WorldWideScience

Sample records for risk assessment safety

  1. Concept of risk: risk assessment and nuclear safety

    International Nuclear Information System (INIS)

    Thompson, P.B.

    1980-01-01

    The dissertation is a critical examination of risk assessment and its role in public policy. Nuclear power safety safety issues are selected as the primary source of illustrations and examples. The dissertation examines how risk assessment studies develop a concept of risk which becomes decisive for policy choices. Risk-assessment techniques are interpreted as instruments which secure an evaluation of risk which, in turn, figures prominently in technical reports on nuclear power. The philosophical critique is mounted on two levels. First, an epistemological critique surveys distinctions between the technical concept of risk and more familiar senses of risk. The critique shows that utilization of risk assessment re-structures the concept of risk. The technical concept is contrasted to the function of risk within a decision-maker's conceptual agenda and hierarchy of values. Second, an ethical critique exposes the value commitments of risk assessment recommendations. Although some of these values might be defended for policy decisions, the technical character of risk assessment obfuscates normative issues. Risk assessment is shown to be a form of factual enquiry which, nonetheless, represents a commitment to a specific selection of ethical and social values. Risk assessment should not be interpreted as a primary guide to decision unless the specific values incorporated into its concept of risk are stated explicitly and justified philosophically. Such a statement would allow value questions which have been sublimated by the factual tone of the analytic techniques to be debated on clear, social and ethical grounds

  2. 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)

  3. Risk assessment of safety violations for coal mines

    Energy Technology Data Exchange (ETDEWEB)

    Megan Orsulaka; Vladislav Kecojevicb; Larry Graysona; Antonio Nietoa [Pennsylvania State University, University Park, PA (United States). Dept of Energy and Mineral Engineering

    2010-09-15

    This article presents an application of a risk assessment approach in characterising the risks associated with safety violations in underground bituminous mines in Pennsylvania using the Mine Safety and Health Administration (MSHA) citation database. The MSHA database on citations provides an opportunity to assess risks in mines through scrutiny of violations of mandatory safety standards. In this study, quantitative risk assessment is performed, which allows determination of the frequency of occurrence of safety violations (through associated citations) as well as the consequences of them in terms of penalty assessments. Focus is on establishing risk matrices on citation experiences of mines, which can give early indication of emerging potentially serious problems. The resulting frequency, consequence and risk rankings present valuable tools for prioritising resource allocations, determining control strategies, and could potentially contribute to more proactive prevention of incidents and injuries.

  4. Safety analysis and risk assessment handbook

    International Nuclear Information System (INIS)

    Peterson, V.L.; Colwell, R.G.; Dickey, R.L.

    1997-01-01

    This Safety Analysis and Risk Assessment Handbook (SARAH) provides guidance to the safety analyst at the Rocky Flats Environmental Technology Site (RFETS) in the preparation of safety analyses and risk assessments. Although the older guidance (the Rocky Flats Risk Assessment Guide) continues to be used for updating the Final Safety Analysis Reports developed in the mid-1980s, this new guidance is used with all new authorization basis documents. With the mission change at RFETS came the need to establish new authorization basis documents for its facilities, whose functions had changed. The methodology and databases for performing the evaluations that support the new authorization basis documents had to be standardized, to avoid the use of different approaches and/or databases for similar accidents in different facilities. This handbook presents this new standardized approach. The handbook begins with a discussion of the requirements of the different types of authorization basis documents and how to choose the one appropriate for the facility to be evaluated. It then walks the analyst through the process of identifying all the potential hazards in the facility, classifying them, and choosing the ones that need to be analyzed further. It then discusses the methods for evaluating accident initiation and progression and covers the basic steps in a safety analysis, including consequence and frequency binning and risk ranking. The handbook lays out standardized approaches for determining the source terms of the various accidents (including airborne release fractions, leakpath factors, etc.), the atmospheric dispersion factors appropriate for Rocky Flats, and the methods for radiological and chemical consequence assessments. The radiological assessments use a radiological open-quotes templateclose quotes, a spreadsheet that incorporates the standard values of parameters, whereas the chemical assessments use the standard codes ARCHIE and ALOHA

  5. The role of risk assessment and safety analysis in integrated safety assessments

    International Nuclear Information System (INIS)

    Niall, R.; Hunt, M.; Wierman, T.E.

    1990-01-01

    To ensure that the design and operation of both nuclear and non- nuclear hazardous facilities is acceptable, and meets all societal safety expectations, a rigorous deterministic and probabilistic assessment is necessary. An approach is introduced, founded on the concept of an ''Integrated Safety Assessment.'' It merges the commonly performed safety and risk analyses and uses them in concert to provide decision makers with the necessary depth of understanding to achieve ''adequacy.'' 3 refs., 1 fig

  6. Safety and security risk assessments--now demystified!

    Science.gov (United States)

    White, Donald E

    2011-01-01

    Safety/security risk assessments no longer need to spook nor baffle healthcare safety/security managers. This grid template provides at-at-glance quick lookup of the possible threats, the affected people and things, a priority ranking of these risks, and a workable solution for each risk. Using the standard document, spreadsheet, or graphics software already available on your computer, you can easily use a scientific method to produce professional looking risk assessments that get quickly understood by both senior managers and first responders alike!

  7. Safety analysis, risk assessment, and risk acceptance criteria

    International Nuclear Information System (INIS)

    Jamali, K.

    1997-01-01

    This paper discusses a number of topics that relate safety analysis as documented in the Department of Energy (DOE) safety analysis reports (SARs), probabilistic risk assessments (PRA) as characterized primarily in the context of the techniques that have assumed some level of formality in commercial nuclear power plant applications, and risk acceptance criteria as an outgrowth of PRA applications. DOE SARs of interest are those that are prepared for DOE facilities under DOE Order 5480.23 and the implementing guidance in DOE STD-3009-94. It must be noted that the primary area of application for DOE STD-3009 is existing DOE facilities and that certain modifications of the STD-3009 approach are necessary in SARs for new facilities. Moreover, it is the hazard analysis (HA) and accident analysis (AA) portions of these SARs that are relevant to the present discussions. Although PRAs can be qualitative in nature, PRA as used in this paper refers more generally to all quantitative risk assessments and their underlying methods. HA as used in this paper refers more generally to all qualitative risk assessments and their underlying methods that have been in use in hazardous facilities other than nuclear power plants. This discussion includes both quantitative and qualitative risk assessment methods. PRA has been used, improved, developed, and refined since the Reactor Safety Study (WASH-1400) was published in 1975 by the Nuclear Regulatory Commission (NRC). Much debate has ensued since WASH-1400 on exactly what the role of PRA should be in plant design, reactor licensing, 'ensuring' plant and process safety, and a large number of other decisions that must be made for potentially hazardous activities. Of particular interest in this area is whether the risks quantified using PRA should be compared with numerical risk acceptance criteria (RACs) to determine whether a facility is 'safe.' Use of RACs requires quantitative estimates of consequence frequency and magnitude

  8. Ensuring the quality of occupational safety risk assessment.

    Science.gov (United States)

    Pinto, Abel; Ribeiro, Rita A; Nunes, Isabel L

    2013-03-01

    In work environments, the main aim of occupational safety risk assessment (OSRA) is to improve the safety level of an installation or site by either preventing accidents and injuries or minimizing their consequences. To this end, it is of paramount importance to identify all sources of hazards and assess their potential to cause problems in the respective context. If the OSRA process is inadequate and/or not applied effectively, it results in an ineffective safety prevention program and inefficient use of resources. An appropriate OSRA is an essential component of the occupational safety risk management process in industries. In this article, we performed a survey to elicit the relative importance for identified OSRA tasks to enable an in-depth evaluation of the quality of risk assessments related to occupational safety aspects on industrial sites. The survey involved defining a questionnaire with the most important elements (tasks) for OSRA quality assessment, which was then presented to safety experts in the mining, electrical power production, transportation, and petrochemical industries. With this work, we expect to contribute to the main question of OSRA in industries: "What constitutes a good occupational safety risk assessment?" The results obtained from the questionnaire showed that experts agree with the proposed OSRA process decomposition in steps and tasks (taxonomy) and also with the importance of assigning weights to obtain knowledge about OSRA task relevance. The knowledge gained will enable us, in the near future, to build a framework to evaluate OSRA quality for industrial sites. © 2012 Society for Risk Analysis.

  9. EFFICIENT QUANTITATIVE RISK ASSESSMENT OF JUMP PROCESSES: IMPLICATIONS FOR FOOD SAFETY

    OpenAIRE

    Nganje, William E.

    1999-01-01

    This paper develops a dynamic framework for efficient quantitative risk assessment from the simplest general risk, combining three parameters (contamination, exposure, and dose response) in a Kataoka safety-first model and a Poisson probability representing the uncertainty effect or jump processes associated with food safety. Analysis indicates that incorporating jump processes in food safety risk assessment provides more efficient cost/risk tradeoffs. Nevertheless, increased margin of safety...

  10. Economic aspects of risk assessment in chemical safety

    Energy Technology Data Exchange (ETDEWEB)

    Drummond, M F; Shannon, H S

    1986-05-01

    This paper considers how the economic aspects of risk assessment in chemical safety can be strengthened. Its main focus is on how economic appraisal techniques, such as cost-benefit and cost-effectiveness analysis, can be adapted to the requirements of the risk-assessment process. Following a discussion of the main methodological issues raised by the use of economic appraisal, illustrated by examples from the health and safety field, a number of practical issues are discussed. These include the consideration of the distribution of costs, effects and benefits, taking account of uncertainty, risk probabilities and public perception, making the appraisal techniques useful to the early stages of the risk-assessment process and structuring the appraisal to permit continuous feedback to the participants in the risk-assessment process. It is concluded that while the way of thinking embodied in economic appraisal is highly relevant to the consideration of choices in chemical safety, the application of these principles in formal analysis of risk reduction procedures presents a more mixed picture. The main suggestions for improvement in the analyses performed are the undertaking of sensitivity analyses of study results to changes in the key assumptions, the presentation of the distribution of costs and benefits by viewpoint, the comparison of health and safety measures in terms of their incremental cost per life-year (or quality-adjusted life-year) gained and the more frequent retrospective review and revision of the economic analyses that are undertaken.

  11. Failure rate data for fusion safety and risk assessment

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1993-01-01

    The Fusion Safety Program (FSP) at the Idaho National Engineering Laboratory (INEL) conducts safety research in materials, chemical reactions, safety analysis, risk assessment, and in component research and development to support existing magnetic fusion experiments and also to promote safety in the design of future experiments. One of the areas of safety research is applying probabilistic risk assessment (PRA) methods to fusion experiments. To apply PRA, we need a fusion-relevant radiological dose code and a component failure rate data base. This paper describes the FSP effort to develop a failure rate data base for fusion-specific components

  12. Quantitative risk assessment of digitalized safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Sung Min; Lee, Sang Hun; Kang, Hym Gook [KAIST, Daejeon (Korea, Republic of); Lee, Seung Jun [UNIST, Ulasn (Korea, Republic of)

    2016-05-15

    A report published by the U.S. National Research Council indicates that appropriate methods for assessing reliability are key to establishing the acceptability of digital instrumentation and control (I and C) systems in safety-critical plants such as NPPs. Since the release of this issue, the methodology for the probabilistic safety assessment (PSA) of digital I and C systems has been studied. However, there is still no widely accepted method. Kang and Sung found three critical factors for safety assessment of digital systems: detection coverage of fault-tolerant techniques, software reliability quantification, and network communication risk. In reality the various factors composing digitalized I and C systems are not independent of each other but rather closely connected. Thus, from a macro point of view, a method that can integrate risk factors with different characteristics needs to be considered together with the micro approaches to address the challenges facing each factor.

  13. Formal safety assessment based on relative risks model in ship navigation

    Energy Technology Data Exchange (ETDEWEB)

    Hu Shenping [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: sphu@mmc.shmtu.edu.cn; Fang Quangen [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: qgfang@mmc.shmtu.edu.cn; Xia Haibo [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: hbxia@mmc.shmtu.edu.cn; Xi Yongtao [Merchant Marine College, Shanghai Maritime University, 1550, Pudong Dadao, Shanghai 200135 (China)]. E-mail: xiyt@mmc.shmtu.edu.cn

    2007-03-15

    Formal safety assessment (FSA) is a structured and systematic methodology aiming at enhancing maritime safety. It has been gradually and broadly used in the shipping industry nowadays around the world. On the basis of analysis and conclusion of FSA approach, this paper discusses quantitative risk assessment and generic risk model in FSA, especially frequency and severity criteria in ship navigation. Then it puts forward a new model based on relative risk assessment (MRRA). The model presents a risk-assessment approach based on fuzzy functions and takes five factors into account, including detailed information about accident characteristics. It has already been used for the assessment of pilotage safety in Shanghai harbor, China. Consequently, it can be proved that MRRA is a useful method to solve the problems in the risk assessment of ship navigation safety in practice.

  14. Formal safety assessment based on relative risks model in ship navigation

    International Nuclear Information System (INIS)

    Hu Shenping; Fang Quangen; Xia Haibo; Xi Yongtao

    2007-01-01

    Formal safety assessment (FSA) is a structured and systematic methodology aiming at enhancing maritime safety. It has been gradually and broadly used in the shipping industry nowadays around the world. On the basis of analysis and conclusion of FSA approach, this paper discusses quantitative risk assessment and generic risk model in FSA, especially frequency and severity criteria in ship navigation. Then it puts forward a new model based on relative risk assessment (MRRA). The model presents a risk-assessment approach based on fuzzy functions and takes five factors into account, including detailed information about accident characteristics. It has already been used for the assessment of pilotage safety in Shanghai harbor, China. Consequently, it can be proved that MRRA is a useful method to solve the problems in the risk assessment of ship navigation safety in practice

  15. Tolerability of risk, safety assessment principles and their implications for probabilistic safety analysis

    International Nuclear Information System (INIS)

    Ewing, D.J.F.; Campbell, J.F.

    1994-01-01

    This paper gives a regulatory view of probabilistic safety assessment as seen by the Nuclear Installations Inspectorate (NII) and in the light of the general regulatory risk aims set out in the Health and Safety Executive's (HSE) The tolerability of risk from nuclear power stations (TOR) and in Safety assessment principles for nuclear plants (SAPs), prepared by NII on behalf of the HSE. Both of these publications were revised and republished in 1992. This paper describes the SAPs, together with the historical background, the motivation for review, the effects of the Sizewell and Hinkley Point C public inquiries, changes since the original versions, comparison with international standards and use in assessment. For new plant, probabilistic safety analysis (PSA) is seen as an essential tool in balancing the safety of the design and in demonstrating compliance with TOR and the SAPs. (Author)

  16. Risk monitor - a tool for operational safety assessment risk monitor - user's manual

    International Nuclear Information System (INIS)

    Hari Prasad, M.; Vinod, Gopika; Saraf, R.K.; Ghosh, A.K.

    2006-06-01

    Probabilistic Safety Assessment has become a key tool as on today to identify and understand Nuclear Power Plant vulnerabilities. As a result of the availability of these PSA studies, there is a desire to use them to enhance plant safety and to operate the nuclear stations in the most efficient manner. Risk Monitor is a PC based tool, which computes the real time safety level and assists plant personnel to manage day-to-day activities. Risk Monitor is a PC based user friendly software tool used for modification and re-analysis of a nuclear Power plant. Operation of Risk Monitor is based on PSA methods for assisting in day to day applications. Risk Monitoring programs can assess the risk profile and are used to optimize the operation of Nuclear Power Plants with respect to a minimum risk level over the operating time. This report presents the background activities of Risk Monitor, its application areas and the step by step procedure for the user.to interact with the software. This software can be used with the PSA model of any Nuclear Power Plant. (author)

  17. Current issues and perspectives in food safety and risk assessment.

    Science.gov (United States)

    Eisenbrand, G

    2015-12-01

    In this review, current issues and opportunities in food safety assessment are discussed. Food safety is considered an essential element inherent in global food security. Hazard characterization is pivotal within the continuum of risk assessment, but it may be conceived only within a very limited frame as a true alternative to risk assessment. Elucidation of the mode of action underlying a given hazard is vital to create a plausible basis for human toxicology evaluation. Risk assessment, to convey meaningful risk communication, must be based on appropriate and reliable consideration of both exposure and mode of action. New perspectives, provided by monitoring human exogenous and endogenous exposure biomarkers, are considered of great promise to support classical risk extrapolation from animal toxicology. © The Author(s) 2015.

  18. An approach for risk informed safety culture assessment for Canadian nuclear power stations

    International Nuclear Information System (INIS)

    Nelson, W.R.

    2010-01-01

    One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

  19. Toward risk assessment 2.0: Safety supervisory control and model-based hazard monitoring for risk-informed safety interventions

    International Nuclear Information System (INIS)

    Favarò, Francesca M.; Saleh, Joseph H.

    2016-01-01

    Probabilistic Risk Assessment (PRA) is a staple in the engineering risk community, and it has become to some extent synonymous with the entire quantitative risk assessment undertaking. Limitations of PRA continue to occupy researchers, and workarounds are often proposed. After a brief review of this literature, we propose to address some of PRA's limitations by developing a novel framework and analytical tools for model-based system safety, or safety supervisory control, to guide safety interventions and support a dynamic approach to risk assessment and accident prevention. Our work shifts the emphasis from the pervading probabilistic mindset in risk assessment toward the notions of danger indices and hazard temporal contingency. The framework and tools here developed are grounded in Control Theory and make use of the state-space formalism in modeling dynamical systems. We show that the use of state variables enables the definition of metrics for accident escalation, termed hazard levels or danger indices, which measure the “proximity” of the system state to adverse events, and we illustrate the development of such indices. Monitoring of the hazard levels provides diagnostic information to support both on-line and off-line safety interventions. For example, we show how the application of the proposed tools to a rejected takeoff scenario provides new insight to support pilots’ go/no-go decisions. Furthermore, we augment the traditional state-space equations with a hazard equation and use the latter to estimate the times at which critical thresholds for the hazard level are (b)reached. This estimation process provides important prognostic information and produces a proxy for a time-to-accident metric or advance notice for an impending adverse event. The ability to estimate these two hazard coordinates, danger index and time-to-accident, offers many possibilities for informing system control strategies and improving accident prevention and risk mitigation

  20. Assessing Risk-Based Performance Indicators in Safety-Critical Systems for Nuclear Power Plants

    OpenAIRE

    TONT Gabriela

    2011-01-01

    The paper proposes framework for a multidisciplinary nuclear risk and safety assessment by modeling uncertainty and combining diverse evidence provided in such a way that it could be used to represent an entire argument about a system's dependability. The identified safety issues are being treated by means of probabilistic safety assessment (PSA). The behavior simulation of power plant in thepresence of risk factors is analyzed from the vulnerability, risk and functional safety viewpoints, hi...

  1. Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Son, Kwang Seop; Jung, Wondea; Kang, Hyun Gook

    2017-01-01

    Highlights: • Safety data communication risk assessment framework and quantitative scheme were proposed. • Fault-tree model of ESFAS unavailability due to safety data communication failure was developed. • Safety data link and network risk were assessed based on various ESF-CCS design specifications. • The effect of fault-tolerant algorithm reliability of safety data network on ESFAS unavailability was assessed. - Abstract: As one of the safety-critical systems in nuclear power plants (NPPs), the Engineered Safety Feature-Component Control System (ESF-CCS) employs safety data link and network communication for the transmission of safety component actuation signals from the group controllers to loop controllers to effectively accommodate various safety-critical field controllers. Since data communication failure risk in the ESF-CCS has yet to be fully quantified, the ESF-CCS employing data communication systems have not been applied in NPPs. This study therefore developed a fault tree model to assess the data link and data network failure-induced unavailability of a system function used to generate an automated control signal for accident mitigation equipment. The current aim is to provide risk information regarding data communication failure in a digital safety feature control system in consideration of interconnection between controllers and the fault-tolerant algorithm implemented in the target system. Based on the developed fault tree model, case studies were performed to quantitatively assess the unavailability of ESF-CCS signal generation due to data link and network failure and its risk effect on safety signal generation failure. This study is expected to provide insight into the risk assessment of safety-critical data communication in a digitalized NPP instrumentation and control system.

  2. Risk assessment and safety regulations in offshore oil and gas ...

    African Journals Online (AJOL)

    Risk management of which risk assessment is part, and safety regulations are common in the offshore oil and gas industry management system. The process of conducting risk assessment is mostly a challenge for operational personnel assigned to perform this function. The most significant problem is the decision to use ...

  3. Risk Assessment in the UK Health and Safety System: Theory and Practice

    Directory of Open Access Journals (Sweden)

    Karen Russ

    2010-09-01

    Full Text Available In the UK, a person or organisation that creates risk is required to manage and control that risk so that it is reduced 'So Far As Is Reasonably Practicable' (SFAIRP. How the risk is managed is to be determined by those who create the risk. They have a duty to demonstrate that they have taken action to ensure all risk is reduced SFAIRP and must have documentary evidence, for example a risk assessment or safety case, to prove that they manage the risks their activities create. The UK Health and Safety Executive (HSE does not tell organisations how to manage the risks they create but does inspect the quality of risk identification and management. This paper gives a brief overview of where responsibility for occupational health and safety lies in the UK, and how risk should be managed through risk assessment. The focus of the paper is three recent major UK incidents, all involving fatalities, and all of which were wholly avoidable if risks had been properly assessed and managed. The paper concludes with an analysis of the common failings of risk assessments and key actions for improvement.

  4. Risk Assessment in the UK Health and Safety System: Theory and Practice.

    Science.gov (United States)

    Russ, Karen

    2010-09-01

    In the UK, a person or organisation that creates risk is required to manage and control that risk so that it is reduced 'So Far As Is Reasonably Practicable' (SFAIRP). How the risk is managed is to be determined by those who create the risk. They have a duty to demonstrate that they have taken action to ensure all risk is reduced SFAIRP and must have documentary evidence, for example a risk assessment or safety case, to prove that they manage the risks their activities create. The UK Health and Safety Executive (HSE) does not tell organisations how to manage the risks they create but does inspect the quality of risk identification and management. This paper gives a brief overview of where responsibility for occupational health and safety lies in the UK, and how risk should be managed through risk assessment. The focus of the paper is three recent major UK incidents, all involving fatalities, and all of which were wholly avoidable if risks had been properly assessed and managed. The paper concludes with an analysis of the common failings of risk assessments and key actions for improvement.

  5. Assessment of Health, Safety and Environmental Risks of Zahedan City Gasoline Stations

    Directory of Open Access Journals (Sweden)

    S. Y. Far

    2018-04-01

    Full Text Available The purpose of this study was to assess the risk and determine the health, safety and environmental status of fuel stations in Zahedan. In this study, failure mode and effects analysis (FMEA method was used for risk assessment in accordance with the HSE guidelines, national and international standards and laws. In this cross-sectional study, 2 governmental stations and 6 active private stations were evaluated after the necessary coordination with the relevant units. As a result of risk assessment, 27 health risks, 55 safety risks and 22 environmental risks were identified. From among all the identified risks, 67 risks had a Risk Priority Number (RPN of less than 91, 31 risks had an RPN ranging between 91 and 201, and 6 risks had an RPN of over 201. The findings of the study indicated that compliance with the HSE requirements was 51.85%, in the area of health, 47.57% in the area of safety and 27.45% in the environmental area. Overall compliance with the HSE requirements was 42.54%. In order to distribute fuel considering health, reducing risk and increasing compliance with the requirements for safety improvement, health and environmental conditions of fuel supplies are essential.

  6. A comparison of integrated safety analysis and probabilistic risk assessment

    International Nuclear Information System (INIS)

    Damon, Dennis R.; Mattern, Kevin S.

    2013-01-01

    The U.S. Nuclear Regulatory Commission conducted a comparison of two standard tools for risk informing the regulatory process, namely, the Probabilistic Risk Assessment (PRA) and the Integrated Safety Analysis (ISA). PRA is a calculation of risk metrics, such as Large Early Release Frequency (LERF), and has been used to assess the safety of all commercial power reactors. ISA is an analysis required for fuel cycle facilities (FCFs) licensed to possess potentially critical quantities of special nuclear material. A PRA is usually more detailed and uses more refined models and data than an ISA, in order to obtain reasonable quantitative estimates of risk. PRA is considered fully quantitative, while most ISAs are typically only partially quantitative. The extension of PRA methodology to augment or supplant ISAs in FCFs has long been considered. However, fuel cycle facilities have a wide variety of possible accident consequences, rather than a few surrogates like LERF or core damage as used for reactors. It has been noted that a fuel cycle PRA could be used to better focus attention on the most risk-significant structures, systems, components, and operator actions. ISA and PRA both identify accident sequences; however, their treatment is quite different. ISA's identify accidents that lead to high or intermediate consequences, as defined in 10 Code of Federal Regulations (CFR) 70, and develop a set of Items Relied on For Safety (IROFS) to assure adherence to performance criteria. PRAs identify potential accident scenarios and estimate their frequency and consequences to obtain risk metrics. It is acceptable for ISAs to provide bounding evaluations of accident consequences and likelihoods in order to establish acceptable safety; but PRA applications usually require a reasonable quantitative estimate, and often obtain metrics of uncertainty. This paper provides the background, features, and methodology associated with the PRA and ISA. The differences between the

  7. Risk assessment on hazards for decommissioning safety of a nuclear facility

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Lee, Kune-Woo; Lim, Hyeon-Kyo

    2010-01-01

    A decommissioning plan should be followed by a qualitative and quantitative safety assessment of it. The safety assessment of a decommissioning plan is applied to identify the potential (radiological and non-radiological) hazards and risks. Radiological and non-radiological hazards arise during decommissioning activities. The non-radiological or industrial hazards to which workers are subjected during a decommissioning and dismantling process may be greater than those experienced during an operational lifetime of a facility. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities and as well as during accidents. The risk assessment method was developed by using risk matrix and fuzzy inference logic, on the basis of the radiological and non-radiological hazards for a decommissioning safety of a nuclear facility. Fuzzy inference of radiological and non-radiological hazards performs a mapping from radiological and non-radiological hazards to risk matrix. Defuzzification of radiological and non-radiological hazards is the conversion of risk matrix and priorities to the maximum criterion method and the mean criterion method. In the end, a composite risk assessment methodology, to rank the risk level on radiological and non-radiological hazards of the decommissioning tasks and to prioritize on the risk level of the decommissioning tasks, by simultaneously combining radiological and non-radiological hazards, was developed.

  8. How to interpret safety critical failures in risk and reliability assessments

    International Nuclear Information System (INIS)

    Selvik, Jon Tømmerås; Signoret, Jean-Pierre

    2017-01-01

    Management of safety systems often receives high attention due to the potential for industrial accidents. In risk and reliability literature concerning such systems, and particularly concerning safety-instrumented systems, one frequently comes across the term ‘safety critical failure’. It is a term associated with the term ‘critical failure’, and it is often deduced that a safety critical failure refers to a failure occurring in a safety critical system. Although this is correct in some situations, it is not matching with for example the mathematical definition given in ISO/TR 12489:2013 on reliability modeling, where a clear distinction is made between ‘safe failures’ and ‘dangerous failures’. In this article, we show that different interpretations of the term ‘safety critical failure’ exist, and there is room for misinterpretations and misunderstandings regarding risk and reliability assessments where failure information linked to safety systems are used, and which could influence decision-making. The article gives some examples from the oil and gas industry, showing different possible interpretations of the term. In particular we discuss the link between criticality and failure. The article points in general to the importance of adequate risk communication when using the term, and gives some clarification on interpretation in risk and reliability assessments.

  9. Safety risk assessment using analytic hierarchy process (AHP) during planning and budgeting of construction projects.

    Science.gov (United States)

    Aminbakhsh, Saman; Gunduz, Murat; Sonmez, Rifat

    2013-09-01

    The inherent and unique risks on construction projects quite often present key challenges to contractors. Health and safety risks are among the most significant risks in construction projects since the construction industry is characterized by a relatively high injury and death rate compared to other industries. In construction project management, safety risk assessment is an important step toward identifying potential hazards and evaluating the risks associated with the hazards. Adequate prioritization of safety risks during risk assessment is crucial for planning, budgeting, and management of safety related risks. In this paper, a safety risk assessment framework is presented based on the theory of cost of safety (COS) model and the analytic hierarchy process (AHP). The main contribution of the proposed framework is that it presents a robust method for prioritization of safety risks in construction projects to create a rational budget and to set realistic goals without compromising safety. The framework provides a decision tool for the decision makers to determine the adequate accident/injury prevention investments while considering the funding limits. The proposed safety risk framework is illustrated using a real-life construction project and the advantages and limitations of the framework are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  10. Development of reliability and probabilistic safety assessment program RiskA

    International Nuclear Information System (INIS)

    Wu, Yican

    2015-01-01

    Highlights: • There are four parts in the structure of RiskA. User input part lets users input the PSA model and some necessary data by GUI or model transformation tool. In calculation engine part, fault tree analysis, event tree analysis, uncertainty analysis, sensitivity analysis, importance analysis and failure mode and effects analysis are supplied. User output part outputs the analysis results, user customized reports and some other data. The last part includes reliability database, some other common tools and help documents. • RiskA has several advanced features. Extensible framework makes it easy to add any new functions, making RiskA to be a large platform of reliability and probabilistic safety assessment. It is very fast to analysis fault tree in RiskA because many advanced algorithm improvement were made. Many model formats can be imported and exported, which made the PSA model in the commercial software can be easily transformed to adapt RiskA platform. Web-based co-modeling let several users in different places work together whenever they are online. • The comparison between RiskA and other mature PSA codes (e.g. CAFTA, RiskSpectrum, XFTA) has demonstrated that the calculation and analysis of RiskA is correct and efficient. Based on the development of this code package, many applications of safety and reliability analysis of some research reactors and nuclear power plants were performed. The development of RiskA appears to be of realistic and potential value for academic research and practical operation safety management of nuclear power plants in China and abroad. - Abstract: PSA (probabilistic safety assessment) software, the indispensable tool in nuclear safety assessment, has been widely used. An integrated reliability and PSA program named RiskA has been developed by FDS Team. RiskA supplies several standard PSA modules including fault tree analysis, event tree analysis, uncertainty analysis, failure mode and effect analysis and reliability

  11. A Practical Risk Assessment Methodology for Safety-Critical Train Control Systems

    Science.gov (United States)

    2009-07-01

    This project proposes a Practical Risk Assessment Methodology (PRAM) for analyzing railroad accident data and assessing the risk and benefit of safety-critical train control systems. This report documents in simple steps the algorithms and data input...

  12. Risk-informed decision making a keystone in advanced safety assessment

    International Nuclear Information System (INIS)

    Reinhart, M.

    2007-01-01

    Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

  13. Outage Risk Assessment and Management (ORAM) technology to improve outage safety and economics

    International Nuclear Information System (INIS)

    Kalra, S.P.

    2004-01-01

    The Electric Power Research Institute (EPRI) has undertaken an aggressive program, called ORAM (Outage Risk Assessment and Management), to provide utilities with tools and technology to assist in managing risk during the planning and conduct of outages. The ORAM program consists of the following 6 steps: i) Perform utility surveys and visits on shutdown risk management needs, ii) Perform probabilistic shutdown safety assessments (PSSAs) to identify generic insights that can be incorporated into risk management guidelines and identify selected areas for the development of contingency actions, iii) Develop risk management guidelines (RMG's) that provide a systematic approach to the planning and conduct of outages from a safety perspective. Incorporate insights from the shutdown safety assessments and other operating experience into the RMG's. iv) Develop selected contingency actions including a thermalhydraulic tool kit to address higher risk time periods and activities identified in the shutdown safety assessments, v) Develop computer software that integrates all of the above capability into an easy to use tool for effective shutdown operation management for utilities, vi) Provide assistance in the transfer of this technology and the application of these tools. This paper briefly describes the technical approach and tools developed under EPRI's ORAM program and its applications for improving outage safety and economics. (author)

  14. German data for risk based fire safety assessment

    International Nuclear Information System (INIS)

    Roewekamp, M.; Berg, H.P.

