. An analysis descriptive statistics show demographic and experience of respondents. Chi-square analysis showed only education level and traffic summon are significant to safety driving. Furthermore, correlation analysis shows psychological factors has strong linear relationship on attitude of drivers towards safety driving while spiritual factor, the perception of the spiritual and practices, both have a strong relationship to safety driving. Regression analysis demonstrates boths psychological and spiritual factors have strong evidence and significant relationship with safety driving. Thus, it can be identified that spiritual psychological factors encourage drivers to drive more safely and reduce road accidents. Therefore, this study propose useful guidelines to related agencies in order to enhance safety among drivers to be able drive safely on the road.

  18. A Risk Analysis Methodology to Address Human and Organizational Factors in Offshore Drilling Safety: With an Emphasis on Negative Pressure Test

    Science.gov (United States)

    Tabibzadeh, Maryam

    According to the final Presidential National Commission report on the BP Deepwater Horizon (DWH) blowout, there is need to "integrate more sophisticated risk assessment and risk management practices" in the oil industry. Reviewing the literature of the offshore drilling industry indicates that most of the developed risk analysis methodologies do not fully and more importantly, systematically address the contribution of Human and Organizational Factors (HOFs) in accident causation. This is while results of a comprehensive study, from 1988 to 2005, of more than 600 well-documented major failures in offshore structures show that approximately 80% of those failures were due to HOFs. In addition, lack of safety culture, as an issue related to HOFs, have been identified as a common contributing cause of many accidents in this industry. This dissertation introduces an integrated risk analysis methodology to systematically assess the critical role of human and organizational factors in offshore drilling safety. The proposed methodology in this research focuses on a specific procedure called Negative Pressure Test (NPT), as the primary method to ascertain well integrity during offshore drilling, and analyzes the contributing causes of misinterpreting such a critical test. In addition, the case study of the BP Deepwater Horizon accident and their conducted NPT is discussed. The risk analysis methodology in this dissertation consists of three different approaches and their integration constitutes the big picture of my whole methodology. The first approach is the comparative analysis of a "standard" NPT, which is proposed by the author, with the test conducted by the DWH crew. This analysis contributes to identifying the involved discrepancies between the two test procedures. The second approach is a conceptual risk assessment framework to analyze the causal factors of the identified mismatches in the previous step, as the main contributors of negative pressure test

  19. Identifying Human Factors Issues in Aircraft Maintenance Operations

    Science.gov (United States)

    Veinott, Elizabeth S.; Kanki, Barbara G.; Shafto, Michael G. (Technical Monitor)

    1995-01-01

    Maintenance operations incidents submitted to the Aviation Safety Reporting System (ASRS) between 1986-1992 were systematically analyzed in order to identify issues relevant to human factors and crew coordination. This exploratory analysis involved 95 ASRS reports which represented a wide range of maintenance incidents. The reports were coded and analyzed according to the type of error (e.g, wrong part, procedural error, non-procedural error), contributing factors (e.g., individual, within-team, cross-team, procedure, tools), result of the error (e.g., aircraft damage or not) as well as the operational impact (e.g., aircraft flown to destination, air return, delay at gate). The main findings indicate that procedural errors were most common (48.4%) and that individual and team actions contributed to the errors in more than 50% of the cases. As for operational results, most errors were either corrected after landing at the destination (51.6%) or required the flight crew to stop enroute (29.5%). Interactions among these variables are also discussed. This analysis is a first step toward developing a taxonomy of crew coordination problems in maintenance. By understanding what variables are important and how they are interrelated, we may develop intervention strategies that are better tailored to the human factor issues involved.

  20. Quantifying human and organizational factors in accident management using decision trees: the HORAAM method

    International Nuclear Information System (INIS)

    Baumont, G.; Menage, F.; Schneiter, J.R.; Spurgin, A.; Vogel, A.

    2000-01-01

    In the framework of the level 2 Probabilistic Safety Study (PSA 2) project, the Institute for Nuclear Safety and Protection (IPSN) has developed a method for taking into account Human and Organizational Reliability Aspects during accident management. Actions are taken during very degraded installation operations by teams of experts in the French framework of Crisis Organization (ONC). After describing the background of the framework of the Level 2 PSA, the French specific Crisis Organization and the characteristics of human actions in the Accident Progression Event Tree, this paper describes the method developed to introduce in PSA the Human and Organizational Reliability Analysis in Accident Management (HORAAM). This method is based on the Decision Tree method and has gone through a number of steps in its development. The first one was the observation of crisis center exercises, in order to identify the main influence factors (IFs) which affect human and organizational reliability. These IFs were used as headings in the Decision Tree method. Expert judgment was used in order to verify the IFs, to rank them, and to estimate the value of the aggregated factors to simplify the quantification of the tree. A tool based on Mathematica was developed to increase the flexibility and the efficiency of the study

  1. Safety coaches in radiology: decreasing human error and minimizing patient harm

    Energy Technology Data Exchange (ETDEWEB)

    Dickerson, Julie M.; Adams, Janet M. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Koch, Bernadette L.; Donnelly, Lane F. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Cincinnati Children' s Hospital Medical Center, Department of Pediatrics, Cincinnati, OH (United States); Goodfriend, Martha A. [Cincinnati Children' s Hospital Medical Center, Department of Quality Improvement, Cincinnati, OH (United States)

    2010-09-15

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

  2. Safety coaches in radiology: decreasing human error and minimizing patient harm

    International Nuclear Information System (INIS)

    Dickerson, Julie M.; Adams, Janet M.; Koch, Bernadette L.; Donnelly, Lane F.; Goodfriend, Martha A.

    2010-01-01

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

  3. Safety coaches in radiology: decreasing human error and minimizing patient harm.

    Science.gov (United States)

    Dickerson, Julie M; Koch, Bernadette L; Adams, Janet M; Goodfriend, Martha A; Donnelly, Lane F

    2010-09-01

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program.

  4. Safety activities and human resource development at NCA

    International Nuclear Information System (INIS)

    Kumanomido, Hironori; Sakurada, Koichi; Yanagisawa, Shigeru; Masuyama, Tadaharu

    2015-01-01

    Toshiba Nuclear Critical Assembly (NCA) has been safely operated since the first criticality in December 1963. The topics covered in this Yayoi Meeting Report are: (1) the outline of NCA, (2) the safety control situation mainly after the Great East Japan Earthquake in 2011, (3) educational training incorporates the lessons learned in this earthquake, and (4) human resource development during 2008-2015. Regarding safety control, facility maintenance has been conducted systematically according to the maintenance plan from the viewpoint of preventive maintenance. Regarding educational training, two disaster handling training based on the safety regulation and one nuclear emergency drill based on the emergency drill plan for licensee of nuclear energy activity based on the Act of Special Measures Concerning Nuclear Emergency Preparedness every year. Regarding human resource development, development training was given to 358 people including students. This year, training that does not require NCA operation was conducted including gamma-ray spectrum measurement of NCA fuel rod and neutron deceleration property measurement using 252 Cf neutron source. (S.K.)

  5. State of science: human factors and ergonomics in healthcare.

    Science.gov (United States)

    Hignett, Sue; Carayon, Pascale; Buckle, Peter; Catchpole, Ken

    2013-01-01

    The past decade has seen an increase in the application of human factors and ergonomics (HFE) techniques to healthcare delivery in a broad range of contexts (domains, locations and environments). This paper provides a state of science commentary using four examples of HFE in healthcare to review and discuss analytical and implementation challenges and to identify future issues for HFE. The examples include two domain areas (occupational ergonomics and surgical safety) to illustrate a traditional application of HFE and the area that has probably received the most research attention. The other two examples show how systems and design have been addressed in healthcare with theoretical approaches for organisational and socio-technical systems and design for patient safety. Future opportunities are identified to develop and embed HFE systems thinking in healthcare including new theoretical models and long-term collaborative partnerships. HFE can contribute to systems and design initiatives for both patients and clinicians to improve everyday performance and safety, and help to reduce and control spiralling healthcare costs. There has been an increase in the application of HFE techniques to healthcare delivery in the past 10 years. This paper provides a state of science commentary using four illustrative examples (occupational ergonomics, design for patient safety, surgical safety and organisational and socio-technical systems) to review and discuss analytical and implementation challenges and identify future issues for HFE.

  6. 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

  7. 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)

  8. 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.

  9. Human-factors methods for assessing and enhancing power-plant maintainability

    International Nuclear Information System (INIS)

    Seminara, J.L.

    1982-05-01

    EPRI Final Report NP-1567, dated February 1981, presented the results of a human factors review of plant maintainability at nine power plants (five nuclear and four fossil). This investigation revealed a wide range of plant and equipment design features that can potentially compromise the effectiveness, safety, and productivity of maintenance personnel. The present study is an extension of the earlier work. It provides those utilities that did not participate in the original study with the methodological tools to conduct a review of maintenance provisions, facilities, and practices. This report describes and provides a self-review checklist; a structured interview; a task analysis approach; methods for reviewing maintenance errors or accidents; and recommended survey techniques for evaluating such factors as noise, illumination, and communications. Application of the human factors methods described in this report should reveal avenues for enhancing existing power plants from the maintainability and availability standpoints. This document may also serve a useful purpose for designers or reviewers of new plant designs or near-operational plants presently being constructed

  10. Identification and assessment of organisational factors related to the safety of NPPs - State-of-the-Art Report

    International Nuclear Information System (INIS)

    Baumont, Genevieve; Bourrier, Mathilde; Frischknecht, Albert; Schoenfeld, Isabelle; Weber, Mike J.

    1999-09-01

    The initiation of this State-of-the-Art Report (SOAR) on Organisational Factors Identification and Assessment comes from operating experience associated with a number of major events world-wide which caused power plants to be shutdown for a significant period of time. Root cause assessments of these events identified weaknesses in organisational factors as contributing to these events. There is general recognition that organisational factors need to be evaluated for their contribution to plant safety performance and risk to prevent their recurrence in events. A special recommendation to create a SOAR was presented in the NEA report on Research Strategies for Human Performance [NEA/CSNI/R(97)24]. Based on this recommendation the Principle Working Group 1 (PWG1) requested, as a top priority, that the Expanded Task Force (ETF) on Human Factors develop a SOAR for the September 1998 meeting. The ETF members were aware that it was a challenging topic. The field of organisational behaviour is not yet fully developed for the nuclear organisation. There is a need to collect and analyse operational and event data from the nuclear environment to determine the safety and risk significance of organisational factors, to identify assessment methods for those factors, and to gain peer review of the results to ensure credibility and acceptability of these methods and possibly their measures. This SOAR reports on the results of the workshop on Organisational Factors Identification and Assessment held in Boettstein Castle, Switzerland, on 14-19 June 1998. Twenty-eight participants from twelve Member countries and Russia represented three different environments: nuclear utilities; regulatory bodies and inspectorates; and the research and academic community. The various approaches discussed in the SOAR reflect the perspective of these entities. The SOAR addresses the following topics: - identification of organisational factors; - identification of methods for the evaluation of

  11. Patient safety risk factors in minimally invasive surgery : A validation study

    NARCIS (Netherlands)

    Rodrigues, S.P.; Ter Kuile, M.; Dankelman, J.; Jansen, F.W.

    2012-01-01

    This study was conducted to adapt and validate a patient safety (PS) framework for minimally invasive surgery (MIS) as a first step in understanding the clinical relevance of various PS risk factors in MIS. Eight patient safety risk factor domains were identified using frameworks from a systems

  12. A computational method for probabilistic safety assessment of I and C systems and human operators in nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Man Cheol; Seong, Poong Hyun

    2006-01-01

    To make probabilistic safety assessment (PSA) more realistic, the improvements of human reliability analysis (HRA) are essential. But, current HRA methods have many limitations including the lack of considerations on the interdependency between instrumentation and control (I and C) systems and human operators, and lack of theoretical basis for situation assessment of human operators. To overcome these limitations, we propose a new method for the quantitative safety assessment of I and C systems and human operators. The proposed method is developed based on the computational models for the knowledge-driven monitoring and the situation assessment of human operators, with the consideration of the interdependency between I and C systems and human operators. The application of the proposed method to an example situation demonstrates that the quantitative description by the proposed method for a probable scenario well matches with the qualitative description of the scenario. It is also demonstrated that the proposed method can probabilistically consider all possible scenarios and the proposed method can be used to quantitatively evaluate the effects of various context factor on the safety of nuclear power plants. In our opinion, the proposed method can be used as the basis for the development of advanced HRA methods

  13. Leveraging Health Care Simulation Technology for Human Factors Research: Closing the Gap Between Lab and Bedside.

    Science.gov (United States)

    Deutsch, Ellen S; Dong, Yue; Halamek, Louis P; Rosen, Michael A; Taekman, Jeffrey M; Rice, John

    2016-11-01

    We describe health care simulation, designed primarily for training, and provide examples of how human factors experts can collaborate with health care professionals and simulationists-experts in the design and implementation of simulation-to use contemporary simulation to improve health care delivery. The need-and the opportunity-to apply human factors expertise in efforts to achieve improved health outcomes has never been greater. Health care is a complex adaptive system, and simulation is an effective and flexible tool that can be used by human factors experts to better understand and improve individual, team, and system performance within health care. Expert opinion is presented, based on a panel delivered during the 2014 Human Factors and Ergonomics Society Health Care Symposium. Diverse simulators, physically or virtually representing humans or human organs, and simulation applications in education, research, and systems analysis that may be of use to human factors experts are presented. Examples of simulation designed to improve individual, team, and system performance are provided, as are applications in computational modeling, research, and lifelong learning. The adoption or adaptation of current and future training and assessment simulation technologies and facilities provides opportunities for human factors research and engineering, with benefits for health care safety, quality, resilience, and efficiency. Human factors experts, health care providers, and simulationists can use contemporary simulation equipment and techniques to study and improve health care delivery. © 2016, Human Factors and Ergonomics Society.