    1998-01-01

    Different types of data are necessary to perform risk based fire safety assessments and, in particular, to quantify the fire event tree considering the plant specific conditions. Data on fire barriers, fire detection and extinguishing, including also data on secondary effects of a fire, have to be used for quantifying the potential hazard and damage states. The existing German database on fires in nuclear power plants (NPPs) is very small. Therefore, in general generic data, mainly from US databases, are used for risk based safety assessments. Due to several differences in the plant design and conditions generic data can only be used as conservative assumptions. World-wide existing generic data on personnel failures in case of fire fighting have only to be adapted to the plant specific conditions inside the NPP to be investigated. In contrary, unavailabilities of fire barrier elements may differ strongly depending on different standards, testing requirements, etc. In addition, the operational behaviour of active fire protection equipment may vary depending on type and manufacturer. The necessity for more detailed and for additional plant specific data was the main reason for generating updated German data on the operational behaviour of active fire protection equipment/features in NPPs to support risk based fire safety analyses being recommended to be carried out as an additional tool to deterministic fire hazard analyses in the frame of safety reviews. The results of these investigations revealed a broader and more realistic database for technical reliability of active fire protection means, but improvements as well as collection of further data are still necessary. (author)

  15. C-Band Airport Surface Communications System Engineering-Initial High-Level Safety Risk Assessment and Mitigation

    Science.gov (United States)

    Zelkin, Natalie; Henriksen, Stephen

    2011-01-01

    This document is being provided as part of ITT's NASA Glenn Research Center Aerospace Communication Systems Technical Support (ACSTS) contract: "New ATM Requirements--Future Communications, C-Band and L-Band Communications Standard Development." ITT has completed a safety hazard analysis providing a preliminary safety assessment for the proposed C-band (5091- to 5150-MHz) airport surface communication system. The assessment was performed following the guidelines outlined in the Federal Aviation Administration Safety Risk Management Guidance for System Acquisitions document. The safety analysis did not identify any hazards with an unacceptable risk, though a number of hazards with a medium risk were documented. This effort represents an initial high-level safety hazard analysis and notes the triggers for risk reassessment. A detailed safety hazards analysis is recommended as a follow-on activity to assess particular components of the C-band communication system after the profile is finalized and system rollout timing is determined. A security risk assessment has been performed by NASA as a parallel activity. While safety analysis is concerned with a prevention of accidental errors and failures, the security threat analysis focuses on deliberate attacks. Both processes identify the events that affect operation of the system; and from a safety perspective the security threats may present safety risks.

  16. Use of reliability engineering tools in safety and risk assessment of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-07-01

    Safety, reliability and availability are fundamental criteria in design, construction and operation of nuclear facilities, as nuclear power plants. Deterministic and probabilistic risk assessments of such facilities are required by regulatory authorities in order to meet licensing regulations, contributing to assure safety, as well as reduce costs and environmental impacts. Probabilistic Risk Assessment has become an important part of licensing requirements of the nuclear power plants in Brazil and in the world. Risk can be defined as a qualitative and/or quantitative assessment of accident sequence frequencies (or probabilities) and their consequences. Risk management is a systematic application of management policies, procedures and practices to identify, analyze, plan, implement, control, communicate and document risks. Several tools and computer codes must be combined, in order to estimate both probabilities and consequences of accidents. Event Tree Analysis (ETA), Fault Tree Analysis (FTA), Reliability Block Diagrams (RBD), and Markov models are examples of evaluation tools that can support the safety and risk assessment for analyzing process systems, identifying potential accidents, and estimating consequences. Because of complexity of such analyzes, specialized computer codes are required, such as the reliability engineering software develop by Reliasoft® Corporation. BlockSim (FTA, RBD and Markov models), RENO (ETA and consequence assessment), Weibull++ (life data and uncertainty analysis), and Xfmea (qualitative risk assessment) are some codes that can be highlighted. This work describes an integrated approach using these tools and software to carry out reliability, safety, and risk assessment of nuclear facilities, as well as, and application example. (author)

  17. Use of reliability engineering tools in safety and risk assessment of nuclear facilities

    International Nuclear Information System (INIS)

    Raso, Amanda Laureano; Vasconcelos, Vanderley de; Marques, Raíssa Oliveira; Soares, Wellington Antonio; Mesquita, Amir Zacarias

    2017-01-01

    Safety, reliability and availability are fundamental criteria in design, construction and operation of nuclear facilities, as nuclear power plants. Deterministic and probabilistic risk assessments of such facilities are required by regulatory authorities in order to meet licensing regulations, contributing to assure safety, as well as reduce costs and environmental impacts. Probabilistic Risk Assessment has become an important part of licensing requirements of the nuclear power plants in Brazil and in the world. Risk can be defined as a qualitative and/or quantitative assessment of accident sequence frequencies (or probabilities) and their consequences. Risk management is a systematic application of management policies, procedures and practices to identify, analyze, plan, implement, control, communicate and document risks. Several tools and computer codes must be combined, in order to estimate both probabilities and consequences of accidents. Event Tree Analysis (ETA), Fault Tree Analysis (FTA), Reliability Block Diagrams (RBD), and Markov models are examples of evaluation tools that can support the safety and risk assessment for analyzing process systems, identifying potential accidents, and estimating consequences. Because of complexity of such analyzes, specialized computer codes are required, such as the reliability engineering software develop by Reliasoft® Corporation. BlockSim (FTA, RBD and Markov models), RENO (ETA and consequence assessment), Weibull++ (life data and uncertainty analysis), and Xfmea (qualitative risk assessment) are some codes that can be highlighted. This work describes an integrated approach using these tools and software to carry out reliability, safety, and risk assessment of nuclear facilities, as well as, and application example. (author)

  18. HSE assessment of explosion risk analysis in offshore safety cases

    Energy Technology Data Exchange (ETDEWEB)

    Brighton, P.W.M.; Fearnley, P.J.; Brearley, I.G. [Health and Safety Executive, Bootle (United Kingdom). Offshore Safety Div.

    1995-12-31

    In the past two years HSE has assessed around 250 Safety Cases for offshore oil and gas installations, building up a unique overview of the current state of the art on fire and explosion risk assessment. This paper reviews the explosion risk methods employed, focusing on the aspects causing most difficulty for assessment and acceptance of Safety Cases. Prediction of overpressures in offshore explosions has been intensively researched in recent years but the justification of the means of prevention, control and mitigation of explosions often depends on much additional analysis of the frequency and damage potential of explosions. This involves a number of factors, the five usually considered being: leak sizes; gas dispersion; ignition probabilities; the frequency distribution of explosion strength; and the prediction of explosion damage. Sources of major uncertainty in these factors and their implications for practical risk management decisions are discussed. (author)

  19. Report on probabilistic safety assessment (PSA) quality assurance in utilization of risk information

    International Nuclear Information System (INIS)

    2006-12-01

    Recently in Japan, introduction of nuclear safety regulations using risk information such as probabilistic safety assessment (PSA) has been considered and utilization of risk information in the rational and practical measures on safety assurance has made a progress to start with the operation or inspection area. The report compiled results of investigation and studies of PSA quality assurance in risk-informed activities in the USA. Relevant regulatory guide and standard review plan as well as issues and recommendations were reviewed for technical adequacy and advancement of probabilistic risk assessment technology in risk-informed decision making. Useful and important information to be referred as issues in PSA quality assurance was identified. (T. Tanaka)

  20. Hazard Identification and Risk Assessment of Health and Safety Approach JSA (Job Safety Analysis) in Plantation Company

    Science.gov (United States)

    Sugarindra, Muchamad; Ragil Suryoputro, Muhammad; Tiya Novitasari, Adi

    2017-06-01

    Plantation company needed to identify hazard and perform risk assessment as an Identification of Hazard and Risk Assessment Crime and Safety which was approached by using JSA (Job Safety Analysis). The identification was aimed to identify the potential hazards that might be the risk of workplace accidents so that preventive action could be taken to minimize the accidents. The data was collected by direct observation to the workers concerned and the results were recorded on a Job Safety Analysis form. The data were as forklift operator, macerator worker, worker’s creeper, shredder worker, workers’ workshop, mechanical line worker, trolley cleaning workers and workers’ crepe decline. The result showed that shredder worker value was 30 and had the working level with extreme risk with the risk value range was above 20. So to minimize the accidents could provide Personal Protective Equipment (PPE) which were appropriate, information about health and safety, the company should have watched the activities of workers, and rewards for the workers who obey the rules that applied in the plantation.

  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. Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA)

    DEFF Research Database (Denmark)

    Leuschner, R. G. K.; Robinson, T. P.; Hugas, M.

    2010-01-01

    Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA) to notified biological agents aiming at simplifying risk assessments across different scientific Panels and Units. The aim of this review is to outline the implementation...... and value of the QPS assessment for EFSA and to explain its principles such as the unambiguous identity of a taxonomic unit, the body of knowledge including potential safety concerns and how these considerations lead to a list of biological agents recommended for QPS which EFSA keeps updated through...

  3. [Patient safety in antibiotics administration: Risk assessment].

    Science.gov (United States)

    Maqueda Palau, M; Pérez Juan, E

    To determine the level of risk in the preparation and administration of antibiotics frequently used in the Intensive Care Unit using a risk matrix. A study was conducted using situation analysis and literature review of databases, protocols and good practice guidelines on intravenous therapy, drugs, and their administration routes. The most used antibiotics in the ICU registered in the ENVIN-HELICS program from 1 April to 30 June 2015 were selected. In this period, 257 patients received antimicrobial treatment and 26 antibiotics were evaluated. Variables studied: A risk assessment of each antibiotic using the scale Risk Assessment Tool, of the National Patient Safety Agency, as well as pH, osmolarity, type of catheter recommended for administration, and compatibility and incompatibility with other antibiotics studied. Almost two-thirds (65.3%) of antibiotics had more than 3 risk factors (represented by a yellow stripe), with the remaining 34.7% of antibiotics having between 0 and 2 risk factors (represented by a green stripe). There were no antibiotics with 6 or more risk factors (represented by a red stripe). Most drugs needed reconstitution, additional dilution, and the use of part of the vial to administer the prescribed dose. More than half of the antibiotics studied had a moderate risk level; thus measures should be adopted in order to reduce it. The risk matrix is a useful tool for the assessment and detection of weaknesses associated with the preparation and administration of intravenous antibiotics. Copyright © 2016 SECA. Publicado por Elsevier España, S.L.U. All rights reserved.

  4. Establishment of safety goal and its quantification based on risk assessment

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Muramatsu, Ken

    2017-01-01

    We must clarify the safety objectives sought by society in securing the safety of nuclear reactors and nuclear power plants. For that purpose, it is useful to utilize risk assessment. Quantitative methods including probabilistic risk assessment (PRA) are superior in terms of scientific rationality and quantitative performance compared with conventional deterministic methods, and able to indicate an objective numerical value of safety level. Consequently, quantitative methods can enhance the transparency, consistency, compliance, predictability, and explanatory power of regulatory decisions toward business operators and citizens. Business operators can explain the validity of their own safety assurance activities to regulators and citizens. The goal to be secured becomes clear by incorporating the safety goal into the specific performance goal required for the nuclear power plant from the viewpoint of deep safeguard, and it becomes easy to evaluate the effectiveness of the safety measures. It helps us greatly in judging and selecting the appropriateness of safety measures. It should be noted: the fact that the result of implementing the PRA satisfies the safety goal is not a sufficient condition in the sense of guaranteeing complete safety but a necessary condition. The nuclear power field is a region with large uncertainty, and research/efforts for accuracy improvement and evaluation validity will be required continuously. (A.O.)

  5. Risk assessment of computer-controlled safety systems for fusion reactors

    International Nuclear Information System (INIS)

    Fryer, M.O.; Bruske, S.Z.

    1983-01-01

    The complexity of fusion reactor systems and the need to display, analyze, and react promptly to large amounts of information during reactor operation will require a number of safety systems in the fusion facilities to be computer controlled. Computer software, therefore, must be included in the reactor safety analyses. Unfortunately, the science of integrating computer software into safety analyses is in its infancy. Combined plant hardware and computer software systems are often treated by making simple assumptions about software performance. This method is not acceptable for assessing risks in the complex fusion systems, and a new technique for risk assessment of combined plant hardware and computer software systems has been developed. This technique is an extension of the traditional fault tree analysis and uses structured flow charts of the software in a manner analogous to wiring or piping diagrams of hardware. The software logic determines the form of much of the fault trees

  6. Risk-informed approaches to assess ecological safety of facilities with radioactive waste

    International Nuclear Information System (INIS)

    Vashchenko, V.N.; Zlochevskij, V.V.; Skalozubov, V.I.

    2011-01-01

    Ingenious risk-informed methods to assess ecological safety of facilities with radioactive waste are proposed in the paper. Probabilistic norms on lethal outcomes and reliability of safety barriers are used as safety criteria. Based on the probability measures, it is established that ecological safety conditions are met for the standard criterion of lethal outcomes

  7. Food Safety Management in a Global Environment: The Role of Risk Assessment Models

    OpenAIRE

    Fuentes-Pila, Joaquin; Jimeno, Vicente; Manzano, Amparo; Rodriguez Monroy, Carlos; Mar Fernandez, Maria Del

    2006-01-01

    Quantitative risk assessment models are playing a minor role in the development of the new EU legal framework for food safety. There is a tendency of the EU institutions to apply the precautionary principle versus the predisposition of the USA institutions to rely on risk analysis. This paper provides a comparison of the role played by quantitative risk assessment models in the development of new policies on food safety in the EU and in the USA, focusing on a study case: the supply chain of s...

  8. Radiological safety and risk assessment

    International Nuclear Information System (INIS)

    Hunter, P.H.; Barg, D.C.; Baird, R.D.; Card, D.H.; de Souza, F.; Elder, J.; Felthauser, K.; Jensen, C.; Winkler, V.

    1982-02-01

    A brief radiological safety and risk assessment of a nuclear power generation center with an adjacent on-site waste disposal facility at a specific site in the State of Utah is presented. The assessment was conducted to assist in determining the feasibility and practicality of developing a nuclear energy center (NEC) in Utah consisting of nine 1250 MWe nuclear pressurized water reactor (PWR) electrical generating units arranged in 3 clusters of 3 units each known as triads. The site selected for this conceptual study is in the Horse Bench area about 15 miles directly south of the town of Green River, Utah. The radiological issues included direct radiation exposures to on-site workers and the off-site population, release of radioactive material, and effects of these releases for both normal operations and accidental occurrences. The basic finding of this study is that the concept of an NEC in the Green River area, specifically at the Horse Bench site, is radiologically feasible

  9. Application of risk assessment in upgrading safety and quality of radiochemical operations

    International Nuclear Information System (INIS)

    Lin, K.H.; Hightower, J.R.; Vaughen, V.C.A.

    1990-01-01

    A Comprehensive Safety Assessment and Upgrade Program (CSAUP) was commenced by the Chemical Technology Division (Chem Tech) at Oak Ridge National Laboratory (ORNL) to achieve excellence in the safety and quality of its operations and condition of its facilities. In the course of conducting CSAUP, a number of issues of concern were identified. The safety risk of these issues has been assessed, and planned actions were prepared for those issues that require corrective actions or improvement/upgrading. The planned actions were evaluated on consideration for the uniqueness of Chem Tech facilities and operations to determine the risks (high, moderate or low) involved by failure to implement the actions. The risk was defined in terms of the frequency and severity of impact. Priority of categorized actions was based on the urgency of the actions. 2 refs., 1 fig., 3 tabs

  10. Cyber Security Risk Assessment for the KNICS Safety Systems

    International Nuclear Information System (INIS)

    Lee, C. K.; Park, G. Y.; Lee, Y. J.; Choi, J. G.; Kim, D. H.; Lee, D. Y.; Kwon, K. C.

    2008-01-01

    In the Korea Nuclear I and C Systems Development (KNICS) project the platforms for plant protection systems are developed, which function as a reactor shutdown, actuation of engineered safety features and a control of the related equipment. Those are fully digitalized through the use of safety-grade programmable logic controllers (PLCs) and communication networks. In 2006 the Regulatory Guide 1.152 (Rev. 02) was published by the U.S. NRC and it describes the application of a cyber security to the safety systems in the Nuclear Power Plant (NPP). Therefore it is required that the new requirements are incorporated into the developed platforms to apply to NPP, and a cyber security risk assessment is performed. The results of the assessment were input for establishing the cyber security policies and planning the work breakdown to incorporate them

  11. Introduction to risk assessment

    International Nuclear Information System (INIS)

    Raina, V.M.

    2002-01-01

    This paper gives an introduction to risk assessment. It discusses the basic concepts of risk assessment, nuclear risk assessment process and products, the role of risk assessment products in nuclear safety assurance, the relationship between risk assessment and other safety analysis and risk assessment and safe operating envelope

  12. Non-animal approaches for consumer safety risk assessments: Unilever's scientific research programme.

    Science.gov (United States)

    Carmichael, Paul; Davies, Michael; Dent, Matt; Fentem, Julia; Fletcher, Samantha; Gilmour, Nicola; MacKay, Cameron; Maxwell, Gavin; Merolla, Leona; Pease, Camilla; Reynolds, Fiona; Westmoreland, Carl

    2009-12-01

    Non-animal based approaches to risk assessment are now routinely used for assuring consumer safety for some endpoints (such as skin irritation) following considerable investment in developing and applying new methods over the past 20 years. Unilever's research programme into non-animal approaches for safety assessment is currently focused on the application of new technologies to risk assessments in the areas of skin allergy, cancer and general toxicity (including inhalation toxicity). In all of these areas, a long-term investment is essential to increase the scientific understanding of the underlying biological and chemical processes that we believe will ultimately form a sound basis for novel risk assessment approaches. Our research programme in these priority areas consists of in-house research as well as Unilever-sponsored academic research, involvement with EU-funded projects (e.g. Sens-it-iv, carcinoGENOMICS), participation in cross-industry collaborative research (e.g. COLIPA, EPAA) and ongoing involvement with other scientific initiatives on non-animal approaches to risk assessment (e.g. UK NC3Rs, US 'Human Toxicology Project' consortium). 2009 FRAME.

  13. HANFORD SAFETY ANALYSIS & RISK ASSESSMENT HANDBOOK (SARAH)

    Energy Technology Data Exchange (ETDEWEB)

    EVANS, C B

    2004-12-21

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

  14. Presentation of a Software Method for Use of Risk Assessment in Building Fire Safety Measure Optimization

    Directory of Open Access Journals (Sweden)

    A. R. Koohpaei

    2012-05-01

    Full Text Available Background and aims: The property loss and physical injuries due to fire events in buildings demonstrate the necessity of implementation of efficient and performance based fire safety measures. Effective and high efficiency protection is possible when design and selection of protection measures are based on risk assessment. This study aims at presenting a software method to make possible selection and design of building fire safety measures based upon quantitative risk assessment and building characteristics. Methods: based on “Fire Risk Assessment Method for Engineer (FRAME” a program in MATLB software was written. The first section of this program, according to the FRAME method and based on the specification of a building, calculates the potential risk and acceptable risk level. In the second section, according to potential risk, acceptable risk level and the fire risk level that user want, program calculate concession of protective factor for that building.Results: The prepared software make it possible to assign the fire safety measure based on quantitative risk level and all building specifications. All calculations were performed with 0.001 of precision and the accuracy of this software was assessed with handmade calculations. During the use of the software if an error occurs in calculations, it can be distinguished in the output. Conclusion: Application of quantitative risk assessment is a suitable tool for increasing of efficiency in designing and execution of fire protection measure in building. With using this software the selected fire safety measure would be more efficient and suitable since the selection of fire safety measures performed on risk assessment and particular specification of a building. Moreover fire risk in the building can be managed easily and carefully.

  15. In prospect: role of safety assessment and risk regulation

    International Nuclear Information System (INIS)

    Novegno, A.; Askulaj, Eh.

    1987-01-01

    Problems of accident prevention in industry and power engineering are considered for the sake of environment and human health protection. Investigations into comparison of power system risks are conducted; based on the data obtained a possibility to control the risk has appeared. The IAEA provides an active assistance in realization of a program of coordinated investigations on the risk assessment using the cost-benefit method. For each NPP investigation into all types of its effect on the environment (risk for personnel and population under normal radioactivity releases and in case of accidents), is conducted. Two approaches to calculating the impacts of accidents at NPPs-'determination' one, based on the designed accident and safety probability evaluation exist. Regional approach appears to be the best one when solving the problems of risk control. Attention is paid to a joint project of the IAEA-UNO and WHO related to risk assessment and control for human health and environment protection at power and other complex commercial systems

  16. Health, Safety and Environmental Risk Assessment in Laboratory Sites

    Directory of Open Access Journals (Sweden)

    2012-05-01

    Full Text Available Introduction: ”Exposing to danger” or in other words, “risk” is a process which is led to an uncertain result in every field. Project risks are uncertain contingent events or situations that if they occur will have positive or negative effects on project’s objectives. Todays, research and educational process and more complicated and the professional risk management become much more difficult, as a result. .Material and Method: In this research, the health and safety issues have been studied and analyzed using ISO 14121 and the environmental issues by EMEA to determine the risk level separately for research laboratories and to prioritize corrective measure in each field (school. .Result: The finding in this study showed that from all the main risks within the rage of 38-86 percent have been decreased. Moreover average of the risk level for the health, safety and environment cases showed a significant decrease (Pvalue<0.0001 by implement controlling and protective countermeasures compariy to the priority state without any measures. . Conclusion: The risk assessment with hazards control strategy based on ISO 14121 is a compatible method in laboratory site as universities and other reasearch sites.

  17. Real-time safety risk assessment based on a real-time location system for hydropower construction sites.

    Science.gov (United States)

    Jiang, Hanchen; Lin, Peng; Fan, Qixiang; Qiang, Maoshan

    2014-01-01

    The concern for workers' safety in construction industry is reflected in many studies focusing on static safety risk identification and assessment. However, studies on real-time safety risk assessment aimed at reducing uncertainty and supporting quick response are rare. A method for real-time safety risk assessment (RTSRA) to implement a dynamic evaluation of worker safety states on construction site has been proposed in this paper. The method provides construction managers who are in charge of safety with more abundant information to reduce the uncertainty of the site. A quantitative calculation formula, integrating the influence of static and dynamic hazards and that of safety supervisors, is established to link the safety risk of workers with the locations of on-site assets. By employing the hidden Markov model (HMM), the RTSRA provides a mechanism for processing location data provided by the real-time location system (RTLS) and analyzing the probability distributions of different states in terms of false positives and negatives. Simulation analysis demonstrated the logic of the proposed method and how it works. Application case shows that the proposed RTSRA is both feasible and effective in managing construction project safety concerns.

  18. Exposure data and risk indicators for safety performance assessment in Europe.

    NARCIS (Netherlands)

    Papadimitriou, E. Yannis, G. Bijleveld, F.D. & Cardoso, J.L.

    2013-01-01

    The objective of this paper is the analysis of the state-of-the-art in risk indicators and exposure data for safety performance assessment in Europe, in terms of data availability, collection methodologies and use. More specifically, the concepts of exposure and risk are explored, as well as the

  19. L-Band Digital Aeronautical Communications System Engineering - Initial Safety and Security Risk Assessment and Mitigation

    Science.gov (United States)

    Zelkin, Natalie; Henriksen, Stephen

    2011-01-01

    This document is being provided as part of ITT's NASA Glenn Research Center Aerospace Communication Systems Technical Support (ACSTS) contract NNC05CA85C, Task 7: "New ATM Requirements--Future Communications, C-Band and L-Band Communications Standard Development." ITT has completed a safety hazard analysis providing a preliminary safety assessment for the proposed L-band (960 to 1164 MHz) terrestrial en route communications system. The assessment was performed following the guidelines outlined in the Federal Aviation Administration Safety Risk Management Guidance for System Acquisitions document. The safety analysis did not identify any hazards with an unacceptable risk, though a number of hazards with a medium risk were documented. This effort represents a preliminary safety hazard analysis and notes the triggers for risk reassessment. A detailed safety hazards analysis is recommended as a follow-on activity to assess particular components of the L-band communication system after the technology is chosen and system rollout timing is determined. The security risk analysis resulted in identifying main security threats to the proposed system as well as noting additional threats recommended for a future security analysis conducted at a later stage in the system development process. The document discusses various security controls, including those suggested in the COCR Version 2.0.

  20. Applicability and feasibility of systematic review for performing evidence-based risk assessment in food and feed safety

    DEFF Research Database (Denmark)

    Aiassa, E.; Higgins, J.P.T.; Frampton, G. K.

    2015-01-01

    for answering questions in health care, and can be implemented to minimise biases in food and feed safety risk assessment. However, no methodological frameworks exist for refining risk assessment multi-parameter models into questions suitable for systematic review, and use of meta-analysis to estimate all......Food and feed safety risk assessment uses multi-parameter models to evaluate the likelihood of adverse events associated with exposure to hazards in human health, plant health, animal health, animal welfare and the environment. Systematic review and meta-analysis are established methods...... parameters in the risk model. This approach to planning and prioritising systematic review seems to have useful implications for producing evidence-based food and feed safety risk assessment....

  1. Development of Risk Assessment Matrix for NASA Engineering and Safety Center

    Science.gov (United States)

    Malone, Roy W., Jr.; Moses, Kelly

    2004-01-01

    This paper describes a study, which had as its principal goal the development of a sufficiently detailed 5 x 5 Risk Matrix Scorecard. The purpose of this scorecard is to outline the criteria by which technical issues can be qualitatively and initially prioritized. The tool using this score card has been proposed to be one of the information resources the NASA Engineering and Safety Center (NESC) takes into consideration when making decisions with respect to incoming information on safety concerns across the entire NASA agency. The contents of this paper discuss in detail each element of the risk matrix scorecard, definitions for those elements and the rationale behind the development of those definitions. This scorecard development was performed in parallel with the tailoring of the existing Futron Corporation Integrated Risk Management Application (IRMA) software tool. IRMA was tailored to fit NESC needs for evaluating incoming safety concerns and was renamed NESC Assessment Risk Management Application (NAFMA) which is still in developmental phase.

  2. BARC-risk monitor- a tool for operational safety assessment in nuclear power plants

    International Nuclear Information System (INIS)

    Vinod, Gopika; Saraf, R.K.; Babar, A.K.; Hadap, Nikhil

    2000-12-01

    Probabilistic safety assessment has become a key tool as on today to identify and understand nuclear power plant vulnerabilities. As a result of the availability of these PSA studies, there is a desire to use them to enhance plant safety and to operate the nuclear stations in the most efficient manner. Risk monitor is a PC based tool, which computes the real time safety level and assists plant personnel to manage day-to-day activities. Risk monitor is a PC based user friendly software tool used for modification and re-analysis of a nuclear power plant. Operation of risk monitor is based on PSA methods for assisting in day to day applications. Risk monitoring programs can assess the risk profile and are used to optimise the operation of nuclear power plants with respect to a minimum risk level over the operating time. This report presents the background activities of risk monitor, its application areas and also gives the status of such tools in international scenarios. The software is based on the PSA model of Kaiga generating station and would be applicable to similar design configuration. (author)

  3. Methodology for assessment of safety risk due to potential accidents in US gaseous diffusion plants

    International Nuclear Information System (INIS)

    Turner, J.H.; O'Kain, D.U.

    1991-01-01

    Gaseous diffusion plants that operate in the United States represent a unique combination of nuclear and chemical hazards. Assessing and controlling the health, safety, and environmental risks that can result from natural phenomena events, process upset conditions, and operator errors require a unique methodology. Such a methodology has been developed for the diffusion plants and is being utilized to assess and control the risk of operating the plants. A summary of the methodology developed to assess the unique safety risks at the US gaseous diffusion plants is presented in this paper

  4. A generic standard for assessing and managing activities with significant risk to health and safety

    International Nuclear Information System (INIS)

    Wilde, T.S.; Sandquist, G.M.

    2005-01-01

    Some operations and activities in industry, business, and government can present an unacceptable risk to health and safety if not performed according to established safety practices and documented procedures. The nuclear industry has extensive experience and commitment to assessing and controlling such risks. This paper provides a generic standard based upon DOE Standard DOE-STD-3007- 93, Nov 1993, Change Notice No. 1, Sep 1998. This generic standard can be used to assess practices and procedures employed by any industrial and government entity to ensure that an acceptable level of safety and control prevail for such operations. When any activity and operation is determined to involve significant risk to health and safety to workers or the public, the organization should adopt and establish an appropriate standard and methodology to ensure that adequate health and safety prevail. This paper uses DOE experience and standards to address activities with recognized potential for impact upon health and safety. Existing and future assessments of health and safety issues can be compared and evaluated against this generic standard for insuring that proper planning, analysis, review, and approval have been made. (authors)

  5. A 3S Risk ?3SR? Assessment Approach for Nuclear Power: Safety Security and Safeguards.

    Energy Technology Data Exchange (ETDEWEB)

    Forrest, Robert; Reinhardt, Jason Christian; Wheeler, Timothy A.; Williams, Adam David

    2017-11-01

    Safety-focused risk analysis and assessment approaches struggle to adequately include malicious, deliberate acts against the nuclear power industry's fissile and waste material, infrastructure, and facilities. Further, existing methods do not adequately address non- proliferation issues. Treating safety, security, and safeguards concerns independently is inefficient because, at best, it may not take explicit advantage of measures that provide benefits against multiple risk domains, and, at worst, it may lead to implementations that increase overall risk due to incompatibilities. What is needed is an integrated safety, security and safeguards risk (or "3SR") framework for describing and assessing nuclear power risks that can enable direct trade-offs and interactions in order to inform risk management processes -- a potential paradigm shift in risk analysis and management. These proceedings of the Sandia ePRA Workshop (held August 22-23, 2017) are an attempt to begin the discussions and deliberations to extend and augment safety focused risk assessment approaches to include security concerns and begin moving towards a 3S Risk approach. Safeguards concerns were not included in this initial workshop and are left to future efforts. This workshop focused on four themes in order to begin building out a the safety and security portions of the 3S Risk toolkit: 1. Historical Approaches and Tools 2. Current Challenges 3. Modern Approaches 4. Paths Forward and Next Steps This report is organized along the four areas described above, and concludes with a summary of key points. 2 Contact: rforres@sandia.gov; +1 (925) 294-2728

  6. Risk-based safety indicators

    International Nuclear Information System (INIS)

    Sedlak, J.

    2001-12-01

    The report is structured as follows: 1. Risk-based safety indicators: Typology of risk-based indicators (RBIs); Tools for defining RBIs; Requirements for the PSA model; Data sources for RBIs; Types of risks monitored; RBIs and operational safety indicators; Feedback from operating experience; PSO model modification for RBIs; RBI categorization; RBI assessment; RBI applications; Suitable RBI applications. 2. Proposal for risk-based indicators: Acquiring information from operational experience; Method of acquiring safety relevance coefficients for the systems from a PSA model; Indicator definitions; On-line indicators. 3. Annex: Application of RBIs worldwide. (P.A.)

  7. HANFORD SAFETY ANALYSIS and RISK ASSESSMENT HANDBOOK (SARAH)

    International Nuclear Information System (INIS)

    EVANS, C.B.

    2004-01-01

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S and M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard

  8. Challenges in Risk Assessment: Quantitative Risk Assessment

    OpenAIRE

    Jacxsens, Liesbeth; Uyttendaele, Mieke; De Meulenaer, Bruno

    2016-01-01

    The process of risk analysis consists out of three components, risk assessment, risk management and risk communication. These components are internationally well spread by Codex Alimentarius Commission as being the basis for setting science based standards, criteria on food safety hazards, e.g. setting maximum limits of mycotoxins in foodstuffs. However, the technical component risk assessment is hard to elaborate and to understand. Key in a risk assessment is the translation of biological or...

  9. Hazard Identification and Risk Assessment in Water Treatment Plant considering Environmental Health and Safety Practice

    Directory of Open Access Journals (Sweden)

    Falakh Fajrul

    2018-01-01

    Full Text Available Water Treatment Plant (WTP is an important infrastructure to ensure human health and the environment. In its development, aspects of environmental safety and health are of concern. This paper case study was conducted at the Water Treatment Plant Company in Semarang, Central Java, Indonesia. Hazard identification and risk assessment is one part of the occupational safety and health program at the risk management stage. The purpose of this study was to identify potential hazards using hazard identification methods and risk assessment methods. Risk assessment is done using criteria of severity and probability of accident. The results obtained from this risk assessment are 22 potential hazards present in the water purification process. Extreme categories that exist in the risk assessment are leakage of chlorine and industrial fires. Chlorine and fire leakage gets the highest value because its impact threatens many things, such as industrial disasters that could endanger human life and the environment. Control measures undertaken to avoid potential hazards are to apply the use of personal protective equipment, but management will also be better managed in accordance with hazard control hazards, occupational safety and health programs such as issuing work permits, emergency response training is required, Very useful in overcoming potential hazards that have been determined.