  14. Human Resources Readiness as TSO for Deterministic Safety Analysis on the First NPP in Indonesia

    International Nuclear Information System (INIS)

    Sony Tjahyani, D. T.

    2010-01-01

    In government regulation no. 43 year 2006 it is mentioned that preliminary safety analysis report and final safety analysis report are one of requirements which should be applied in construction and operation licensing for commercial power reactor (NPPs). The purpose of safety analysis report is to confirm the adequacy and efficiency of provisions within the defence in depth of nuclear reactor. Deterministic analysis is used on the safety analysis report. One of the TSO task is to evaluate this report based on request of operator or regulatory body. This paper discusses about human resources readiness as TSO for deterministic safety analysis on the first NPP in Indonesia. The assessment is done by comparing the analysis step on SS-23 and SS-30 with human resources status of BATAN currently. The assessment results showed that human resources for deterministic safety analysis are ready as TSO especially to review preliminary safety analysis report and to revise final safety analysis report in licensing on the first NPP in Indonesia. Otherwise, to prepare the safety analysis report is still needed many competency human resources. (author)

  15. Decomobil, Deliverable 3.6, Human Centred Design for Safety Critical Transport Systems

    OpenAIRE

    PAUZIE, Annie; MENDOZA, Lucile; SIMOES, Anabela; BELLET, Thierry; MOREAU, Fabien

    2014-01-01

    The scientific seminar on 'Human Centred Design for Safety Critical Transport Systems' organized in the framework of DECOMOBIL has been held the 8th of September 2014 in Lisbon, Portugal, hosted by ADI/ISG. The aims of the event were to present the scientific problematic related to the safety of the complex transport systems and the increasing importance of human-­centred design, with a specific focus on Resilience Engineering concept, a new approach to safety management in highly complex sys...

  16. Organisational and human factors in risk management: common beliefs, deceived ideas; Les Facteurs Organisationnels et Humains de la gestion des risques: idees recues, idees decues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-09-22

    The author propose critical discussions of common beliefs about the ineluctability of human error, individual ability, the validity of written procedures, good organisation, the culture of safety, the contribution of quality approaches to safety, the continuous improvement of safety, the good usage of the return on experience, the rigour and objectivity of the FOH (organisational and human factor) approach, and appealing to experts in FOHs

  17. To the problem of the statistical basis of evaluation of the mechanical safety factor

    International Nuclear Information System (INIS)

    Tsyganov, S.V.

    2009-01-01

    The methodology applied for the safety factor assessment of the WWER fuel cycles uses methods and terms of statistics. Value of the factor is calculated on the basis of estimation of probability to meet predefined limits. Such approach demands the special attention to the statistical properties of parameters of interest. Considering the mechanical constituents of the engineering factor it is assumed uncertainty factors of safety parameters are stochastic values. It characterized by probabilistic distributions that can be unknown. Traditionally in the safety factor assessment process the unknown parameters are estimated from the conservative points of view. This paper analyses how the refinement of the factors distribution parameters is important for the assessment of the mechanical safety factor. For the analysis the statistical approach is applied for modelling of different type of factor probabilistic distributions. It is shown the significant influence of the shape and parameters of distributions for some factors on the value of mechanical safety factor. (Authors)

  18. To the problem of the statistical basis of evaluation of the mechanical safety factor

    International Nuclear Information System (INIS)

    Tsyganov, S.

    2009-01-01

    The methodology applied for the safety factor assessment of the VVER fuel cycles uses methods and terms of statistics. Value of the factor is calculated on the basis of estimation of probability to meet predefined limits. Such approach demands the special attention to the statistical properties of parameters of interest. Considering the mechanical constituents of the engineering factor it is assumed uncertainty factors of safety parameters are stochastic values. It characterized by probabilistic distributions that can be unknown. Traditionally in the safety factor assessment process the unknown parameters are estimated from the conservative points of view. This paper analyses how the refinement of the factors distribution parameters is important for the assessment of the mechanical safety factor. For the analysis the statistical approach is applied for modelling of different type of factor probabilistic distributions. It is shown the significant influence of the shape and parameters of distributions for some factors on the value of mechanical safety factor. (author)

  19. Applications of probabilistic risk analysis in nuclear criticality safety design

    International Nuclear Information System (INIS)

    Chang, J.K.

    1992-01-01

    Many documents have been prepared that try to define the scope of the criticality analysis and that suggest adding probabilistic risk analysis (PRA) to the deterministic safety analysis. The report of the US Department of Energy (DOE) AL 5481.1B suggested that an accident is credible if the occurrence probability is >1 x 10 -6 /yr. The draft DOE 5480 safety analysis report suggested that safety analyses should include the application of methods such as deterministic safety analysis, risk assessment, reliability engineering, common-cause failure analysis, human reliability analysis, and human factor safety analysis techniques. The US Nuclear Regulatory Commission (NRC) report NRC SG830.110 suggested that major safety analysis methods should include but not be limited to risk assessment, reliability engineering, and human factor safety analysis. All of these suggestions have recommended including PRA in the traditional criticality analysis

  20. Identification and assessment of organisational factors related to the safety of NPPs - State-of-the-Art Report

    International Nuclear Information System (INIS)

    Baumont, Genevieve; Bourrier, Mathilde; Frischknecht, Albert; Schoenfeld, Isabelle; Weber, Mike J.

    1999-01-01

    The initiation of this State-of-the-Art Report (SOAR) on Organisational Factors Identification and Assessment comes from operating experience associated with a number of major events world-wide which caused power plants to be shutdown for a significant period of time. Root cause assessments of these events identified weaknesses in organisational factors as contributing to these events. There is general recognition that organisational factors need to be evaluated for their contribution to plant safety performance and risk to prevent their recurrence in events. There is a need to collect and analyse operational and event data from the nuclear environment to determine the safety and risk significance of organisational factors, to identify assessment methods for those factors, and to gain peer review of the results to ensure credibility and acceptability of these methods and possibly their measures. The SOAR presents a representative view of developments in this field and addresses the following topics: - identification of organisational factors; - identification of methods for the evaluation of organisational factors; - identification of methods for the evaluation of whole organisations; - identification of gaps in knowledge and needed research to evaluate adequately the influence of organisation and management on safety and risk. The workshop participants identified 12 organisational factors as important to assess in determining organisational safety performance. They are: external influences; goals and strategies; management functions and overview; resource allocation; human resource management; training; co-ordination of work; organisational knowledge; proceduralization; organisational culture; organisational learning; and communication. Different cultural backgrounds of participants using their own terminology sometimes made it difficult to have a common definition for certain factors. Some factors could be defined by consensus; other factors such as

  1. Habitability and Human Factors Contributions to Human Space Flight

    Science.gov (United States)

    Sumaya, Jennifer Boyer

    2011-01-01

    This slide presentation reviews the work of the Habitability and Human Factors Branch in support of human space flight in two main areas: Applied support to major space programs, and Space research. The field of Human Factors applies knowledge of human characteristics for the design of safer, more effective, and more efficient systems. This work is in several areas of the human space program: (1) Human-System Integration (HSI), (2) Orion Crew Exploration Vehicle, (3) Extravehicular Activity (EVA), (4) Lunar Surface Systems, (5) International Space Station (ISS), and (6) Human Research Program (HRP). After detailing the work done in these areas, the facilities that are available for human factors work are shown.

  2. A Survey on the HFE-related Technologies for the Improvements of Human Performance of Safety Personnel in Rail System

    International Nuclear Information System (INIS)

    Koo, I. S.; Park, G. O.; Suh, S. M.; Sim, Y. R.; Go, J. H.; Jeong, J. H.; Son, C. H.

    2005-08-01

    Many studies have shown that the most cases of rail accidents have occurred because of performing his/her tasks in inappropriate way. It is generally recognised that the rail system without human element could never be happened quite long time. So human element in rail system is going to be the major factor to the next tragic accident. This state-of-the-art report describes three major HFE-related technologies, training simulator, the integrated test facility for human factors engineering, and human performance evaluation system, that are used in the other industries including nuclear power industry for the purpose of increasing rail safety through out the improvement of human task performance. Base on this report, the way of developing those technologies that should be applied to the korean rail system is presented

  3. A Survey on the HFE-related Technologies for the Improvements of Human Performance of Safety Personnel in Rail System

    Energy Technology Data Exchange (ETDEWEB)

    Koo, I. S.; Park, G. O.; Suh, S. M.; Sim, Y. R.; Go, J. H.; Jeong, J. H.; Son, C. H

    2005-08-15

    Many studies have shown that the most cases of rail accidents have occurred because of performing his/her tasks in inappropriate way. It is generally recognised that the rail system without human element could never be happened quite long time. So human element in rail system is going to be the major factor to the next tragic accident. This state-of-the-art report describes three major HFE-related technologies, training simulator, the integrated test facility for human factors engineering, and human performance evaluation system, that are used in the other industries including nuclear power industry for the purpose of increasing rail safety through out the improvement of human task performance. Base on this report, the way of developing those technologies that should be applied to the korean rail system is presented.

  4. Factors impacting on the microbiological quality and safety of ...

    African Journals Online (AJOL)

    Problems with the safety and shelf life of export hake have been raised by the Namibian fishing industry. This prompted an investigation into the factors that may have an impact on the microbiological quality and safety of processed hake. Samples were collected along the processing line; the general microbiological quality ...

  5. Tendencies in human factor influence on initiating events occurrence in NPP Kozloduy

    International Nuclear Information System (INIS)

    Hristova, R.

    2001-01-01

    Overview of the methods and documents concerning human factor in nuclear safety and selection of the most appropriate methods and concept for human factor assessment in the reported events in Kozloduy NPP are presented. List of human error types and statistical data (the mean time between similar errors, the human rate λ, the number of occurrences ect.) is given. Some general results from the human error behavior investigation for all units of Kozloduy NPP related to the 4 personnel categories: Management personnel, Designers, Operating personnel, Maintenance personnel are also shown. At the end the following conclusion are made:18 % operating personnel errors (for comparison for the same category personnel in similar NPPs abroad this value is between 10 % and 30%); Human errors in Kozloduy NPP tend to increase after year 1990; only for the operating personnel a maximum near year 1997 was observed, after which the error values was decreased; at the beginning of year 2000 the reliability characteristics for all units have similar values; it is necessary to be taken into account the observed tendencies to take measurements for reducing of the most important error types for Kozloduy NPP personnel

  6. SEIPS 2.0: A human factors framework for studying and improving the work of healthcare professionals and patients

    Science.gov (United States)

    Holden, Richard J.; Carayon, Pascale; Gurses, Ayse P.; Hoonakker, Peter; Hundt, Ann Schoofs; Ozok, A. Ant; Rivera-Rodriguez, A. Joy

    2013-01-01

    Healthcare practitioners, patient safety leaders, educators, and researchers increasingly recognize the value of human factors/ergonomics and make use of the discipline’s person-centered models of sociotechnical systems. This paper first reviews one of the most widely used healthcare human factors systems models, the Systems Engineering Initiative for Patient Safety (SEIPS) model, and then introduces an extended model, “SEIPS 2.0.” SEIPS 2.0 incorporates three novel concepts into the original model: configuration, engagement, and adaptation. The concept of configuration highlights the dynamic, hierarchical, and interactive properties of sociotechnical systems, making it possible to depict how health-related performance is shaped at “a moment in time.” Engagement conveys that various individuals and teams can perform health-related activities separately and collaboratively. Engaged individuals often include patients, family caregivers, and other non-professionals. Adaptation is introduced as a feedback mechanism that explains how dynamic systems evolve in planned and unplanned ways. Key implications and future directions for human factors research in healthcare are discussed. PMID:24088063

  7. DEVELOPMENT OF HUMAN FACTORS ENGINEERING GUIDANCE FOR SAFETY EVALUATIONS OF ADVANCED REACTORS

    International Nuclear Information System (INIS)

    O'HARA, J.; PERSENSKY, J.; SZABO, A.

    2006-01-01

    Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools

  8. Diabetes technology and the human factor.

    Science.gov (United States)

    Liberman, A; Buckingham, B; Phillip, M

    2011-02-01

    When developing new technologies for human use the developer should take into consideration not only the efficacy and safety of the technology but also the desire and capabilities of the potential user. Any chronic disease is a challenge for both the patient and his/her caregivers. This statement is especially true in the case of patients with type 1 diabetes mellitus (T1DM) where adherence to therapy is crucial 24 hours a day 365 days a year. No vacation days are possible for the T1DM patient. It is therefore obvious why any new technology which is developed for helping patients cope with the disease should take into consideration the 'human factor' before, during and after the production process starts. There is no doubt that technology has changed the life of patients with T1DM in the last few decades, but despite the availability of new meters, new syringes, new sophisticated insulin pumps and continuous glucose sensors and communication tools, these technologies have not been well utilised by many patients. It is therefore important to understand why the technology is not always utilised and to find new ways to maximise use and benefits from the technology to as many patients as possible. The present chapter will review papers published in the last year where the patient's ability or willingness was an important factor in the success of the technology. We will try to understand why insulin pumps, glucose sensors and self-monitoring of blood glucose (SMBG) are not used enough or appropriately, whether there is a specific group that finds it more difficult than others to adopt new technologies and what can be done to overcome that issue. For this chapter we chose articles from a Public Medicine review of the literature related to human factors affecting the outcome of studies and of user acceptance of continuous glucose monitoring, insulin infusion pump therapy. We also searched the literature in the field of psychology in order to accurately define the problems

  9. Human Factors Engineering: Current Practices and Development Needs in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Savioja, Paula; Norros, Leena; Liinasuo, Marja; Laarni, Jari [VTT Technical Research Centre of Finland, Finland (Finland)

    2011-08-15

    This paper describes initial findings from a study concerning the practices and development needs of Human Factors Engineering (HFE) in Finland. HFE is increasing in importance as the Radiation and Nuclear Safety Authority Finland (STUK) is renewing the regulatory guidelines and the intention is to include requirements concerning HFE. The motivation for the paper is to discover how HFE is conducted currently in order to envision what should be aimed at when modifying requirements for design practices. In an interview with STUK it was discovered that current HFE practices encompass mainly activities related to control room modifications and as such namely verification and validation of new designs. The adoption of the entire HFE process in design and modification projects requires changes that include better integration of technical and Human Factors Engineering approaches. Boundary objects that mediate between different design disciplines are needed in order to enforce the stronger integration. Concept of operations (CONOPS) is suggested as a such boundary object.