  10. Hazard Identification and Risk Assessment in Water Treatment Plant considering Environmental Health and Safety Practice

    Science.gov (United States)

    Falakh, Fajrul; Setiani, Onny

    2018-02-01

    Water Treatment Plant (WTP) is an important infrastructure to ensure human health and the environment. In its development, aspects of environmental safety and health are of concern. This paper case study was conducted at the Water Treatment Plant Company in Semarang, Central Java, Indonesia. Hazard identification and risk assessment is one part of the occupational safety and health program at the risk management stage. The purpose of this study was to identify potential hazards using hazard identification methods and risk assessment methods. Risk assessment is done using criteria of severity and probability of accident. The results obtained from this risk assessment are 22 potential hazards present in the water purification process. Extreme categories that exist in the risk assessment are leakage of chlorine and industrial fires. Chlorine and fire leakage gets the highest value because its impact threatens many things, such as industrial disasters that could endanger human life and the environment. Control measures undertaken to avoid potential hazards are to apply the use of personal protective equipment, but management will also be better managed in accordance with hazard control hazards, occupational safety and health programs such as issuing work permits, emergency response training is required, Very useful in overcoming potential hazards that have been determined.

  11. Probabilistic safety assessment based expert systems in support of dynamic risk assessment

    International Nuclear Information System (INIS)

    Varde, P.V.; Sharma, U.L.; Marik, S.K.; Raina, V.K.; Tikku, A.C.

    2006-01-01

    Probabilistic Safety Assessment (PSA) studies are being performed, world over as part of integrated risk assessment for Nuclear Power Plants and in many cases PSA insight is utilized in support of decision making. Though the modern plants are built with inherent safety provisions, particularly to reduce the supervisory requirements during initial period into the accident, it is always desired to develop an efficient user friendly real-time operator advisory system for handling of plant transients/emergencies which would be of immense benefit for the enhancement of operational safety of the plant. This paper discusses an integrated approach for the development of operator support system. In this approach, PSA methodology and the insight obtained from PSA has been utilized for development of knowledge based or rule based experts system. While Artificial Neural Network (ANN) approach has been employed for transient identification, rule-base expert system shell environment was used for the development of diagnostic module in this system. Attempt has been made to demonstrate that this approach offers an efficient framework for addressing requirements related to handling of real-time/dynamic scenario. (author)

  12. Contrasting safety assessments of a runway incursion scenario: Event sequence analysis versus multi-agent dynamic risk modelling

    International Nuclear Information System (INIS)

    Stroeve, Sybert H.; Blom, Henk A.P.; Bakker, G.J.

    2013-01-01

    In the safety literature it has been argued, that in a complex socio-technical system safety cannot be well analysed by event sequence based approaches, but requires to capture the complex interactions and performance variability of the socio-technical system. In order to evaluate the quantitative and practical consequences of these arguments, this study compares two approaches to assess accident risk of an example safety critical sociotechnical system. It contrasts an event sequence based assessment with a multi-agent dynamic risk model (MA-DRM) based assessment, both of which are performed for a particular runway incursion scenario. The event sequence analysis uses the well-known event tree modelling formalism and the MA-DRM based approach combines agent based modelling, hybrid Petri nets and rare event Monte Carlo simulation. The comparison addresses qualitative and quantitative differences in the methods, attained risk levels, and in the prime factors influencing the safety of the operation. The assessments show considerable differences in the accident risk implications of the performance of human operators and technical systems in the runway incursion scenario. In contrast with the event sequence based results, the MA-DRM based results show that the accident risk is not manifest from the performance of and relations between individual human operators and technical systems. Instead, the safety risk emerges from the totality of the performance and interactions in the agent based model of the safety critical operation considered, which coincides very well with the argumentation in the safety literature.

  13. Marked point process framework for living probabilistic safety assessment and risk follow-up

    International Nuclear Information System (INIS)

    Arjas, Elja; Holmberg, Jan

    1995-01-01

    We construct a model for living probabilistic safety assessment (PSA) by applying the general framework of marked point processes. The framework provides a theoretically rigorous approach for considering risk follow-up of posterior hazards. In risk follow-up, the hazard of core damage is evaluated synthetically at time points in the past, by using some observed events as logged history and combining it with re-evaluated potential hazards. There are several alternatives for doing this, of which we consider three here, calling them initiating event approach, hazard rate approach, and safety system approach. In addition, for a comparison, we consider a core damage hazard arising in risk monitoring. Each of these four definitions draws attention to a particular aspect in risk assessment, and this is reflected in the behaviour of the consequent risk importance measures. Several alternative measures are again considered. The concepts and definitions are illustrated by a numerical example

  14. Risk analysis methods: their importance for safety assessment of practices using radiation

    International Nuclear Information System (INIS)

    Dumenigo, C; Vilaragut, J.J.; Ferro, R.; Guillen, A.; Ramirez, M.L.; Ortiz Lopez, P.; Rodriguez, M.; McDonnell, J.D.; Papadopulos, S.; Pereira, P.P.; Goncalvez, M.; Morales, J.; Larrinaga, E.; Lopez Morones, R.; Sanchez, R.; Delgado, J.M.; Sanchez, C.; Somoano, F.

    2008-01-01

    Radiation safety has been based for many years on verification of compliance with regulatory requirements, codes of practice and international standards, which can be considered prescriptive methods. Accident analyses have been published, lessons have been learned and safety assessments have incorporated the need to check whether a facility is ready to avoid accidents similar to the reported ones. These approaches can be also called 'reactive methods'. They have in common the fundamental limitation of being restricted to reported experience, but do not take into account other potential events, which were never published or never happened, i.e. latent risks. Moreover, they focus on accident sequences with major consequences and low probability but may not pay enough attention to other sequences leading to lower, but still significant consequences with higher probability. More proactive approaches are, therefore, needed, to assess risk in radiation facilities. They aim at identifying all potential equipment faults and human error, which can lead to predefined unwanted consequences and are based on the general risk equation: Risk = Probability of occurrence of an accidental sequence * magnitude of the consequences. In this work, a review is given of the experience obtained by the countries of the Ibero American Forum of Nuclear and Radiation Safety Regulatory Organizations, by applying proactive methods to radiotherapy practice. In particular, probabilistic safety assessment (PSA) used for external beam treatments with linear electron accelerators and two studies, on cobalt 60 therapy and brachytherapy using the risk-matrix approach are presented. The work has identified event sequences, their likelihood of occurrence, the consequences, the efficiency of interlocks and control checks and the global importance in terms of overall risk, to facilitate decision making and implementation of preventive measures. A comparison is presented of advantages and limitations of

  15. Probabilistic Causal Analysis for System Safety Risk Assessments in Commercial Air Transport

    Science.gov (United States)

    Luxhoj, James T.

    2003-01-01

    Aviation is one of the critical modes of our national transportation system. As such, it is essential that new technologies be continually developed to ensure that a safe mode of transportation becomes even safer in the future. The NASA Aviation Safety Program (AvSP) is managing the development of new technologies and interventions aimed at reducing the fatal aviation accident rate by a factor of 5 by year 2007 and by a factor of 10 by year 2022. A portfolio assessment is currently being conducted to determine the projected impact that the new technologies and/or interventions may have on reducing aviation safety system risk. This paper reports on advanced risk analytics that combine the use of a human error taxonomy, probabilistic Bayesian Belief Networks, and case-based scenarios to assess a relative risk intensity metric. A sample case is used for illustrative purposes.

  16. Risk analysis and safety rationale

    International Nuclear Information System (INIS)

    Bengtsson, G.

    1989-01-01

    Decision making with respect to safety is becoming more and more complex. The risk involved must be taken into account together with numerous other factors such as the benefits, the uncertainties and the public perception. Can the decision maker be aided by some kind of system, general rules of thumb, or broader perspective on similar decisions? This question has been addressed in a joint Nordic project relating to nuclear power. Modern techniques for risk assessment and management have been studied, and parallels drawn to such areas as offshore safety and management of toxic chemicals in the environment. The report summarises the finding of 5 major technical reports which have been published in the NORD-series. The topics includes developments, uncertainties and limitations in probabilistic safety assessments, negligible risks, risk-cost trade-offs, optimisation of nuclear safety and radiation protection, and the role of risks in the decision making process. (author) 84 refs

  17. Risk-based approach to long-term safety assessment for near surface disposal of radioactive waste in Korea

    International Nuclear Information System (INIS)

    Jeong, C.W.; Kim, K.I.; Lee, J.I.

    2000-01-01

    This paper presents the Korean regulatory approach to safety assessment consistent with probabilistic, risk-based long-term safety requirements for near surface disposal facilities. The approach is based on: (1) From the standpoint of risk limitation, normal processes and probabilistic disruptive events should be integrated in a similar manner in terms of potential exposures; and (2) The uncertainties inherent in the safety assessment should be reduced using appropriate exposure scenarios. In addition, this paper emphasizes the necessity of international guidance for quantifying potential exposures and the corresponding risks from radioactive waste disposal. (author)

  18. Safety assessment principles for nuclear plants

    International Nuclear Information System (INIS)

    1992-01-01

    The present Safety Assessment Principles result from the revision of those which were drawn up following a recommendation arising from the Sizewell-B enquiry. The principles presented here relate only to nuclear safety; there is a section on risks from normal operation and accident conditions and the standards against which those risks are assessed. A major part of the document deals with the principles that cover the design of nuclear plants. The revised Safety assessment principles are aimed primarily at the safety assessment of new nuclear plants but they will also be used in assessing existing plants. (UK)

  19. HTGR accident and risk assessment

    International Nuclear Information System (INIS)

    Silady, F.A.; Everline, C.J.; Houghton, W.J.

    1982-01-01

    This paper is a synopsis of the high-temperature gas-cooled reactor probabilistic risk assessments (PRAs) performed by General Atomic Company. Principal topics presented include: HTGR safety assessments, peer interfaces, safety research, process gas explosions, quantitative safety goals, licensing applications of PRA, enhanced safety, investment risk assessments, and PRA design integration

  20. Neuropsychological assessment of driving safety risk in older adults with and without neurologic disease.

    Science.gov (United States)

    Anderson, Steven W; Aksan, Nazan; Dawson, Jeffrey D; Uc, Ergun Y; Johnson, Amy M; Rizzo, Matthew

    2012-01-01

    Decline in cognitive abilities can be an important contributor to the driving problems encountered by older adults, and neuropsychological assessment may provide a practical approach to evaluating this aspect of driving safety risk. The purpose of the present study was to evaluate several commonly used neuropsychological tests in the assessment of driving safety risk in older adults with and without neurological disease. A further goal of this study was to identify brief combinations of neuropsychological tests that sample performances in key functional domains and thus could be used to efficiently assess driving safety risk. A total of 345 legally licensed and active drivers over the age of 50, with no neurologic disease (N = 185), probable Alzheimer's disease (N = 40), Parkinson's disease (N = 91), or stroke (N = 29), completed vision testing, a battery of 10 neuropsychological tests, and an 18-mile drive on urban and rural roads in an instrumented vehicle. Performances on all neuropsychological tests were significantly correlated with driving safety errors. Confirmatory factor analysis was used to identify 3 key cognitive domains assessed by the tests (speed of processing, visuospatial abilities, and memory), and several brief batteries consisting of one test from each domain showed moderate corrected correlations with driving performance. These findings are consistent with the notion that driving places demands on multiple cognitive abilities that can be affected by aging and age-related neurological disease, and that neuropsychological assessment may provide a practical off-road window into the functional status of these cognitive systems.

  1. Exposure data and risk indicators for safety performance assessment in Europe.

    Science.gov (United States)

    Papadimitriou, Eleonora; Yannis, George; Bijleveld, Frits; Cardoso, João L

    2013-11-01

    The objective of this paper is the analysis of the state-of-the-art in risk indicators and exposure data for safety performance assessment in Europe, in terms of data availability, collection methodologies and use. More specifically, the concepts of exposure and risk are explored, as well as the theoretical properties of various exposure measures used in road safety research (e.g. vehicle- and person-kilometres of travel, vehicle fleet, road length, driver population, time spent in traffic, etc.). Moreover, the existing methods for collecting disaggregate exposure data for risk estimates at national level are presented and assessed, including survey methods (e.g. travel surveys, traffic counts) and databases (e.g. national registers). A detailed analysis of the availability and quality of existing risk exposure data is also carried out. More specifically, the results of a questionnaire survey in the European countries are presented, with detailed information on exposure measures available, their possible disaggregations (i.e. variables and values), their conformity to standard definitions and the characteristics of their national collection methods. Finally, the potential of international risk comparisons is investigated, mainly through the International Data Files with exposure data (e.g. Eurostat, IRTAD, ECMT, UNECE, IRF, etc.). The results of this review confirm that comparing risk rates at international level may be a complex task, as the availability and quality of exposure estimates in European countries varies significantly. The lack of a common framework for the collection and exploitation of exposure data limits significantly the comparability of the national data. On the other hand, the International Data Files containing exposure data provide useful statistics and estimates in a systematic way and are currently the only sources allowing international comparisons of road safety performance under certain conditions. Copyright © 2013 Elsevier Ltd. All

  2. Risk measures in living probabilistic safety assessment

    International Nuclear Information System (INIS)

    Holmberg, J.; Niemelae, I.

    1993-05-01

    The main objectives of the study are: to define risk measures and suggested uses of them in various living PSA applications for the operational safety management and to describe specific model features required for living PSA applications. The report is based on three case studies performed within the Nordic research project Safety Evaluation by Use of Living PSA and Safety Indicators. (48 refs., 11 figs., 17 tabs.)

  3. [Safety Walkround as a risk assessment tool: the first Italian experience].

    Science.gov (United States)

    Levati, A; Amato, S; Adrario, E; De Flaviis, C; Delia, C; Milesi, S; Petrini, F; Bevilacqua, L

    2009-01-01

    In 2007 the Study Group "Clinical Risk Management" of the Italian Society of Anaesthesia and Intensive Care Unit (SIAARTI) performed a multicentric study in Intensive Care Unit (ICU) to assess the feasibility and efficacy of the Safety WalkRound (SWR) as a tool for the risk assessment. As the environment and organization of ICU are more complex than anaesthesia ones, mainly due to the severity of patients, high number of involved healthcare givers and different kinds of procedures, the Study Group decided that a check list is not fit for ICU and , after a careful review of the literature, chose to test the Safety WalkRound. in four Italian General ICUs. The SWR was born in 2003 when Frankel plans a structured interview of 15 questions (about 50% open) to collect operators' opinion about rate and type of errors, near misses, communication, problems regarding the report of adverse events and suggestions to increase patient safety. Consequently SWR is a tool of risk assessment alternative to the Incident Reporting which is marked by a diffuse underreporting of operators. Although the SWR is a new tool not validated in Italian language neither published in Italy on PubMed journals , the Study Group has decided that it might be fit for the organization of Italian Healthcare System. A back translation of the validated model of Joint Commission was provided and the translated version has been lightly changed to be employed in hospitals with and without Incident Reporting . The questions have been changed or introduced on the basis of the organization vulnerabilities detected with observational techniques or Focus Group. The interview performed in Italy contains 16 questions classified into five groups: a) error, b) error prevention, c) communication, teamwork and leadership, d) error discussion and e) relationship with patients and their families. The answers collected have been analyzed to detect the vulnerabilities in the organizations and specify the improvements to

  4. Integrated Safety and Security Risk Assessment Methods: A Survey of Key Characteristics and Applications

    NARCIS (Netherlands)

    Chockalingam, Sabarathinam; Hadziosmanovic, D.; Pieters, Wolter; Texeira, Andre; van Gelder, Pieter

    2016-01-01

    Over the last years, we have seen several security incidents that compromised system safety, of which some caused physical harm to people. Meanwhile, various risk assessment methods have been developed that integrate safety and security, and these could help to address the corresponding threats by

  5. Risk perception, risk management and safety assessment: what can governments do to increase public confidence in their vaccine system?

    Science.gov (United States)

    MacDonald, Noni E; Smith, Jennifer; Appleton, Mary

    2012-09-01

    For decades vaccine program managers and governments have devoted many resources to addressing public vaccine concerns, vaccine risk perception, risk management and safety assessment. Despite ever growing evidence that vaccines are safe and effective, public concerns continue. Education and evidence based scientific messages have not ended concerns. How can governments and programs more effectively address the public's vaccine concerns and increase confidence in the vaccine safety system? Vaccination hesitation has been attributed to concerns about vaccine safety, perceptions of high vaccine risks and low disease risk and consequences. Even when the public believes vaccines are important for protection many still have concerns about vaccine safety. This overview explores how heuristics affect public perception of vaccines and vaccine safety, how the public finds and uses vaccine information, and then proposes strategies for changes in the approach to vaccine safety communications. Facts and evidence confirming the safety of vaccines are not enough. Vaccine beliefs and behaviours must be shaped. This will require a shift in the what, when, how and why of vaccine risk and benefit communication content and practice. A change to a behavioural change strategy such as the WHO COMBI program that has been applied to disease eradication efforts is suggested. Copyright © 2011. Published by Elsevier Ltd.. All rights reserved.

  6. Procedures to relate the NII safety assessment principles for nuclear reactors to risk

    CERN Document Server

    Kelly, G N; Hemming, C R

    1985-01-01

    Within the framework of the Public Inquiry into the proposed pressurised water reactor (PWR) at Sizewell, estimates were made of the levels of individual and societal risk from a PWR designed in a manner which would conform to the safety assessment principles formulated by the Nuclear Installations Inspectorate (NII). The procedures used to derive these levels of risk are described in this report. The opportunity has also been taken to revise the risk estimates made at the time of the Inquiry by taking account of additional data which were not then available, and to provide further quantification of the likely range of uncertainty in the predictions. This re-analysis has led to small changes in the levels of risk previously evaluated, but these are not sufficient to affect the broad conclusions reached before. For a reactor just conforming to the NII safety assessment principles a maximum individual risk of fatal cancer of about 10 sup - sup 6 per year of reactor operation has been estimated; the societal ris...

  7. Integrated Safety and Security Risk Assessment Methods: A Survey of Key Characteristics and Applications

    OpenAIRE

    Chockalingam, Sabarathinam; Hadziosmanovic, Dina; Pieters, Wolter; Teixeira, Andre; van Gelder, Pieter

    2017-01-01

    Over the last years, we have seen several security incidents that compromised system safety, of which some caused physical harm to people. Meanwhile, various risk assessment methods have been developed that integrate safety and security, and these could help to address the corresponding threats by implementing suitable risk treatment plans. However, an overarching overview of these methods, systematizing the characteristics of such methods, is missing. In this paper, we conduct a systematic l...

  8. Risk assessment for safety laboratories in Politeknik Negeri Medan

    Science.gov (United States)

    Viyata Sundawa, Bakti; Hutajulu, Elferida; Sirait, Regina; Banurea, Waldemar; Indrayadi; Mulyadi, Sangap

    2017-09-01

    International Labour Organization (ILO) estimated 2.34 million people die each year because accidents and diseases in workplace. It also impact to economic losses in some countries. It need to do safety and healthy in working environment especially in laboratory. Identification of potential hazards and risks must be done in Telecommunication Laboratory Politeknik Negeri Medan. Therefore, this study was assessed 5 of potential hazards and risks in our laboratory by Likert Scale. This object was divided into 2 assessment namely likelihood of hazards and severity of consequences. Collecting data is taken from questionnaire who involved 100 students at random academic level. The result showed The highest score is chemical hazards 73.2% in likelihood of hazards and electrical hazards 85% in severity of consequences. This condition is classified as “high” state. Big attention must be given to “high” state because it can help us to determine mitigate action.

  9. Evaluation of safety assessment methodologies in Rocky Flats Risk Assessment Guide (1985) and Building 707 Final Safety Analysis Report (1987)

    International Nuclear Information System (INIS)

    Walsh, B.; Fisher, C.; Zigler, G.; Clark, R.A.

    1990-01-01

    FSARs. Rockwell International, as operating contractor at the Rocky Flats plant, conducted a safety analysis program during the 1980s. That effort resulted in Final Safety Analysis Reports (FSARs) for several buildings, one of them being the Building 707 Final Safety Analysis Report, June 87 (707FSAR) and a Plant Safety Analysis Report. Rocky Flats Risk Assessment Guide, March 1985 (RFRAG85) documents the methodologies that were used for those FSARs. Resources available for preparation of those Rocky Flats FSARs were very limited. After addressing the more pressing safety issues, some of which are described below, the present contractor (EG ampersand G) intends to conduct a program of upgrading the FSARs. This report presents the results of a review of the methodologies described in RFRAG85 and 707FSAR and contains suggestions that might be incorporated into the methodology for the FSAR upgrade effort

  10. Metrics design for safety assessment

    NARCIS (Netherlands)

    Luo, Yaping; van den Brand, M.G.J.

    2016-01-01

    Context:In the safety domain, safety assessment is used to show that safety-critical systems meet the required safety objectives. This process is also referred to as safety assurance and certification. During this procedure, safety standards are used as development guidelines to keep the risk at an

  11. Risk-Informed Safety Assurance and Probabilistic Assessment of Mission-Critical Software-Intensive Systems

    Science.gov (United States)

    Guarro, Sergio B.

    2010-01-01

    This report validates and documents the detailed features and practical application of the framework for software intensive digital systems risk assessment and risk-informed safety assurance presented in the NASA PRA Procedures Guide for Managers and Practitioner. This framework, called herein the "Context-based Software Risk Model" (CSRM), enables the assessment of the contribution of software and software-intensive digital systems to overall system risk, in a manner which is entirely compatible and integrated with the format of a "standard" Probabilistic Risk Assessment (PRA), as currently documented and applied for NASA missions and applications. The CSRM also provides a risk-informed path and criteria for conducting organized and systematic digital system and software testing so that, within this risk-informed paradigm, the achievement of a quantitatively defined level of safety and mission success assurance may be targeted and demonstrated. The framework is based on the concept of context-dependent software risk scenarios and on the modeling of such scenarios via the use of traditional PRA techniques - i.e., event trees and fault trees - in combination with more advanced modeling devices such as the Dynamic Flowgraph Methodology (DFM) or other dynamic logic-modeling representations. The scenarios can be synthesized and quantified in a conditional logic and probabilistic formulation. The application of the CSRM method documented in this report refers to the MiniAERCam system designed and developed by the NASA Johnson Space Center.

  12. Probabilistic earthquake risk assessment as a tool to improve safety and explanatory adequacy

    International Nuclear Information System (INIS)

    Itoi, Tatsuya

    2015-01-01

    This paper explains the concept of probabilistic earthquake risk assessment, mainly from the viewpoint as a tool to improve safety and explanatory adequacy. The definition of risk is the expected value of undesirable effect in an engineering meaning that is likely to occur in the future, and it is defined in risk management as the triplet of scenario (what can happen), frequency, and impact. As for the earthquake risk assessment of a nuclear power plant, the fragility of structure / system / component (SSC) against earthquake (so-called earthquake fragility) is assessed, and by combining with the earthquake hazard that has been separately obtained, the occurrence frequency and impact of the accident are obtained. From the view of the authors, earthquake risk assessment is for the purpose of decision-making, and is not intended to calculate the probability in a scientifically rigorous manner. For ensuring the quality of risk assessment, the table of 'Expert utilization standards for the evaluation of epistemological uncertainty' is used. Sole quantitative risk assessment is not necessarily sufficient for risk management. It would be important to find how to build the 'framework for comprehensive decision-making.' (A.O.)

  13. Probabilistic risk assessment as an aid to risk management

    International Nuclear Information System (INIS)

    Garrick, B.J.

    1982-01-01

    Probabilistic risk assessments are providing important insights into nuclear power plant safety. Their value is two-fold: first as a means of quantifying nuclear plant risk including contributors to risk, and second as an aid to risk management. A risk assessment provides an analytical plant model that can be the basis for performing meaningful decision analyses for controlling safety. It is the aspect of quantitative risk management that makes probabilistic risk assessment an important technical discipline of the future

  14. Relationship between Risk Assessment and Compliance to Health and Safety in Ugandan Secondary Schools

    Science.gov (United States)

    Sekiwu, Denis; Kabanda, Milly; Naluwemba, Esther Frances; Kaggwa, Victoria Tamale

    2015-01-01

    Health hazards are part and parcel of human life necessitating the provision of safety in every organizational environment (WHO regional Office for Africa, 2004). Likewise, the area of safety and accident prevention is of great concern to school improvement. The study sought to investigate the relationship between Risk Assessment and Compliancy to…

  15. Stockholm Safety Conference. Analysis of the sessions on radiological protection, licensing and risk assessment

    International Nuclear Information System (INIS)

    Gea, A.

    1981-01-01

    A summary of the sessions on radiological protection, licensing and risk assessment in the safety conference of Stockholm is presented. It is considered the new point of view of the nuclear safety, probabilistic analysis, components failures probability and accident analysis. They are included conclusions applicable in many cases to development countries. (author)

  16. Advanced korean industrial safety and health policy with risk assessment.

    Science.gov (United States)

    Kwon, Hyuckmyun; Cho, Jae Hyun; Moon, Il; Choi, Jaewook; Park, Dooyong; Lee, Youngsoon

    2010-09-01

    This article describes a systematic roadmap master plan for advanced industrial safety and health policy in Korea, with an emphasis on. Since Korean industries had first emergence of industrial safety and health policy in 1953, enormous efforts have been made on upgrading the relevant laws in order to reflect real situation of industrial work environment in accordance with rapid changes of Korean and global business over three decades. Nevertheless, current policy has major defects; too much techniques-based articles, diverged contents in less organization, combined enforcement and punishments and finally enforcing regulations full of commands and control. These deficiencies have make it difficult to accommodate changes of social, industrial and employment environment in customized fashion. The approach to the solution must be generic at the level of paradigm-shift rather than local modifications and enhancement. The basic idea is to establish a new system integrated with a risk assessment scheme, which encourages employers to apply to their work environment under comprehensive responsibility. The risk assessment scheme is designed to enable to inspect employers' compliances afterwards. A project comprises four yearly phases based on applying zones; initially designating and operating a specified risk zone, gradually expanding the special zones during a period of 3 years (2010-2012) and the final zone expanded to entire nation. In each phase, the intermediate version of the system is updated through a process of precise and unbiased validation in terms of its operability, feasibility and sustainability with building relevant infrastructures as needed.

  17. Pedestrian safety management using the risk-based approach

    Directory of Open Access Journals (Sweden)

    Romanowska Aleksandra

    2017-01-01

    Full Text Available The paper presents a concept of a multi-level pedestrian safety management system. Three management levels are distinguished: strategic, tactical and operational. The basis for the proposed approach to pedestrian safety management is a risk-based method. In the approach the elements of behavioural and systemic theories were used, allowing for the development of a formalised and repeatable procedure integrating the phases of risk assessment and response to the hazards of road crashes involving pedestrians. Key to the method are tools supporting pedestrian safety management. According to the risk management approach, the tools can be divided into two groups: tools supporting risk assessment and tools supporting risk response. In the paper attention is paid to selected tools supporting risk assessment, with particular emphasis on the methods for estimating forecasted pedestrian safety measures (at strategic, national and regional level and identification of particularly dangerous locations in terms of pedestrian safety at tactical (regional and local and operational level. The proposed pedestrian safety management methods and tools can support road administration in making rational decisions in terms of road safety, safety of road infrastructure, crash elimination measures or reducing the consequences suffered by road users (particularly pedestrians as a result of road crashes.

  18. Radiation safety assessment of cobalt 60 external beam radiotherapy using the risk-matrix method

    International Nuclear Information System (INIS)

    Dumenigo, C; Vilaragut, J.J.; Ferro, R.; Guillen, A.; Ramirez, M.L.; Ortiz Lopez, P.; Rodriguez, M.; McDonnell, J.D.; Papadopulos, S.; Pereira, P.P.; Goncalvez, M.; Morales, J.; Larrinaga, E.; Lopez Morones, R.; Sanchez, R.; Delgado, J.M.; Sanchez, C.; Somoano, F.

    2008-01-01

    External beam radiotherapy is the only practice in which humans are placed directly in a radiation beam with the intention to deliver a very high dose. This is why safety in radiotherapy is very critical, and is a matter of interest to both radiotherapy departments and regulatory bodies. Accidental exposures have occurred throughout the world, thus showing the need for systematic safety assessments, capable to identify preventive measures and to minimize consequences of accidental exposure. Risk-matrix is a systematic approach which combines the relevant event features to assess the overall risk of each particular event. Once an event sequence is identified, questions such as how frequent the event, how severe the potential consequences and how reliable the existing safety measures are answered in a risk-matrix table. The ultimate goal is to achieve that the overall risk for events with severe consequences should always be low o very low. In the present study, the risk-matrix method has been applied to an hypothetical radiotherapy department, which could be equivalent to an upper level hospital of the Ibero American region, in terms of safety checks and preventive measures. The application of the method has identified 76 event sequences and revealed that the hypothetical radiotherapy department is sufficiently protected (low risk) against them, including 23 event sequences with severe consequences. The method has revealed that the risk of these sequences could grow to high level if certain specific preventive measures were degraded with time. This study has identified these preventive measures, thus facilitating a rational allocation of resources in regular controls to detect any loss of reliability. The method has proven to have an important practical value and is affordable at hospital level. The elaborated risk-matrix can be easily adapted to local circumstances, in terms of existing controls and safety measures. This approach can help hospitals to identify

  19. Health risk from radioactive and chemical environmental contamination: common basis for assessment and safety decision making

    International Nuclear Information System (INIS)

    Demin, V.

    2004-01-01

    To meet the growing practical need in risk analysis in Russia health risk assessment tools and regulations have been developed in the frame of few federal research programs. RRC Kurchatov Institute is involved in R and D on risk analysis activity in these programs. One of the objectives of this development is to produce a common, unified basis of health risk analysis for different sources of risk. Current specific and different approaches in risk assessment and establishing safety standards developed for chemicals and ionising radiation are analysed. Some recommendations are given to produce the common approach. A specific risk index R has been proposed for safety decision-making (establishing safety standards and other levels of protective actions, comparison of various sources of risk, etc.). The index R is defined as the partial mathematical expectation of lost years of healthy life (LLE) due to exposure during a year to a risk source considered. The more concrete determinations of this index for different risk sources derived from the common definition of R are given. Generic safety standards (GSS) for the public and occupational workers have been suggested in terms of this index. Secondary specific safety standards have been derived from GSS for ionizing radiation and a number of other risk sources including environmental chemical pollutants. Other general and derived levels for decision-making have also been proposed including the e-minimum level. Their possible dependence on the national or regional health-demographic data is shortly considered. Recommendations are given on methods and criteria for comparison of various sources of risk. Some examples of risk comparison are demonstrated in the frame of different comparison tasks. The paper has been prepared on the basis of the research work supported by International Science and Technology Centre, Moscow (project no. 2558). (author)

  20. Risk management and safety

    International Nuclear Information System (INIS)

    Niehaus, F.; Novegno, A.

    1985-01-01

    Risk assessment, including probabilistic analyses, has made great progress over the past decade. In spite of the inherent uncertainties it has now become possible to utilize methods and results for decision making at various levels. This paper will, therefore, review risk management in industrial installations, risk management for energy safety policy and prospects of risk management in highly industrialized areas. (orig.) [de

  1. A risk assessment approach to evaluating food safety based on product surveillance

    NARCIS (Netherlands)

    Notermans, S.; Nauta, M.J.; Jansen, J.; Jouve, J.L.; Mead, G.C.

    1998-01-01

    This paper outlines a risk assessment approach to food safety evaluation, which is based on testing a particular type of food, or group of similar foods, for relevant microbial pathogens. The results obtained are related to possible adverse effects on the health of consumers. The paper also gives an

  2. [OCCUPATIONAL HEALTH RISK ASSESSMENT AND MANAGEMENT IN WORKERS IN IMPROVEMENT OF NATIONAL POLICY IN OCCUPATIONAL HYGIENE AND SAFETY].

    Science.gov (United States)

    Shur, P Z; Zaĭtseva, N V; Alekseev, V B; Shliapnikov, D M

    2015-01-01

    In accordance with the international documents in the field of occupational safety and hygiene, the assessment and minimization of occupational risks is a key instrument for the health maintenance of workers. One of the main ways to achieve it is the minimization of occupational risks. Correspondingly, the instrument for the implementation of this method is the methodology of analysis of occupational risks. In Russian Federation there were the preconditions for the formation of the system for the assessment and management of occupational risks. As the target of the national (state) policy in the field of occupational safety in accordance with ILO Conventions it can be offered the prevention of accidents and injuries to health arising from work or related with it, minimizing the causes of hazards inherent in the working environment, as far as it is reasonably and practically feasible. Global trend ofusing the methodology of the assessment and management of occupational risks to life and health of citizens requires the improvement of national policies in the field of occupational hygiene and safety. Achieving an acceptable level of occupational risk in the formation of national policy in the field of occupational hygiene and safety can be considered as one of the main tasks.