  10. 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)

  11. Maturing safety in the UK

    International Nuclear Information System (INIS)

    Debenham, A.; Kovan, D.

    1994-01-01

    AEA Technology provides UK nuclear industry with technical services and R+D support, concentrating on plant performance, safety and environmental issues. Today, safety has a new set of priorities, reflected by a more demanding regulatory regime which takes account of concerns such as human factors, severe accidents, risks during plant outages, the need for improving safety culture, etc

  12. Human factors for the Moon: the gap in anthropometric data.

    Science.gov (United States)

    Lia Schlacht, Irene; Foing, Bernard H.; Rittweger, Joern; Masali, Melchiorre; Stevenin, Hervé

    2016-07-01

    Since the space era began, we learned first to survive and then to live in space. In the state of the art, we know how important human factors research and development is to guarantee maximum safety and performance for human missions. With the extension of the duration of space missions, we also need to learn how habitability and comfort factors are closely related to safety and performance. Humanities disciplines such as design, architecture, anthropometry, and anthropology are now involved in mission design from the start. Actual plans for building a simulated Moon village in order to simulate and test Moon missions are now being carried out using a holistic approach, involving multidisciplinary experts cooperating concurrently with regard to the interactions among humans, technology, and the environment. However, in order to implement such plans, we need basic anthropometrical data, which is still missing. In other words: to optimize performance, we need to create doors and ceilings with dimensions that support a natural human movement in the reduced gravity environment of the Moon, but we are lacking detailed anthropometrical data on human movement on the Moon. In the Apollo missions more than 50 years ago, no anthropometrical studies were carried in hypogravity out as far as we know. The necessity to collect data is very consistent with state-of-the-art research. We still have little knowledge of how people will interact with the Moon environment. Specifically, it is not known exactly which posture, which kind of walking and running motions astronauts will use both inside and outside a Moon station. Considering recent plans for a Moon mission where humans will spend extensive time in reduced gravity conditions, the need for anthropometric, biomechanics and kinematics field data is a priority in order to be able to design the right architecture, infrastructure, and interfaces. Objective of this paper: Bring knowledge on the relevance of anthropometrical and

  13. 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

  14. A human factors evaluation of advanced control facilities in Korea Next Generation Reactor

    International Nuclear Information System (INIS)

    Byun, Seong Nam; Lee, Dong Hoon; Chung, Sung Hak; Kim, Dong Nam; Hwang, Sang Ho

    2001-07-01

    The objectives of this study are as follows: to evaluate the impacts of advanced MMIs on operator performance; to identify new types of human errors; to present Human Factors Engineering (HFE) issues to support the safety reviews performed by the Korea Institute for Nuclear Safety. General trends in the performance measures of cognitive task demand, mental workload, and situation awareness were analyzed. The results showed that the conventional plant was superior to KNGR on the operator performance. The results of the questionnaire revealed that WDS was the most frequently used MMI resource, followed by CPS, LDP, SC, and AS. The evaluation of operator's satisfaction showed that WDS was the most satisfactory resource, followed by LDP, SC, CPS', and AS, AS was rated as the most worst resource due to inappropriate functional organization and lack of operator's visibility. Stepwise regression analyses showed that human errors of SRO and RO were mainly dominated by the cognitive behavior of 'interpretation' with WDS, while the cognitive behavior of TO was mainly dominated by 'observation' with WDS and AS. The ten HFE issues for the KNGR MCR were presented to address important design deficiencies identified in this study. The issues should be resolved to improve safety of KNGR at least up to the level of the conventional NPPs. Verification and validation activities after implementing those resolutions should be also performed to reach optimal plant safety and other operational goals

  15. A human factors evaluation of advanced control facilities in Korea Next Generation Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Byun, Seong Nam; Lee, Dong Hoon; Chung, Sung Hak; Kim, Dong Nam; Hwang, Sang Ho [Kyunghee Univ., Seoul (Korea, Republic of)

    2001-07-15

    The objectives of this study are as follows: to evaluate the impacts of advanced MMIs on operator performance; to identify new types of human errors; to present Human Factors Engineering (HFE) issues to support the safety reviews performed by the Korea Institute for Nuclear Safety. General trends in the performance measures of cognitive task demand, mental workload, and situation awareness were analyzed. The results showed that the conventional plant was superior to KNGR on the operator performance. The results of the questionnaire revealed that WDS was the most frequently used MMI resource, followed by CPS, LDP, SC, and AS. The evaluation of operator's satisfaction showed that WDS was the most satisfactory resource, followed by LDP, SC, CPS', and AS, AS was rated as the most worst resource due to inappropriate functional organization and lack of operator's visibility. Stepwise regression analyses showed that human errors of SRO and RO were mainly dominated by the cognitive behavior of 'interpretation' with WDS, while the cognitive behavior of TO was mainly dominated by 'observation' with WDS and AS. The ten HFE issues for the KNGR MCR were presented to address important design deficiencies identified in this study. The issues should be resolved to improve safety of KNGR at least up to the level of the conventional NPPs. Verification and validation activities after implementing those resolutions should be also performed to reach optimal plant safety and other operational goals.

  16. EDUCATION IN THE FIELD safety of human life AND THE SUSTAINABLE DEVELOPMENT

    Directory of Open Access Journals (Sweden)

    M. A. Kartavykh

    2016-01-01

    Full Text Available The publication purpose - pedagogical design of education of bachelors in the field safety of human life in the context of ideas of a sustainable development as one of the modern and perspective directions of the higher education. Philosophical and methodological, scientific and technical and pedagogical aspects of provisions of the concept of a sustainable development are opened. It is shown that the greatest potential for realization of ideas of a sustainable development the invariant subject matter the " Safety of human life " studied by future bachelors irrespective of the direction and a profile of preparation possesses. The fundamental principles of education in the field safety of human life of future bachelors are formulated. Key functions of education of bachelors in the field of health and safety are defined: valuable and orientation, teoretiko-world outlook, it is constructive - activity, it is reflexive - estimated. The methodical tasks approaching the project to specific sociocultural and pedagogical conditions are opened: definition of target reference points, modular structuring content of education, development of procedural and technological features of creation of educational activity; diagnostics of results. The idea of a didactic cycle at development of the content of education in the field safety of human life is proved and opened. The educations of future bachelors got in the course of approbation results in the field safety of human life in the context of ideology of sustainable (safe development allow to speak about efficiency of the chosen scientific and methodological and organizational and technological bases and to project new models of practical experience in conditions of providing optimum ways of productive pedagogical interaction.

  17. Evaluating the impact of grade crossing safety factors through signal detection theory

    Science.gov (United States)

    2012-10-22

    The purpose of this effort was to apply signal detection theory to descriptively model the impact : of five grade crossing safety factors to understand their effect on driver decision making. The : safety factors consisted of: improving commercial mo...

  18. Human Factors Review Plan

    International Nuclear Information System (INIS)

    Paramore, B.; Peterson, L.R.

    1985-12-01

    ''Human Factors'' is concerned with the incorporation of human user considerations into a system in order to maximize human reliability and reduce errors. This Review Plan is intended to assist in the assessment of human factors conditions in existing DOE facilities. In addition to specifying assessment methodologies, the plan describes techniques for improving conditions which are found to not adequately support reliable human performance. The following topics are addressed: (1) selection of areas for review describes techniques for needs assessment to assist in selecting and prioritizing areas for review; (2) human factors engineering review is concerned with optimizing the interfaces between people and equipment and people and their work environment; (3) procedures review evaluates completeness and accuracy of procedures, as well as their usability and management; (4) organizational interface review is concerned with communication and coordination between all levels of an organization; and (5) training review evaluates training program criteria such as those involving: trainee selection, qualification of training staff, content and conduct of training, requalification training, and program management

  19. Human Factors Review Plan

    Energy Technology Data Exchange (ETDEWEB)

    Paramore, B.; Peterson, L.R. (eds.)

    1985-12-01

    ''Human Factors'' is concerned with the incorporation of human user considerations into a system in order to maximize human reliability and reduce errors. This Review Plan is intended to assist in the assessment of human factors conditions in existing DOE facilities. In addition to specifying assessment methodologies, the plan describes techniques for improving conditions which are found to not adequately support reliable human performance. The following topics are addressed: (1) selection of areas for review describes techniques for needs assessment to assist in selecting and prioritizing areas for review; (2) human factors engineering review is concerned with optimizing the interfaces between people and equipment and people and their work environment; (3) procedures review evaluates completeness and accuracy of procedures, as well as their usability and management; (4) organizational interface review is concerned with communication and coordination between all levels of an organization; and (5) training review evaluates training program criteria such as those involving: trainee selection, qualification of training staff, content and conduct of training, requalification training, and program management.

  20. Safety culture measurements results in the agricultural sector

    OpenAIRE

    Terjék, László

    2013-01-01

    The author examined the safety culture and in relation to that the safety and health-related human factors. The examination was conducted primarily in the agricultural sector. Safety culture is also a key factor in business life especially in productive sectors. Basically, it determines the general work safety and occupational hazard situations, which may have an impact on business, competitiveness, and efficiency, and also employee satisfaction.The concept of safety culture is new in the app...

  1. Studying the Relationship between Individual and Organizational Factors and Nurses' Perception of Patient Safety Culture

    Directory of Open Access Journals (Sweden)

    Farahnaz Abdolahzadeh

    2012-11-01

    Full Text Available Introduction: Safety culture is considered as an important factor in improving patient safety. Therefore, identifying individual and organizational factors affecting safety culture is crucial. This study was carried out to determine individual and organizational factors associated with nurses' perception of patient safety culture. Methods: The present descriptive study included 940 nurses working in four training hospitals affiliated with Urmia University of Medical Sciences (Iran. Data was collected through the self-report questionnaire of patient safety culture. Descriptive (number, percent, mean, and standard deviation and inferential (t-test and analysis of variance statistics were used to analyze the data in SPSS. Results: Nurses' perception of patient safety culture was significantly correlated with marital status, workplace, and overtime hours. Conclusion: The results of this study revealed that some individual and organizational factors can impact on nurses' perception of patient safety culture. Nursing authorities should thus pay more attention to factors which promote patient safety culture and ultimately the safety of provided services.

  2. Workforce scheduling: A new model incorporating human factors

    Directory of Open Access Journals (Sweden)

    Mohammed Othman

    2012-12-01

    Full Text Available Purpose: The majority of a company’s improvement comes when the right workers with the right skills, behaviors and capacities are deployed appropriately throughout a company. This paper considers a workforce scheduling model including human aspects such as skills, training, workers’ personalities, workers’ breaks and workers’ fatigue and recovery levels. This model helps to minimize the hiring, firing, training and overtime costs, minimize the number of fired workers with high performance, minimize the break time and minimize the average worker’s fatigue level.Design/methodology/approach: To achieve this objective, a multi objective mixed integer programming model is developed to determine the amount of hiring, firing, training and overtime for each worker type.Findings: The results indicate that the worker differences should be considered in workforce scheduling to generate realistic plans with minimum costs. This paper also investigates the effects of human fatigue and recovery on the performance of the production systems.Research limitations/implications: In this research, there are some assumptions that might affect the accuracy of the model such as the assumption of certainty of the demand in each period, and the linearity function of Fatigue accumulation and recovery curves. These assumptions can be relaxed in future work.Originality/value: In this research, a new model for integrating workers’ differences with workforce scheduling is proposed. To the authors' knowledge, it is the first time to study the effects of different important human factors such as human personality, skills and fatigue and recovery in the workforce scheduling process. This research shows that considering both technical and human factors together can reduce the costs in manufacturing systems and ensure the safety of the workers.

  3. The development of human factors technologies -The development of human factors experimental evaluation techniques-

    International Nuclear Information System (INIS)

    Shim, Bong Sik; Oh, In Suk; Cha, Kyung Hoh; Lee, Hyun Chul

    1995-07-01

    In this year, we studied the followings: 1) Development of operator mental workload evaluation techniques, 2) Development of a prototype for preliminary human factors experiment, 3) Suitability test of information display on a large scale display panel, 4) Development of guidelines for VDU-based control room design, 5) Development of integrated test facility (ITF). 6) Establishment of an eye tracking system, and we got the following results: 1) Mental workload evaluation techniques for MMI evaluation, 2) PROTOPEX (PROTOtype for preliminary human factors experiment) for preliminary human factors experiments, 3) Usage methods of APTEA (Analysis-Prototyping-Training-Experiment-Analysis) experiment design, 4) Design guidelines for human factors verification, 5) Detail design requirements and development plan of ITF, 6) Eye movement measurement system. 38 figs, 20 tabs, 54 refs. (Author)

  4. Factors Influencing the Safety Behavior of German Equestrians: Attitudes towards Protective Equipment and Peer Behaviors

    Directory of Open Access Journals (Sweden)

    Christina-Maria Ikinger

    2016-02-01

    Full Text Available Human interactions with horses entail certain risks. Although the acceptance and use of protective gear is increasing, a high number of incidents and very low or inconsistent voluntary use of safety equipment are reported. While past studies have examined factors influencing the use of safety gear, they have explored neither their influence on the overall safety behavior, nor their relative influence in relation to each other. The aim of the present study is to fill this gap. We conducted an online survey with 2572 participants. By means of a subsequent multiple regression analysis, we explored 23 different variables in view of their influence on the protective behavior of equestrians. In total, we found 17 variables that exerted a significant influence. The results show that both having positive or negative attitudes towards safety products as well as the protective behavior of other horse owners or riding pupils from the stable have the strongest influence on the safety behavior of German equestrians. We consider such knowledge to be important for both scientists and practitioners, such as producers of protective gear or horse sport associations who might alter safety behavior in such a way that the number of horse-related injuries decreases in the long term.

  5. Modelling of Safety Factors in the Design of GRP Composite Products

    DEFF Research Database (Denmark)

    Babu, B.J.C.; Prabhakaran, R.T. Durai; Lystrup, Aage

    2010-01-01

    as independent, while in real applications these factors may interact/influence each other. Following the concept developed by the authors, a simple graph theoretic model has been used to determine overall factor of safety. This is described with the help of an example and it has been demonstrated......An attempt has been made in this paper to arrive at the safety factor design of glass fibre reinforced polymer (GRP) composite products using graph theoretic model. In the conventional design and recommendations of the standards, these design factors affecting properties have been considered...

  6. Survey of factors associated with nurses' perception of patient safety.

    Science.gov (United States)

    Park, Sun A; Lee, Sui Jin; Choi, Go Un

    2011-01-01

    To describe the nurses' perception of hospital organization related to cultural issues on the safety of the patient and reporting medical errors. In addition, to identify factors associated with the safety of the patient and the nurse. A survey conducted during December 2008-Jannuary 2009, with 126 nurses using the Korean version of the AHRQ patient safety survey, a self-report 5-point Likert scale. Stata 10.0 was used for descriptive analysis, ANOVA (Analysis of variance) and logistic regression. National Cancer Center in Korea. The means for a working environment related to patient safety was 3.4 (±0.62). The associated factors of duration were at a present hospital, a special area, and direct contact with patients. Among organizational culture factors related to patient safety, the means were 3.81(±0.54) for the boss/manager's perception of patient safety and 3.37(±0.49) for the cooperation/collaboration between units. The frequent number of errors reported by nurses were 1~2(22.2%) times over the past 12 months. For incidence reporting, the items that the 'nurses perceived for communication among clinicians as fair' had a means of 3.23(±0.40) and the 'overall evaluation of patient safety was a good' 3.34(±0.73). The nurses' perception of cooperation and collaboration between units were associated with the direct contact between the patient and the nurse. The frequency of incidence reporting was associated with the duration of working hours at the present hospital and also their work experience. The nurses' perception of hospital environment, organizational culture, and incidence reporting was above average and mostly associated with organizational culture.

  7. Human Factors in Marine Casualties

    Directory of Open Access Journals (Sweden)

    Jelenko Švetak

    2002-05-01

    Full Text Available Human factors play an important role in the origin of accidents,and it is commonly claimed that between seventy andninety-five percent of industrial and transport accidents involvehuman factors, see Figure 1.Some authorities, however, claim that ultimately, all accidentsinvolve human factors.

  8. Human factors considerations in the design and evaluation of flight deck displays and controls : version 2.0

    Science.gov (United States)

    2016-12-01

    The objective of this effort is to have a single source reference document for human factors regulatory and guidance material for flight deck displays and controls, in the interest of improving aviation safety. This document identifies guidance on hu...

  9. The socio-technical system and nuclear safety

    International Nuclear Information System (INIS)

    Stefanescu, Petre; Mihailescu, Nicolae; Dragusin, Octavian

    1999-01-01

    In the field of nuclear safety there have been defined notions like 'technical factors' and 'human factors'. The technical factors depend on designing and manufacturing of components/equipment, actually depend on the people's work. The study of human factors consists in analyzing and recommending the terms that allow an individual to be a reliable and safety agent. Accordingly, he/she is placed in working conditions corresponding to human abilities, associating the means of three levels: - designing, i.e. the action upon the technical system and upon work organization; - correction, i.e. the action upon the evolution of the technical system and organizing; - formation/training, i.e. action upon operators. The paper presents a characterization of the socio-technical system and on this basis discusses the issue of individual adjustment to the socio-technical system and reciprocally, the issue of the socio-technical system adjustment to the individual. Concepts as: ergonomics, physical medium, man/machine interface and support of the operator, man/machine task sharing, the work organizing are put in relation with the central subject, the nuclear safety

  10. A cross-cultural study of organizational factors on safety: Japanese vs. Taiwanese oil refinery plants.

    Science.gov (United States)

    Hsu, Shang Hwa; Lee, Chun-Chia; Wu, Muh-Cherng; Takano, Kenichi

    2008-01-01

    This study attempts to identify idiosyncrasies of organizational factors on safety and their influence mechanisms in Taiwan and Japan. Data were collected from employees of Taiwanese and Japanese oil refinery plants. Results show that organizational factors on safety differ in the two countries. Organizational characteristics in Taiwanese plants are highlighted as: higher level of management commitment to safety, harmonious interpersonal relationship, more emphasis on safety activities, higher devotion to supervision, and higher safety self-efficacy, as well as high quality of safety performance. Organizational characteristics in Japanese plants are highlighted as: higher level of employee empowerment and attitude towards continuous improvement, more emphasis on systematic safety management approach, efficient reporting system and teamwork, and high quality of safety performance. The casual relationships between organizational factors and workers' safety performance were investigated using structural equation modeling (SEM). Results indicate that the influence mechanisms of organizational factors in Taiwan and Japan are different. These findings provide insights into areas of safety improvement in emerging countries and developed countries respectively.

  11. Arabian, Asian, western: a cross-cultural comparison of aircraft accidents from human factor perspectives.

    Science.gov (United States)

    Al-Wardi, Yousuf

    2017-09-01

    Rates of aviation accident differ in different regions; and national culture has been implicated as a factor. This invites a discussion about the role of national culture in aviation accidents. This study makes a cross-cultural comparison between Oman, Taiwan and the USA. A cross-cultural comparison was acquired using data from three studies, including this study, by applying the Human Factors Analysis and Classification System (HFACS) framework. The Taiwan study presented 523 mishaps with 1762 occurrences of human error obtained from the Republic of China Air Force. The study from the USA carried out for commercial aviation had 119 accidents with 245 instances of human error. This study carried out in Oman had a total of 40 aircraft accidents with 129 incidences. Variations were found between Oman, Taiwan and the USA at the levels of organisational influence and unsafe supervision. Seven HFACS categories showed significant differences between the three countries (p culture can have an impact on aviation safety. This study revealed that national culture plays a role in aircraft accidents related to human factors that cannot be disregarded.

  12. Human Factors Process Task Analysis Liquid Oxygen Pump Acceptance Test Procedure for the Advanced Technology Development Center

    Science.gov (United States)

    Diorio, Kimberly A.

    2002-01-01

    A process task analysis effort was undertaken by Dynacs Inc. commencing in June 2002 under contract from NASA YA-D6. Funding was provided through NASA's Ames Research Center (ARC), Code M/HQ, and Industrial Engineering and Safety (IES). The John F. Kennedy Space Center (KSC) Engineering Development Contract (EDC) Task Order was 5SMA768. The scope of the effort was to conduct a Human Factors Process Failure Modes and Effects Analysis (HF PFMEA) of a hazardous activity and provide recommendations to eliminate or reduce the effects of errors caused by human factors. The Liquid Oxygen (LOX) Pump Acceptance Test Procedure (ATP) was selected for this analysis. The HF PFMEA table (see appendix A) provides an analysis of six major categories evaluated for this study. These categories include Personnel Certification, Test Procedure Format, Test Procedure Safety Controls, Test Article Data, Instrumentation, and Voice Communication. For each specific requirement listed in appendix A, the following topics were addressed: Requirement, Potential Human Error, Performance-Shaping Factors, Potential Effects of the Error, Barriers and Controls, Risk Priority Numbers, and Recommended Actions. This report summarizes findings and gives recommendations as determined by the data contained in appendix A. It also includes a discussion of technology barriers and challenges to performing task analyses, as well as lessons learned. The HF PFMEA table in appendix A recommends the use of accepted and required safety criteria in order to reduce the risk of human error. The items with the highest risk priority numbers should receive the greatest amount of consideration. Implementation of the recommendations will result in a safer operation for all personnel.

  13. Quantitative risk analysis offshore-Human and organizational factors

    International Nuclear Information System (INIS)

    Espen Skogdalen, Jon; Vinnem, Jan Erik

    2011-01-01

    Quantitative Risk Analyses (QRAs) are one of the main tools for risk management within the Norwegian and UK oil and gas industry. Much criticism has been given to the limitations related to the QRA-models and that the QRAs do not include human and organizational factors (HOF-factors). Norway and UK offshore legislation and guidelines require that the HOF-factors are included in the QRAs. A study of 15 QRAs shows that the factors are to some extent included, and there are large differences between the QRAs. The QRAs are categorized into four levels according to the findings. Level 1 QRAs do not describe or comment on the HOF-factors at all. Relevant research projects have been conducted to fulfill the requirements of Level 3 analyses. At this level, there is a systematic collection of data related to HOF. The methods are systematic and documented, and the QRAs are adjusted. None of the QRAs fulfill the Level 4 requirements. Level 4 QRAs include the model and describe the HOF-factors as well as explain how the results should be followed up in the overall risk management. Safety audits by regulatory authorities are probably necessary to point out the direction for QRA and speed up the development.

  14. The advancement of a new human factors report--'The Unique Report'--facilitating flight crew auditing of performance/operations as part of an airline's safety management system.

    Science.gov (United States)

    Leva, M C; Cahill, J; Kay, A M; Losa, G; McDonald, N

    2010-02-01

    This paper presents the findings of research relating to the specification of a new human factors report, conducted as part of the work requirements for the Human Integration into the Lifecycle of Aviation Systems project, sponsored by the European Commission. Specifically, it describes the proposed concept for a unique report, which will form the basis for all operational and safety reports completed by flight crew. This includes all mandatory and optional reports. Critically, this form is central to the advancement of improved processes and technology tools, supporting airline performance management, safety management, organisational learning and knowledge integration/information-sharing activities. Specifically, this paper describes the background to the development of this reporting form, the logic and contents of this form and how reporting data will be made use of by airline personnel. This includes a description of the proposed intelligent planning process and the associated intelligent flight plan concept, which makes use of airline operational and safety analyses information. Primarily, this new reporting form has been developed in collaboration with a major Spanish airline. In addition, it has involved research with five other airlines. Overall, this has involved extensive field research, collaborative prototyping and evaluation of new reports/flight plan concepts and a number of evaluation activities. Participants have included both operational and management personnel, across different airline flight operations processes. Statement of Relevance: This paper presents the development of a reporting concept outlined through field research and collaborative prototyping within an airline. The resulting reporting function, embedded in the journey log compiled at the end of each flight, aims at enabling employees to audit the operations of the company they work for.

  15. Development of a safety decision-making scenario to measure worker safety in agriculture.

    Science.gov (United States)

    Mosher, G A; Keren, N; Freeman, S A; Hurburgh, C R

    2014-04-01

    Human factors play an important role in the management of occupational safety, especially in high-hazard workplaces such as commercial grain-handling facilities. Employee decision-making patterns represent an essential component of the safety system within a work environment. This research describes the process used to create a safety decision-making scenario to measure the process that grain-handling employees used to make choices in a safety-related work task. A sample of 160 employees completed safety decision-making simulations based on a hypothetical but realistic scenario in a grain-handling environment. Their choices and the information they used to make their choices were recorded. Although the employees emphasized safety information in their decision-making process, not all of their choices were safe choices. Factors influencing their choices are discussed, and implications for industry, management, and workers are shared.

  16. Factor Analysis and Framework Development for Incorporating Public Trust on Nuclear Safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seongkyung; Lee, Gyebong [The Myongji Univ., Seoul (Korea, Republic of); Lee, Gihyung; Lee, Gyehwi; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization in charge of nuclear safety in Korea, realized that a more fundamental and systematic analysis of activities is needed to actively meet the greater variety of concerns people have and increase the reliability of the results of regulation. Nuclear safety, a highly specialized field, has previously been discussed primarily from the viewpoint of the engineers who deal with the technology, but now 'public trust in nuclear safety' has to be viewed from the standpoint of the general public and from the socio-cultural perspective. Specific measures must be taken to examine which factors affect public trust and how we can secure and reproduce those factors to gain it. Also, an efficient system for incorporating public trust in nuclear safety must be established. In this study, various case studies were examined to identify the factors that affect public trust in nuclear safety. First, nuclear safety laws and information disclosure systems of major countries were examined by investigating data and conducting in-depth interviews. To explore a public framework concerning nuclear safety, big data of social media were analyzed. Also, Q methodology was used to analyze the risk schemata of the opinion leaders living in areas near nuclear power plants. Several surveys were conducted to analyze the amount of trust the public had in nuclear safety as well as their awareness of nuclear safety issues. Based on these analyses, factors affecting public trust in nuclear safety were extracted, and measures to build systems incorporating public trust in nuclear safety were proposed. This study addresses the public trust in nuclear safety on condition that the safety is ensured technically and mechanically.

  17. Factor Analysis and Framework Development for Incorporating Public Trust on Nuclear Safety issues

    International Nuclear Information System (INIS)

    Cho, Seongkyung; Lee, Gyebong; Lee, Gihyung; Lee, Gyehwi; Jeong, Jina

    2014-01-01

    The Korea Institute of Nuclear Safety (KINS), a regulatory expert organization in charge of nuclear safety in Korea, realized that a more fundamental and systematic analysis of activities is needed to actively meet the greater variety of concerns people have and increase the reliability of the results of regulation. Nuclear safety, a highly specialized field, has previously been discussed primarily from the viewpoint of the engineers who deal with the technology, but now 'public trust in nuclear safety' has to be viewed from the standpoint of the general public and from the socio-cultural perspective. Specific measures must be taken to examine which factors affect public trust and how we can secure and reproduce those factors to gain it. Also, an efficient system for incorporating public trust in nuclear safety must be established. In this study, various case studies were examined to identify the factors that affect public trust in nuclear safety. First, nuclear safety laws and information disclosure systems of major countries were examined by investigating data and conducting in-depth interviews. To explore a public framework concerning nuclear safety, big data of social media were analyzed. Also, Q methodology was used to analyze the risk schemata of the opinion leaders living in areas near nuclear power plants. Several surveys were conducted to analyze the amount of trust the public had in nuclear safety as well as their awareness of nuclear safety issues. Based on these analyses, factors affecting public trust in nuclear safety were extracted, and measures to build systems incorporating public trust in nuclear safety were proposed. This study addresses the public trust in nuclear safety on condition that the safety is ensured technically and mechanically

  18. Factors associated with the enactment of safety belt and motorcycle helmet laws.

    Science.gov (United States)

    Law, Teik Hua; Noland, Robert B; Evans, Andrew W

    2013-07-01

    It has been shown that road safety laws, such as motorcycle helmet and safety belt laws, have a significant effect in reducing road fatalities. Although an expanding body of literature has documented the effects of these laws on road safety, it remains unclear which factors influence the likelihood that these laws are enacted. This study attempts to identify the factors that influence the decision to enact safety belt and motorcycle helmet laws. Using panel data from 31 countries between 1963 and 2002, our results reveal that increased democracy, education level, per capita income, political stability, and more equitable income distribution within a country are associated with the enactment of road safety laws. © 2012 Society for Risk Analysis.