  3. HSE's safety assessment principles for criticality safety

    International Nuclear Information System (INIS)

    Simister, D N; Finnerty, M D; Warburton, S J; Thomas, E A; Macphail, M R

    2008-01-01

    The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs relate to all aspects of safety in nuclear facilities including the technical discipline of criticality safety. The purpose of this paper is to set out for the benefit of a wider audience some of the thinking behind the final published words and to provide an insight into the development of UK regulatory guidance. The paper notes that it is HSE's intention that the Safety Assessment Principles should be viewed as a reflection of good practice in the context of interpreting primary legislation such as the requirements under site licence conditions for arrangements for producing an adequate safety case and for producing a suitable and sufficient risk assessment under the Ionising Radiations Regulations 1999 (SI1999/3232 www.opsi.gov.uk/si/si1999/uksi_19993232_en.pdf). (memorandum)

  4. Risk assessment: An employer's perspective

    International Nuclear Information System (INIS)

    Williams, K.C.

    1992-01-01

    There is no question that a careful assessment of risk is essential for safe industrial operations. For that reason, a thoughtful analysis of the effectiveness of available risk assessment technologies is prerequisite for responsible corporate decision making. An 'employer's' perspective on risk assessment cannot be constrained by any artificial restrictions which that term may imply. In reality, all those who are involved in the execution of an industrial enterprise: managers, regulators, the affected public, and especially those employees exposed to hazards, are necessarily partners in assessment of risk. The perspective of this paper is that of the oil and gas industry, in which the author's organization, Exxon Company, International, participates. The paper addresses what Exxon requires to assess and manage risk in its worldwide operations. The author is aware, however, through contacts with industry colleagues, that some of Exxon's initiatives are representative of similar actions being taken by others. 1992 is the European Year of Safety, Health and Hygiene, coinciding with the United Kingdom's Presidency of the European Council. It is also the year in which new 'goal-setting' regulations covering safety in the U.K. offshore oil industry were put forward by the Health and Safety Commission. These regulations, based largely on Lord Cullen's recommendations following the Piper Alpha tragedy, set the pace for safety in the British North Sea and will significantly impact the safety of offshore oil installations worldwide. The requirement for risk assessment, using a systematic process of analysing and evaluating risk, is a key component of this safety regime

  5. Risk assessment: An employer's perspective

    Energy Technology Data Exchange (ETDEWEB)

    Williams, K C [Exxon International (United States)

    1992-07-01

    There is no question that a careful assessment of risk is essential for safe industrial operations. For that reason, a thoughtful analysis of the effectiveness of available risk assessment technologies is prerequisite for responsible corporate decision making. An 'employer's' perspective on risk assessment cannot be constrained by any artificial restrictions which that term may imply. In reality, all those who are involved in the execution of an industrial enterprise: managers, regulators, the affected public, and especially those employees exposed to hazards, are necessarily partners in assessment of risk. The perspective of this paper is that of the oil and gas industry, in which the author's organization, Exxon Company, International, participates. The paper addresses what Exxon requires to assess and manage risk in its worldwide operations. The author is aware, however, through contacts with industry colleagues, that some of Exxon's initiatives are representative of similar actions being taken by others. 1992 is the European Year of Safety, Health and Hygiene, coinciding with the United Kingdom's Presidency of the European Council. It is also the year in which new 'goal-setting' regulations covering safety in the U.K. offshore oil industry were put forward by the Health and Safety Commission. These regulations, based largely on Lord Cullen's recommendations following the Piper Alpha tragedy, set the pace for safety in the British North Sea and will significantly impact the safety of offshore oil installations worldwide. The requirement for risk assessment, using a systematic process of analysing and evaluating risk, is a key component of this safety regime.

  6. Advanced Korean Industrial Safety and Health Policy with Risk Assessment

    Directory of Open Access Journals (Sweden)

    Hyuckmyun Kwon

    2010-09-01

    Full Text Available This article describes a systematic roadmap master plan for advanced industrial safety and health policy in Korea, with an emphasis on. Since Korean industries had first emergence of industrial safety and health policy in 1953, enormous efforts have been made on upgrading the relevant laws in order to reflect real situation of industrial work environment in accordance with rapid changes of Korean and global business over three decades. Nevertheless, current policy has major defects; too much techniques-based articles, diverged contents in less organization, combined enforcement and punishments and finally enforcing regulations full of commands and control. These deficiencies have make it difficult to accommodate changes of social, industrial and employment environment in customized fashion. The approach to the solution must be generic at the level of paradigm- shift rather than local modifications and enhancement. The basic idea is to establish a new system integrated with a risk assessment scheme, which encourages employers to apply to their work environment under comprehensive responsibility. The risk assessment scheme is designed to enable to inspect employers’ compliances afterwards. A project comprises four yearly phases based on applying zones; initially designating and operating a specified risk zone, gradually expanding the special zones during a period of 3 years (2010-2012 and the final zone expanded to entire nation. In each phase, the intermediate version of the system is updated through a process of precise and unbiased validation in terms of its operability, feasibility and sustainability with building relevant infrastructures as needed.

  7. Probabilistic risk assessment, Volume I

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    This book contains 158 papers presented at the International Topical Meeting on Probabilistic Risk Assessment held by the American Nuclear Society (ANS) and the European Nuclear Society (ENS) in Port Chester, New York in 1981. The meeting was second in a series of three. The main focus of the meeting was on the safety of light water reactors. The papers discuss safety goals and risk assessment. Quantitative safety goals, risk assessment in non-nuclear technologies, and operational experience and data base are also covered. Included is an address by Dr. Chauncey Starr

  8. Applications of nuclear safety probabilistic risk assessment to nuclear security for optimized risk mitigation

    Energy Technology Data Exchange (ETDEWEB)

    Donnelly, S.K.; Harvey, S.B. [Amec Foster Wheeler, Toronto, Ontario (Canada)

    2016-06-15

    Critical infrastructure assets such as nuclear power generating stations are potential targets for malevolent acts. Probabilistic methodologies can be applied to evaluate the real-time security risk based upon intelligence and threat levels. By employing this approach, the application of security forces and other protective measures can be optimized. Existing probabilistic safety analysis (PSA) methodologies and tools employed. in the nuclear industry can be adapted to security applications for this purpose. Existing PSA models can also be adapted and enhanced to consider total plant risk, due to nuclear safety risks as well as security risks. By creating a Probabilistic Security Model (PSM), safety and security practitioners can maximize the safety and security of the plant while minimizing the significant costs associated with security upgrades and security forces. (author)

  9. Safety methodology and risk targets

    International Nuclear Information System (INIS)

    Kazimi, M.S.

    1983-01-01

    In assessing the potential safety concerns of fusion, the experience from other energy sources lead to a variety of safety assessment approaches. The available approaches are: (1) The maximum possible accident approach; (2) The maximum credible accident approach; (3) The probabilistic total risk assessment. In the first approach, the mechanistic development of the events leading to the safety concern is ignored. Instead, the total radioactivity of the plant is assumed accessible to the public. Such an approach is obviously conservative and unrealistic. In the second approach a selection is made among the most severe of the possible accidents, and the progression of the accident is modeled as mechanistically as possible. In this case, the passive and active accident mitigation capabilities of the plant are taken into consideration. The result is expected to be that none or only a fraction of the total radioactivity can be released to the public. The adverse effect of this approach is to concentrate attention on a particular accident class, and perhaps not allow for other classes, a judgement that may later become undesirable. The probabilistic risk assessment requires the safety analysts to consider all classes of accidents and estimate both the probabilities of their occurrences and their consequences. Thus, the plant design in fact is subjected to a thorough investigation and the impact of alterations in design can be reflected in the total risk estimate. The disadvantage of this approach lies in the absence of well defined acceptable risk criteria as well as the large effect of public perception factors on the accepted risk. This paper will review the impact of application of these approaches in determination of the level of protection needed against activation product release to the atmosphere. (author)

  10. Preliminary Marine Safety Risk Assessment, Brandon Road Lock and Dam Invasive Species Control Measures

    Science.gov (United States)

    2016-12-01

    Decision makers must include control-measure monitoring and emergency “interventions” to insure safety. The Coast Guard operational commanders...system” incorporates a travelling car on a rail above the barge-loading wharf to prevent loading personnel, cargo surveyors, or others from falling...to the Gulf of Mexico . As “Loopers”, they will have already transited the CSSC electric barriers. Preliminary Marine Safety Risk Assessment, BRLD

  11. The issue of risk dilution in risk assessments

    International Nuclear Information System (INIS)

    Wilmot, R.; Robinson, P.

    2004-01-01

    This paper explores an issue that was first highlighted more than 20 years ago during an inquiry concerning the Sizeweli B nuclear power station in the UK. In the probabilistic safety assessment for this plant, the proponent had apparently reduced its estimates of risk by admitting to increased uncertainty about the timing of certain events. This situation is counter-intuitive, since an increase in uncertainty about the factors contributing to safety would be expected to lead to less confidence and hence to greater risk. This paradoxical situation was termed 'risk dilution' and it has been a topic of interest to reviewers of safety cases since. The recent international peer review of the Yucca Mountain performance assessments concluded that there was a potential for risk dilution in the assumptions and calculations presented. The next section describes how assumptions about the timing of events and other aspects of an assessment may lead to risk dilution, and this is followed by two examples based on recent performance assessments. The final section discusses how potential problems can be identified in safety cases, and the types of response that a regulator might adopt as a result. (authors)

  12. Assessing systemwide occupational health and safety risks of energy technologies

    International Nuclear Information System (INIS)

    Rowe, M.D.

    1982-01-01

    Input-output modelling is now being used to assess systemwide occupational and public health and safety risks of energy technologies. Some of the advantages and disadvantages of this method are presented and some of its important limitations are discussed. Its primary advantage is that it provides a standard method with which to compare technologies on a consistent basis without extensive economic analysis. Among the disadvantages are limited range of applicability, limited spectrum of health impacts, and inability to identify unusual health impacts unique to a new technology. (author)

  13. Risk assessment by the occupational safety and health at work in the process of geological exploration

    Directory of Open Access Journals (Sweden)

    Staletović Novica M.

    2015-01-01

    Full Text Available This paper presents a model of risk assessment in terms of safety and health at work in the process of geological work/ drilling. Optimization model estimates OH & S risk for work place qualified driller, is in line with the provisions of the Mining and Geological exploration, the Law on Safety and Health at Work, the application of the requirements of ISO 31000 and criteria Kinny methods. Model estimates OH & S risks is the basis for the development and implementation of the management system of protection of health and safety at work according to BS OHSAS 18001: 2008 model is applied, checked and verified the approved exploration areas during execution and supervision applied geological exploration (of metals on the territory of the Republic of Serbia.

  14. Additional safety assessment of ITER - Addition safety investigation of the INB ITER

    International Nuclear Information System (INIS)

    2012-01-01

    This assessment aims at re-assessing safety margins in the light of events which occurred in Fukushima Daiichi, i.e. extreme natural events challenging the safety of installations. After a presentation of some characteristics of the ITER installation (location, activities, buildings, premise detritiation systems, electric supply, handling means, radioactive materials, chemical products, nuclear risks, specific risks), the report addresses the installation robustness by identifying cliff-edge effect risks which can be related to a loss of confinement of radioactive materials, explosions, a significant increase of exposure level, a possible effect on water sheets, and so on. The next part addresses the various aspects related to a seismic risk: installation sizing (assessment methodology, seismic risk characterization in Cadarache), sizing protection measures, installation compliance, and margin assessment. External flooding is the next addressed risk: installation sizing with respect to this specific risk, protection measures, installation compliance, margin assessment, and studied additional measures. Other extreme natural phenomena are considered (meteorological conditions, earthquake and flood) which may have effects on other installations (dam, canal). Then, the report addresses technical risks like the loss of electric supplies and cooling systems, the way a crisis is managed in terms of technical and human means and organization in different typical accidental cases. Subcontracting practices are also discussed. A synthesis proposes an overview of this additional safety assessment and discusses the impact which could have additional measures which could be implemented

  15. Issues regarding Risk Effect Analysis of Digitalized Safety Systems and Main Risk Contributors

    International Nuclear Information System (INIS)

    Kang, Hyun Gook; Jang, Seung-Cheol

    2008-01-01

    Risk factors of safety-critical digital systems affect overall plant risk. In order to assess this risk effect, a risk model of a digitalized safety system is required. This article aims to provide an overview of the issues when developing a risk model and demonstrate their effect on plant risk quantitatively. Research activities in Korea for addressing these various issues, such as the software failure probability and the fault coverage of self monitoring mechanism are also described. The main risk contributors related to the digitalized safety system were determined in a quantitative manner. Reactor protection system and engineered safety feature component control system designed as part of the Korean Nuclear I and C System project are used as example systems. Fault-tree models were developed to assess the failure probability of a system function which is designed to generate an automated signal for actuating both of the reactor trip and the complicated accident-mitigation actions. The developed fault trees were combined with a plant risk model to evaluate the effect of a digitalized system's failure on the plant risk. (authors)

  16. IAEA safety requirements for safety assessment of fuel cycle facilities and activities

    International Nuclear Information System (INIS)

    Jones, G.

    2013-01-01

    The IAEA's Statute authorises the Agency to establish standards of safety for protection of health and minimisation of danger to life and property. In that respect, the IAEA has established a Safety Fundamentals publication which contains ten safety principles for ensuring the protection of workers, the public and the environment from the harmful effects of ionising radiation. A number of these principles require safety assessments to be carried out as a means of evaluating compliance with safety requirements for all nuclear facilities and activities and to determine the measures that need to be taken to ensure safety. The safety assessments are required to be carried out and documented by the organisation responsible for operating the facility or conducting the activity, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorisation process. In addition to the principles of the Safety Fundamentals, the IAEA establishes requirements that must be met to ensure the protection of people and the environment and which are governed by the principles in the Safety Fundamentals. The IAEA's Safety Requirements publication 'Safety Assessment for Facilities and Activities', establishes the safety requirements that need to be fulfilled in conducting and maintaining safety assessments for the lifetime of facilities and activities, with specific attention to defence in depth and the requirement for a graded approach to the application of these safety requirements across the wide range of fuel cycle facilities and activities. Requirements for independent verification of the safety assessment that needs to be carried out by the operating organisation, including the requirement for the safety assessment to be periodically reviewed and updated are also covered. For many fuel cycle facilities and activities, environmental impact assessments and non-radiological risk assessments will be required. The

  17. University building safety index measurement using risk and implementation matrix

    Science.gov (United States)

    Rahman, A.; Arumsari, F.; Maryani, A.

    2018-04-01

    Many high rise building constructed in several universities in Indonesia. The high-rise building management must provide the safety planning and proper safety equipment in each part of the building. Unfortunately, most of the university in Indonesia have not been applying safety policy yet and less awareness on treating safety facilities. Several fire accidents in university showed that some significant risk should be managed by the building management. This research developed a framework for measuring the high rise building safety index in university The framework is not only assessed the risk magnitude but also designed modular building safety checklist for measuring the safety implementation level. The safety checklist has been developed for 8 types of the university rooms, i.e.: office, classroom, 4 type of laboratories, canteen, and library. University building safety index determined using risk-implementation matrix by measuring the risk magnitude and assessing the safety implementation level. Building Safety Index measurement has been applied in 4 high rise buildings in ITS Campus. The building assessment showed that the rectorate building in secure condition and chemical department building in beware condition. While the library and administration center building was in less secure condition.

  18. Nuclear power plant's safety and risk

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1975-01-01

    Starting with a comprehensive safety strategy as evolved over the past years and the present legal provisions for the construction and operation of nuclear power plants, the risk of the intended operation, of accidents and unforeseen events is discussed. Owing to the excellent safety record of nuclear power plants, main emphasis in discussing accidents is given to the precautionary analysis within the framework of the licensing procedure. In this context, hypothetical accidents are mentioned only as having been utilized for general risk comparisons. The development of a comprehensive risk concept for a completely objective safety assessment of nuclear power plants remains as a final goal. (orig.) [de

  19. Food and drinking water safety: Can risk assessment help us to get our priorities right?

    International Nuclear Information System (INIS)

    Denner, W.H.B.

    1992-01-01

    Huge resources are devoted worldwide by governments and food producers to ensure that food and water are produced with due regard to the safety of consumers. This inevitably involves some form of risk assessment but in the field of food safety a formalised process of risk assessment has been slow to develop. An ad hoc mosaic or approaches has evolved which varies not only between countries but sometimes within countries as well. This may not be unexpected considering the vast variety of kinds of food hazards (table 1). Not only do food-related hazards themselves vary widely, so do the effects which they can cause. For example microorganisms can cause mild stomach upsets or death within a few hours depending upon the organism involved. For chemical contaminants in food the potential effects are usually less acute although no less serious. Many of the chemicals of concern are believed to be carcinogens whose effects might only be realised after many years of exposure. Nutritional imbalances may result in an increased risk from diseases, such as heart disease and cancer, which can also arise from other causes. In these latter examples it is often difficult to relate cause to effect even when extensive epidemiological evidence is available. It is important to understand the enormous diversity in possible food-related hazards before describing the assessment of risks associated with them. This great diversity makes it unlikely that any single approach to risk assessment can suit all situations. This means that making comparisons between risks from different hazards is extremely difficult. In fact trying to allocate resources in a logical way between all the different kinds of food-related hazards is a major problem in itself. For with finite resources there is always the danger of finding that focusing on one area of concern results in a potential risk elsewhere being neglected. The aim of this paper is to take a general look at some of the issues facing those with

  20. Food and drinking water safety: Can risk assessment help us to get our priorities right?

    Energy Technology Data Exchange (ETDEWEB)

    Denner, W H.B. [Ministry of Agriculture, Fisheries and Food, London (United Kingdom)

    1992-07-01

    Huge resources are devoted worldwide by governments and food producers to ensure that food and water are produced with due regard to the safety of consumers. This inevitably involves some form of risk assessment but in the field of food safety a formalised process of risk assessment has been slow to develop. An ad hoc mosaic or approaches has evolved which varies not only between countries but sometimes within countries as well. This may not be unexpected considering the vast variety of kinds of food hazards (table 1). Not only do food-related hazards themselves vary widely, so do the effects which they can cause. For example microorganisms can cause mild stomach upsets or death within a few hours depending upon the organism involved. For chemical contaminants in food the potential effects are usually less acute although no less serious. Many of the chemicals of concern are believed to be carcinogens whose effects might only be realised after many years of exposure. Nutritional imbalances may result in an increased risk from diseases, such as heart disease and cancer, which can also arise from other causes. In these latter examples it is often difficult to relate cause to effect even when extensive epidemiological evidence is available. It is important to understand the enormous diversity in possible food-related hazards before describing the assessment of risks associated with them. This great diversity makes it unlikely that any single approach to risk assessment can suit all situations. This means that making comparisons between risks from different hazards is extremely difficult. In fact trying to allocate resources in a logical way between all the different kinds of food-related hazards is a major problem in itself. For with finite resources there is always the danger of finding that focusing on one area of concern results in a potential risk elsewhere being neglected. The aim of this paper is to take a general look at some of the issues facing those with

  1. Road Safety Risk Assessment: An Analysis of Transport Policy and Management for Low-, Middle-, and High-Income Asian Countries

    Directory of Open Access Journals (Sweden)

    Syyed Adnan Raheel Shah

    2018-02-01

    Full Text Available Road safety assessment has played a crucial role in the theory and practice of transport management systems. This paper focuses on risk evaluation in the Asian region by exploring the interaction between road safety risk and influencing factors. In the first stage, a data envelopment analysis (DEA method is applied to calculate and rank the road safety risk levels of Asian countries. In the second stage, a structural equation model (SEM with latent variables is applied to analyze the interaction between the road safety risk level and the latent variables, measured by six observed performance indicators, i.e., financial impact, institutional framework, infrastructure and mobility, legislation and policy, vehicular road users, and trauma management. Finally, this paper illustrates the applicability of this DEA-SEM approach for road safety performance analysis.

  2. Implementation of a risk assessment tool based on a probabilistic safety assessment developed for radiotherapy practices

    International Nuclear Information System (INIS)

    Paz, A.; Godinez, V.; Lopez, R.

    2010-10-01

    The present work describes the implementation process and main results of the risk assessment to the radiotherapy practices with Linear Accelerators (Linac), with cobalt 60, and with brachytherapy. These evaluations were made throughout the risk assessment tool for radiotherapy practices SEVRRA (risk evaluation system for radiotherapy), developed at the Mexican National Commission in Nuclear Safety and Safeguards derived from the outcome obtained with the Probabilistic Safety Analysis developed at the Ibero-American Regulators Forum for these radiotherapy facilities. The methodology used is supported by risk matrices method, a mathematical tool that estimates the risk to the patient, radiation workers and public from mechanical failures, mis calibration of the devices, human mistakes, and so. The initiating events are defined as those undesirable events that, together with other failures, can produce a delivery of an over-dose or an under-dose of the medical prescribed dose, to the planned target volume, or a significant dose to non prescribed human organs. Initiating events frequency and reducer of its frequency (actions intended to avoid the accident) are estimated as well as robustness of barriers to those actions, such as mechanical switches, which detect and prevent the accident from occurring. The spectrum of the consequences is parameterized, and the actions performed to reduce the consequences are identified. Based on this analysis, a software tool was developed in order to simplify the evaluations to radiotherapy installations and it has been applied as a first step forward to some Mexican installations, as part of a national implementation process, the final goal is evaluation of all Mexican facilities in the near future. The main target and benefits of the SEVRRA implementation are presented in this paper. (Author)

  3. Implementation of a risk assessment tool based on a probabilistic safety assessment developed for radiotherapy practices

    Energy Technology Data Exchange (ETDEWEB)

    Paz, A.; Godinez, V.; Lopez, R., E-mail: abpaz@cnsns.gob.m [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2010-10-15

    The present work describes the implementation process and main results of the risk assessment to the radiotherapy practices with Linear Accelerators (Linac), with cobalt 60, and with brachytherapy. These evaluations were made throughout the risk assessment tool for radiotherapy practices SEVRRA (risk evaluation system for radiotherapy), developed at the Mexican National Commission in Nuclear Safety and Safeguards derived from the outcome obtained with the Probabilistic Safety Analysis developed at the Ibero-American Regulators Forum for these radiotherapy facilities. The methodology used is supported by risk matrices method, a mathematical tool that estimates the risk to the patient, radiation workers and public from mechanical failures, mis calibration of the devices, human mistakes, and so. The initiating events are defined as those undesirable events that, together with other failures, can produce a delivery of an over-dose or an under-dose of the medical prescribed dose, to the planned target volume, or a significant dose to non prescribed human organs. Initiating events frequency and reducer of its frequency (actions intended to avoid the accident) are estimated as well as robustness of barriers to those actions, such as mechanical switches, which detect and prevent the accident from occurring. The spectrum of the consequences is parameterized, and the actions performed to reduce the consequences are identified. Based on this analysis, a software tool was developed in order to simplify the evaluations to radiotherapy installations and it has been applied as a first step forward to some Mexican installations, as part of a national implementation process, the final goal is evaluation of all Mexican facilities in the near future. The main target and benefits of the SEVRRA implementation are presented in this paper. (Author)

  4. Reactor safety study. An assessment of accident risks in U.S. commercial nuclear power plants. Executive summary: main report

    International Nuclear Information System (INIS)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks

  5. 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

  6. Managing risk in healthcare: understanding your safety culture using the Manchester Patient Safety Framework (MaPSaF).

    Science.gov (United States)

    Parker, Dianne

    2009-03-01

    To provide sufficient information about the Manchester Patient Safety Framework (MaPSaF) to allow healthcare professionals to assess its potential usefulness. The assessment of safety culture is an important aspect of risk management, and one in which there is increasing interest among healthcare organizations. Manchester Patient Safety Framework offers a theory-based framework for assessing safety culture, designed specifically for use in the NHS. The framework covers multiple dimensions of safety culture, and five levels of safety culture development. This allows the generation of a profile of an organization's safety culture in terms of areas of relative strength and challenge, which can be used to identify focus issues for change and improvement. Manchester Patient Safety Framework provides a useful method for engaging healthcare professionals in assessing and improving the safety culture in their organization, as part of a programme of risk management.

  7. Safety and risk assessment of ceramide 3 in cosmetic products.

    Science.gov (United States)

    Choi, Seul Min; Lee, Byung-Mu

    2015-10-01

    Ceramide 3 is used mainly as a moisturizer in various cosmetic products. Although several safety studies on formulations containing pseudo-ceramide or ceramide have been conducted at the preclinical and clinical levels for regulatory approval, no studies have evaluated the systemic toxicity of ceramide 3. To address this issue, we conducted a risk assessment and comprehensive toxicological review of ceramide and pseudo-ceramide. We assumed that ceramide 3 is present in various personal and cosmetic products at concentrations of 0.5-10%. Based on previously reported exposure data, the margin of safety (MOS) was calculated for product type, use pattern, and ceramide 3 concentration. Lipsticks with up to 10% ceramide 3 (MOS = 4111) are considered safe, while shampoos containing 0.5% ceramide 3 (MOS = 148) are known to be safe. Reported MOS values for body lotion applied to the hands (1% ceramide 3) and back (5% ceramide 3) were 103 and 168, respectively. We anticipate that face cream would be safe up to a ceramide 3 concentration of 3% (MOS = 149). Collectively, the MOS approach indicated no safety concerns for cosmetic products containing less than 1% ceramide 3. Copyright © 2015 Elsevier Ltd. All rights reserved.

  8. Estimating and controlling workplace risk: an approach for occupational hygiene and safety professionals.

    Science.gov (United States)

    Toffel, Michael W; Birkner, Lawrence R

    2002-07-01

    The protection of people and physical assets is the objective of health and safety professionals and is accomplished through the paradigm of anticipation, recognition, evaluation, and control of risks in the occupational environment. Risk assessment concepts are not only used by health and safety professionals, but also by business and financial planners. Since meeting health and safety objectives requires financial resources provided by business and governmental managers, the hypothesis addressed here is that health and safety risk decisions should be made with probabilistic processes used in financial decision-making and which are familiar and recognizable to business and government planners and managers. This article develops the processes and demonstrates the use of incident probabilities, historic outcome information, and incremental impact analysis to estimate risk of multiple alternatives in the chemical process industry. It also analyzes how the ethical aspects of decision-making can be addressed in formulating health and safety risk management plans. It is concluded that certain, easily understood, and applied probabilistic risk assessment methods used by business and government to assess financial and outcome risk have applicability to improving workplace health and safety in three ways: 1) by linking the business and health and safety risk assessment processes to securing resources, 2) by providing an additional set of tools for health and safety risk assessment, and 3) by requiring the risk assessor to consider multiple risk management alternatives.

  9. Health, safety and environment risk assessment in gas pipelines by indexing method:case of Kermanshah Sanandaj oil pipeline

    OpenAIRE

    Y. Hamidi; I. Mohamadfam; M. Motamedzadeh

    2009-01-01

    Background and AimsUsing pipelines for oil products transportation involves ranges of safety, health and environmental risks, this option however, is dominant with numerous  advantages. The purpose of this study was; relative risk assessment of abovementioned risk in Kermanshah-Sanandaj Oil Pipeline.MethodsThe method used in this study was Kent Muhlbauer method in which relative risk was assessed using third-party damage, corrosion, design, incorrect operations and leak impact  factor.Results...

  10. Incorporation of formal safety assessment and Bayesian network in navigational risk estimation of the Yangtze River

    International Nuclear Information System (INIS)

    Zhang, D.; Yan, X.P.; Yang, Z.L.; Wall, A.; Wang, J.

    2013-01-01

    Formal safety assessment (FSA), as a structured and systematic risk evaluation methodology, has been increasingly and broadly used in the shipping industry around the world. Concerns have been raised as to navigational safety of the Yangtze River, China's largest and the world's busiest inland waterway. Over the last few decades, the throughput of ships in the Yangtze River has increased rapidly due to the national development of the Middle and Western parts of China. Accidents such as collisions, groundings, contacts, oil-spills and fires occur repeatedly, often causing serious consequences. In order to improve the navigational safety in the Yangtze River, this paper estimates the navigational risk of the Yangtze River using the FSA concept and a Bayesian network (BN) technique. The navigational risk model is established by considering both probability and consequences of accidents with respect to a risk matrix method, followed by a scenario analysis to demonstrate the application of the proposed model

  11. Probabilistic risk assessment: Number 219

    International Nuclear Information System (INIS)

    Bari, R.A.

    1985-01-01

    This report describes a methodology for analyzing the safety of nuclear power plants. A historical overview of plants in the US is provided, and past, present, and future nuclear safety and risk assessment are discussed. A primer on nuclear power plants is provided with a discussion of pressurized water reactors (PWR) and boiling water reactors (BWR) and their operation and containment. Probabilistic Risk Assessment (PRA), utilizing both event-tree and fault-tree analysis, is discussed as a tool in reactor safety, decision making, and communications. (FI)

  12. Comparison between Canadian probabilistic safety assessment methods formulated by Atomic Energy of Canada limited and probabilistic risk assessment methods

    International Nuclear Information System (INIS)

    Shapiro, H.S.; Smith, J.E.

    1989-01-01

    The procedures used by Atomic Energy of Canada Limited (AECL) to perform probabilistic safety assessments (PRAs) differ somewhat from conventionally accepted probabilistic risk assessment (PRA) procedures used elsewhere. In Canada, PSA is used by AECL as an audit tool for an evolving design. The purpose is to assess the safety of the plant in engineering terms. Thus, the PSA procedures are geared toward providing engineering feedback so that necessary changes can be made to the design at an early stage, input can be made to operating procedures, and test and maintenance programs can be optimized in terms of costs. Most PRAs, by contrast, are performed in plants that are already built. Their main purpose is to establish the core melt frequency and the risk to the public due to core melt. Also, any design modification is very expensive. The differences in purpose and timing between PSA and PRA have resulted in differences in methodology and scope. The PSA procedures are used on all plants being designed by AECL

  13. 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.

  14. 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

  15. Application of non-dose/risk indicators for confidence-building in the H12 safety assessment

    International Nuclear Information System (INIS)

    Miyahara, K.; Makino, H.; Takasu, A.; Naito, M.; Umeke, H.; Wakasugi, K.; Ishiguro, K.

    2002-01-01

    In the H12 study, non-dose/risk safety indicators have also been considered with a view to increasing confidence in the safety assessment. The H12 safety assessment considers system evolution for a range of scenarios; not only normal groundwater scenarios but also isolation failure scenarios due to unlikely natural disruptive events. The calculated nuclide concentrations and fluxes in the surface environment for the reference groundwater scenario were compared with measurements of naturally occurring nuclides. This comparison indicated that the concentration and fluxes of radionuclides released from the repository would be several orders of magnitude lower than those of natural radionuclides. There may exist cases, such as some natural disruptive events, where the likelihood of occurrence is extremely low and the 'Reference Biosphere' approach is difficult to be applied for biosphere modelling. The use of qualitative assessment to allow comparison with naturally occurring nuclides based on observations of natural systems may play a role in supporting the robustness of the system concept. These examples suggest that relevant application of these non-dose/risk indicators supports a more robust case. An advantage to applying such indicators is that both technical and non-technical audiences can judge the relative, long-term impact of a deep geological repository. (author)

  16. Safety risk assessment for vertical concrete formwork activities in civil engineering construction.

    Science.gov (United States)

    López-Arquillos, Antonio; Rubio-Romero, Juan Carlos; Gibb, Alistair G F; Gambatese, John A

    2014-01-01

    The construction sector has one of the worst occupational health and safety records in Europe. Of all construction tasks, formwork activities are associated with a high frequency of accidents and injuries. This paper presents an investigation of the activities and related safety risks present in vertical formwork for in-situ concrete construction in the civil engineering sector. Using the methodology of staticized groups, twelve activities and ten safety risks were identified and validated by experts. Every safety risk identified in this manner was quantified for each activity using binary methodology according to the frequency and severity scales developed in prior research. A panel of experts was selected according to the relevant literature on staticized groups. The results obtained show that the activities with the highest risk in vertical formwork tasks are: Plumbing and leveling of forms, cutting of material, handling materials with cranes, and climbing or descending ladders. The most dangerous health and safety risks detected were falls from height, cutting and overexertion. The research findings provide construction practitioners with further evidence of the hazardous activities associated with concrete formwork construction and a starting point for targeting worker health and safety programmes.