  19. Safety lessons from aviation.

    Science.gov (United States)

    Higton, Phil

    2005-07-01

    Thirty years ago the world of Commercial Aviation provided a challenging environment. In my early flying days, aircraft accidents were not unusual, flying was seen as a risky business and those who took part, either as a provider or passenger, appeared grudgingly willing to accept the hazards involved. A reduction in the level of risk was sought in technological advances, greater knowledge of physics and science, and access to higher levels of skill through simulation, practice and experience. While these measures did have an impact, the expected safety dividend was not realized. The most experienced, technically competent individuals with the best equipment featured far too regularly in the accident statistics. We had to look at the human element, the impact of flaws or characteristics of the human condition. We call this area Human Factors. My paper describes the concept of Human Factors, its establishment as a key safety tool in aviation and the impact of this on my working life.

  20. Experiences in the application of human factors engineering to human-system interface modernization

    International Nuclear Information System (INIS)

    Trueba Alonso, Pedro; Illobre, Luis Fernandez; Ortega Pascual, Fernando

    2014-01-01

    Almost all the existing Nuclear Power Plants (NPPs) include plans to modernize their existing Instrumentation and Control (I and C) systems and associated Human System Interfaces (HSIs), due to obsolescence problems. Tecnatom, S.A. has been participating in modernization programs in NPPs to help them to plan, specify, design and implement the modernization of control rooms and associated I and C and HSIs. The application of Human Factors Engineering (HFE) in modernization programs is nowadays unavoidable. This is because is becoming a regulatory requirement, and also because it is needed to ensure that any plant modification, involving the modernization of I and C and HSI, is well designed to improve overall plant operations, reliability, and safety. This paper shows some experiences obtained during the application of HFE to the modernization of these HSIs. The experience applying HFE in modernizations and design modifications show a positive effect, improving the associated HSIs, with the acceptability of the final user. (authors)

  1. Experiences in the application of human factors engineering to human-system interface modernization

    International Nuclear Information System (INIS)

    Trueba Alonso, Pedro; Fernandez Illobre, Luis; Ortega Pascual, Fernando

    2015-01-01

    Almost all the existing Nuclear Power Plants (NPPs) include plans to modernize their existing Instrumentation and Control (I and C) systems and associated Human System Interfaces (HSIs), due to obsolescence problems. Tecnatom, S.A. has been participating in modernization programs in NPPs to help them to plan, specify, design and implement the modernization of control rooms and associated I and C and HSIs. The application of Human Factors Engineering (HFE) in modernization programs is nowadays unavoidable. This is because is becoming a regulatory requirement, and also because it is needed to ensure that any plant modification, involving the modernization of I and C and HSI, is well designed to improve overall plant operations, reliability, and safety. This paper shows some experiences obtained during the application of HFE to the modernization of these HSIs. The experience applying HFE in modernizations and design modifications show a positive effect, improving the associated HSIs, with the acceptability of the final user.

  2. Experiences in the application of human factors engineering to human-system interface modernization

    Energy Technology Data Exchange (ETDEWEB)

    Trueba Alonso, Pedro; Fernandez Illobre, Luis; Ortega Pascual, Fernando [Tecnatom S.A., San Sebastian de los Reyes (Spain). Simulation and Control Rooms Div.

    2015-07-15

    Almost all the existing Nuclear Power Plants (NPPs) include plans to modernize their existing Instrumentation and Control (I and C) systems and associated Human System Interfaces (HSIs), due to obsolescence problems. Tecnatom, S.A. has been participating in modernization programs in NPPs to help them to plan, specify, design and implement the modernization of control rooms and associated I and C and HSIs. The application of Human Factors Engineering (HFE) in modernization programs is nowadays unavoidable. This is because is becoming a regulatory requirement, and also because it is needed to ensure that any plant modification, involving the modernization of I and C and HSI, is well designed to improve overall plant operations, reliability, and safety. This paper shows some experiences obtained during the application of HFE to the modernization of these HSIs. The experience applying HFE in modernizations and design modifications show a positive effect, improving the associated HSIs, with the acceptability of the final user.

  3. Human Factors Engineering in Designing the Passengers' Cockpit of the Malaysian Commercial Suborbital Spaceplane

    Science.gov (United States)

    Ridzuan Zakaria, Norul; Mettauer, Adrian; Abu, Jalaluddin; Hassan, Mohd Roshdi; Ismail, Anwar Taufeek; Othman, Jamaluddin; Shaari, Che Zhuhaida; Nasron, Nasri

    2010-09-01

    The design of the passengers’ cabin or cockpit of commercial suborbital spaceplane is a new and exciting frontier in human factors engineering, which emphasizes on comfort and safety. There is a program to develop small piloted 3 seats commercial suborbital spaceplane by a group of Malaysians with their foreign partners, and being relatively small and due to its design philosophy, the spaceplane does not require a cabin, but only a cockpit for its 2 passengers. In designing the cockpit, human factors engineering and safety principles are given priority. The cockpit is designed with the intention to provide comfort and satisfaction to the passengers without compromising the safety, in such a way that there are passenger-view wide angled video camera to observe the passengers at all time in flight, “rear-view”, “under-the-floor-view” and “fuselage-view” video cameras for the passengers, personalized gauges and LCDs on the dashboard to provide vital and useful information during the flight to the passengers, and biomedical engineered products which not only entertain the passengers, but also provide important information on the passengers to the ground crews who are responsible in the comfort and safety of the passengers. The passenger-view video-camera, which record the passengers with Earth visible through the glass canopy as the background, not only provides live visual of the passengers for safety reason, but also provide the most preferred memorable video collection for the passengers, while other video cameras provide the opportunity to view at various angles from unique positions to both the passengers and the ground observers. The gauges and LCDs on the dashboard provide access to the passengers to information such as the gravity, orientation, rate of climb and flight profile of the spaceplane, graphical presentation of the spaceplane in flight, and live video from the onboard video cameras. There is also a control stick for each passenger to

  4. National Nuclear Safety Department Experience of Supervision over Safety Culture of BNPP-1

    International Nuclear Information System (INIS)

    Sepanloo, K.; Ardeshir, A.T.

    2016-01-01

    The analysis of the past major NPPs accidents, TMI, Chernobyl and Fukushima Daiichi shows that causes of these accidents can be explained by a complex combination of human, technological and organizational factors. One of the findings of accident investigations and risk assessments is the growing recognition of the impact of cultural context of work practices on safety. The assumed link between culture and safety, epitomized through the concept of safety culture, has been the subject of extensive research in recent years. The term “safety culture” was first introduced into the nuclear industry by the IAEA in INSAG-1 to underline the role and importance of the organizational factors. The objective of this paper is to conduct an assessment of some safety culture indicators of Bushehr Nuclear Power Plant (BNPP-1).

  5. A Study on the Holding Capacity Safety Factors for Torpedo Anchors

    Directory of Open Access Journals (Sweden)

    Luís V. S. Sagrilo

    2012-01-01

    Full Text Available The use of powerful numerical tools based on the finite-element method has been improving the prediction of the holding capacity of fixed anchors employed by the offshore oil industry. One of the main achievements of these tools is the reduction of the uncertainty related to the holding capacity calculation of these anchors. Therefore, it is also possible to reduce the values of the associated design safety factors, which have been calibrated relying on models with higher uncertainty, without impairing the original level of structural safety. This paper presents a study on the calibration of reliability-based safety factors for the design of torpedo anchors considering the statistical model uncertainty evaluated using results from experimental tests and their correspondent finite-element-based numerical predictions. Both working stress design (WSD and load and resistance factors design (LRFD design methodologies are investigated. Considering the WSD design methodology, the single safety is considerably lower than the value typically employed in the design of torpedo anchors. Moreover, a LRFD design code format for torpedo anchors is more appropriate since it leads to designs having less-scattered safety levels around the target value.

  6. Human-centred radiological software techniques supporting improved nuclear safety

    International Nuclear Information System (INIS)

    Szoeke, Istvan; Johnsen, Terje

    2013-01-01

    The Institute for Energy Technology (IFE) is an international research foundation for energy and nuclear technology. IFE is also the host for the international OECD Halden Reactor Project. The Software Engineering Department in the Man Technology Organisation at IFE is a leading international centre of competence for the development and evaluation of human-centred technologies, process visualisation, and the lifecycle of high integrity software important to safety. This paper is an attempt to give a general overview of the current, and some of the foreseen, research and development of human-centred radiological software technologies at the Software Engineering department to meet with the need of improved radiological safety for not only nuclear industry but also other industries around the world. (author)

  7. Occuptional Health and Safety and Employer Motivation

    DEFF Research Database (Denmark)

    Jensen, Per Langå

    2004-01-01

    It is often argued and supported by a number of case studies that investment in human factors and occupational health and safety can pay. But any employer has a number of possible in-vestments, and many of these may have a larger marginal utility than health and safety. In addition it is often...... difficult to calculate the exact pay off for human factors and health and safety – how to calculate higher motivation for instance. The economic benefit as a possible driving force for improvement of occupational health and safety is likely to exist but it must be considered a relatively weak force. Another...... important driving force for improvements in health and safety. No employer likes to be ‘branded’ as immoral, manifested in fines by the labour inspectors or media attention to an unsafe conduct. Strategies to im-prove health and safety therefore need to focus on the legitimacy as the probably strongest...

  8. Occupational Health and Safety and Employer Motivation

    DEFF Research Database (Denmark)

    Hasle, Peter; Jensen, Per Langå

    2004-01-01

    It is often argued and supported by a number of case studies that investment in human factors and occupational health and safety can pay. But any employer has a number of possible in-vestments, and many of these may have a larger marginal utility than health and safety. In addition it is often...... difficult to calculate the exact pay off for human factors and health and safety – how to calculate higher motivation for instance. The economic benefit as a possible driving force for improvement of occupational health and safety is likely to exist but it must be considered a relatively weak force. Another...... important driving force for improvements in health and safety. No employer likes to be ‘branded’ as immoral, manifested in fines by the labour inspectors or media attention to an unsafe conduct. Strategies to im-prove health and safety therefore need to focus on the legitimacy as the probably strongest...

  9. Assessment of Human Performance and Safety Culture at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Toth, Janos; Hadnagy, Lajos

    2002-01-01

    Evaluation of human performance and safety culture of the personnel at a Nuclear Power Plant is a very important element of the self assessment process. At the Paks NPP a systematic approach to this problem started in the early 90's. The first comprehensive analysis of the human performance of the personnel was performed by the Hungarian Research Institute for Electric Power (VEIKI). The analysis of human failures is also a part of the investigation and analysis of safety related reported events. This human performance analysis of events is carried out by the Laboratory of Psychology of the plant and a supporting organisation namely the Department of Ergonomics and Psychology of the Budapest University of Technical and Economical Sciences. The analysis of safety culture at the Paks NPP has been in the focus of attention since the implementation of the INSAG-4 document started world-wide. In 1993 an IAEA model project namely 'Strengthening Training for Operational Safety' was initiated with a sub-project called 'Enhancement of Safety Culture'. Within this project the first step was the initial assessment of the safety culture level at the Paks NPP. It was followed by some corrective actions and safety culture improvement programme. In 1999 the second assessment was performed in order to evaluate the progress as a result of the improvement programme. A few indicators reflecting the elements of safety culture were defined and compared. The assessment of the safety culture with a survey among the managers was performed in September 2000 and the results are being evaluated at the moment. The intention of the plant management is to repeat the assessment every 2-3 years and evaluate the trend of the indicator. (authors)

  10. Critical human-factors issues in nuclear-power regulation and a recommended comprehensive human-factors long-range plan. Executive summary

    International Nuclear Information System (INIS)

    Hopkins, C.O.; Snyder, H.L.; Price, H.E.; Hornick, R.J.; Mackie, R.R.; Smillie, R.J.; Sugarman, R.C.