  17. Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

    International Nuclear Information System (INIS)

    Chung, Dae Wook

    2011-01-01

    Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

  18. On the Regulation of Life Safety Risk

    DEFF Research Database (Denmark)

    Faber, Michael Havbro; Sørensen, John Dalsgaard; Vrouwenvelder, A.C.W.M.

    2015-01-01

    . Starting point is taken in a short outline of what is considered to comprise the present best practice rationale for life safety and health risk regulation. Thereafter, based on selected principal examples from different application areas, inconsistencies in present best practice risk quantification...... absolute level of individual life safety risk subject to assessment of acceptability. It is highlighted that a major cause of inconsistency in risk quantifications and comparisons originates from the fact that present regulations partly address societal activities and partly address applied technologies...

  19. ALARP considerations in criticality safety assessments

    International Nuclear Information System (INIS)

    Bowden, Russell L.; Barnes, Andrew; Thorne, Peter R.; Venner, Jack

    2003-01-01

    Demonstrating that the risk to the public and workers is As Low As Reasonably Practicable (ALARP) is a fundamental requirement of safety cases for nuclear facilities in the United Kingdom. This is embodied in the Safety Assessment Principles (SAPs) published by the Regulator, the essence of which is incorporated within the safety assessment processes of the various nuclear site licensees. The concept of ALARP within criticality safety assessments has taken some time to establish in the United Kingdom. In principle, the licensee is obliged to search for a deterministic criticality safety solution, such as safe geometry vessels and passive control features, rather than placing reliance on active measurement devices and plant administrative controls. This paper presents a consideration of some ALARP issues in relation to the development of criticality safety cases. The paper utilises some idealised examples covering a range of issues facing the criticality safety assessor, including new plant design, operational plant and decommissioning activities. These examples are used to outline the elements of the criticality safety cases and present a discussion of ALARP in the context of criticality safety assessments. (author)

  20. The assessment of the safety and the radiological risks associated with the transport of radioactive wastes in Romania

    International Nuclear Information System (INIS)

    Vieru, G.

    2000-01-01

    Problems related to the handling, treatment, packaging, storage, transportation, and disposal of radioactive wastes (radwastes) are very important and the responsibility for the safe management of radioactive wastes for the protection of human health and the environment has long been recognized. Safety and public welfare are to be considered within the radioactive waste management, particularly in the field of transportation because of the potential risk that it could pose to the public and to the environment. The IAEA regulations ensure safety in the transport of Radioactive Materials (RAM) by laying down detailed requirements, appropriate to the degree of hazard represented by the respective material, taking into account its form and quantity. Risk assessment provides a basis for routing radwastes and developing mitigation plans, prioritizing initiatives and enacting legislation to protect human beings and the environment. Factors such as shipment cost, distance, population exposed, environmental impacts or sensitivity, time in transit and infrastructure related issues, could be included in the terms of safety and risk. The paper presents risk assessment activities aimed to evaluate risk categories and the radiological consequences that may arise during normal (accident free) transport and those resulting from transport accidents involving waste shipments in Romania. (author)

  1. Risk Assessment for Bridges Safety Management during Operation Based on Fuzzy Clustering Algorithm

    Directory of Open Access Journals (Sweden)

    Xia Hanyu

    2016-01-01

    Full Text Available In recent years, large span and large sea-crossing bridges are built, bridges accidents caused by improper operational management occur frequently. In order to explore the better methods for risk assessment of the bridges operation departments, the method based on fuzzy clustering algorithm is selected. Then, the implementation steps of fuzzy clustering algorithm are described, the risk evaluation system is built, and Taizhou Bridge is selected as an example, the quantitation of risk factors is described. After that, the clustering algorithm based on fuzzy equivalence is calculated on MATLAB 2010a. In the last, Taizhou Bridge operation management departments are classified and sorted according to the degree of risk, and the safety situation of operation departments is analyzed.

  2. 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

  3. Risk assessment for transport operations

    International Nuclear Information System (INIS)

    Appleton, P.R.; Miles, J.C.

    1990-01-01

    The world-wide safety of the transport of radioactive material is based on the IAEA Transport Regulations. Risk assessment can provide quantitative data to help in the demonstration, understanding and improvement of the effectiveness of the Regulations in assuring safety. In this Paper the methodology, data and computer codes necessary and available for transport risk assessment are reviewed. Notable examples of assessments carried out over the past 15 years are briefly described along with current research, and the benefits and limitations of the techniques are discussed. (author)

  4. Risk investigation for safety assessment of nuclear power stations

    International Nuclear Information System (INIS)

    Heuser, F.W.; Hoertner, H.; Kersting, E.

    1987-01-01

    The most important results of the technical system investigations for Phase B of the German Risk Study and the insight gained from them are discussed in connection with the risk analyses in judging the safety-related design. The results of the German Precursor Study for the Biblis A and B plants are given. There is also a comparison of the German with more recent American risk analyses. (DG) [de

  5. A study on the assessment of safety culture impacts on risk of nuclear power plants using common uncertainty source model

    International Nuclear Information System (INIS)

    Lee, Yong Suk; Bang, Young Suk; Chung, Chang Hyun; Jeong, Ji Hwan

    2004-01-01

    Since International Safety Advisory Group (INSAG) introduced term 'safety culture', it has been widely recognized that safety culture has an important role in safety of nuclear power plants. Research on the safety culture can be divided in the following two parts. 1) Assessment of safety culture (by interview, questionnaire, etc.) 2) Assessment of link between safety culture and safety of nuclear power plants. There is a substantial body of literature that addresses the first part, but there is much less work that addresses the second part. To address the second part, most work focused on the development of model incorporating safety culture into Probabilistic Safety Assessment (PSA). One of the most advanced methodology in the area of incorporating safety culture quantitatively into PSA is System Dynamics (SD) model developed by Kwak et al. It can show interactions among various factors which affect employees' productivity and job quality. Also various situations in nuclear power plant can be simulated and time-dependent risk can be recalculated with this model. But this model does not consider minimal cut set (MCS) dependency and uncertainty of risk. Another well-known methodology is Work Process Analysis Model (WPAM) developed by Davoudian. It considers MCS dependency by modifying conditional probability values using SLI methodology. But we found that the modified conditional probability values in WPAM are somewhat artificial and have no sound basis. WPAM tend to overestimate conditional probability of hardware failure, because it uses SLI methodology which is normally used in Human Reliability Analysis (HRA). WPAM also does not consider uncertainty of risk. In this study, we proposed methodology to incorporate safety culture into PSA quantitatively that can deal with MCS dependency and uncertainty of risk by applying the Common Uncertainty Source (CUS) model developed by Zhang. CUS is uncertainty source that is common to basic events, and this can be physical

  6. A Risk Assessment Model for Reduced Aircraft Separation: A Quantitative Method to Evaluate the Safety of Free Flight

    Science.gov (United States)

    Cassell, Rick; Smith, Alex; Connors, Mary; Wojciech, Jack; Rosekind, Mark R. (Technical Monitor)

    1996-01-01

    As new technologies and procedures are introduced into the National Airspace System, whether they are intended to improve efficiency, capacity, or safety level, the quantification of potential changes in safety levels is of vital concern. Applications of technology can improve safety levels and allow the reduction of separation standards. An excellent example is the Precision Runway Monitor (PRM). By taking advantage of the surveillance and display advances of PRM, airports can run instrument parallel approaches to runways separated by 3400 feet with the same level of safety as parallel approaches to runways separated by 4300 feet using the standard technology. Despite a wealth of information from flight operations and testing programs, there is no readily quantifiable relationship between numerical safety levels and the separation standards that apply to aircraft on final approach. This paper presents a modeling approach to quantify the risk associated with reducing separation on final approach. Reducing aircraft separation, both laterally and longitudinally, has been the goal of several aviation R&D programs over the past several years. Many of these programs have focused on technological solutions to improve navigation accuracy, surveillance accuracy, aircraft situational awareness, controller situational awareness, and other technical and operational factors that are vital to maintaining flight safety. The risk assessment model relates different types of potential aircraft accidents and incidents and their contribution to overall accident risk. The framework links accident risks to a hierarchy of failsafe mechanisms characterized by procedures and interventions. The model will be used to assess the overall level of safety associated with reducing separation standards and the introduction of new technology and procedures, as envisaged under the Free Flight concept. The model framework can be applied to various aircraft scenarios, including parallel and in

  7. Biosafety Risk Assessment Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Caskey, Susan Adele [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). International Biological Threat Reduction Program; Gaudioso, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). International Biological Threat Reduction Program; Salerno, Reynolds Mathewson [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). International Biological Threat Reduction Program; Wagner, Stefan M. [Public Health Agency of Canada, Winnipeg, MB (Canada). Canadian Science Centre for Human and Animal Health (CSCHAH); Shigematsu, Mika [National Inst. of Infectious Diseases (NIID), Tokyo (Japan); Risi, George [Infectious Disease Specialists, P.C, Missoula, MT (United States); Kozlovac, Joe [US Dept. of Agriculture (USDA)., Beltsville, MD (United States); Halkjaer-Knudsen, Vibeke [Statens Serum Inst., Copenhagen (Denmark); Prat, Esmeralda [Bayer CropScience, Monheim am Rhein (Germany)

    2010-10-01

    Laboratories that work with biological agents need to manage their safety risks to persons working the laboratories and the human and animal community in the surrounding areas. Biosafety guidance defines a wide variety of biosafety risk mitigation measures, which include measures which fall under the following categories: engineering controls, procedural and administrative controls, and the use of personal protective equipment; the determination of which mitigation measures should be used to address the specific laboratory risks are dependent upon a risk assessment. Ideally, a risk assessment should be conducted in a manner which is standardized and systematic which allows it to be repeatable and comparable. A risk assessment should clearly define the risk being assessed and avoid over complication.

  8. Improving ICU risk management and patient safety.

    Science.gov (United States)

    Kielty, Lucy Ann

    2017-06-12

    Purpose The purpose of this paper is to describe a study which aimed to develop and validate an assessment method for the International Electrotechnical Commission (IEC) 80001-1 (IEC, 2010) standard (the Standard); raise awareness; improve medical IT-network project risk management processes; and improve intensive care unit patient safety. Design/methodology/approach An assessment method was developed and piloted. A healthcare IT-network project assessment was undertaken using a semi-structured group interview with risk management stakeholders. Participants provided feedback via a questionnaire. Descriptive statistics and thematic analysis was undertaken. Findings The assessment method was validated as fit for purpose. Participants agreed (63 per cent, n=7) that assessment questions were clear and easy to understand, and participants agreed (82 per cent, n=9) that the assessment method was appropriate. Participant's knowledge of the Standard increased and non-compliance was identified. Medical IT-network project strengths, weaknesses, opportunities and threats in the risk management processes were identified. Practical implications The study raised awareness of the Standard and enhanced risk management processes that led to improved patient safety. Study participants confirmed they would use the assessment method in future projects. Originality/value Findings add to knowledge relating to IEC 80001-1 implementation.

  9. Therapeutic risk management of the suicidal patient: safety planning.

    Science.gov (United States)

    Matarazzo, Bridget B; Homaifar, Beeta Y; Wortzel, Hal S

    2014-05-01

    This column is the fourth in a series describing a model for therapeutic risk management of the suicidal patient. Previous columns presented an overview of the therapeutic risk management model, provided recommendations for how to augment risk assessment using structured assessments, and discussed the importance of risk stratification in terms of both severity and temporality. This final column in the series discusses the safety planning intervention as a critical component of therapeutic risk management of suicide risk. We first present concerns related to the relatively common practice of using no-suicide contracts to manage risk. We then present the safety planning intervention as an alternative approach and provide recommendations for how to use this innovative strategy to therapeutically mitigate risk in the suicidal patient.

  10. National Waste Repository Novi Han operational safety analysis report. Safety assessment methodology

    International Nuclear Information System (INIS)

    2003-01-01

    The scope of the safety assessment (SA), presented includes: waste management functions (acceptance, conditioning, storage, disposal), inventory (current and expected in the future), hazards (radiological and non-radiological) and normal and accidental modes. The stages in the development of the SA are: criteria selection, information collection, safety analysis and safety assessment documentation. After the review the facilities functions and the national and international requirements, the criteria for safety level assessment are set. As a result from the 2nd stage actual parameters of the facility, necessary for safety analysis are obtained.The methodology is selected on the base of the comparability of the results with the results of previous safety assessments and existing standards and requirements. The procedure and requirements for scenarios selection are described. A radiological hazard categorisation of the facilities is presented. Qualitative hazards and operability analysis is applied. The resulting list of events are subjected to procedure for prioritization by method of 'criticality analysis', so the estimation of the risk is given for each event. The events that fall into category of risk on the boundary of acceptability or are unacceptable are subjected to the next steps of the analysis. As a result the lists with scenarios for PSA and possible design scenarios are established. PSA logical modeling and quantitative calculations of accident sequences are presented

  11. Track 6: safety and risk management. Plant operational risk management. Plant Configuration Risk Assessment Methodology Development for Periodic Maintenance

    International Nuclear Information System (INIS)

    Yang, Huichang; Chung, Chang Hyun; Sung, Key Yong

    2001-01-01

    As the operation experiences of nuclear power plants (NPPs) in Korea accumulate and NPP safety functions become enhanced, the role of stable and optimal NPP operation within acceptable safety criteria becomes important at present. To accomplish the goal of safe and optimal operation, maintenance and its related activities should be regarded as the issues of most concern. Studies of methodologies for maintenance improvement and optimization have focused on system performance rather than on the hardware itself. From this point of view, the probabilistic methods are most useful. In terms of risk including core damage frequency and unavailability, the cause that might impact plant safety during normal maintenance activities can be identified and evaluated effectively. The results from these probabilistic analyses can provide insightful information for the reallocation of risk-contributing maintenance activity. This information can be utilized in a way that separates the significant risk-contributing maintenance activities from each other unless they are timely related. In Korea, the risk-monitoring program for operating NPPs is under development and will be implemented in 2003. To accomplish the risk-monitoring program objectives, suitable risk evaluation methods should be developed before the implementation of the risk-monitoring program. The plant configuration assessment methodology was developed for these reasons, and this method is to incorporate the field experiences into the risk calculation exactly within the limit of probabilistic methods. During normal plant operation, the plant operational risk changes frequently depending on the status of the plant system and the arrangement of the components. Specific plant systems or components are typically removed from service because of random equipment failure, planned preventive/predictive maintenance, corrective maintenance, surveillance testing, and operational bypass activities, and such events usually impact the

  12. Probabilistic safety assessment

    International Nuclear Information System (INIS)

    Hoertner, H.; Schuetz, B.

    1982-09-01

    For the purpose of assessing applicability and informativeness on risk-analysis methods in licencing procedures under atomic law, the choice of instruments for probabilistic analysis, the problems in and experience gained in their application, and the discussion of safety goals with respect to such instruments are of paramount significance. Naturally, such a complex field can only be dealt with step by step, making contribution relative to specific problems. The report on hand shows the essentials of a 'stocktaking' of systems relability studies in the licencing procedure under atomic law and of an American report (NUREG-0739) on 'Quantitative Safety Goals'. (orig.) [de

  13. Risk management for industrial safety

    International Nuclear Information System (INIS)

    Novogno, A.

    1989-01-01

    The catastrophic accidents which have occurred in the last decade, in both developed and developing countries, have drawn the attention of decision-makers in the safety area to the urgent necessity to assess and manage risks from hazardous industrial activities which are concentrated in large industrialized areas. The aim of this paper is to review experience gained in conducting studies in the area of 'comparisons of risks in energy systems' and on the practical application of 'cost effectiveness of risk reduction analysis among different energy systems' (case studies). It is also the aim of the paper to discuss and propose a general framework for defining an 'integrated approach' to risk assessment and management in highly industrialized regions within a country. (author)

  14. Risk assessment methods in radiotherapy: Probabilistic safety assessment (PSA); Los metodos de analisis de riesgo en radioterapia: Analisis Probabilistico de seguridad (APS)

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez Vera, M. L.; Perez Mulas, A.; Delgado, J. M.; Barrientos Ontero, M.; Somoano, F.; Alvarez Garcia, C.; Rodriguez Marti, M.

    2011-07-01

    The understanding of accidents that have occurred in radiotherapy and the lessons learned from them are very useful to prevent repetition, but there are other risks that have not been detected to date. With a view to identifying and preventing such risks, proactive methods successfully applied in other fields, such as probabilistic safety assessment (PSA), have been developed. (Author)

  15. Demonstration of Risk Profiling for promoting safety in SME´s

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten; Duijm, Nijs Jan; Troen, Hanne

    2011-01-01

    Purpose – The purpose of this paper is to identify and assess the risks and potential risks that may lead to accidents. It aims to look at how to improve risk assessment within SMEs for the benefit of all staff. Design/methodology/approach – The research included results from a Dutch project which...... identifies accident risks and safety barriers that are presented in a huge database and risk calculator. The method was first to develop a simple way of accessing this enormous amount of data, second, to develop a tool to observe risks and safety barriers in SMEs and to investigate the usefulness...... of the developed tools in real life, third, to collect data on risks and safety barriers in SMEs for two occupations by following 20 people for three days each and to create a risk profile for each occupations. Findings – The result is a simple way to go through all types of risks for accidents – a tool for risk...

  16. Probabilistic risk assessment in nuclear power plant regulation

    Energy Technology Data Exchange (ETDEWEB)

    Wall, J B

    1980-09-01

    A specific program is recommended to utilize more effectively probabilistic risk assessment in nuclear power plant regulation. It is based upon the engineering insights from the Reactor Safety Study (WASH-1400) and some follow-on risk assessment research by USNRC. The Three Mile Island accident is briefly discussed from a risk viewpoint to illustrate a weakness in current practice. The development of a probabilistic safety goal is recommended with some suggestions on underlying principles. Some ongoing work on risk perception and the draft probabilistic safety goal being reviewed on Canada is described. Some suggestions are offered on further risk assessment research. Finally, some recent U.S. Nuclear Regulatory Commission actions are described.

  17. Survey of probabilistic methods in safety and risk assessment for nuclear power plant licensing

    International Nuclear Information System (INIS)

    1984-04-01

    After an overview about the goals and general methods of probabilistic approaches in nuclear safety the main features of probabilistic safety or risk assessment (PRA) methods are discussed. Mostly in practical applications not a full-fledged PRA is applied but rather various levels of analysis leading from unavailability assessment of systems over the more complex analysis of the probable core damage stages up to the assessment of the overall health effects on the total population from a certain practice. The various types of application are discussed in relation to their limitation and benefits for different stages of design or operation of nuclear power plants. This gives guidance for licensing staff to judge the usefulness of the various methods for their licensing decisions. Examples of the application of probabilistic methods in several countries are given. Two appendices on reliability analysis and on containment and consequence analysis provide some more details on these subjects. (author)

  18. On a systematic perspective on risk for formal safety assessment (FSA)

    International Nuclear Information System (INIS)

    Montewka, Jakub; Goerlandt, Floris; Kujala, Pentti

    2014-01-01

    In the maritime domain, risk is evaluated within the framework of the Formal Safety Assessment (FSA), introduced by the International Maritime Organization in 2002. Although the FSA has become an internationally recognized and recommended method, the definition, which is adopted there, to describe the risk, seems to be too narrow to reflect the actual content of the FSA. Therefore this article discusses methodological requirements for the risk perspective, which is appropriate for risk management in the maritime domain with special attention to maritime transportation systems. A perspective that is proposed here considers risk as a set encompassing the following: a set of plausible scenarios leading to an accident, the likelihoods of unwanted events within the scenarios, the consequences of the events and description of uncertainty. All these elements are conditional upon the available knowledge (K) about the analyzed system and understanding (N) of the system behavior. Therefore, the quality of K and the level of N of a risk model should be reflected in the uncertainty description. For this purpose we introduce a qualitative scoring system, and we show its applicability on an exemplary risk model for a RoPax ship. - Highlights: • We present a risk perspective for the maritime domain. • A distinction between knowledge and understanding is made. • We describe risk as (Scenario, Consequences, Uncertainty/Knowledge, Understanding). • The perspective highlights the strength and weaknesses of a given risk analysis

  19. Offshore risk assessment

    CERN Document Server

    Vinnem, Jan-Erik

    2014-01-01

      Offshore Risk Assessment was the first book to deal with quantified risk assessment (QRA) as applied specifically to offshore installations and operations. Risk assessment techniques have been used for more than three decades in the offshore oil and gas industry, and their use is set to expand increasingly as the industry moves into new areas and faces new challenges in older regions.   This updated and expanded third edition has been informed by a major R&D program on offshore risk assessment in Norway and summarizes research from 2006 to the present day. Rooted with a thorough discussion of risk metrics and risk analysis methodology,  subsequent chapters are devoted to analytical approaches to escalation, escape, evacuation and rescue analysis of safety and emergency systems.   Separate chapters analyze the main hazards of offshore structures: fire, explosion, collision, and falling objects as well as structural and marine hazards. Risk mitigation and control are discussed, as well as an illustrat...

  20. Value-impact assessment of safety-related modifications

    International Nuclear Information System (INIS)

    Knowles, W.M.C.; Dinnie, K.S.; Gordon, C.W.

    1992-01-01

    Like other nuclear utilities, Ontario Hydro, as part of its risk management activities, continually assesses the safety of its nuclear operations. In addition, new regulatory requirements are being applied to the older nuclear power plants. Both of these result in proposed plant modifications designed to reduce the risk to the public. However, modifications to an operating plant can have serious economic effects, and the resources, both financial and personnel, required for the implementation of these modifications are limited. Thus, all potential benefits and effects of a proposed modification must be thoroughly investigated to judge whether the modification is beneficial. Ontario Hydro has begun to use comprehensive value-impact assessments, utilizing plant-specific probabilistic risk assessments (PRAs), as tools to provide an informed basis for judgments on the benefit of safety-related modifications. The results from value-impact assessments can also be used to prioritize the implementation of these modifications

  1. Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Curtis L; Mandelli, Diego; Zhegang Ma

    2014-11-01

    As part of the Light Water Sustainability Program (LWRS) [1], the purpose of the Risk Informed Safety Margin Characterization (RISMC) [2] Pathway research and development (R&D) is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” (SBO) wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario. We also describe our approach we are using to represent advanced flooding analysis.

  2. Probabilistic safety assessment as a standpoint for decision making

    International Nuclear Information System (INIS)

    Cepin, M.

    2001-01-01

    This paper focuses on the role of probabilistic safety assessment in decision-making. The prerequisites for use of the results of probabilistic safety assessment and the criteria for the decision-making based on probabilistic safety assessment are discussed. The decision-making process is described. It provides a risk evaluation of impact of the issue under investigation. Selected examples are discussed, which highlight the described process. (authors)

  3. Understanding Risk Tolerance and Building an Effective Safety Culture

    Science.gov (United States)

    Loyd, David

    2018-01-01

    Estimates range from 65-90 percent of catastrophic mishaps are due to human error. NASA's human factors-related mishaps causes are estimated at approximately 75 percent. As much as we'd like to error-proof our work environment, even the most automated and complex technical endeavors require human interaction... and are vulnerable to human frailty. Industry and government are focusing not only on human factors integration into hazardous work environments, but also looking for practical approaches to cultivating a strong Safety Culture that diminishes risk. Industry and government organizations have recognized the value of monitoring leading indicators to identify potential risk vulnerabilities. NASA has adapted this approach to assess risk controls associated with hazardous, critical, and complex facilities. NASA's facility risk assessments integrate commercial loss control, OSHA (Occupational Safety and Health Administration) Process Safety, API (American Petroleum Institute) Performance Indicator Standard, and NASA Operational Readiness Inspection concepts to identify risk control vulnerabilities.

  4. Risk-based rules for crane safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Ruud, Stian [Section for Control Systems, DNV Maritime, 1322 Hovik (Norway)], E-mail: Stian.Ruud@dnv.com; Mikkelsen, Age [Section for Lifting Appliances, DNV Maritime, 1322 Hovik (Norway)], E-mail: Age.Mikkelsen@dnv.com

    2008-09-15

    The International Maritime Organisation (IMO) has recommended a method called formal safety assessment (FSA) for future development of rules and regulations. The FSA method has been applied in a pilot research project for development of risk-based rules and functional requirements for systems and components for offshore crane systems. This paper reports some developments in the project. A method for estimating target reliability for the risk-control options (safety functions) by means of the cost/benefit decision criterion has been developed in the project and is presented in this paper. Finally, a structure for risk-based rules is proposed and presented.

  5. Risk-based rules for crane safety systems

    International Nuclear Information System (INIS)

    Ruud, Stian; Mikkelsen, Age

    2008-01-01

    The International Maritime Organisation (IMO) has recommended a method called formal safety assessment (FSA) for future development of rules and regulations. The FSA method has been applied in a pilot research project for development of risk-based rules and functional requirements for systems and components for offshore crane systems. This paper reports some developments in the project. A method for estimating target reliability for the risk-control options (safety functions) by means of the cost/benefit decision criterion has been developed in the project and is presented in this paper. Finally, a structure for risk-based rules is proposed and presented

  6. Savannah River Site K-Reactor Probabilistic Safety Assessment

    International Nuclear Information System (INIS)

    Brandyberry, M.D.; Bailey, R.T.; Baker, W.H.; Kearnaghan, D.P.; O'Kula, K.R.; Wittman, R.S.; Woody, N.D.; Amos, C.N.; Weingardt, J.J.

    1992-12-01

    This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these accidents and to assess the resultant consequences. The report is issued to provide useful information to the U. S. Department of Energy (DOE) on the risk of operation of SRS reactors, for insights into severe accident phenomena that contribute to this risk, and in support of improved bases for other DOE programs in Heavy Water Reactor safety

  7. Benchmarking Global Food Safety Performances: The Era of Risk Intelligence.

    Science.gov (United States)

    Valleé, Jean-Charles Le; Charlebois, Sylvain

    2015-10-01

    Food safety data segmentation and limitations hamper the world's ability to select, build up, monitor, and evaluate food safety performance. Currently, there is no metric that captures the entire food safety system, and performance data are not collected strategically on a global scale. Therefore, food safety benchmarking is essential not only to help monitor ongoing performance but also to inform continued food safety system design, adoption, and implementation toward more efficient and effective food safety preparedness, responsiveness, and accountability. This comparative study identifies and evaluates common elements among global food safety systems. It provides an overall world ranking of food safety performance for 17 Organisation for Economic Co-Operation and Development (OECD) countries, illustrated by 10 indicators organized across three food safety risk governance domains: risk assessment (chemical risks, microbial risks, and national reporting on food consumption), risk management (national food safety capacities, food recalls, food traceability, and radionuclides standards), and risk communication (allergenic risks, labeling, and public trust). Results show all countries have very high food safety standards, but Canada and Ireland, followed by France, earned excellent grades relative to their peers. However, any subsequent global ranking study should consider the development of survey instruments to gather adequate and comparable national evidence on food safety.

  8. Work-related stress risk assessment in Italy: the validation study of health safety and executive indicator tool.

    Science.gov (United States)

    Rondinone, Bruna Maria; Persechino, Benedetta; Castaldi, Tiziana; Valenti, Antonio; Ferrante, Pierpaolo; Ronchetti, Matteo; Iavicoli, Sergio

    2012-01-01

    In compliance with the Italian occupational health and safety regulatory framework, as provided by the Lgs. Decree 81/2008, the "work-related stress" risk assessment should follow the same principles as other risk assessments, in accordance with the European Agreement of 8 October 2004; therefore, validated and scientifically proven methodological tools are needed to conduct an adequate work-related stress risk assessment. The UK's Health Safety and Executive (HSE) Indicator Tool (IT) is used for assessing the risk of work-related stress. The aim of this study is to test the factor structure of IT as a measure of work-related stress in a sample of Italian workers. Data collected from 65 Italian organizations (6378 workers) was used for a Confirmatory Factor Analysis (CFA) on the 35-item seven-factor model. The results showed acceptable fit to the data (CFI .90; TLI .89, RMSEA .045). A second CFA was done to test a 35-item six-factor model (CFI .89, TLI .87, RMSEA .047). Both models were tested after removing six items (factor loadings less than .50.), resulting in a 29-item model. Here again, there was an acceptable fit to the data (29-item seven-factor model: CFI .93, TLI .91, RMSEA .044; 29-item six-factor model: CFI .92, TLI .90, RMSEA .046). These findings show that the HSE model satisfactorily adapts to use in a sample of Italian workers. One of the most important innovations introduced in the assessment of work-related stress with the HSE IT is the global approach for identifying work-related stress risk factors, aimed at establishing the best strategy from the viewpoints of prevention officers and also of workers.

  9. Preliminary Safety and Risk HSE Assessment. Application to the Potential Locations of a CO2 Geological Storage Pilot

    International Nuclear Information System (INIS)

    Recreo, F.; Eguilior, S.; Ruiz, C.; Lomba, L.; Hurtado, A.

    2015-01-01

    The location of a site safe and able to sequester CO2 for long periods of time is essential to gain public acceptance. This requires a long-term safety assessment developed in a robust and reliable framework. Site selection is the first step and requires specific research. This paper describes the application of the Selection and Classification Method of Geological Formations (SCF) developed to assess the potential of geological formations to CO2 storage. This assessment is based in the analysis of risks to Health, Safety and Environment (HSE) derived from potential CO2 leakage. Comparisons of the results obtained from a number of potential sites can help to select the best candidate for CO2 injection. The potential impact will be related to three key potential features of CO2 geological storage: the potential of the target geological formation for long term CO2 containment; the potential for secondary containment on containment failure of the target formation; and the site's potential to mitigate and/or disperse CO2 leakage if the primary and secondary containments fail. The methodology assesses each of these three characteristics through an analysis and assessment of properties of certain attributes of them. Uncertainty will remain as an input and output value of the methodology due to the usual lack of data in most site selection processes. The global uncertainty reports on the trust on the knowledge of the site characteristics. Therefore, the methodology enables comparing sites taking into account both the HSE risk expectation and the estimation of the quality of knowledge concerning such risk. The objective is to contribute to the selection of potential sites for a CO2 injection pilot plant in the Iberian Peninsula from the perspective of Safety and Risk Analysis.

  10. Tools for Microbiological risk assessment

    DEFF Research Database (Denmark)

    Bassett, john; Nauta, Maarten; Lindqvist, Roland

    can increase the understanding of microbiological risks in foods. It is timely to inform food safety professionals about the availability and utility of MRA tools. Therefore, the focus of this report is to aid the food safety manager by providing a concise summary of the tools available for the MRA......Microbiological Risk Assessment (MRA) has emerged as a comprehensive and systematic approach for addressing the risk of pathogens in specific foods and/or processes. At government level, MRA is increasingly recognised as a structured and objective approach to understand the level of risk in a given...... food/pathogen scenario. Tools developed so far support qualitative and quantitative assessments of the risk that a food pathogen poses to a particular population. Risk can be expressed as absolute numbers or as relative (ranked) risks. The food industry is beginning to appreciate that the tools for MRA...

  11. Confidence building in safety assessments

    International Nuclear Information System (INIS)

    Grundfelt, Bertil

    1999-01-01

    Future generations should be adequately protected from damage caused by the present disposal of radioactive waste. This presentation discusses the core of safety and performance assessment: The demonstration and building of confidence that the disposal system meets the safety requirements stipulated by society. The major difficulty is to deal with risks in the very long time perspective of the thousands of years during which the waste is hazardous. Concern about these problems has stimulated the development of the safety assessment discipline. The presentation concentrates on two of the elements of safety assessment: (1) Uncertainty and sensitivity analysis, and (2) validation and review. Uncertainty is associated both with respect to what is the proper conceptual model and with respect to parameter values for a given model. A special kind of uncertainty derives from the variation of a property in space. Geostatistics is one approach to handling spatial variability. The simplest way of doing a sensitivity analysis is to offset the model parameters one by one and observe how the model output changes. The validity of the models and data used to make predictions is central to the credibility of safety assessments for radioactive waste repositories. There are several definitions of model validation. The presentation discusses it as a process and highlights some aspects of validation methodologies

  12. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks.