    1982-08-01

    This comprehensive long-range human factors plan for nuclear reactor regulation was developed by a Study Group of the Human Factors Society, Inc. This Study Group was selected by the Executive Council of the Society to provide a balanced, experienced human factors perspective to the applications of human factors scientific and engineering knowledge to nuclear power generation. The report is presented in three volumes. Volume 1 contains an Executive Summary of the 18-month effort and its conclusions. Volume 2 summarizes all known nuclear-related human factors activities, evaluates these activities wherever adequate information is available, and describes the recommended long-range (10-year) plan for human factors in regulation. Volume 3 elaborates upon each of the human factors issues and areas of recommended human factors involvement contained in the plan, and discusses the logic that led to the recommendations

  11. Patient safety in the operating room: an intervention study on latent risk factors

    Directory of Open Access Journals (Sweden)

    van Beuzekom Martie

    2012-06-01

    Full Text Available Abstract Background Patient safety is one of the greatest challenges in healthcare. In the operating room errors are frequent and often consequential. This article describes an approach to a successful implementation of a patient safety program in the operating room, focussing on latent risk factors that influence patient safety. We performed an intervention to improve these latent risk factors (LRFs and increase awareness of patient safety issues amongst OR staff. Methods Latent risk factors were studied using a validated questionnaire applied to the OR staff before and after an intervention. A pre-test/post-test control group design with repeated measures was used to evaluate the effects of the interventions. The staff from one operating room of an university hospital acted as the intervention group. Controls consisted of the staff of the operating room in another university hospital. The outcomes were the changes in LRF scores, perceived incident rate, and changes in incident reports between pre- and post-intervention. Results Based on pre-test scores and participants’ key concerns about organizational factors affecting patient safety in their department the intervention focused on the following LRFs: Material Resources, Training and Staffing Recourses. After the intervention, the intervention operating room - compared to the control operating room - reported significantly fewer problems on Material Resources and Staffing Resources and a significantly lower score on perceived incident rate. The contribution of technical factors to incident causation decreased significantly in the intervention group after the intervention. Conclusion The change of state of latent risk factors can be measured using a patient safety questionnaire aimed at these factors. The change of the relevant risk factors (Material and Staffing resources concurred with a decrease in perceived and reported incident rates in the relevant categories. We conclude that

  12. Consensus achievement of leadership, organisational and individual factors that influence safety climate: Implications for nursing management.

    Science.gov (United States)

    Fischer, Shelly A; Jones, Jacqueline; Verran, Joyce A

    2018-01-01

    To validate a framework of factors that influence the relationship of transformational leadership and safety climate, and to enable testing of safety chain factors by generating hypotheses regarding their mediating and moderating effects. Understanding the patient safety chain and mechanisms by which leaders affect a strong climate of safety is essential to transformational leadership practice, education, and research. A systematic review of leadership and safety literature was used to develop an organising framework of factors proposed to influence the climate of safety. A panel of 25 international experts in leadership and safety engaged a three-round modified Delphi study with Likert-scored surveys. Eighty per cent of participating experts from six countries were retained to the final survey round. Consensus (>66% agreement) was achieved on 40 factors believed to influence safety climate in the acute care setting. Consensus regarding specific factors that play important roles in an organisation's climate of safety can be reached. Generally, the demonstration of leadership commitment to safety is key to cultivating a culture of patient safety. Transformational nurse leaders should consider and employ all three categories of factors in daily leadership activities and decision-making to drive a strong climate of patient safety. © 2017 John Wiley & Sons Ltd.

  13. The Challenges of Safety Culture: No more risk!

    Directory of Open Access Journals (Sweden)

    Julija Melnikova

    2016-12-01

    Full Text Available According to A. Maslow’s [1] hierarchy of human needs the need for safety and security is a priority for mankind. The concept ‘safety culture’ appeared only in 1986, when theChernobyldisaster made the whole world muse upon human relationship with technology [2]. This global catastrophe was a caution, but not for everyone. Potent academic systems and elaborated instruments of a huge economical value have been invoked in maintaining the satisfaction of biogenetic needs, whereas any manual on safety topic has not been issued yet. Even such progressive communities as the European Union, elaborating long-term strategic decisions, do not find clear and reasonable principles that would encourage to choose safe technologies with respect to present and future generations. Giving way to the ostensible effectiveness of centralized technologies such as equipment, communication, energetic that are well-disposed to big business, the majority of politicians and even scientists are not able to estimate the risk that is programmed in the choice of dangerous and insecure technical decisions. It is not still realized that none of the technologies is worth a human life or safety.The level of social maturity is a factor stipulating the merge of two concepts ‘safety’ and „a person“. At the time when industrial priorities were dominant the concept ‘safety techniques’ had been used putting stress on peculiarities of working with technical devices and on the ways manpower could be adjusted to them. Later the term ‘Safety of labour’ appeared. It drew attention to the labour process and its peculiarities. The assimilation of European culture has determined the introduction of the notion ‘personnel safety and health’ to labour relations. The postindustrial stage of humanity development brings the new understanding of major values. Individual is now identified as a personality as well as human life is understood as the major value. The natural

  14. Effects of the safety factor on ion temperature gradient modes

    International Nuclear Information System (INIS)

    Wang, A.K.; Dong, J.Q.; Sanuki, H.; Itoh, K.

    2003-01-01

    A model for the ion temperature gradient (ITG) driven instability is derived from Braginskii magnetohydrodynamic equations of ions. The safety factor q in a toroidal plasma is introduced into the model through the current density J parallel . The effects of q or J parallel on both the ITG instability in k perpendicular and k parallel spectra and the critical stability thresholds are studied. It is shown that the current density // J or the safety factor q plays an important role in stabilizing the ITG instability. (author)

  15. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Swain, A.D.

    1981-01-01

    This report describes some of the human factors problems in nuclear power plants and the technology that can be employed to reduce those problems. Many of the changes to improve the human factors in existing plants are inexpensive, and the expected gain in human reliability is substantial. The human factors technology is well-established and there are practitioners in most countries that have nuclear power plants. (orig.) [de

  16. 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

  17. Safety climate in university and college laboratories: impact of organizational and individual factors.

    Science.gov (United States)

    Wu, Tsung-Chih; Liu, Chi-Wei; Lu, Mu-Chen

    2007-01-01

    Universities and colleges serve to be institutions of education excellence; however, problems in the areas of occupational safety may undermine such goals. Occupational safety must be the concern of every employee in the organization, regardless of job position. Safety climate surveys have been suggested as important tools for measuring the effectiveness and improvement direction of safety programs. Thus, this study aims to investigate the influence of organizational and individual factors on safety climate in university and college laboratories. Employees at 100 universities and colleges in Taiwan were mailed a self-administered questionnaire survey; the response rate was 78%. Multivariate analysis of variance revealed that organizational category of ownership, the presence of a safety manager and safety committee, gender, age, title, accident experience, and safety training significantly affected the climate. Among them, accident experience and safety training affected the climate with practical significance. The authors recommend that managers should address important factors affecting safety issues and then create a positive climate by enforcing continuous improvements.

  18. Evaluating Models of Human Performance: Safety-Critical Systems Applications

    Science.gov (United States)

    Feary, Michael S.

    2012-01-01

    This presentation is part of panel discussion on Evaluating Models of Human Performance. The purpose of this panel is to discuss the increasing use of models in the world today and specifically focus on how to describe and evaluate models of human performance. My presentation will focus on discussions of generating distributions of performance, and the evaluation of different strategies for humans performing tasks with mixed initiative (Human-Automation) systems. I will also discuss issues with how to provide Human Performance modeling data to support decisions on acceptability and tradeoffs in the design of safety critical systems. I will conclude with challenges for the future.

  19. Nuclear safety: an international approach: the convention on nuclear safety

    International Nuclear Information System (INIS)

    Rosen, M.

    1994-01-01

    This paper is a general presentation of the IAEA Convention on Nuclear Safety which has already be signed by 50 countries and which is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The paper gives a review of its development and some key provisions for a better understanding of how this agreement will operate in practice. The Convention consists of an introductory preamble and four chapters consisting of 35 articles dealing with: the principal objectives, definitions and scope of application; the various obligations (general provisions, legislation, responsibility and regulation, general safety considerations taking into account: the financial and human resources, the human factors, the quality assurance, the assessment and verification of safety, the radiation protection and the emergency preparedness; the safety of installations: sitting, design and construction, operation); the periodic meetings of the contracting parties to review national reports on the measures taken to implement each of the obligations, and the final clauses and other judicial provisions common to international agreements. (J.S.). 1 append

  20. Human factors in nuclear power plants

    International Nuclear Information System (INIS)

    Pack, R.W.

    1978-01-01

    The Electric Power Research Institute has started research in human factors in nuclear power plants. One project, completed in March 1977, reviewed human factors problems in operating power plants and produced a report evaluating those problems. A second project developed computer programs for evaluating operator performance on training simulators. A third project is developing and evaluating control-room design approaches. A fourth project is reviewing human factors problems associated with power-plant maintainability and instrumentation and control technician activities. 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 Electric Power Research Institute (EPRI) has undertaken four projects studying the application of human factors engineering principles to nuclear power plants. (author)

  1. Patient safety

    African Journals Online (AJOL)

    Page 1 .... BMJ 2012;344:e832. Table 2. Unsafe medical care. Structural factors. Organisational determinants. Structural accountability (accreditation and regulation). Safety culture. Training, education and human resources. Stress and fatigue .... for routine take-off and landing, yet doctors feel that it is demeaning to do so?

  2. Classification analysis of organization factors related to system safety

    International Nuclear Information System (INIS)

    Liu Huizhen; Zhang Li; Zhang Yuling; Guan Shihua

    2009-01-01

    This paper analyzes the different types of organization factors which influence the system safety. The organization factor can be divided into the interior organization factor and exterior organization factor. The latter includes the factors of political, economical, technical, law, social culture and geographical, and the relationships among different interest groups. The former includes organization culture, communication, decision, training, process, supervision and management and organization structure. This paper focuses on the description of the organization factors. The classification analysis of the organization factors is the early work of quantitative analysis. (authors)

  3. Human reliability guidance - How to increase the synergies between human reliability, human factors, and system design and engineering. Phase 1: The Nordic Point of View - A user needs analysis

    International Nuclear Information System (INIS)

    Oxstrand, J.; Boring, R.L.

    2010-12-01

    The main goal of this Nordic Nuclear Safety Research (NKS) council project is to produce guidance for how to use human reliability analysis (HRA) to strengthen overall safety. This project is intended to work across (and hopefully diminish) the borders that exist between human reliability analysis (HRA) and human-system interaction, human performance, human factors, and probabilistic risk assessment at Nordic nuclear power plants. This project consists of two major phases, where the initial phase (phase 1) is a study of current practices in the Nordic region, which is presented in this report. Even though the project covers the synergies between HRA and all other relevant fields, the main focus for the phase is to bridge HRA and design. Interviews with 26 Swedish and Finnish plant experts are summarized the present report, and 10 principles to improve the utilization of HRA at plants are presented. A second study, which is not documented in this preliminary report, will chronicle insights into how the US nuclear industry works with HRA. To gain this knowledge the author will conduct interviews with the US regulator, research laboratories, and utilities. (Author)

  4. Nuclear Safety. 1997

    International Nuclear Information System (INIS)

    1998-01-01

    A quick review of the nuclear safety at EDF may be summarized as follows: - the nuclear safety at EDF maintains at a rather good standard; - none of the incidents that took place has had any direct impact upon safety; - the availability remained good; - initiation of the floor 4 reactor generation (N4 unit - 1450 MW) ensued without major difficulties (the Civaux 1 NPP has been coupled to the power network at 24 december 1997); - the analysis of the incidents interesting from the safety point of view presents many similarities with earlier ones. Significant progress has been recorded in promoting actively and directly a safe operation by making visible, evident and concrete the exertion of the nuclear operation responsibility and its control by the hierarchy. The report develops the following chapters and subjects: 1. An overview on 1997; 1.1. The technical issues of the nuclear sector; 1.2. General performances in safety; 1.3. The main incidents; 1.4. Wastes and radiation protection; 2. Nuclear safety management; 2.1. Dynamics and results; 2.2. Ameliorations to be consolidated; 3. Other important issues in safety; 3.1. Probabilistic safety studies; 3.2. Approach for safety re-evaluation; 3.3. The network safety; 3.4. Crisis management; 3.5. The Lifetime program; 3.6. PWR; 3.7. Documentation; 3.8. Competence; 4. Safety management in the future; 4.1. An open future; 4.2. The fast neutron NPP at Creys-Malville; 4.3. Stabilization of the PWR reference frame; 4.4. Implementing the EURATOM directive regarding the radiation protection standards; 4.5. Development of biomedical research and epidemiological studies; 4.6. New regulations concerning the liquid and gaseous effluents; 5. Visions of an open future; 5.1. Alternative views upon safety ay EDF; 5.2. Safety authority; 5.3. International considerations; 5.4. What happens abroad; 5.5. References from non-nuclear domain. Four appendices are added referring to policy of safety management, policy of human factors in NPPs

  5. Mathematical models for prediction of safety factors for a simply ...

    African Journals Online (AJOL)

    From the results obtained, mathematical prediction models were developed using a least square regression analysis for bending, shear and deflection modes of failure considered in the study. The results showed that the safety factors for material, dead and live load are not unique, but they are influenced by safety index ...

  6. Seeking a safety culture

    International Nuclear Information System (INIS)

    Lee, T.

    1993-01-01

    Human organisational failure has been shown to play a significant role in major accidents world-wide in both the nuclear and non-nuclear industries. A recent report called Organising for Safety, published by The Health and Safety Commission, suggests that the nuclear industry should give organisational factors the same emphasis as it does the reduction of equipment failures and individual error. (Author)

  7. A Randomized Case-Controlled Study of Recombinant Human Granulocyte Colony Stimulating Factor for the Treatment of Sepsis in Preterm Neutropenic Infants

    OpenAIRE

    Aktaş, Doğukan; Demirel, Bilge; Gürsoy, Tuğba; Ovalı, Fahri

    2015-01-01

    To investigate the efficacy and safety of recombinant human granulocyte colony-stimulating factor, recombinant human granulocyte-macrophage colony-stimulating factor (rhG-CSF) to treat sepsis in neutropenic preterm infants. Methods: Fifty-six neutropenic preterm infants with suspected or culture-proven sepsis hospitalized in Zeynep Kamil Maternity and Children's Educational and Training Hospital, Kozyatağı/Istanbul, Turkey between January 2008 and January 2010 were enrolled. Patients were ...

  8. MMOSA – A new approach of the human and organizational factor analysis in PSA

    International Nuclear Information System (INIS)

    Farcasiu, M.; Prisecaru, I.

    2014-01-01

    The results of many Probabilistic Safety Assessment (PSA) studies show a very significant contribution of human errors to nuclear installations failure. This paper is intended to analyze both the human performance importance in PSA studies and the elements that influence it. Starting from Man–Machine–Organization System (MMOS) concept a new approach (MMOSA) was developed to allow an explicit incorporation of the human and organizational factor in PSA studies. This method uses old techniques from Human Reliability Analysis (HRA) methods (THERP, SPAR-H) and new techniques to analyze human performance. The main novelty included in MMOSA is the identification of the machine–organization interfaces (maintenance, modification and aging management plan and state of man–machine interface) and the human performance evaluation based on them. A detailed result of the Human Performance Analysis (HPA) using the MMOSA methodology can identify any serious deficiencies of human performance which can usually be corrected through the improvement of the related MMOS interfaces. - Highlights: • MMOSA allows the incorporation of the human and organizational factor in PSA. • The method uses old techniques and new techniques to analyze human performance. • The main novelty is the identification of the machine–organization interfaces. • The MMOSA methodology identifies any serious deficiencies which can be corrected

  9. Industrial hazard and safety handbook

    CERN Document Server

    King, Ralph W

    1979-01-01

    Industrial Hazard and Safety Handbook (Revised Impression) describes and exposes the main hazards found in industry, with emphasis on how these hazards arise, are ignored, are identified, are eliminated, or are controlled. These hazard conditions can be due to human stresses (for example, insomnia), unsatisfactory working environments, as well as secret industrial processes. The book reviews the cost of accidents, human factors, inspections, insurance, legal aspects, planning for major emergencies, organization, and safety measures. The text discusses regulations, codes of practice, site layou

  10. Specifications for human factors guiding documents

    Energy Technology Data Exchange (ETDEWEB)

    Rhodes, W; Szlapetis, I; MacGregor, C [Rhodes and Associates Inc., Toronto, ON (Canada)

    1995-04-01

    This report specifies the content, function and appearance of three proposed human factors guiding documents to be used by the Atomic Energy Control board and its licensees. These three guiding documents, to be developed at a later date, are: (a) Human Factors Process Guide; (b) Human Factors Activities Guide; and (c) Human Factors Design Integration Guide. The specifications were developed by examining the best documents as identified in a previous contract with the AECB (Review of Human Factors Guidelines and Methods by W. Rhodes, I. Szlapetis et al. 1992), and a brief literature review. The best features and content were selected from existing documents and used to develop specifications for the guiding documents. The developer of the actual guides would use these specifications to produce comprehensive and consolidated documents at a later date. (author). 128 ref., 7 figs.

  11. Specifications for human factors guiding documents

    International Nuclear Information System (INIS)

    Rhodes, W.; Szlapetis, I.; MacGregor, C.

    1995-04-01

    This report specifies the content, function and appearance of three proposed human factors guiding documents to be used by the Atomic Energy Control board and its licensees. These three guiding documents, to be developed at a later date, are: (a) Human Factors Process Guide; (b) Human Factors Activities Guide; and (c) Human Factors Design Integration Guide. The specifications were developed by examining the best documents as identified in a previous contract with the AECB (Review of Human Factors Guidelines and Methods by W. Rhodes, I. Szlapetis et al. 1992), and a brief literature review. The best features and content were selected from existing documents and used to develop specifications for the guiding documents. The developer of the actual guides would use these specifications to produce comprehensive and consolidated documents at a later date. (author). 128 ref., 7 figs

  12. A Study on the Allowable Safety Factor of Cut-Slopes for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Soo; Yee, Eric [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    In this study, the issues of allowable safety factor design criteria for cut-slopes in nuclear facilities is derived through case analysis, a proposed construction work slope design criteria that provides relatively detailed conditions can be applied in case of the dry season and some unclear parts of slope design criteria be modified in case of the rainy season. This safety factor can be further subdivided into two; normal and earthquake factors, a factor of 1.5 is applied for normal conditions and a factor of 1.2 is applied for seismic conditions. This safety factor takes into consideration the effect of ground water and rainfall conditions. However, no criteria for the case of cut-slope in nuclear facilities and its response to seismic conditions is clearly defined, this can cause uncertainty in design. Therefore, this paper investigates the allowable safety factor for cut-slopes in nuclear facilities, reviews conditions of both local and international cut-slope models and finally suggests an alternative method of analysis. It is expected that the new design criteria adequately ensures the stability of the cut-slope to reflect clear conditions for both the supervising and design engineers.

  13. Safety of human papillomavirus vaccines: a review.

    Science.gov (United States)

    Stillo, Michela; Carrillo Santisteve, Paloma; Lopalco, Pier Luigi

    2015-05-01

    Between 2006 and 2009, two different human papillomavirus virus (HPV) vaccines were licensed for use: a quadrivalent (qHPVv) and a bivalent (bHPVv) vaccine. Since 2008, HPV vaccination programmes have been implemented in the majority of the industrialized countries. Since 2013, HPV vaccination has been part of the national programs of 66 countries including almost all countries in North America and Western Europe. Despite all the efforts made by individual countries, coverage rates are lower than expected. Vaccine safety represents one of the main concerns associated with the lack of acceptance of HPV vaccination both in the European Union/European Economic Area and elsewhere. Safety data published on bivalent and quadrivalent HPV vaccines, both in pre-licensure and post-licensure phase, are reviewed. Based on the latest scientific evidence, both HPV vaccines seem to be safe. Nevertheless, public concern and rumors about adverse events (AE) represent an important barrier to overcome in order to increase vaccine coverage. Passive surveillance of AEs is an important tool for detecting safety signals, but it should be complemented by activities aimed at assessing the real cause of all suspect AEs. Improved vaccine safety surveillance is the first step for effective communication based on scientific evidence.

  14. Development of safety factors to be used for evaluation of cracked nuclear components

    International Nuclear Information System (INIS)

    Brickstad, B.; Bergman, M.

    1996-10-01

    A modified concept for safety evaluation is introduced which separately accounts for the failure mechanisms fracture and plastic collapse. For application on nuclear components a set of safety factors are also proposed that retain the safety margins expressed in ASME, section III and XI. By performing comparative studies of the acceptance levels for surface cracks in pipes and a pressure vessel, it is shown that some of the anomalies connected with the old safety procedures are removed. It is the authors belief that the outlined safety evaluation procedure has the capability of treating cracks in a consistent way and that the procedure together with the proposed safety factors fulfill the basic safety requirements for nuclear components. Hopefully, it is possible in the near future to develop a probabilistic safety assessment procedure in Sweden, which enables a systematic treatment of uncertainties in the involved data. 14 refs

  15. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  16. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  17. In vivo recovery and safety of human factor VIII product AAFACT in patients with haemophilia A

    NARCIS (Netherlands)

    Vossebeld, P. J. M.; Tissing, M. H.; van den Berg, H. M.; Leebeek, F. W. G.; de Goede-Bolder, A.; Novakova, I. R. O.; Gerrits, W. B. J.; Peters, M.; Koopman, M. M. W.; Faber, A.; Hiemstra, H.; Grob, P.; Strengers, P. F. W.

    2003-01-01

    AAFACT, a monoclonal purified, solvent/detergent treated human plasma-derived coagulation factor VIII concentrate obtained from plasma of voluntary, non-remunerated blood donors, is manufactured and marketed in the Netherlands by Sanquin Plasma Products since 1995. In a postmarketing surveillance

  18. Functionality of road safety devices – identification and analysis of factors

    Directory of Open Access Journals (Sweden)

    Jeliński Łukasz

    2017-01-01

    Full Text Available Road safety devices are designed to protect road users from the risk of injury or death. The principal type of restraint is the safety barrier. Deployed on sites with the highest risk of run-off-road accidents, safety barriers are mostly found on bridges, flyovers, central reservations, and on road edges which have fixed obstacles next to them. If properly designed and installed, safety barriers just as other road safety devices, should meet a number of functional features. This report analyses factors which may deteriorate functionality, ways to prevent this from happening and the thresholds for loss of road safety device functionality.

  19. Resilience Safety Culture in Aviation Organisations

    OpenAIRE

    Akselsson, R.; Koornneef, F.; Stewart, S.; Ward, M.

    2009-01-01

    Chapter 2: Resilience Safety Culture in Aviation Organisations The European Commission HILAS project (Human Integration into the Lifecycle of Aviation Systems - a project supported by the European Commission’s 6th Framework between 2005-2009) was focused on using human factors knowledge and methodology to address key challenges for aviation (current and future) including a performance based approach for safety and fatigue management in the aviation sector, mainly inflight operations and maint...

  20. Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

    International Nuclear Information System (INIS)

    Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

    2001-01-01

    In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

  1. Fifty years of driving safety research.

    Science.gov (United States)

    Lee, John D

    2008-06-01

    This brief review covers the 50 years of driving-related research published in Human Factors, its contribution to driving safety, and emerging challenges. Many factors affect driving safety, making it difficult to assess the impact of specific factors such as driver age, cell phone distractions, or collision warnings. The author considers the research themes associated with the approximately 270 articles on driving published in Human Factors in the past 50 years. To a large extent, current and past research has explored similar themes and concepts. Many articles published in the first 25 years focused on issues such as driver impairment, individual differences, and perceptual limits. Articles published in the past 25 years address similar issues but also point toward vehicle technology that can exacerbate or mitigate the negative effect of these issues. Conceptual and computational models have played an important role in this research. Improved crash-worthiness has contributed to substantial improvements in driving safety over the past 50 years, but future improvements will depend on enhancing driver performance and perhaps, more important, improving driver behavior. Developing models to guide this research will become more challenging as new technology enters the vehicle and shifts the focus from driver performance to driver behavior. Over the past 50 years, Human Factors has accumulated a large base of driving-related research that remains relevant for many of today's design and policy concerns.

  2. 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)

  3. 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)

  4. Human factors in surgery: from Three Mile Island to the operating room.

    Science.gov (United States)

    D'Addessi, Alessandro; Bongiovanni, Luca; Volpe, Andrea; Pinto, Francesco; Bassi, PierFrancesco

    2009-01-01

    Human factors is a definition that includes the science of understanding the properties of human capability, the application of this understanding to the design and development of systems and services, the art of ensuring their successful applications to a program. The field of human factors traces its origins to the Second World War, but Three Mile Island has been the best example of how groups of people react and make decisions under stress: this nuclear accident was exacerbated by wrong decisions made because the operators were overwhelmed with irrelevant, misleading or incorrect information. Errors and their nature are the same in all human activities. The predisposition for error is so intrinsic to human nature that scientifically it is best considered as inherently biologic. The causes of error in medical care may not be easily generalized. Surgery differs in important ways: most errors occur in the operating room and are technical in nature. Commonly, surgical error has been thought of as the consequence of lack of skill or ability, and is the result of thoughtless actions. Moreover the 'operating theatre' has a unique set of team dynamics: professionals from multiple disciplines are required to work in a closely coordinated fashion. This complex environment provides multiple opportunities for unclear communication, clashing motivations, errors arising not from technical incompetence but from poor interpersonal skills. Surgeons have to work closely with human factors specialists in future studies. By improving processes already in place in many operating rooms, safety will be enhanced and quality increased.

  5. In-vehicle human factors for integrated multi-function systems: Making ITS user-friendly

    Energy Technology Data Exchange (ETDEWEB)

    Spelt, P.F.; Scott, S.

    1998-04-01

    As more and more Intelligent Transportation System in-vehicle equipment enters the general consumer market, the authors are about to find out how different design engineers are from ordinary drivers. Driver information systems are being developed and installed in vehicles at an ever-increasing rate. These systems provide information on diverse topics of concern and convenience to the driver, such as routing and navigation, emergency and collision warnings, and a variety of motorists services, or yellow pages functions. Most of these systems are being developed and installed in isolation from each other, with separate means of gathering the information and of displaying it to the driver. The current lack of coordination among on-board systems threatens to create a situation in which different messages on separate displays will be competing with each other for the drivers attention. Urgent messages may go unnoticed, and the number of messages may distract the driver from the most critical task of controlling the vehicle. Thus, without good human factors design and engineering for integrating multiple systems in the vehicle, consumers may find ITS systems confusing and frustrating to use. The current state of the art in human factors research and design for in-vehicle systems has a number of fundamental gaps. Some of these gaps were identified during the Intelligent Vehicle Initiative Human Factors Technology Workshop, sponsored by the US Department of Transportation, in Troy, Michigan, December 10--11, 1997. One task for workshop participants was to identify needed research areas or topics relating to in-vehicle human factors. The top ten unmet research needs from this workshop are presented. Many of these gaps in human factors research knowledge indicate the need for standardization in the functioning of interfaces for safety-related devices such as collision avoidance systems (CAS) and adaptive cruise controls (ACC). Such standards and guidelines will serve to make

  6. A soft-contact model for computing safety margins in human prehension.

    Science.gov (United States)

    Singh, Tarkeshwar; Ambike, Satyajit

    2017-10-01

    The soft human digit tip forms contact with grasped objects over a finite area and applies a moment about an axis normal to the area. These moments are important for ensuring stability during precision grasping. However, the contribution of these moments to grasp stability is rarely investigated in prehension studies. The more popular hard-contact model assumes that the digits exert a force vector but no free moment on the grasped object. Many sensorimotor studies use this model and show that humans estimate friction coefficients to scale the normal force to grasp objects stably, i.e. the smoother the surface, the tighter the grasp. The difference between the applied normal force and the minimal normal force needed to prevent slipping is called safety margin and this index is widely used as a measure of grasp planning. Here, we define and quantify safety margin using a more realistic contact model that allows digits to apply both forces and moments. Specifically, we adapt a soft-contact model from robotics and demonstrate that the safety margin thus computed is a more accurate and robust index of grasp planning than its hard-contact variant. Previously, we have used the soft-contact model to propose two indices of grasp planning that show how humans account for the shape and inertial properties of an object. A soft-contact based safety margin offers complementary insights by quantifying how humans may account for surface properties of the object and skin tissue during grasp planning and execution. Copyright © 2017 Elsevier B.V. All rights reserved.