  13. Categorization of reactor safety issues from a risk perspective

    International Nuclear Information System (INIS)

    1985-03-01

    This report presents the results of an effort to identify and rank reactor safety and risk issues identified from past Probabilistic Risk Assessments (PRAs) and other safety analyses. Because of the varied scope of these analyses, the list of issues may be incomplete. Nevertheless, those studies comprised ordered analyses to whatever their respective depths; hence, they warranted scrutiny for whatever insights they could reveal with respect to issue importance. The top-ranked issues in terms of their contribution to the uncertainty in risk are described in some detail. All of these risk issues are compared to the generic safety issues for completeness and omissions

  14. Impediments for the application of risk-informed decision making in nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2001-01-01

    A broad application of risk-informed decision making in the regulation of safety of nuclear power plants is hindered by the lack of quantitative risk and safety standards as well as of precise instruments to demonstrate an appropriate safety. An additional severe problem is associated with the difficulty to harmonize deterministic design requirements and probabilistic safety assessment. The problem is strengthened by the vulnerability of PSA for subjective influences and the potential of misuse. Beside this scepticism the nuclear community is encouraged to intensify the efforts to improve the quality standards for probabilistic safety assessments and their quality assurance. A prerequisite for reliable risk-informed decision making processes is also a well-defined and transparent relationship between deterministic and probabilistic safety approaches. (author)

  15. 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.

  16. Complementary safety assessments - Report by the French Nuclear Safety Authority

    International Nuclear Information System (INIS)

    2011-12-01

    As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

  17. Hybrid causal methodology and software platform for probabilistic risk assessment and safety monitoring of socio-technical systems

    Energy Technology Data Exchange (ETDEWEB)

    Groth, Katrina, E-mail: kgroth@umd.ed [Center for Risk and Reliability, 0151 Glenn L. Martin Hall, University of Maryland, College Park, MD 20742 (United States); Wang Chengdong; Mosleh, Ali [Center for Risk and Reliability, 0151 Glenn L. Martin Hall, University of Maryland, College Park, MD 20742 (United States)

    2010-12-15

    This paper introduces an integrated framework and software platform for probabilistic risk assessment (PRA) and safety monitoring of complex socio-technical systems. An overview of the three-layer hybrid causal logic (HCL) modeling approach and corresponding algorithms, implemented in the Trilith software platform, are provided. The HCL approach enhances typical PRA methods by quantitatively including the influence of soft causal factors introduced by human and organizational aspects of a system. The framework allows different modeling techniques to be used for different aspects of the socio-technical system. The HCL approach combines the power of traditional event sequence diagram (ESD)event tree (ET) and fault tree (FT) techniques for modeling deterministic causal paths, with the flexibility of Bayesian belief networks for modeling non-deterministic cause-effect relationships among system elements (suitable for modeling human and organizational influences). Trilith enables analysts to construct HCL models and perform quantitative risk assessment and management of complex systems. The risk management capabilities included are HCL-based risk importance measures, hazard identification and ranking, precursor analysis, safety indicator monitoring, and root cause analysis. This paper describes the capabilities of the Trilith platform and power of the HCL algorithm by use of example risk models for a type of aviation accident (aircraft taking off from the wrong runway).

  18. Hybrid causal methodology and software platform for probabilistic risk assessment and safety monitoring of socio-technical systems

    International Nuclear Information System (INIS)

    Groth, Katrina; Wang Chengdong; Mosleh, Ali

    2010-01-01

    This paper introduces an integrated framework and software platform for probabilistic risk assessment (PRA) and safety monitoring of complex socio-technical systems. An overview of the three-layer hybrid causal logic (HCL) modeling approach and corresponding algorithms, implemented in the Trilith software platform, are provided. The HCL approach enhances typical PRA methods by quantitatively including the influence of soft causal factors introduced by human and organizational aspects of a system. The framework allows different modeling techniques to be used for different aspects of the socio-technical system. The HCL approach combines the power of traditional event sequence diagram (ESD)event tree (ET) and fault tree (FT) techniques for modeling deterministic causal paths, with the flexibility of Bayesian belief networks for modeling non-deterministic cause-effect relationships among system elements (suitable for modeling human and organizational influences). Trilith enables analysts to construct HCL models and perform quantitative risk assessment and management of complex systems. The risk management capabilities included are HCL-based risk importance measures, hazard identification and ranking, precursor analysis, safety indicator monitoring, and root cause analysis. This paper describes the capabilities of the Trilith platform and power of the HCL algorithm by use of example risk models for a type of aviation accident (aircraft taking off from the wrong runway).

  19. Research on advanced system safety assessment procedures (4)

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Shimada, Yukiyasu

    2001-03-01

    The past research reports in the area of safety engineering proposed the Computer-aided HAZOP system to be applied to Nuclear Reprocessing Facilities. Automated HAZOP system has great advantage compared with human analysts in terms of accuracy of the results, and time required to conduct HAZOP studies. This report surveys the literature on risk assessment and safety design based on the concept of independent protection layers (IPLs). Furthermore, to improve HAZOP System, tool is proposed to construct the basic model and the internal state model. Such HAZOP system is applied to analyze two kinds of processes, where the ability of the proposed system is verified. In addition, risk assessment support system is proposed to integrate safety design environment and assessment result to be used by other plants as well as to enable the underline plant to use other plants' information. This technique can be implemented using web-based safety information systems. (author)

  20. A simplified method for quantitative assessment of the relative health and safety risk of environmental management activities

    International Nuclear Information System (INIS)

    Eide, S.A.; Smith, T.H.; Peatross, R.G.; Stepan, I.E.

    1996-09-01

    This report presents a simplified method to assess the health and safety risk of Environmental Management activities of the US Department of Energy (DOE). The method applies to all types of Environmental Management activities including waste management, environmental restoration, and decontamination and decommissioning. The method is particularly useful for planning or tradeoff studies involving multiple conceptual options because it combines rapid evaluation with a quantitative approach. The method is also potentially applicable to risk assessments of activities other than DOE Environmental Management activities if rapid quantitative results are desired

  1. “Shake, Rattle and Roll”: risk assessment and management for food safety during two Christchurch earthquakes

    Directory of Open Access Journals (Sweden)

    Sally Johnston

    2012-06-01

    Full Text Available Problem: Two earthquakes recently struck the Christchurch region. The 2010 earthquake in Canterbury was strong yet sustained less damage than the 2011 earthquake in Christchurch, which although not as strong, was more damaging and resulted in 185 deaths. Both required activation of a food safety response.Context: The food safety response for both earthquakes was focused on reducing the risk of gastroenteritis by limiting the use of contaminated water and food, both in households and food businesses. Additional food safety risks were identified in the 2011 Christchurch earthquake due the use of large-scale catering for rescue workers, volunteers and residents unable to return home.Action: Using a risk assessment framework, the food safety response involved providing water and food safety advice, issuing a boil water notice for the region and initiating water testing on reticulation systems. Food businesses were contacted to ensure the necessary measures were being taken. Additional action during the 2011 Christchurch earthquake response included making contact with food businesses using checklists and principles developed in the first response and having regular contact with those providing catering for large numbers.Outcome: In the 2010 earthquake in Canterbury, several cases of gastroenteritis were reported, although most resulted from person-to-person contact rather than contamination of food. There was a small increase in gastroenteritis cases following the 2011 Christchurch earthquake.Discussion: The food safety response for both earthquakes was successful in meeting the goal of ensuring that foodborne illness did not put additional pressure on hospitals or affect search and rescue efforts.

  2. Risk Assessment Overview

    Science.gov (United States)

    Prassinos, Peter G.; Lyver, John W., IV; Bui, Chinh T.

    2011-01-01

    Risk assessment is used in many industries to identify and manage risks. Initially developed for use on aeronautical and nuclear systems, risk assessment has been applied to transportation, chemical, computer, financial, and security systems among others. It is used to gain an understanding of the weaknesses or vulnerabilities in a system so modification can be made to increase operability, efficiency, and safety and to reduce failure and down-time. Risk assessment results are primary inputs to risk-informed decision making; where risk information including uncertainty is used along with other pertinent information to assist management in the decision-making process. Therefore, to be useful, a risk assessment must be directed at specific objectives. As the world embraces the globalization of trade and manufacturing, understanding the associated risk become important to decision making. Applying risk assessment techniques to a global system of development, manufacturing, and transportation can provide insight into how the system can fail, the likelihood of system failure and the consequences of system failure. The risk assessment can identify those elements that contribute most to risk and identify measures to prevent and mitigate failures, disruptions, and damaging outcomes. In addition, risk associated with public and environment impact can be identified. The risk insights gained can be applied to making decisions concerning suitable development and manufacturing locations, supply chains, and transportation strategies. While risk assessment has been mostly applied to mechanical and electrical systems, the concepts and techniques can be applied across other systems and activities. This paper provides a basic overview of the development of a risk assessment.

  3. Risk-based safety indicators

    International Nuclear Information System (INIS)

    Szikszai, T.

    1997-01-01

    The presentation discusses the following issues: The objectives of the risk-based indicator programme. The characteristics of the risk-based indicators. The objectives of risk-based safety indicators - in monitoring safety; in PSA applications. What indicators? How to produce the risk based indicators? PSA requirements

  4. Risk prediction, safety analysis and quantitative probability methods - a caveat

    International Nuclear Information System (INIS)

    Critchley, O.H.

    1976-01-01

    Views are expressed on the use of quantitative techniques for the determination of value judgements in nuclear safety assessments, hazard evaluation, and risk prediction. Caution is urged when attempts are made to quantify value judgements in the field of nuclear safety. Criteria are given the meaningful application of reliability methods but doubts are expressed about their application to safety analysis, risk prediction and design guidances for experimental or prototype plant. Doubts are also expressed about some concomitant methods of population dose evaluation. The complexities of new designs of nuclear power plants make the problem of safety assessment more difficult but some possible approaches are suggested as alternatives to the quantitative techniques criticized. (U.K.)

  5. Environmental Risk Communication through Qualitative Risk Assessment

    Directory of Open Access Journals (Sweden)

    Sabre J. Coleman

    2014-06-01

    Full Text Available Environmental analysts are often hampered in communicating the risks of environmental contaminants due to the myriad of regulatory requirements that are applicable. The use of a qualitative, risk-based control banding strategy for assessment and control of potential environmental contaminants provides a standardized approach to improve risk communication. Presented is a model that provides an effective means for determining standardized responses and controls for common environmental issues based on the level of risk. The model is designed for integration within an occupational health and safety management system to provide a multidisciplinary environmental and occupational risk management approach. This environmental model, which utilizes multidisciplinary control banding strategies for delineating risk, complements the existing Risk Level Based Management System, a proven method in a highly regulated facility for occupational health and safety. A simplified environmental risk matrix is presented that is stratified over four risk levels. Examples of qualitative environmental control banding strategies are presented as they apply to United States regulations for construction, research activities, facility maintenance, and spill remediation that affect air, water, soil, and waste disposal. This approach offers a standardized risk communication language for multidisciplinary issues that will improve communications within and between environmental health and safety professionals, workers, and management.

  6. Upholding science in health, safety and environmental risk assessments and regulations

    International Nuclear Information System (INIS)

    Aschner, Michael; Autrup, Herman N.; Berry, Sir Colin L.; Boobis, Alan R.; Cohen, Samuel M.; Creppy, Edmond E.; Dekant, Wolfgang; Doull, John; Galli, Corrado L.; Goodman, Jay I.; Gori, Gio B.; Greim, Helmut A.; Joudrier, Philippe

    2016-01-01

    A public appeal has been advanced by a large group of scientists, concerned that science has been misused in attempting to quantify and regulate unmeasurable hazards and risks. The appeal recalls that science is unable to evaluate hazards that cannot be measured, and that science in such cases should not be invoked to justify risk assessments in health, safety and environmental regulations. The appeal also notes that most national and international statutes delineating the discretion of regulators are ambiguous about what rules of evidence ought to apply. Those statutes should be revised to ensure that the evidence for regulatory action is grounded on the standards of the scientific method, whenever feasible. When independent scientific evidence is not possible, policies and regulations should be informed by publicly debated trade-offs between socially desirable uses and social perceptions of affordable precaution. This article explores the premises, implications and actions supporting the appeal and its objectives.

  7. ILO activities in the field of risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Pinnagoda, C [Occupational Safety and Health Branch, Working Conditions and Environment Department, International Labor Organization, Geneva (Switzerland)

    1992-07-01

    Control of chemical risks has become a matter of increasing concern for the occupational safety and health activities of the ILO. Its chemical safety programme focuses attention on a series of comprehensive measures to promote national level action for effective control of chemical risks aimed at the protection of workers and consequently of the general public. The supply and use of information based on risk assessment for exposure control and the application of practical improvement measures through improved risk management and training continue to receive increasing importance. The important and direct role of employers and workers in the assessment of risks and planning and implementation of workplace improvements is an identified need. Risk assessment is a component of the chemical safety programme of the ILO that places significant emphasis on: the setting of international standards that lay down basic principles in chemical risk assessment and control; national level action to promote coherent policies and programmes on safety in the use of chemicals and prevention of industrial disasters (major hazard control); technical advisory services through the development of guides and training programmes that focus on workplace participatory approaches; collection and dissemination of practical information; and technical co-operation assistance to developing countries.

  8. ILO activities in the field of risk assessment

    International Nuclear Information System (INIS)

    Pinnagoda, C.

    1992-01-01

    Control of chemical risks has become a matter of increasing concern for the occupational safety and health activities of the ILO. Its chemical safety programme focuses attention on a series of comprehensive measures to promote national level action for effective control of chemical risks aimed at the protection of workers and consequently of the general public. The supply and use of information based on risk assessment for exposure control and the application of practical improvement measures through improved risk management and training continue to receive increasing importance. The important and direct role of employers and workers in the assessment of risks and planning and implementation of workplace improvements is an identified need. Risk assessment is a component of the chemical safety programme of the ILO that places significant emphasis on: the setting of international standards that lay down basic principles in chemical risk assessment and control; national level action to promote coherent policies and programmes on safety in the use of chemicals and prevention of industrial disasters (major hazard control); technical advisory services through the development of guides and training programmes that focus on workplace participatory approaches; collection and dissemination of practical information; and technical co-operation assistance to developing countries

  9. Use of cut-off values as meaningfulness limits in probabilistic studies and its effect on NPPs risk assessment and safety improvement

    International Nuclear Information System (INIS)

    Petrangeli, G.; Valeri, A.; Zaffiro, C.

    1991-01-01

    This paper discusses the use of cut-off values in probabilistic risk assessment/probabilistic safety assessment (PRA/PSA) of nuclear power plants (NPPs), in order to explore under which conditions this practice may help improve the meaningfulness of the results of the analyses and safety of plants, and how it may affect the assessment of risk. Reference is made, in particular, to some past practical applications, also taken from the experience of the authors within the frame of the Italian licensing process. The paper describes the Italian probabilistic criteria which use probabilistic targets and cut-off values to assess safety and identify plant safety improvements. The rationale of the approach is also discussed in the paper and results of sample applications are illustrated. The paper concludes that the use of cut-off values, if properly implemented, could be productive to improve the plant safety as it helps the analyst to focus on a restricted field of analysis, ignoring lower probability and less known events. It also points out that cut-off values should be considered as living numbers to be lowered and even eliminated as soon as significant advancements are made, through research and operational experience, in the knowledge of the pertinent events

  10. Advanced Test Reactor outage risk assessment

    International Nuclear Information System (INIS)

    Thatcher, T.A.; Atkinson, S.A.

    1997-01-01

    Beginning in 1997, risk assessment was performed for each Advanced Test Reactor (ATR) outage aiding the coordination of plant configuration and work activities (maintenance, construction projects, etc.) to minimize the risk of reactor fuel damage and to improve defense-in-depth. The risk assessment activities move beyond simply meeting Technical Safety Requirements to increase the awareness of risk sensitive configurations, to focus increased attention on the higher risk activities, and to seek cost-effective design or operational changes that reduce risk. A detailed probabilistic risk assessment (PRA) had been performed to assess the risk of fuel damage during shutdown operations including heavy load handling. This resulted in several design changes to improve safety; however, evaluation of individual outages had not been performed previously and many risk insights were not being utilized in outage planning. The shutdown PRA provided the necessary framework for assessing relative and absolute risk levels and assessing defense-in-depth. Guidelines were written identifying combinations of equipment outages to avoid. Screening criteria were developed for the selection of work activities to receive review. Tabulation of inherent and work-related initiating events and their relative risk level versus plant mode has aided identification of the risk level the scheduled work involves. Preoutage reviews are conducted and post-outage risk assessment is documented to summarize the positive and negative aspects of the outage with regard to risk. The risk for the outage is compared to the risk level that would result from optimal scheduling of the work to be performed and to baseline or average past performance

  11. 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)

  12. Risk, fear and public safety

    International Nuclear Information System (INIS)

    Siddall, E.

    1981-04-01

    Part 1 of the paper advocates a rational approach to public safety based on unbiassed quantitative assessment of overall risks and benefits of any technological activity. It shows that improved safety should be attainable at less cost than is the case at present. Part 2 offers an explanation of why so little has been achieved in this direction and outlines the major errors in present practices. Part 3 suggests what might realistically be done towards the achievement of some of the possible benefits. Factors which are important in the study of safety and evidence supporting the arguments are discussed in six appendices. It is urged that the scientific and technological community should improve its understanding of safety as a specialization and should endeavour to lead rather than follow in our present political system

  13. A review of the report ''IAEA safety targets and probabilistic risk assessment'' prepared for Greenpeace International

    International Nuclear Information System (INIS)

    1991-01-01

    At the request of the Director General, INSAG reviewed the report ''IAEA Safety Targets and Probabilistic Risk Assessment'' prepared for Greenpeace International by the Gesellschaft fuer Oekologische Forschung und Beratung mbH, Hannover, Germany. The conclusions of the report as well as the review results of INSAG experts are reproduced in this document

  14. Dams and Levees: Safety Risks

    Science.gov (United States)

    Carter, N. T.

    2017-12-01

    The nation's flood risk is increasing. The condition of U.S. dams and levees contributes to that risk. Dams and levee owners are responsible for the safety, maintenance, and rehabilitation of their facilities. Dams-Of the more than 90,000 dams in the United States, about 4% are federally owned and operated; 96% are owned by state and local governments, public utilities, or private companies. States regulate dams that are not federally owned. The number of high-hazard dams (i.e., dams whose failure would likely result in the loss of human life) has increased in the past decade. Roughly 1,780 state-regulated, high-hazard facilities with structural ratings of poor or unsatisfactory need rehabilitation. Levees-There are approximately 100,000 miles of levees in the nation; most levees are owned and maintained by municipalities and agricultural districts. Few states have levee safety programs. The U.S. Army Corps of Engineers (Corps) inspects 15,000 miles of levees, including levees that it owns and local levees participating in a federal program to assist with certain post-flood repairs. Information is limited on how regularly other levees are inspected. The consequence of a breach or failure is another aspect of risk. State and local governments have significant authority over land use and development, which can shape the social and economic impacts of a breach or failure; they also lead on emergency planning and related outreach. To date, federal dam and levee safety efforts have consisted primarily of (1) support for state dam safety standards and programs, (2) investments at federally owned dams and levees, and (3) since 2007, creation of a national levee database and enhanced efforts and procedures for Corps levee inspections and assessments. In Public Law 113-121, enacted in 2014, Congress (1) directed the Corps to develop voluntary guidelines for levee safety and an associated hazard potential classification system for levees, and (2) authorized support for the

  15. Truck shipment risks for assessing hazardous materials - a new paradigm incorporating safety and security

    Energy Technology Data Exchange (ETDEWEB)

    Greenberg, A.; McSweeney, T.; Allen, J.; Lepofsky, M. [Battelle Memorial Inst., Columbus, OH (United States); Abkowitz, M. [Dept. of Civil Engineering, Vanderbilt Univ., Nashville, TN (United States)

    2004-07-01

    Recent terrorist events, most notably September 11, 2001, have taught us that transportation risk management must be performed with a different lens to accommodate terrorism scenarios that would have previously been considered unlikely to warrant serious attention. Given these circumstances, a new paradigm is needed for managing the risks associated with highway transport of hazardous materials. In particular, this paradigm must: 1) more explicitly consider security threat and vulnerability, and 2) integrate security considerations into an overall framework for addressing natural and man-made disasters, be they accidental or planned. This paper summarizes the results of a study sponsored by the U.S. Department of Transportation, Federal Motor Carrier Safety Administration for the purpose of exploring how a paradigm might evolve in which both safety and security risks can be evaluated as a systematic, integrated process. The work was directed at developing a methodology for assessing the impacts of hazardous materials safety and security incident consequences when transported by highway. This included consideration of the manner in which these materials could be involved in initiating events as well as potential outcomes under a variety of release conditions. The methodology is subsequently applied to various classes of hazardous materials to establish an economic profile of the impacts that might be expected if a major release were to occur. The paper concludes with a discussion of the findings and implications associated with this effort.

  16. Truck shipment risks for assessing hazardous materials - a new paradigm incorporating safety and security

    International Nuclear Information System (INIS)

    Greenberg, A.; McSweeney, T.; Allen, J.; Lepofsky, M.; Abkowitz, M.

    2004-01-01

    Recent terrorist events, most notably September 11, 2001, have taught us that transportation risk management must be performed with a different lens to accommodate terrorism scenarios that would have previously been considered unlikely to warrant serious attention. Given these circumstances, a new paradigm is needed for managing the risks associated with highway transport of hazardous materials. In particular, this paradigm must: 1) more explicitly consider security threat and vulnerability, and 2) integrate security considerations into an overall framework for addressing natural and man-made disasters, be they accidental or planned. This paper summarizes the results of a study sponsored by the U.S. Department of Transportation, Federal Motor Carrier Safety Administration for the purpose of exploring how a paradigm might evolve in which both safety and security risks can be evaluated as a systematic, integrated process. The work was directed at developing a methodology for assessing the impacts of hazardous materials safety and security incident consequences when transported by highway. This included consideration of the manner in which these materials could be involved in initiating events as well as potential outcomes under a variety of release conditions. The methodology is subsequently applied to various classes of hazardous materials to establish an economic profile of the impacts that might be expected if a major release were to occur. The paper concludes with a discussion of the findings and implications associated with this effort

  17. Safety regulations: Implications of the new risk perspectives

    International Nuclear Information System (INIS)

    Aven, T.; Ylönen, M.

    2016-01-01

    The current safety regulations for industrial activities are to a large extent functionally oriented and risk-based (informed), expressing what to achieve rather than the means and solutions needed. They are founded on a probability-based perspective on risk, with the use of risk assessment, risk acceptance criteria and tolerability limits. In recent years several risk researchers have argued for the adoption of some new types of risk perspectives which highlight uncertainties rather than probabilities in the way risk is defined, the point being to better reflect the knowledge, and lack of knowledge, dimension of risk. The Norwegian Petroleum Safety Authority has recently implemented such a perspective. The new ISO standard 31000 is based on a similar thinking. In this paper we discuss the implications of these perspectives on safety regulation, using the oil & gas and nuclear industries as illustrations. Several suggestions for how to develop the current safety regulations in line with the ideas of the new risk perspectives are outlined, including some related to the use of risk acceptance criteria (tolerability limits). We also point to potential obstacles and incentives that the larger societal and institutional setting may impose on industry as regards the adoption of the new risk perspectives. - Highlights: • Some new types of risk perspectives have been promoted. • They have been implemented for example by the Norwegian Petroleum Safety Authority. • The paper studies the implication of these perspectives on the risk regulation. • Suggestions for how to develop the regulations are provided • Obstacles and incentives for the implementation of the perspectives are pointed to.

  18. Engineering measures and risk assessment against fault displacement

    International Nuclear Information System (INIS)

    Narabayashi, Tadashi; Okamoto, Koji; Dodo, Takashi; Kamiya, Masanobu

    2017-01-01

    A special committee on 'assessment on fault activities and engineering risk' was established at the Japan Atomic Energy Society. With a participation of the Japan Society of Maintenology, a study group on nuclear safety regulations was established at the Japan Society of Maintenology, and this theme has been examined. Among the technics for evaluating the effects of fault displacement on nuclear facilities, the concept of application of the safety margin evaluation method is shown. By applying this method, it is possible to evaluate nuclear safety against fault displacement, and it is also possible to obtain risk information such as the conditions of facilities and safety functions (retention or loss) as well as the safety margin against core damage, including the event exceeding prediction. Thus, it is possible to verify the effectiveness of accident management and to make decisions for further countermeasures to reduce risk through using the obtained risk information. The countermeasures prepared for large scale damage can also be effectively utilized. It is necessary not only the fault displacement targeted in this paper, but also the results of risk assessment obtained by safety margin assessment etc. are reflected on the improvement of accident management at the site, education and training, and assumption of various events and desk training, and are linked to safety improvement. Efforts for encouraging these actions are also required. (A.O.)

  19. Operational safety assessment of underground test facilities for mined geologic waste disposal

    International Nuclear Information System (INIS)

    Elder, H.K.

    1993-01-01

    This paper describes the operational safety assessment for the underground facilities for the exploratory studies facility (ESF) at the Yucca Mountain Project. The systematic identification and evaluation of hazards related to the ESF is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach based on the analysis of potential accidents was used since radiological safety analysis was not required. The risk assessment summarized credible accident scenarios and the design provides mitigation of the risks to a level that the facility can be constructed and operated with an adequate level of safety. The risk assessment also provides reasonable assurance that all identifiable major accident scenarios have been reviewed and design mitigation features provided to ensure an adequate level of safety

  20. Risk Assessment in the Maritime Industry

    Directory of Open Access Journals (Sweden)

    M. Mousavi

    2017-02-01

    Full Text Available Risk assessment is a well-developed field which many operators are currently applying to improve their operations and reduce their risk exposure. This paper is intended to provide an overview of the risk assessment for mariners in the Maritime transportation. The risks addressed are primarily those affecting the safety of a vessel, facility or operation. The concept of risk is defined, and the methods available to assess the risks associated with an operation are described. Regulatory requirements that have prompted the development of modern risk assessment practices are described, and future regulatory trends are discussed. There are many different analysis techniques and models that have been developed to aid in conducting risk assessments. A key to any successful risk analysis is choosing the right method (or combination of methods for the situation at hand. This is achieved through critical analysis of the available data concerning marine crises. This paper provides a brief introduction to some of the analysis methods available and suggests risk analysis approaches to support different types of decision making within the maritime transportation to cope with crises. Finally, as awareness of risk assessment increases, the benefits which can be realized through its application will continue to increase. Organizations in both the public and the private sector are becoming more and more familiar with the benefits associated with risk-based approaches to managing safety and consequently reducing crisis in maritime transportation.

  1. The Risk Assessment at the Workplace of Assembly Operation

    Directory of Open Access Journals (Sweden)

    Marek Burda

    2014-01-01

    Full Text Available Risk Assessment Process by FMEA method involve hazard identification, risk assessment and risk control processes and their input is fundamental to a successful EH&S system. This Risk assessment tool follows the general process and requirements of the Health and Safety Risk Assessment Procedure.

  2. Preparing Safety Cases for Operating Outside Prescriptive Fatigue Risk Management Regulations.

    Science.gov (United States)

    Gander, Philippa; Mangie, Jim; Wu, Lora; van den Berg, Margo; Signal, Leigh; Phillips, Adrienne

    2017-07-01

    Transport operators seeking to operate outside prescriptive fatigue management regulations are typically required to present a safety case justifying how they will manage the associated risk. This paper details a method for constructing a successful safety case. The method includes four elements: 1) scope (prescriptive rules and operations affected); 2) risk assessment; 3) risk mitigation strategies; and 4) monitoring ongoing risk. A successful safety case illustrates this method. It enables landing pilots in 3-pilot crews to choose the second or third in-flight rest break, rather than the regulatory requirement to take the third break. Scope was defined using a month of scheduled flights that would be covered (N = 4151). These were analyzed in the risk assessment using existing literature on factors affecting fatigue to estimate the maximum time awake at top of descent and sleep opportunities in each break. Additionally, limited data collected before the new regulations showed that pilots flying at landing chose the third break on only 6% of flights. A prospective survey comparing subjective reports (N = 280) of sleep in the second vs. third break and fatigue and sleepiness ratings at top of descent confirmed that the third break is not consistently superior. The safety case also summarized established systems for fatigue monitoring, risk assessment and hazard identification, and multiple fatigue mitigation strategies that are in place. Other successful safety cases have used this method. The evidence required depends on the expected level of risk and should evolve as experience with fatigue risk management systems builds.Gander P, Mangie J, Wu L, van den Berg M, Signal L, Phillips A. Preparing safety cases for operating outside prescriptive fatigue risk management regulations. Aerosp Med Hum Perform. 2017; 88(7):688-696.

  3. Integrating risk management and safety culture in a framework for risk informed decision making

    International Nuclear Information System (INIS)

    Nelson, W.R.

    2009-01-01

    Operators and regulators of nuclear power plants agree on the importance of maintaining safety and controlling accident risks. Effective safety and risk management requires treatment of both technical and organizational components. Probabilistic Risk Assessment (PRA) provides tools for technical risk management. However, organizational factors are not treated in PRA, but are addressed using different approaches. To bring both components together, a framework of Risk Informed Decision Making (RIDM) is needed. The objective tree structure of the International Atomic Energy Agency (IAEA) is a promising approach to combine both elements. Effective collaboration involving regulatory and industry groups is needed to accomplish the integration. (author)

  4. Safety and reliability assessment

    International Nuclear Information System (INIS)

    1979-01-01

    This report contains the papers delivered at the course on safety and reliability assessment held at the CSIR Conference Centre, Scientia, Pretoria. The following topics were discussed: safety standards; licensing; biological effects of radiation; what is a PWR; safety principles in the design of a nuclear reactor; radio-release analysis; quality assurance; the staffing, organisation and training for a nuclear power plant project; event trees, fault trees and probability; Automatic Protective Systems; sources of failure-rate data; interpretation of failure data; synthesis and reliability; quantification of human error in man-machine systems; dispersion of noxious substances through the atmosphere; criticality aspects of enrichment and recovery plants; and risk and hazard analysis. Extensive examples are given as well as case studies

  5. Risk concepts in UK nuclear safety decision-making

    International Nuclear Information System (INIS)

    Brighton, P.W.M.

    2001-01-01

    This paper discusses the concept of risk as understood in the UK, with particular reference to the use of probabilistic safety assessment (PSA) in nuclear safety decision making. The way 'risk' appears in UK fundamental legislation means that the concept cannot be limited to evaluation of numerical probabilities of physical harm. Rather the focus is on doing all that is reasonably practicable to reduce risks: this entails applying relevant good practice and then seeking further safety measures until the money, time and trouble required are grossly disproportionate to the residual risk. PSA is used to inform rather than dictate such decisions. This approach is reinforced by considering how far any practical PSA can be said to measure risk. The behaviour of complex socio-technical systems such as nuclear power stations does not meet the conditions under which probability theory can be applied in an absolutely objective statistical sense. Risk is not an intrinsic real property of such systems. Rather PSA is a synthesis of data and subjective expert judgements, dependent on the extent of detailed knowledge of the plant. There are many other aspects of engineering judgement involved in safety decisions which cannot be so captured. (author)

  6. A model for managing cold-related health and safety risks at workplaces.

    Science.gov (United States)

    Risikko, Tanja; Mäkinen, Tiina M; Påsche, Arvid; Toivonen, Liisa; Hassi, Juhani

    2003-05-01

    Cold conditions increase health and safety risks at work in several ways. The effects of cold have not been sufficiently taken into consideration in occupational safety and health practices. A systematic model and methods were developed for managing cold-related health and safety risks at workplaces. The development work was performed, in a context-bound manner, in pilot industries and workplaces. The model can be integrated into the company's occupational health and safety management system, such as OHSAS 18001. The cold risks are identified and assessed by using a checklist. The preventive measures are systematically planned in a written form specifically produced for cold workplaces. It includes the organisational and technical preventive measures, protective clothing and personal protective equipment, as well as training and information of the personnel. According to the model, all the workers, foremen, occupational safety personnel and occupational health care personnel are trained to recognise the cold risks and to conduct preventive actions. The developed model was evaluated in the context of cold outdoor (construction) and indoor work (fish processing), and by occupational health and safety professionals. According to the feedback, the model and methods were easy to use after a one-day introduction session. The continuum between the cold risk assessment and management worked well, although there was some overlap in the documentation. The cold risk management model and its methods form an essential part of ISO CD 15743 Strategy for risk assessment, management and work practice in cold environments.

  7. Risk assessment activities at NIOSH: Information resources and needs

    Energy Technology Data Exchange (ETDEWEB)

    Stayner, L.T.; Meinhardt, T.; Hardin, B. [National Institute for Occupational Safety and Health, Cincinnati, OH (United States)

    1990-12-31

    Under the Occupational Safety and Health, and Mine Safety and Health Acts, the National Institute for Occupational Safety and Health (NIOSH) is charged with development of recommended occupational safety and health standards, and with conducting research to support the development of these standards. Thus, NIOSH has been actively involved in the analysis of risk associated with occupational exposures, and in the development of research information that is critical for the risk assessment process. NIOSH research programs and other information resources relevant to the risk assessment process are described in this paper. Future needs for information resources are also discussed.

  8. Probabilistic safety assessment for food irradiation facility

    International Nuclear Information System (INIS)

    Solanki, R.B.; Prasad, M.; Sonawane, A.U.; Gupta, S.K.

    2012-01-01

    Highlights: ► Different considerations are required in PSA for Non-Reactor Nuclear Facilities. ► We carried out PSA for food irradiation facility as a part of safety evaluation. ► The results indicate that the fatal exposure risk is below the ‘acceptable risk’. ► Adequate operator training and observing good safety culture would reduce the risk. - Abstract: Probabilistic safety assessment (PSA) is widely used for safety evaluation of Nuclear Power Plants (NPPs) worldwide. The approaches and methodologies are matured and general consensus exists on using these approaches in PSA applications. However, PSA applications for safety evaluation for non-reactor facilities are limited. Due to differences in the processes in nuclear reactor facilities and non-reactor facilities, the considerations are different in application of PSA to these facilities. The food irradiation facilities utilize gamma irradiation sources, X-ray machines and electron accelerators for the purpose of radiation processing of variety of food items. This is categorized as Non-Reactor Nuclear Facility. In this paper, the application of PSA to safety evaluation of food irradiation facility is presented considering the ‘fatality due to radiation overexposure’ as a risk measure. The results indicate that the frequency of the fatal exposure is below the numerical acceptance guidance for the risk to the individual. Further, it is found that the overall risk to the over exposure can be reduced by providing the adequate operator training and observing good safety culture.

  9. 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

  10. Risk assessment of forensic patients: nurses' role.

    Science.gov (United States)

    Encinares, Maxima; McMaster, Jeff James; McNamee, Jim

    2005-03-01

    One of the unique roles of forensic nurses is to conduct risk assessments. Establishing a therapeutic nurse-patient relationship helps forensic nurses perform accurate and useful risk assessments. Accurate risk assessments can facilitate formulation of individualized risk management plans, designed to meet patients' needs and ensure public safety. The importance of forensic nurses' knowledge and application of appropriate communication and proper documentation cannot be overemphasized.

  11. Probabilistic safety and risk assessments in the field of nuclear technology - Mode of operation, possibilities and limits

    International Nuclear Information System (INIS)

    Mertens, J.

    1993-01-01

    In this study probabilistic safety and risk assessments in the field of nuclear energy are explained. Mainly qualitative results and conclusions are presented. Explanations for often discussed aspects of such analysis reveal the procedure and reasonable limits of application. The mentioned literature contains detailed results. (orig./DG) [de

  12. Assessment of safety measures and plant risks during shut-down periods at NPP Biblis

    International Nuclear Information System (INIS)

    Pamme, H.; Roess, P.H.

    1996-01-01

    Results of French probabilistic PWR-studies indicated a high contribution of shut down states to the overall plant risk. Mainly inspired by these results qualitative and also probabilistic analyses were started in Germany since 1991. As the Biblis-B-NPP was already reference plant of the German Risk Study first studies of shut-down-states were again focuses on Biblis-B. These studies were mainly performed by the German Association for Reactor Safety (GRS) in close cooperation with the utility RWE Energie AG. This paper briefly reviews the chosen approach to model and assess shut-down-states at Biblis-NPP. An in-depth-presentation is focuses on the quantification of risk in mid-loop-operation (MLO) which was performed by the authors with intensive support of plant personnel

  13. Risk Assessment for an Unmanned Merchant Ship

    Directory of Open Access Journals (Sweden)

    Ø.J. Rødseth

    2015-09-01

    Full Text Available The MUNIN project is doing a feasibility study on an unmanned bulk carrier on an intercontinental voyage. To develop the technical and operational concepts, MUNIN has used a risk-based design method, based on the Formal Safety Analysis method which is also recommended by the International Mari-time Organization. Scenario analysis has been used to identify risks and to simplify operational scope. Systematic hazard identification has been used to find critical safety and security risks and how to address these. Technology and operational concept testing is using a hypothesis-based test method, where the hypotheses have been created as a result of the risk assessment. Finally, the cost-benefit assessment will also use results from the risk assessment. This paper describes the risk assessment method, some of the most important results and also describes how the results have been or will be used in the different parts of the project.

  14. The use of safety indicators, complementary to dose and risk, in the assessment of radioactive waste disposal

    International Nuclear Information System (INIS)

    Gera, F.; Vovk, I.; Wingefors, S.

    1998-01-01

    The use of safety indicators, other than dose and risk, to complement the safety assessment of disposal systems for radioactive waste, is not a new idea. Several possible approaches have been proposed through the years, including a discussion in an IAEA document of 1994. The present paper reviews critically the various proposed indicators, identifies the most promising ones and suggests a possible approach for the assessment of their viability. In particular it suggests that a Coordinated Research Project should be organized with the main objectives of assembling, reviewing and generating the necessary scientific information on natural values, particularly fluxes and concentrations of pollutants, and on their impacts on public health and environmental quality. (author)

  15. Risk assessment in maritime transportation

    International Nuclear Information System (INIS)

    Soares, C. Guedes; Teixeira, A.P.

    2001-01-01

    A review is presented of different approaches to quantify the risk in maritime transportation. The discussion of several accident statistics provides a global assessment of the risk levels and its differentiation in ship types and main types of ship losses. Early studies in the probability of ship loss by foundering and capsizing are reviewed. The approaches used to assess the risk of structural design are addressed. Finally a brief account is given of recent development of using formal safety assessments to support decision making on legislation applicable internationally to maritime transportation

  16. Development of safety function assessment trees for pressurized heavy water reactor LP/SD operations

    International Nuclear Information System (INIS)

    Yang, Hui Chang; Chung, Chang Hyun; Kim, Ki Yong; Jee, Moon Hak; Sung, Chang Kyoung

    2003-01-01

    The objective of Configuration Risk Management Program(CRMP) is to maintain the safety level by assuring the defense-in-depth of nuclear power plant while the configurations are changed during plant operations, especially for the LP/SD. Such a safety purpose can be achieved by establishing the risk monitoring programs with both quantitative and qualitative features. Generally, the quantitative risk evaluation models, i.e., PRA models are used for the risk evaluation during full power operation, and the qualitative risk evaluation models such as safety function assessment trees are used. Through this study, safety function assessment trees were developed

  17. Safety Climate, Perceived Risk, and Involvement in Safety Management

    OpenAIRE

    Kouabenan , Dongo Rémi; Ngueutsa , Robert ,; Safiétou , Mbaye

    2015-01-01

    International audience; This article examines the relationship between safety climate, risk perception and involvement in safety management by first-line managers (FLM). Sixty-three FLMs from two French nuclear plants answered a questionnaire measuring perceived workplace safety climate, perceived risk, and involvement in safety management. We hypothesized that a positive perception of safety climate would promote substantial involvement in safety management, and that this effect would be str...

  18. Implications of probabilistic risk assessment

    International Nuclear Information System (INIS)

    Cullingford, M.C.; Shah, S.M.; Gittus, J.H.

    1987-01-01

    Probabilistic risk assessment (PRA) is an analytical process that quantifies the likelihoods, consequences and associated uncertainties of the potential outcomes of postulated events. Starting with planned or normal operation, probabilistic risk assessment covers a wide range of potential accidents and considers the whole plant and the interactions of systems and human actions. Probabilistic risk assessment can be applied in safety decisions in design, licensing and operation of industrial facilities, particularly nuclear power plants. The proceedings include a review of PRA procedures, methods and technical issues in treating uncertainties, operating and licensing issues and future trends. Risk assessment for specific reactor types or components and specific risks (eg aircraft crashing onto a reactor) are used to illustrate the points raised. All 52 articles are indexed separately. (U.K.)

  19. Implications of applying cumulative risk assessment to the workplace.

    Science.gov (United States)

    Fox, Mary A; Spicer, Kristen; Chosewood, L Casey; Susi, Pam; Johns, Douglas O; Dotson, G Scott

    2018-06-01

    Multiple changes are influencing work, workplaces and workers in the US including shifts in the main types of work and the rise of the 'gig' economy. Work and workplace changes have coincided with a decline in unions and associated advocacy for improved safety and health conditions. Risk assessment has been the primary method to inform occupational and environmental health policy and management for many types of hazards. Although often focused on one hazard at a time, risk assessment frameworks and methods have advanced toward cumulative risk assessment recognizing that exposure to a single chemical or non-chemical stressor rarely occurs in isolation. We explore how applying cumulative risk approaches may change the roles of workers and employers as they pursue improved health and safety and elucidate some of the challenges and opportunities that might arise. Application of cumulative risk assessment should result in better understanding of complex exposures and health risks with the potential to inform more effective controls and improved safety and health risk management overall. Roles and responsibilities of both employers and workers are anticipated to change with potential for a greater burden of responsibility on workers to address risk factors both inside and outside the workplace that affect health at work. A range of policies, guidance and training have helped develop cumulative risk assessment for the environmental health field and similar approaches are available to foster the practice in occupational safety and health. Copyright © 2018 Elsevier Ltd. All rights reserved.

  20. Safety assessment of multi-unit NPP sites subject to external events

    International Nuclear Information System (INIS)

    Samaddar, Sujit; Hibino, Kenta; Coman, Ovidiu

    2014-01-01

    This paper presents a framework for conducting a probabilistic safety assessment of multi-unit sites against external events. The treatment of multiple hazard on a unit, interaction between units, implementation of severe accident measures, human reliability, environmental conditions, metric of risk for both reactor and non-reactor sources, integration of risk and responses and many such important factors need to be addressed within the context of this framework. The framework facilitates the establishment of a comprehensive methodology that can be applied internationally to the peer review of safety assessment of multi-unit sites under the impact of multiple external hazards. In summary, it can be said that the site safety assessment for a multi-unit site will be quite complex and need to start with individual unit risk assessments, these need to be combined considering the interactions between units and their responses, and the fragilities of the installations established considering the combined demands from all interactions. Using newly established risk metric the risk can then be integrated for the overall site. Fig. 2 shows schematically such a proposal. Much work has to done and the IAEA has established a working group that is systematically establishing the structure and process to incorporate the many issues that are a part of a multi-unit site safety assessment. (authors)

  1. Mastery of risks and operational safety, risks and opportunities

    International Nuclear Information System (INIS)

    2004-01-01

    Creating socially useful richness is certainly the prime reason for companies to exist. Reaching this always moving target leads to seize opportunities and to take risks at the same time. For companies, risks and opportunities are two indissociable factors. Any decision making has to deal with an uncertain environment with random events of technological, economical, biological, human, environmental or natural origin. Because of the fear of uncertainty, risk acts as a brake to initiatives. In front of this problem, companies have to adopt a prevention policy based on a global and systemic approach, by identifying, evaluating, quantifying, sorting, mastering and managing unwanted events and by communicating about the way to treat them. In front of uncertainties, the operational safety, thanks to its methods and tools, supplies an incomparable contribution in the form of an help to any decision made with uncertainties. Operational safety contributes to the evaluation of costs and makes more realistic the economical estimations by taking into account the foreseeable and unforeseeable risks. The mastery of unwanted events, of their stakes and uncertainties, allows companies to carry out their projects in non-determined contexts and in a competitive environment. This colloquium concerns all socio-economical actors: industrialists, investors, decision makers, university and laboratory staffs, etc., who need a better evaluation of risks for a better mastery of their decisions in all sectors of activity. Seventeen papers of this conference, dealing with safety analysis and risk assessment at nuclear facilities and at other energy-related facilities, have been selected for Inis. (J.S.)

  2. Hydrogen safety risk assessment methodology applied to a fluidized bed membrane reactor for autothermal reforming of natural gas

    NARCIS (Netherlands)

    Psara, N.; Van Sint Annaland, M.; Gallucci, F.

    2015-01-01

    The scope of this paper is the development and implementation of a safety risk assessment methodology to highlight hazards potentially prevailing during autothermal reforming of natural gas for hydrogen production in a membrane reactor, as well as to reveal potential accidents related to hydrogen

  3. Safety and immunotoxicity assessment of immunomodulatory monoclonal antibodies

    Science.gov (United States)

    Morton, Laura Dill; Spindeldreher, Sebastian; Kiessling, Andrea; Allenspach, Roy; Hey, Adam; Muller, Patrick Y; Frings, Werner; Sims, Jennifer

    2010-01-01

    Most therapeutic monoclonal antibodies (mAbs) licensed for human use or in clinical development are indicated for treatment of patients with cancer and inflammatory/autoimmune disease and as such, are designed to directly interact with the immune system. A major hurdle for the development and early clinical investigation of many of these immunomodulatory mAbs is their inherent risk for adverse immune-mediated drug reactions in humans such as infusion reactions, cytokine storms, immunosuppression and autoimmunity. A thorough understanding of the immunopharmacology of a mAb in humans and animals is required to both anticipate the clinical risk of adverse immunotoxicological events and to select a safe starting dose for first-in-human (FIH) clinical studies. This review summarizes the most common adverse immunotoxicological events occurring in humans with immunomodulatory mAbs and outlines non-clinical strategies to define their immunopharmacology and assess their immunotoxic potential, as well as reduce the risk of immunotoxicity through rational mAb design. Tests to assess the relative risk of mAb candidates for cytokine release syndrome, innate immune system (dendritic cell) activation and immunogenicity in humans are also described. The importance of selecting a relevant and sensitive toxicity species for human safety assessment in which the immunopharmacology of the mAb is similar to that expected in humans is highlighted, as is the importance of understanding the limitations of the species selected for human safety assessment and supplementation of in vivo safety assessment with appropriate in vitro human assays. A tiered approach to assess effects on immune status, immune function and risk of infection and cancer, governed by the mechanism of action and structural features of the mAb, is described. Finally, the use of immunopharmacology and immunotoxicity data in determining a minimum anticipated biologic effect Level (MABEL) and in the selection of safe human

  4. RESIDUAL RISK ASSESSMENT: ETHYLENE OXIDE ...

    Science.gov (United States)

    This document describes the residual risk assessment for the Ethylene Oxide Commercial Sterilization source category. For stationary sources, section 112 (f) of the Clean Air Act requires EPA to assess risks to human health and the environment following implementation of technology-based control standards. If these technology-based control standards do not provide an ample margin of safety, then EPA is required to promulgate addtional standards. This document describes the methodology and results of the residual risk assessment performed for the Ethylene Oxide Commercial Sterilization source category. The results of this analyiss will assist EPA in determining whether a residual risk rule for this source category is appropriate.

  5. Risk assessment and risk management of mycotoxins.

    Science.gov (United States)

    2012-01-01

    Risk assessment is the process of quantifying the magnitude and exposure, or probability, of a harmful effect to individuals or populations from certain agents or activities. Here, we summarize the four steps of risk assessment: hazard identification, dose-response assessment, exposure assessment, and risk characterization. Risk assessments using these principles have been conducted on the major mycotoxins (aflatoxins, fumonisins, ochratoxin A, deoxynivalenol, and zearalenone) by various regulatory agencies for the purpose of setting food safety guidelines. We critically evaluate the impact of these risk assessment parameters on the estimated global burden of the associated diseases as well as the impact of regulatory measures on food supply and international trade. Apart from the well-established risk posed by aflatoxins, many uncertainties still exist about risk assessments for the other major mycotoxins, often reflecting a lack of epidemiological data. Differences exist in the risk management strategies and in the ways different governments impose regulations and technologies to reduce levels of mycotoxins in the food-chain. Regulatory measures have very little impact on remote rural and subsistence farming communities in developing countries, in contrast to developed countries, where regulations are strictly enforced to reduce and/or remove mycotoxin contamination. However, in the absence of the relevant technologies or the necessary infrastructure, we highlight simple intervention practices to reduce mycotoxin contamination in the field and/or prevent mycotoxin formation during storage.

  6. TWRS safety and technical integration risk management plan

    International Nuclear Information System (INIS)

    Fordham, R.A.

    1996-01-01

    The objectives of the Tank Waste Remediation System (TWRS) Safety and Technical Integration (STI) programmatic risk management program are to assess, analyze, and handle risks associated with TWRS STI responsibilities and to communicate information about the actions being taken and the results to enable decision making. The objective of this TWRS STI Risk Management Plan is to communicate a consistent approach to risk management that will be used by the organization

  7. Pesticide Exposure, Safety Issues, and Risk Assessment Indicators

    Directory of Open Access Journals (Sweden)

    Christos A. Damalas

    2011-05-01

    Full Text Available Pesticides are widely used in agricultural production to prevent or control pests, diseases, weeds, and other plant pathogens in an effort to reduce or eliminate yield losses and maintain high product quality. Although pesticides are developed through very strict regulation processes to function with reasonable certainty and minimal impact on human health and the environment, serious concerns have been raised about health risks resulting from occupational exposure and from residues in food and drinking water. Occupational exposure to pesticides often occurs in the case of agricultural workers in open fields and greenhouses, workers in the pesticide industry, and exterminators of house pests. Exposure of the general population to pesticides occurs primarily through eating food and drinking water contaminated with pesticide residues, whereas substantial exposure can also occur in or around the home. Regarding the adverse effects on the environment (water, soil and air contamination from leaching, runoff, and spray drift, as well as the detrimental effects on wildlife, fish, plants, and other non-target organisms, many of these effects depend on the toxicity of the pesticide, the measures taken during its application, the dosage applied, the adsorption on soil colloids, the weather conditions prevailing after application, and how long the pesticide persists in the environment. Therefore, the risk assessment of the impact of pesticides either on human health or on the environment is not an easy and particularly accurate process because of differences in the periods and levels of exposure, the types of pesticides used (regarding toxicity and persistence, and the environmental characteristics of the areas where pesticides are usually applied. Also, the number of the criteria used and the method of their implementation to assess the adverse effects of pesticides on human health could affect risk assessment and would possibly affect the characterization

  8. Pesticide Exposure, Safety Issues, and Risk Assessment Indicators

    Science.gov (United States)

    Damalas, Christos A.; Eleftherohorinos, Ilias G.

    2011-01-01

    Pesticides are widely used in agricultural production to prevent or control pests, diseases, weeds, and other plant pathogens in an effort to reduce or eliminate yield losses and maintain high product quality. Although pesticides are developed through very strict regulation processes to function with reasonable certainty and minimal impact on human health and the environment, serious concerns have been raised about health risks resulting from occupational exposure and from residues in food and drinking water. Occupational exposure to pesticides often occurs in the case of agricultural workers in open fields and greenhouses, workers in the pesticide industry, and exterminators of house pests. Exposure of the general population to pesticides occurs primarily through eating food and drinking water contaminated with pesticide residues, whereas substantial exposure can also occur in or around the home. Regarding the adverse effects on the environment (water, soil and air contamination from leaching, runoff, and spray drift, as well as the detrimental effects on wildlife, fish, plants, and other non-target organisms), many of these effects depend on the toxicity of the pesticide, the measures taken during its application, the dosage applied, the adsorption on soil colloids, the weather conditions prevailing after application, and how long the pesticide persists in the environment. Therefore, the risk assessment of the impact of pesticides either on human health or on the environment is not an easy and particularly accurate process because of differences in the periods and levels of exposure, the types of pesticides used (regarding toxicity and persistence), and the environmental characteristics of the areas where pesticides are usually applied. Also, the number of the criteria used and the method of their implementation to assess the adverse effects of pesticides on human health could affect risk assessment and would possibly affect the characterization of the already

  9. Risk indices in comparative risk assessment studies

    International Nuclear Information System (INIS)

    Hubert, P.

    1984-01-01

    More than a decade ago the development of comparative risk assessment studies aroused overwhelming interest. There was no doubt that data on the health and safety aspects of energy systems would greatly benefit, or even end, the debate on nuclear energy. Although such attempts are still strongly supported, the rose-coloured expectations of the early days have faded. The high uncertainties, and the contradictory aspect, of the first results might explain this evolution. The loose connection between the range of computed risk indices and the questions on which the debate was focused is another reason for this decline in interest. Important research work is being carried out aiming at reducing the different kinds of uncertainties. Rather than the uncertainties, the paper considers the meaning of available risk indices and proposes more significant indices with respect to the goals of risk assessment. First, the indices which are of frequent use in comparative studies are listed. The stress is put on a French comparative study from which most examples are drawn. Secondly, the increase in magnitude of the indices and the decrease in the attributability of the risk to a given system is shown to be a consequence of the trend towards more comprehensive analyses. Thirdly, the ambiguity of such indices as the collective occupational risk is underlined, and a possible solution is suggested. Whenever risk assessments are related to pragmatic decision making problems it is possible to find satisfactory risk indices. The development of cost-effectiveness analyses and the proposals for quantitative safety goals clearly demonstrate this point. In the field of comparison of social impacts some proposals are made, but there remain some gaps still to be filled. (author)

  10. Application of the Integrated Safety Assessment methodology to safety margins. Dynamic Event Trees, Damage Domains and Risk Assessment

    International Nuclear Information System (INIS)

    Ibánez, L.; Hortal, J.; Queral, C.; Gómez-Magán, J.; Sánchez-Perea, M.; Fernández, I.; Meléndez, E.; Expósito, A.; Izquierdo, J.M.; Gil, J.; Marrao, H.; Villalba-Jabonero, E.

    2016-01-01

    The Integrated Safety Assessment (ISA) methodology, developed by the Consejo de Seguridad Nuclear, has been applied to an analysis of Zion NPP for sequences with Loss of the Component Cooling Water System (CCWS). The ISA methodology proposal starts from the unfolding of the Dynamic Event Tree (DET). Results from this first step allow assessing the sequence delineation of standard Probabilistic Safety Analysis results. For some sequences of interest of the outlined DET, ISA then identifies the Damage Domain (DD). This is the region of uncertain times and/or parameters where a safety limit is exceeded, which indicates the occurrence of certain damage situation. This paper illustrates application of this concept obtained simulating sequences with MAAP and with TRACE. From information of simulation results of sequence transients belonging to the DD and the time-density probability distributions of the manual actions and of occurrence of stochastic phenomena, ISA integrates the dynamic reliability equations proposed to obtain the sequence contribution to the global Damage Exceedance Frequency (DEF). Reported results show a slight increase in the DEF for sequences investigated following a power uprate from 100% to 110%. This demonstrates the potential use of the method to help in the assessment of design modifications. - Highlights: • This paper illustrates an application of the ISA methodology to safety margins. • Dynamic Event Trees are useful tool for verifying the standard PSA Event Trees. • The ISA methodology takes into account the uncertainties in human action times. • The ISA methodology shows the Damage Exceedance Frequency increase in power uprates.

  11. Environmental risk index: A tool to assess the safety of dams for leachate

    International Nuclear Information System (INIS)

    Colomer Mendoza, Francisco J.; Gallardo Izquierdo, Antonio

    2009-01-01

    Dams for leachate store very toxic substances that contain a large amount of organic material and, probably, heavy metals; they therefore constitute an important threat to the environment. Existing models of environmental risk assessment for landfills do not take into consideration the specific risk that leachate dams may represent for the environment. In this paper a methodology to improve the environmental safety is presented according to the parameters used in their construction and management. In order to do that, the following characteristics of the dam must be known: (1) geotechnical stability, (2) erosion of downstream slope, (3) type of sealing of the dam, (4) overtopping probability, (5) volume of leachate stored inside the dam and (6) pollution load of leachate. Once these parameters have been calculated, they are transformed by means of rating curves into homogeneous units, so as to make it possible to operate between them. From the study and analysis of these parameters an environmental risk index for a dam for leachate can be calculated. If the environmental risk index exceeds an established value then it involves a dam for leachate with high environmental risk, therefore preventive measures in its design, construction and management would be necessary

  12. N reactor individual risk comparison to quantitative nuclear safety goals

    International Nuclear Information System (INIS)

    Wang, O.S.; Rainey, T.E.; Zentner, M.D.

    1990-01-01

    A full-scope level III probabilistic risk assessment (PRA) has been completed for N reactor, a US Department of Energy (DOE) production reactor located on the Hanford Reservation in the state of Washington. Sandia National Laboratories (SNL) provided the technical leadership for this work, using the state-of-the-art NUREG-1150 methodology developed for the US Nuclear Regulatory Commission (NRC). The main objectives of this effort were to assess the risks to the public and to the on-site workers posed by the operation of N reactor, to identify changes to the plant that could reduce the overall risk, and to compare those risks to the proposed NRC and DOE quantitative safety goals. This paper presents the methodology adopted by Westinghouse Hanford Company (WHC) and SNL for individual health risk evaluation, its results, and a comparison to the NRC safety objectives and the DOE nuclear safety guidelines. The N reactor results, are also compared with the five NUREG-1150 nuclear plants. Only internal events are compared here because external events are not yet reported in the current draft NUREG-1150. This is the first full-scope level III PRA study with a detailed quantitative safety goal comparison performed for DOE production reactors

  13. Risk monitor-a tool for computer aided risk assessment for NPPs

    International Nuclear Information System (INIS)

    Vinod, Gopika; Saraf, R.K.; Babar, A.K.; Kushwaha, H.S.; Hadap, Nikhil

    2001-01-01

    Considerable changes occur in components status and system design and subsequent operation due to changes in plant configuration and their operating procedures. These changes are organised because some components are randomly down and other can be planned for test, maintenance and repair. This results in a fluctuation of risk level over operating time, which is termed as risk profile. Probabilistic Safety Assessment (PSA) is an analytical technique for assessing the risk by integrating diverse aspects of design and operation of a Nuclear Power Plant. Risk can be defined as the product of the probability of an accident and the consequences from that accident. Reactor Safety Division of BARC has developed PC based tool, which can assess the risk profile. This package can be used to optimise the operation in Nuclear Power Plants with respect to a minimum risk level over the operating time, and is termed as Risk Monitor. Risk Monitor is user friendly and can re-evaluate core damage frequency for changes in component status, test interval, initiating event frequency etc. Plant restoration advice, when the plant is in high risk configuration, current status of all plant equipment, and equipment prioritization are also provided by the package. (author)

  14. Safety Goal, Multi-unit Risk and PSA Uncertainty

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Joon-Eon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The safety goal is an answer of each country to the question 'How safe is safe enough?'. Table 1 shows some examples of the safety goal. However, many countries including Korea do not have the official safety goal for NPPs up to now since the establishment of safety goal is not just a technical issue but a very complex socio-technical issue. In establishing the safety goal for nuclear facilities, we have to consider various factors including not only technical aspects but also social, cultural ones. Recently, Korea is trying to establish the official safety goal. In this paper, we will review the relationship between the safety goal and Probabilistic Safety Assessment (PSA). We will also address some important technical issues to be considered in establishing the safety goal for NPPs from PSA point of view, i.e. a multi-unit risk issue and the uncertainty of PSA. In this paper, we reviewed some issues related to the safety goal and PSA. We believe that the safety goal is to be established in Korea considering the multi-unit risk. In addition, the relationship between the safety goal and PSA should be also defined clearly since PSA is the only way to answer to the question 'How safe is safe enough?'.

  15. National report of France. Risks and risk assessment according to the law of France

    International Nuclear Information System (INIS)

    Backhaus, L.

    1980-01-01

    This report encompasses the following chapters: the fundamentals of the law governing conventional industrial facilities, normative principles of atomic energy law; risk assessments in the law concerning conventional industrial facilities, risk assessment in the law concerning nuclear power plants; application of probabilistic methods in the field of nuclear safety, probabilistic methods in the safety assessment of modern aircraft; concept of risk in police regulations, 'Theorie des risques anormaux de voisinage' in public law on indemnification, causality and probability in civil law. It is stated in this report that in France, too, the idea of completely reforming the procedures of safety analysis is gaining ground, and the change from hitherto applied deterministic methods to logical risk analyses and probabilistic licensing is to be expected in the long run. This change will most probably be effected by defining a general risk acceptance criterion by means of conventions and, on the basis of this generally accepted criterion, proceed to defining an accepted, quantitatively determined risk standard both for a complete plant and for individual systems. (orig./HSCH) [de

  16. Microbiological risk assessment for personal care products.

    Science.gov (United States)

    Stewart, S E; Parker, M D; Amézquita, A; Pitt, T L

    2016-12-01

    Regulatory decisions regarding microbiological safety of cosmetics and personal care products are primarily hazard-based, where the presence of a potential pathogen determines decision-making. This contrasts with the Food industry where it is a commonplace to use a risk-based approach for ensuring microbiological safety. A risk-based approach allows consideration of the degree of exposure to assess unacceptable health risks. As there can be a number of advantages in using a risk-based approach to safety, this study explores the Codex Alimentarius (Codex) four-step Microbiological Risk Assessment (MRA) framework frequently used in the Food industry and examines how it can be applied to the safety assessment of personal care products. The hazard identification and hazard characterization steps (one and two) of the Codex MRA framework consider the main microorganisms of concern. These are addressed by reviewing the current industry guidelines for objectionable organisms and analysing reports of contaminated products notified by government agencies over a recent 5-year period, together with examples of reported outbreaks. Data related to estimation of exposure (step three) are discussed, and examples of possible calculations and references are included. The fourth step, performed by the risk assessor (risk characterization), is specific to each assessment and brings together the information from the first three steps to assess the risk. Although there are very few documented uses of the MRA approach for personal care products, this study illustrates that it is a practicable and sound approach for producing products that are safe by design. It can be helpful in the context of designing products and processes going to market and with setting of microbiological specifications. Additionally, it can be applied reactively to facilitate decision-making when contaminated products are released on to the marketplace. Currently, the knowledge available may only allow a

  17. A Study on Safety and Risk Assessment of Dangerous Cargo Operations in Oil/Chemical Tankers

    OpenAIRE

    Cenk ŞAKAR; Yusuf ZORBA

    2017-01-01

    The safety and risk assessment of dangerous cargo operations in oil and chemical tankers is a necessary process to prevent possible accidents during these operations. Fire and explosion are the major accidents encountered in tanker operations. In this study, a model was constructed through the Fuzzy Bayes Network Method for the probabilistic relationships between the causes of fire and explosion accidents that could occur during the tank cleaning process. The study is composed of two stages. ...

  18. Qualitative Risk Assessment for an LNG Refueling Station and Review of Relevant Safety Issues

    Energy Technology Data Exchange (ETDEWEB)

    Siu, N.; Herring, J.S.; Cadwallader, L.; Reece, W.; Byers, J.

    1998-02-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural gas (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tank truck deliveries, and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects Analysis, and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of ``best practice`` information throughout the LNG community.

  19. Impact of shutdown risk on risk-based assessment of technical specifications

    International Nuclear Information System (INIS)

    Deriot, S.

    1992-10-01

    This paper describes the current work performed by the Research and Development Division of EDF concerning risk-based assessment of Operating Technical Specifications (OTS). The current risk-based assessment of OTS at EDF is presented. Then, the level 1 Probabilistic Safety Assessment of unit 3 of the Paluel nuclear power station (called PSA 1300) is described. It is fully computerized and takes into account the risk in shutdown states. A case study is presented. It shows that the fact of considering shutdown risk suggests that the current OTS should be modified

  20. Fire Risk Assessment in Germany

    International Nuclear Information System (INIS)

    Berg, H. P.

    2000-01-01

    Quantitative fire risk assessment can serve as an additional tool to assess the safety level of a nuclear power plant (NPP) and to set priorities for fire protection improvement measures. The recommended approach to be applied within periodic safety reviews of NPPs in Germany starts with a screening process providing critical fire zones in which a fully developed fire has the potential to both cause an initiating event and impair the function of at least one component or system critical to safety. The second step is to perform a quantitative analysis using a standard event tree has been developed with elements for fire initiation, ventilation of the room, fire detection, fire suppression, and fire propagation. In a final step, the fire induced frequency of initiating events, the main contributors and the calculated hazard state frequency for the fire event are determined. Results of the first quantitative fire risk studies performed in Germany are reported. (author)

  1. Discussing Firearm Ownership and Access as Part of Suicide Risk Assessment and Prevention: "Means Safety" versus "Means Restriction".

    Science.gov (United States)

    Stanley, Ian H; Hom, Melanie A; Rogers, Megan L; Anestis, Michael D; Joiner, Thomas E

    2017-01-01

    The goal of this study was to describe the relative utility of the terms "means safety" versus "means restriction" in counseling individuals to limit their access to firearms in the context of a mock suicide risk assessment. Overall, 370 participants were randomized to read a vignette depicting a clinical scenario in which managing firearm ownership and access was discussed either using the term "means safety" or "means restriction." Participants rated the term "means safety" as significantly more acceptable and preferable than "means restriction." Participants randomized to the "means safety" condition reported greater intentions to adhere to clinicians' recommendations to limit access to a firearm for safety purposes (F[1,367] = 7.393, p = .007, [Formula: see text]). The term "means safety" may be more advantageous than "means restriction" when discussing firearm ownership and access in clinical settings and public health-oriented suicide prevention efforts.