  7. Development of a quantitative safety assessment method for nuclear I and C systems including human operators

    International Nuclear Information System (INIS)

    Kim, Man Cheol

    2004-02-01

    propose a new method for the quantitative safety assessment of the integrated system which consists of I and C systems, MMI and human operators. The proposed method is developed in the framework of Bayesian networks, and describes the information flow from a nuclear power plant to I and C systems and human operators, and the flow of control signals back to the nuclear power plant. The proposed method is applied to an example situation, a loss of coolant accident (LOCA) with common cause failure (CCF) of pressurizer pressure sensors in a Westinghouse 900MWe 3-loop pressurized water reactor (PWR) type plant. Application of the proposed method to the example situation reveals that the quantitative analysis using the proposed method explains the qualitative description of a probable scenario well. It is also shown that the proposed method produces quantitative safety assessment results after examining all possible scenarios and their probabilities. It is also shown that the proposed method can be used to quantitatively evaluate the effects of various context factors and operator support systems on the safety of nuclear power plants, by making quantitative assumptions. As a result, it is expected that the proposed method can be used to improve the quality of probabilistic safety assessment (PSA), quantitative evaluate the effects of instrument faults on the situation assessment of human operators, identify the possibilities of unsafe actions (so-called errors-of-commission) in various situations, and quantitatively evaluate the contribution of various context factors and operator support systems to the increase in the safety of NPPs

  8. Large Scale System Safety Integration for Human Rated Space Vehicles

    Science.gov (United States)

    Massie, Michael J.

    2005-12-01

    Since the 1960s man has searched for ways to establish a human presence in space. Unfortunately, the development and operation of human spaceflight vehicles carry significant safety risks that are not always well understood. As a result, the countries with human space programs have felt the pain of loss of lives in the attempt to develop human space travel systems. Integrated System Safety is a process developed through years of experience (since before Apollo and Soyuz) as a way to assess risks involved in space travel and prevent such losses. The intent of Integrated System Safety is to take a look at an entire program and put together all the pieces in such a way that the risks can be identified, understood and dispositioned by program management. This process has many inherent challenges and they need to be explored, understood and addressed.In order to prepare truly integrated analysis safety professionals must gain a level of technical understanding of all of the project's pieces and how they interact. Next, they must find a way to present the analysis so the customer can understand the risks and make decisions about managing them. However, every organization in a large-scale project can have different ideas about what is or is not a hazard, what is or is not an appropriate hazard control, and what is or is not adequate hazard control verification. NASA provides some direction on these topics, but interpretations of those instructions can vary widely.Even more challenging is the fact that every individual/organization involved in a project has different levels of risk tolerance. When the discrete hazard controls of the contracts and agreements cannot be met, additional risk must be accepted. However, when one has left the arena of compliance with the known rules, there can be no longer be specific ground rules on which to base a decision as to what is acceptable and what is not. The integrator must find common grounds between all parties to achieve

  9. Proceedings of the Human Factors Society 31st annual meeting

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    Topics covered include: operator/user modeling; automation safety; manual materials handling (includes a paper on materials handling in underground coal mining); impact of human performance on system performance; transportation safety; ergonomic design; mining safety, sleep deprivation and stressors; environmental design; training evaluation and research; and design and evaluation.

  10. Behavioral safety and OHSAS 18001:2007

    International Nuclear Information System (INIS)

    Rama Rao, B.S.; Hemantha Rao, G.V.S.

    2009-01-01

    Analysis of industrial accidents reveals that majority of them are due to human errors. And human errors can be due to lack of knowledge/awareness or inherent behavior of the person(s) involved in the accident. While the former can be tackled through training, the latter requires interventions aimed at behavior modification. Realizing the importance of behavioral aspect of safety, Revised Version of Occupational Health and Safety Management System standard - OHSAS 18001:2007 has incorporated 'behavior' in the planning clause 'Hazard identification, risk assessment and determining controls -4.3.1. (c)'. It reads The organization shall establish, implement and maintain a procedure for the ongoing hazard identification, risk assessment and determination of necessary controls. The procedure for hazard identification and risk assessment shall take into account HUMAN BEHAVIOR, CAPABILITIES and other HUMAN FACTORS. Planning and Control are the mantra. Thus, Risk Management and Mitigation strategies should factor in 'behavioral aspect' so as to be effective. In the absence of this, any amount of focus on safety will be incomplete and does not yield desired results. Best stage to take care of the behavioral safety is during the design of Plant and Machinery. Regular monitoring and periodical inspections will ensure early detection of unsafe behavior/practices and renders preventive measures possible. This paper discusses some of the behavioral patterns of industrial workforce, their ramifications for safety and possible remedies to minimize risk and save human capital for the overall well being of the organization, family and ultimately, the society. (author)

  11. Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

    2009-04-01

    In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

  12. Modeling the factors affecting unsafe behavior in the construction industry from safety supervisors' perspective.

    Science.gov (United States)

    Khosravi, Yahya; Asilian-Mahabadi, Hassan; Hajizadeh, Ebrahim; Hassanzadeh-Rangi, Narmin; Bastani, Hamid; Khavanin, Ali; Mortazavi, Seyed Bagher

    2014-01-01

    There can be little doubt that the construction is the most hazardous industry in the worldwide. This study was designed to modeling the factors affecting unsafe behavior from the perspective of safety supervisors. The qualitative research was conducted to extract a conceptual model. A structural model was then developed based on a questionnaire survey (n=266) by two stage Structural Equation Model (SEM) approach. An excellent confirmed 12-factors structure explained about 62% of variances unsafe behavior in the construction industry. A good fit structural model indicated that safety climate factors were positively correlated with safety individual factors (Pconstruction workers' engagement in safe or unsafe behavior. In order to improve construction safety performance, more focus on the workplace condition is required.

  13. The role of human intrusion in the dutch safety study

    International Nuclear Information System (INIS)

    Prij, J.; Weers, A.W.v.; Glasbergen, P.; Slot, A.F.M.

    1989-01-01

    In the Netherlands the OPLA research program in which a large number of possible disposal concepts for radioactive waste is investigated has been carried out recently. The disposal concepts concern three different waste strategies, two disposal techiques and three different types of salt formations. In the OPLA program the post-closure safety of the disposal concepts has been investigated. The paper reviews the role of the human intrusion in this safety study. The hydrological consequences of human activities in the underground are discussed and it has been demonstrated that these effects could be taken into account during the groundwater transport calculations. Four different scenario's for human intrusion in the repository have been studied to obtain an indication of the radiological effects. The results show that extremely high doses may result if, after several hundred years, human beings come into direct contact with highly active waste. For the final assessment the probability that the doses will be received should be calculated. This should be done in a subsequent research

  14. Influence of organizational factors on safety

    International Nuclear Information System (INIS)

    Haber, S.B.; Metlay, D.S.; Crouch, D.A.

    1990-01-01

    There is a need for a better understanding of exactly how organizational management factors at a nuclear power plant (NPP) affect plant safety performance, either directly or indirectly, and how these factors might be observed, measured, and evaluated. The purpose of this research project is to respond to that need by developing a general methodology for characterizing these organizational and management factors, systematically collecting information on their status and integrating that information into various types of evaluative activities. Research to date has included the development of the Nuclear Organization and Management Analysis Concept (NOMAC) of a NPP, the identification of key organizational and management factors, and the identification of the methods for systematically measuring and analyzing the influence of these factors on performance. Most recently, two field studies, one at a fossil fuel plant and the other at a NPP, were conducted using the developed methodology. Results are presented from both studies highlighting the acceptability, practicality, and usefulness of the methods used to assess the influence of various organizational and management factors including culture, communication, decision-making, standardization, and oversight. 6 refs., 3 figs., 1 tab

  15. The Relationship Between Antecedent and Consequence Factors with Safety Behaviour in PT.X

    OpenAIRE

    Fitriani, Apris; Nawawiwetu, Erwin Dyah

    2017-01-01

    Background : Safety behaviour is an act worker to minimize the possibility of accidents in workplace. Based on the Antecedents-Behaviour-Consequence (ABC) theory, safety behaviour of worker related with the antecedent and consequence factors. Purpose : The purpose of this research was to study the association between antecedent and consequence factors with safety behaviour of workers in Ring Frame Unit Spinning II PT. X. Methods : This was an observational descriptive research with cross sect...

  16. Organisational factors. Their definition and influence on nuclear safety. Final report

    International Nuclear Information System (INIS)

    Baumont, G.; Wahlstroem, B.; Sola, R.; Williams, J.; Frischknecht, A.; Wilpert, B.; Rollenhagen, C.

    2000-12-01

    The importance of organisational factors in the operational safety and efficiency of nuclear power plants (NPP) has been recognised by many organisations around the world. Despite this recognition, however, there are as yet very few methods by which organisational factors can be systematically assessed and improved. The majority of research efforts applied so far have tended to be modest and scattered. The ORFA project was created as a remedy to these problems. The objective of the project is to create a better understanding of how organisation and management factors influence nuclear safety. A key scientific objective of the project is to identify components of a theoretical framework, which would help in understanding the relationships between organisational factors and nuclear safety. Three work packages were planned. First, a review of literature listed out the identified factors and methods for assessing them. Then, a draft version of the present report was prepared to clarify the environment context and the main issues of the topics. This draft was discussed at the ORFA seminar in Madrid 21-22 October 1999. During the seminar views and comments were collected on preliminary results of the project. Finally, this information has been integrated in the present and other reports and will be used to give further guidance to the European Commission in the development of forthcoming research programmes in the field. The project has addressed nuclear safety taking a broad perspective, which reflected and took into account the views of senior NPP management and regulators. The questions discussed during the project have been: how can organisational factors be included in safety assessments, how can good and bad operational practices be identified, which methods can be used for detecting weak signals of deteriorating performance, how should incidents be analysed with respect to organisational factors to give the largest learning benefit, how can data on organisational

  17. Organizational factors influencing improvements in safety

    International Nuclear Information System (INIS)

    Marcus, A.; Nichols, M.L.; Olson, J.; Osborn, R.; Thurber, J.

    1991-01-01

    Results of conceptual and empirical research conducted by this research team, and published in NUREG-CR 5437, suggested that processes of organizational problem solving and learning provide a promising area for understanding improvement in safety-related performance in nuclear power plants. In this paper the authors describe the way in which they have built upon that work and gone much further in empirically examining a range of potentially important organizational factors related to safety. The paper describes (1) overall trends in plant performance over time on the Nuclear Regulatory Commission performance indicators, (2) the major elements in the conceptual framework guiding the current work, which seeks among other things to explain those trends, (3) the specific variables used as measures of the central concepts, (4) the results to date of the quantitative empirical work and qualitative work in progress, and (5) conclusions from the research

  18. Discussion on the Safety Factors of Slopes Recommended for Small Dams

    Directory of Open Access Journals (Sweden)

    Jan Vrubel

    2017-01-01

    Full Text Available The design and assessment of the slope stability of small embankment dams is usually not carried out using slope stability calculations but rather by the comparison of proposed or existing dam slopes with those recommended by technical standards or guidelines. Practical experience shows that in many cases the slopes of small dams are steeper than those recommended. However, most of such steeper slopes at existing dams do not exhibit any visible signs of instability, defects or sliding. For the dam owner and also for dam stability engineers, the safety of the slope, expressed e.g. via a factor of safety, is crucial. The aim of this study is to evaluate the safety margin provided by recommended slopes. The factor of safety was evaluated for several dam shape and layout variants via the shear strength reduction method using PLAXIS software. The study covers various dam geometries, dam core and shoulder positions and parameter values of utilised soils. Three load cases were considered: one with a steady state seepage condition and two with different reservoir water level drawdown velocities – standard and critical. As numerous older small dams lack a drainage system, variants with and without a toe drain were assessed. Calculated factors of safety were compared with required values specified by national standards and guidelines.

  19. The safety and clinical efficacy of recombinant human granulocyte colony stimulating factor injection for colon cancer patients undergoing chemotherapy

    Directory of Open Access Journals (Sweden)

    Jie Chen

    Full Text Available Summary Objective: The present study was designed to evaluate safety and efficacy of recombinant human granulocyte colony stimulating factor (G-CSF injection and whether this regimen could reduce the incidence of adverse events caused by chemotherapy. Method: A total of 100 patients with colon cancer who were treated with chemotherapy in our hospital from January 2011 to December 2014 were randomly divided into two groups, with 50 patients in each group. The patients in the treatment group received G-CSF 24 hours after chemotherapy for consecutive three days; the patients in the control group received the same dose of normal saline. Routine blood tests were performed 7 days and 14 days after chemotherapy. Results: Compared with the control group, the incidences of febrile neutropenia and leukocytopenia in the treatment group were significantly lower (p<0.05. In addition, the incidence of liver dysfunction in the treatment group was lower than that of the control group, without statistical significance. The incidence of myalgia in the treatment was higher than that of the control group without statistical significance. Conclusion: The present study indicated that G-CSF injection after chemotherapy is safe and effective for preventing adverse events in colon cancer patients with chemotherapy.

  20. Basic Safety Considerations for Nuclear Power Plant Dealing with External Human Induced Events

    Energy Technology Data Exchange (ETDEWEB)

    Salem, W., E-mail: wafaasalem21@yahoo.com [Nuclear and Radiological Regulatory Authority (Egypt)

    2014-10-15

    Facilities and human activities in the region in which a nuclear power plant is located may under some conditions affect its safety. The potential sources of human induced events external to the plant should be identified and the severity of the possible resulting hazard phenomena should be evaluated to derive the appropriate design bases for the plant. They should also be monitored and periodically assessed over the lifetime of the plant to ensure that consistency with the design assumptions is maintained. External human induced events that could affect safety should be investigated in the site evaluation stage for every nuclear power plant site. The region is required to be examined for facilities and human activities that have the potential, under certain conditions, to endanger the nuclear power plant over its entire lifetime. Each relevant potential source is required to be identified and assessed to determine the potential interactions with personnel and plant items important to safety. (author)

Some links on this page may take you to non-federal websites. Their policies may differ from this site.