  2. Risk management: integration of social and technical risk variables into safety assessments of LWR'S

    International Nuclear Information System (INIS)

    Turnage, J.J.; Husseiny, A.A.

    1980-01-01

    A risk management methodology is developed here to formalize the acceptability levels of commercial LWR power plants via the estimation of risk levels acceptable to the public and the integration of such estimates into risk-benefit analysis. Utility theory is used for developing preference models based on value trade-offs among multiple objectives and uncertainties about the impact of alternatives. The method involves reducing the various variables affecting safety acceptability decisions to a single function that provides a metric for acceptability levels. The function accomondates for technical criteria related to design and licensing decisions, as well as public reactions to certain choices

  3. Selection of tolerable risk criteria for dam safety decision making

    International Nuclear Information System (INIS)

    Nielsen, N.M.; Hartford, D.N.D.; MacDonald, T.F.

    1994-01-01

    Risk assessment has received increasing attention in recent years as a means of aiding decision making on dams by providing systematic and rational methods for dealing with risk and uncertainty. Risk assessment is controversial and decisions affecting risk to life are the most controversial. Tolerable criteria, based on the risks that society is prepared to accept in order to avoid excessive costs, set bounds within which risk-based decisions may be made. The components of risk associated with dam safety are addressed on an individual basis and criteria established for each component, thereby permitting flexibility in the balance between component risk and avoiding the problems of placing a monetary value on life. The guiding principle of individual risk is that dams do not impose intolerable risks on any individual. A risk to life of 1 in 10 4 per annum is generally considered the maximum tolerable risk. When considering societal risk, the safety of a dam should be proportional to the consequences of its failure. Risks of financial losses beyond the corporation's ability to finance should be so low as to be considered negligible. 17 refs., 3 figs

  4. A holistic approach to control process safety risks: Possible ways forward

    International Nuclear Information System (INIS)

    Pasman, H.J.; Knegtering, B.; Rogers, W.J.

    2013-01-01

    Pursuing process safety in a world of continuously increasing requirements is not a simple matter. Keeping balance between producing quality and volume under budget constraints while maintaining an adequate safety level proves time and time again a difficult task given that evidently major accidents cannot be avoided. Lack of resilience from an organizational point of view to absorb unwanted and unforeseen disturbances has in recent years been put forward as a major cause, while organizational erosive drift is shown to be responsible for complacency and degradation of safety attitude. A systems approach to safety provides a new paradigm with the promise of new comprehensive tools. At the same time, one realizes that risk assessment will fall short of identifying and quantifying all possible scenarios. First, human error is in most assessments not included. It is even argued that determining human failure probability by decomposing it to basic elements of error is not possible. Second, the crux of the systemic approach is that safety is an emergent property, which means the same holds for the technological aspect: risk is not fully predictable from failure of components. By surveying and applying recent literature, besides analysing, this paper proposes a way forward by considering resilience of a socio-technical system both from an organizational and a technical side. The latter will for a large part be determined by the plant design. Sufficient redundancy and reserve shall be kept to preserve sufficient resilience, but the question that rises is how. Available methods are risk assessment and process simulation. It is helpful that the relation between risk and resilience analysis has been recently defined. Also, in a preliminary study the elements of resilience of a process have become listed. In the latter, receiving and interpreting weak signals to boost situational awareness plays an important role. To maintain alertness on the functioning of a safety management

  5. Payload Safety: Risk and Characteristic-Based Control of Engineered Nanomaterials

    Science.gov (United States)

    Abou, Seraphin Chally; Saad, Maarouf

    2013-09-01

    In the last decade progress has been made to assist organizations that are developing payloads intended for flight on the International Space Station (ISS) and/or Space Shuttle. Collaboration programs for comprehensive risk assessment have been initiated between the U.S. and the European Union to generate requirements and data needed to comply with payloads safety and to perform risk assessment and controls guidance. Yet, substantial research gaps remain, as do challenges in the translation of these research findings to control for exposure to nanoscale material payloads, and the health effects. Since nanomaterial structures are different from traditional molecules, some standard material properties can change at size of 50nm or less. Changes in material properties at this scale challenge our understanding of hazards posed by nanomaterial payloads in the ISS realistic exposure conditions, and our ability to anticipate, evaluate, and control potential health issues, and safety. The research question addressed in this framework is: what kind of descriptors can be developed for nanomaterial payloads risks assessment? Methods proposed incorporate elements of characteristic- based risk an alysis: (1) to enable characterization of anthropogenic nanomaterials which can result in incidental from natural nanoparticles; and (2) to better understand safety attributes in terms of human health impacts from exposure to varying types of engineered nanomaterials.

  6. 合成洗涤剂的人体安全性风险评估和控制%Human safety risk assessment and management of synthetic detergent

    Institute of Scientific and Technical Information of China (English)

    杨利川; 郑翔龙

    2011-01-01

    合成洗涤剂对人体的安全性一直是消费者关注的问题。结合欧洲家用清洁产品HERA(Human&Environmental Risk Assessment)安全性评估报告的内容,从合成洗涤剂产品组分的安全性角度,对洗涤产品组份安全性评估的主要内容和使用安全性风险评估的方法进行了详细论述,说明洗涤剂的人体安全性风险是可以被控制的。%The human safety of synthetic detergent are always much concerned by consumer.Based on the content of Human Environmental Risk Assessment on ingredients of European household cleaning products,this paper from the components of synthetic detergent safety point of view,discussed the content of the safety assessment and the methods of risk assessment about the components of synthetic detergent in detail.The results showed that the human safety risks of synthetic detergents can be controlled.

  7. Uncertainty estimation in nuclear power plant probabilistic safety assessment

    International Nuclear Information System (INIS)

    Guarro, S.B.; Cummings, G.E.

    1989-01-01

    Probabilistic Risk Assessment (PRA) was introduced in the nuclear industry and the nuclear regulatory process in 1975 with the publication of the Reactor Safety Study by the U.S. Nuclear Regulatory Commission. Almost fifteen years later, the state-of-the-art in this field has been expanded and sharpened in many areas, and about thirty-five plant-specific PRAs (Probabilistic Risk Assessments) have been performed by the nuclear utility companies or by the U.S. Nuclear Regulatory commission. Among the areas where the most evident progress has been made in PRA and PSA (Probabilistic Safety Assessment, as these studies are more commonly referred to in the international community outside the U.S.) is the development of a consistent framework for the identification of sources of uncertainty and the estimation of their magnitude as it impacts various risk measures. Techniques to propagate uncertainty in reliability data through the risk models and display its effect on the top level risk estimates were developed in the early PRAs. The Seismic Safety Margin Research Program (SSMRP) study was the first major risk study to develop an approach to deal explicitly with uncertainty in risk estimates introduced not only by uncertainty in component reliability data, but by the incomplete state of knowledge of the assessor(s) with regard to basic phenomena that may trigger and drive a severe accident. More recently NUREG-1150, another major study of reactor risk sponsored by the NRC, has expanded risk uncertainty estimation and analysis into the realm of model uncertainty related to the relatively poorly known post-core-melt phenomena which determine the behavior of the molten core and of the rector containment structures

  8. Integrated Deterministic-Probabilistic Safety Assessment Methodologies

    Energy Technology Data Exchange (ETDEWEB)

    Kudinov, P.; Vorobyev, Y.; Sanchez-Perea, M.; Queral, C.; Jimenez Varas, G.; Rebollo, M. J.; Mena, L.; Gomez-Magin, J.

    2014-02-01

    IDPSA (Integrated Deterministic-Probabilistic Safety Assessment) is a family of methods which use tightly coupled probabilistic and deterministic approaches to address respective sources of uncertainties, enabling Risk informed decision making in a consistent manner. The starting point of the IDPSA framework is that safety justification must be based on the coupling of deterministic (consequences) and probabilistic (frequency) considerations to address the mutual interactions between stochastic disturbances (e.g. failures of the equipment, human actions, stochastic physical phenomena) and deterministic response of the plant (i.e. transients). This paper gives a general overview of some IDPSA methods as well as some possible applications to PWR safety analyses. (Author)

  9. Laboratory Biosafety and Biosecurity Risk Assessment Technical Guidance Document

    Energy Technology Data Exchange (ETDEWEB)

    Astuto-Gribble, Lisa M; Caskey, Susan Adele

    2014-07-01

    The purpose of this document is threefold: 1) to describe the laboratory bio safety and biosecurity risk assessment process and its conceptual framework; 2) provide detailed guidance and suggested methodologies on how to conduct a risk assessment; and 3) present some practical risk assessment process strategies using realistic laboratory scenarios.

  10. Risk assessment of complex accident scenarios

    International Nuclear Information System (INIS)

    Kluegel, Jens-Uwe

    2012-01-01

    The use of methods of risk assessment in accidents in nuclear plants is based on an old tradition. The first consistent systematic study is considered to be the Rasmussen Study of the U.S. Nuclear Regulatory Commission, NRC, WASH-1400. Above and beyond the realm of nuclear technology, there is an extensive range of accident, risk and reliability research into technical-administrative systems. In the past, it has been this area of research which has led to the development of concepts of safety precautions of the type also introduced into nuclear technology (barrier concept, defense in depth, single-failure criterion), where they are now taken for granted as trivial concepts. Also for risk analysis, nuclear technology made use of methods (such as event and fault tree analyses) whose origins were outside the nuclear field. One area in which the use of traditional methods of probabilistic safety analysis is encountering practical problems is risk assessment of complex accident scenarios in nuclear technology. A definition is offered of the term 'complex accident scenarios' in nuclear technology. A number of problems are addressed which arise in the use of traditional PSA procedures in risk assessment of complex accident scenarios. Cases of complex accident scenarios are presented to demonstrate methods of risk assessment which allow robust results to be obtained even when traditional techniques of risk analysis are maintained as a matter of principle. These methods are based on the use of conditional risk metrics. (orig.)

  11. Safety assessments for deep geological disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Lyon, R.B.

    1984-01-01

    The objective of safety assessment for deep geological disposal of radioactive wastes is to evaluate how well the engineered barriers and geological setting inhibit radionuclide migration and prevent radiation dose to man. Safety assessment is influenced through interaction with the regulatory agencies, research groups, the public and the various levels of government. Under the auspices of the IAEA, a generic disposal system description has been developed to facilitate international exchange and comparison of data and results, and to enable development and comparison of performance for all components of the disposal system. It is generally accepted that a systems modelling approach is required and that safety assessment can be considered on two levels. At the systems level, all components of the system are taken into account to evaluate the risk to man. At the systems level, critical review and quality assurance on software provide the major validation techniques. Risk is a combination of dose estimate and probability of that dose. For analysis of the total system to be practical, the components are usually represented by simplified models. Recently, assessments have been taking uncertainties in the input data into account. At the detailed level, large-scale, complex computer programs model components of the system in sufficient detail that validation by comparison with field and laboratory measurements is possible. For example, three-dimensional fluid-flow, heat-transport and solute-transport computer programs have been used. Approaches to safety assessment are described, with illustrations from safety assessments performed in a number of countries. (author)

  12. Risk Assessment in Underground Coalmines Using Fuzzy Logic in the Presence of Uncertainty

    Science.gov (United States)

    Tripathy, Debi Prasad; Ala, Charan Kumar

    2018-04-01

    Fatal accidents are occurring every year as regular events in Indian coal mining industry. To increase the safety conditions, it has become a prerequisite to performing a risk assessment of various operations in mines. However, due to uncertain accident data, it is hard to conduct a risk assessment in mines. The object of this study is to present a method to assess safety risks in underground coalmines. The assessment of safety risks is based on the fuzzy reasoning approach. Mamdani fuzzy logic model is developed in the fuzzy logic toolbox of MATLAB. A case study is used to demonstrate the applicability of the developed model. The summary of risk evaluation in case study mine indicated that mine fire has the highest risk level among all the hazard factors. This study could help the mine management to prepare safety measures based on the risk rankings obtained.

  13. Interim qualitative risk assessment for an LNG refueling station and review of relevant safety issues

    Energy Technology Data Exchange (ETDEWEB)

    Siu, N.; Herring, S.; Cadwallader, L.; Reece, W.; Byers, J.

    1997-07-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tanker truck delivers and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects analysis and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of best practice information throughout the LNG community.

  14. 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.

  15. Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

    International Nuclear Information System (INIS)

    Johanson, Gunnar; Holmberg, J.

    1994-01-01

    Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

  16. Probabilistic Risk Assessment Procedures Guide for NASA Managers and Practitioners (Second Edition)

    Science.gov (United States)

    Stamatelatos,Michael; Dezfuli, Homayoon; Apostolakis, George; Everline, Chester; Guarro, Sergio; Mathias, Donovan; Mosleh, Ali; Paulos, Todd; Riha, David; Smith, Curtis; hide

    2011-01-01

    Probabilistic Risk Assessment (PRA) is a comprehensive, structured, and logical analysis method aimed at identifying and assessing risks in complex technological systems for the purpose of cost-effectively improving their safety and performance. NASA's objective is to better understand and effectively manage risk, and thus more effectively ensure mission and programmatic success, and to achieve and maintain high safety standards at NASA. NASA intends to use risk assessment in its programs and projects to support optimal management decision making for the improvement of safety and program performance. In addition to using quantitative/probabilistic risk assessment to improve safety and enhance the safety decision process, NASA has incorporated quantitative risk assessment into its system safety assessment process, which until now has relied primarily on a qualitative representation of risk. Also, NASA has recently adopted the Risk-Informed Decision Making (RIDM) process [1-1] as a valuable addition to supplement existing deterministic and experience-based engineering methods and tools. Over the years, NASA has been a leader in most of the technologies it has employed in its programs. One would think that PRA should be no exception. In fact, it would be natural for NASA to be a leader in PRA because, as a technology pioneer, NASA uses risk assessment and management implicitly or explicitly on a daily basis. NASA has probabilistic safety requirements (thresholds and goals) for crew transportation system missions to the International Space Station (ISS) [1-2]. NASA intends to have probabilistic requirements for any new human spaceflight transportation system acquisition. Methods to perform risk and reliability assessment in the early 1960s originated in U.S. aerospace and missile programs. Fault tree analysis (FTA) is an example. It would have been a reasonable extrapolation to expect that NASA would also become the world leader in the application of PRA. That was

  17. Safety assessment for Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Leahy, T.J.

    2012-01-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Recent RSWG work has focused on the definition of an integrated safety assessment methodology (ISAM) for evaluating the safety of Generation IV systems. ISAM is an integrated 'tool-kit' consisting of 5 analytical techniques that are available and matched to appropriate stages of Generation IV system concept development: 1) qualitative safety features review - QSR, 2) phenomena identification and ranking table - PIRT, 3) objective provision tree - OPT, 4) deterministic and phenomenological analyses - DPA, and 5) probabilistic safety analysis - PSA. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time

  18. Health, safety and environment risk assessment in gas pipelines by indexing method:case of Kermanshah Sanandaj oil pipeline

    Directory of Open Access Journals (Sweden)

    Y. Hamidi

    2009-10-01

    Full Text Available Background and AimsUsing pipelines for oil products transportation involves ranges of safety, health and environmental risks, this option however, is dominant with numerous  advantages. The purpose of this study was; relative risk assessment of abovementioned risk in Kermanshah-Sanandaj Oil Pipeline.MethodsThe method used in this study was Kent Muhlbauer method in which relative risk was assessed using third-party damage, corrosion, design, incorrect operations and leak impact  factor.ResultsOnce applying this method, collection of required data and performing needed experiments, scoring results showed 96 risk segments along the pipeline length in which lengths 100+860, 101+384 and 103+670 had relative risk scores 9.74, 9.82 and 9.91 respectively and therefore these segments were identified as focal risk points and priority for improvement actions.ConclusionRegarding importance of pipeline failure, inspection and regular patrol along the pipeline route, precise control of cathodic protection of pipeline and using communication technologies such as SCADA or optical fibers along the pipeline route were amongst the mostimportant control action suggested by the study.

  19. Assessment of reliability and validity of a new safety culture questionnaire

    Directory of Open Access Journals (Sweden)

    A.A. Farshad

    2010-04-01

    Full Text Available Background and aims   As a Development of Industrial process, human, environment, equipment, material and validity of system has been exposed to hazardous conditions. Regards of 32.3 percent of occupations in industries, this study focused on risk assessment of foundry unit by energy trace and barrier analysis (ETBA method and presented approaches to control of accident.     Methods   the recent study is as a case study one to risk assessment in a foundry unit in Qazvin industrial city in1387. In this study risks were founded by ETBA method and evaluated by MILSTD- 882B. Data were collected by direct observations, interview with workers and supervisor and engineers, walking-talking through method, documents investigation of operational processors, preventive maintenances, equipment technical properties, accidental and medical documents. Finally ETBA worksheets completed.     Results   totally 154 risks has been found. 40 from total are been unacceptable risk, 68 unfavorable and also 46 acceptable but with remediation action. Casting workshop had risks more than other workshops (with 74 identified risks.Potential and heat energies were founded as most   hazardous energies, with respectively 51 and 38 risk cases.     Conclusion   This study recommended to be done actions for identification and control risk, such as: safety training, occupation training, preventive maintenance, contract safety, safety  communication and safety audit group.  

  20. Simulation for Prediction of Entry Article Demise (SPEAD): An Analysis Tool for Spacecraft Safety Analysis and Ascent/Reentry Risk Assessment

    Science.gov (United States)

    Ling, Lisa

    2014-01-01

    For the purpose of performing safety analysis and risk assessment for a potential off-nominal atmospheric reentry resulting in vehicle breakup, a synthesis of trajectory propagation coupled with thermal analysis and the evaluation of node failure is required to predict the sequence of events, the timeline, and the progressive demise of spacecraft components. To provide this capability, the Simulation for Prediction of Entry Article Demise (SPEAD) analysis tool was developed. The software and methodology have been validated against actual flights, telemetry data, and validated software, and safety/risk analyses were performed for various programs using SPEAD. This report discusses the capabilities, modeling, validation, and application of the SPEAD analysis tool.

  1. Flightdeck Automation Problems (FLAP) Model for Safety Technology Portfolio Assessment

    Science.gov (United States)

    Ancel, Ersin; Shih, Ann T.

    2014-01-01

    NASA's Aviation Safety Program (AvSP) develops and advances methodologies and technologies to improve air transportation safety. The Safety Analysis and Integration Team (SAIT) conducts a safety technology portfolio assessment (PA) to analyze the program content, to examine the benefits and risks of products with respect to program goals, and to support programmatic decision making. The PA process includes systematic identification of current and future safety risks as well as tracking several quantitative and qualitative metrics to ensure the program goals are addressing prominent safety risks accurately and effectively. One of the metrics within the PA process involves using quantitative aviation safety models to gauge the impact of the safety products. This paper demonstrates the role of aviation safety modeling by providing model outputs and evaluating a sample of portfolio elements using the Flightdeck Automation Problems (FLAP) model. The model enables not only ranking of the quantitative relative risk reduction impact of all portfolio elements, but also highlighting the areas with high potential impact via sensitivity and gap analyses in support of the program office. Although the model outputs are preliminary and products are notional, the process shown in this paper is essential to a comprehensive PA of NASA's safety products in the current program and future programs/projects.

  2. Swedish REGULATORY APPROACH TO SAFETY Assessment AND SEVERE ACCIDENT MANAGEMENT

    International Nuclear Information System (INIS)

    Frid, W.; Sandervaag, O.

    1997-01-01

    The Swedish regulatory approach to safety assessment and severe accident management is briefly described. The safety assessment program, which focuses on prevention of incidents and accidents, has three main components: periodic safety reviews, probabilistic safety analysis, and analysis of postulated disturbances and accident progression sequences. Management and man-technology-organisation issues, as well as inspections, play a key role in safety assessment. Basis for severe accident management were established by the Government decisions in 1981 and 1986. By the end of 1988, the severe accident mitigation systems and emergency operating procedures were implemented at all Swedish reactors. The severe accident research has continued after 1988 for further verification of the protection provided by the systems and reduction of remaining uncertainties in risk dominant phenomena

  3. NANoREG framework for the safety assessment of nanomaterials

    OpenAIRE

    Gottardo, Stefania; Alessandrelli, Maria; Amenta, Valeria; Atluri, Rambabu; Barberio, Grazia; Bekker, Cindy; Bergonzo, Philippe; Bleeker, Eric; Booth, Andy; Borges, Teresa; Buttol, Patrizia; Carlander, David; Castelli, Stefano; Chevillard, Sylvie

    2017-01-01

    The NANoREG framework addresses the need to ease the nanomaterials safety assessment in the REACH Regulation context. It offers forward-looking strategies: Safe-by-Design, a Nanospecific Prioritisation and Risk Assessment, and Life Cycle Assessment. It is intended for scientific experts, regulatory authorities and industry.

  4. From Risk Analysis to the Safety Case. Values in Risk Assessments. A Report Based on Interviews with Experts in the Nuclear Waste Programs in Sweden and Finland. A Report from the RISCOM II Project

    International Nuclear Information System (INIS)

    Drottz Sjoeberg, Britt-Marie

    2004-06-01

    The report focuses on values in risk assessment, and is based on interviews with safety assessment experts and persons working at the national authorities in Sweden and Finland working in the area of nuclear waste management. The interviews contained questions related to definitions of risk and safety, standards, constraints and degrees of freedom in the work, data collections, reliability and validity of systems and the safety assessments, as well as communication between experts, and experts and non-experts. The results pointed to an increased amount of data and relevant factors considered in the analyses over time, changing the work content and process from one of risk analysis to a multifaceted teamwork towards the assessment of 'the safety case'. The multifaceted systems approach highlighted the increased importance of investigating assumptions underlying e.g. integration of diverse systems, and simplification procedures. It also highlighted the increased reliance on consensus building processes within the extended expert group, the importance of adequate communication abilities within the extended expert group, as well as the importance of transparency and communication relative the larger society. The results are discussed with reference to e.g. Janis 'groupthink' theory and Kuhns ideas of paradigmatic developments in science. It is concluded that it is well advised, in addition to the ordinary challenges of the work, to investigate also the implicit assumptions involved in the work processes to further enhance the understanding of safety assessments

  5. From Risk Analysis to the Safety Case. Values in Risk Assessments. A Report Based on Interviews with Experts in the Nuclear Waste Programs in Sweden and Finland. A Report from the RISCOM II Project

    Energy Technology Data Exchange (ETDEWEB)

    Drottz Sjoeberg, Britt-Marie [Norwegian Univ. of Science and Technology, Trondheim (Norway). Dept. of Psychology

    2004-06-01

    The report focuses on values in risk assessment, and is based on interviews with safety assessment experts and persons working at the national authorities in Sweden and Finland working in the area of nuclear waste management. The interviews contained questions related to definitions of risk and safety, standards, constraints and degrees of freedom in the work, data collections, reliability and validity of systems and the safety assessments, as well as communication between experts, and experts and non-experts. The results pointed to an increased amount of data and relevant factors considered in the analyses over time, changing the work content and process from one of risk analysis to a multifaceted teamwork towards the assessment of 'the safety case'. The multifaceted systems approach highlighted the increased importance of investigating assumptions underlying e.g. integration of diverse systems, and simplification procedures. It also highlighted the increased reliance on consensus building processes within the extended expert group, the importance of adequate communication abilities within the extended expert group, as well as the importance of transparency and communication relative the larger society. The results are discussed with reference to e.g. Janis 'groupthink' theory and Kuhns ideas of paradigmatic developments in science. It is concluded that it is well advised, in addition to the ordinary challenges of the work, to investigate also the implicit assumptions involved in the work processes to further enhance the understanding of safety assessments.

  6. Quantitative risk assessment: an emerging tool for emerging foodborne pathogens.

    OpenAIRE

    Lammerding, A. M.; Paoli, G. M.

    1997-01-01

    New challenges to the safety of the food supply require new strategies for evaluating and managing food safety risks. Changes in pathogens, food preparation, distribution, and consumption, and population immunity have the potential to adversely affect human health. Risk assessment offers a framework for predicting the impact of changes and trends on the provision of safe food. Risk assessment models facilitate the evaluation of active or passive changes in how foods are produced, processed, d...

  7. Proposal for the improvement of IRD safety culture based on risk analysis

    International Nuclear Information System (INIS)

    Aguiar, L.A.; Ferreira, P.R.R.; Silveira, C.S.

    2017-01-01

    The Safety Culture (SC) is a concept about the relationship of individuals and organizations towards the safety in a specific activity. Any organization that carries out activities with risks has a SC, even at minimum levels. People perceive different types of radiation risks in very different ways, therefore, to identify and to analysis of the possible radiation risks resulting from normal operation or accident conditions is an important issue in order to improve the SC in organization. The main is to present guidelines for the improvement of the safety culture in the Institute of Radiation Protection and Dosimetry - IRD through on risk-based approach. The methodology proposed here is: A) select a division of the IRD for case study; B) assess the level of the 10 culture safety basic elements of the IRD division selected; C) conduct a survey of the hazards and risks associated with the various activities developed by the division; D) reassess the level of the 10 basic elements of CS; And E) analyze the results and correlate the impact of risk knowledge on safety culture improvement. The expected result is improvement the safety and of safety culture by understanding of radiation risks and hazards relating to work and to the working environment; and thus enforce a collective commitment to safety by teams and individuals and raise the safety culture to higher levels. (author)

  8. Proposal for the improvement of IRD safety culture based on risk analysis

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, L.A.; Ferreira, P.R.R. [Instituto de Radioproteção e Dosimetria (DIRAD/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Silveira, C.S., E-mail: laguiar@ird.gov.br [Comissão Nacional de Energia Nuclear (DRS/CGMI/CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The Safety Culture (SC) is a concept about the relationship of individuals and organizations towards the safety in a specific activity. Any organization that carries out activities with risks has a SC, even at minimum levels. People perceive different types of radiation risks in very different ways, therefore, to identify and to analysis of the possible radiation risks resulting from normal operation or accident conditions is an important issue in order to improve the SC in organization. The main is to present guidelines for the improvement of the safety culture in the Institute of Radiation Protection and Dosimetry - IRD through on risk-based approach. The methodology proposed here is: A) select a division of the IRD for case study; B) assess the level of the 10 culture safety basic elements of the IRD division selected; C) conduct a survey of the hazards and risks associated with the various activities developed by the division; D) reassess the level of the 10 basic elements of CS; And E) analyze the results and correlate the impact of risk knowledge on safety culture improvement. The expected result is improvement the safety and of safety culture by understanding of radiation risks and hazards relating to work and to the working environment; and thus enforce a collective commitment to safety by teams and individuals and raise the safety culture to higher levels. (author)

  9. Risk management and safety culture

    International Nuclear Information System (INIS)

    Takano, K.

    2007-01-01

    Paper informs on the efforts to elaborate a feedback system for risk comprehensive evaluation and a system to improve structure safety foreseeing the possibility to control the latent risk, ensuring the qualitative evaluation of the safety level and improvement of safety culture in various branches of industry, first and foremost, in the electricity producing sector including the nuclear power industry [ru

  10. Public transport risk assessment through fault tree analysis

    Directory of Open Access Journals (Sweden)

    Z. Yaghoubpour

    2016-04-01

    Full Text Available This study focused on the public transport risk assessment in District one of ​​Tehran through Fault Tree Analysis involving the three criteria of human, vehicle and road in Haddon matrix. In fact, it examined the factors contributing to the occurrence of road accidents at several urban black spots within District 1. Relying on road safety checklists and survey of experts, this study made an effort to help urban managers to assess the risks in the public transport and prevent road accidents. Finally, the risk identification and assessment of public transport in District one yielded several results to answer the research questions. The hypotheses analysis suggested that safety issues involved in public transport are concerned by urban managers. The key reactive measures are investigation of accidents, identification of causes and correction of black spots. In addition to high costs, however, the reactive measures give rise to multiple operational problems such as traffic navigation and guaranteeing user safety in every operation. The case study highlighted the same fact. The macro-level management in the metropolis of Tehran is critical. The urban road casualties and losses can be curtailed by preventive measures such as continuous assessment of road safety.

  11. Taking the Risk Out of Risk Assessment

    Science.gov (United States)

    2005-01-01

    The ability to understand risks and have the right strategies in place when risky events occur is essential in the workplace. More and more organizations are being confronted with concerns over how to measure their risks or what kind of risks they can take when certain events transpire that could have a negative impact. NASA is one organization that faces these challenges on a daily basis, as effective risk management is critical to the success of its missions especially the Space Shuttle missions. On July 29, 1996, former NASA Administrator Daniel Goldin charged NASA s Office of Safety and Mission Assurance with developing a probabilistic risk assessment (PRA) tool to support decisions on the funding of Space Shuttle upgrades. When issuing the directive, Goldin said, "Since I came to NASA [in 1992], we've spent billions of dollars on Shuttle upgrades without knowing how much they improve safety. I want a tool to help base upgrade decisions on risk." Work on the PRA tool began immediately. The resulting prototype, the Quantitative Risk Assessment System (QRAS) Version 1.0, was jointly developed by NASA s Marshall Space Flight Center, its Office of Safety and Mission Assurance, and researchers at the University of Maryland. QRAS software automatically expands the reliability logic models of systems to evaluate the probability of highly detrimental outcomes occurring in complex systems that are subject to potential accident scenarios. Even in its earliest forms, QRAS was used to begin PRA modeling of the Space Shuttle. In parallel, the development of QRAS continued, with the goal of making it a world-class tool, one that was especially suited to NASA s unique needs. From the beginning, an important conceptual goal in the development of QRAS was for it to help bridge the gap between the professional risk analyst and the design engineer. In the past, only the professional risk analyst could perform, modify, use, and perhaps even adequately understand PRA. NASA wanted

  12. LWR safety studies. Analyses and further assessments relating to the German Risk Assessment Study on Nuclear Power Plants. Vol. 1

    International Nuclear Information System (INIS)

    1983-01-01

    This documentation of the activities of the Oeko-Institut is intended to show errors made and limits encountered in the experimental approaches and in results obtained by the work performed under phase A of the German Risk Assessment Study on Nuclear Power Plants (DRS). Concern is expressed and explained relating to the risk definition used in the Study, and the results of other studies relied on; specific problems of methodology are discussed with regard to the value of fault-tree/accident analyses for describing the course of safety-related events, and to the evaluations presented in the DRS. The Markov model is explained as an approach offering alternative solutions. The identification and quantification of common-mode failures is discussed. Origin, quality and methods of assessing the reliability characteristics used in the DRS as well as the statistical models for describing failure scenarios of reactor components and systems are critically reviewed. (RF) [de

  13. Safety assessment of a lithium target

    International Nuclear Information System (INIS)

    Burgazzi, Luciano; Roberta, Ferri; Barbara, Giannone

    2006-01-01

    This paper addresses the safety assessment of the lithium target of the International Fusion Materials Irradiation Facility (IFMIF) through evaluating the most important risk factors related to system operation and verifying the fulfillment of the safety criteria. The hazard assessment is based on using a well-structured Failure Mode and Effect Analysis (FMEA) procedure by detailing on a component-by-component basis all the possible failure modes and identifying their effects on the plant. Additionally, a systems analysis, applying the fault tree technique, is performed in order to evaluate, from a probabilistic standpoint, all the relevant and possible failures of each component required for safe system operation and assessing the unavailability of the lithium target system. The last task includes the thermal-hydraulic transient analysis of the target lithium loop, including operational and accident transients. A lithium target loop model is developed, using the RELAP5/Mod3.2 thermal-hydraulic code, which has been modified to include specific features of IFMIF itself. The main conclusions are that target safety is fulfilled, the hazards associated with lithium operation are confined within the IFMIF security boundaries, the environmental impact is negligible, and the plant responds to the simulated transients by being able to reach steady conditions in a safety situation

  14. Product Engineering Class in the Software Safety Risk Taxonomy for Building Safety-Critical Systems

    Science.gov (United States)

    Hill, Janice; Victor, Daniel

    2008-01-01

    When software safety requirements are imposed on legacy safety-critical systems, retrospective safety cases need to be formulated as part of recertifying the systems for further use and risks must be documented and managed to give confidence for reusing the systems. The SEJ Software Development Risk Taxonomy [4] focuses on general software development issues. It does not, however, cover all the safety risks. The Software Safety Risk Taxonomy [8] was developed which provides a construct for eliciting and categorizing software safety risks in a straightforward manner. In this paper, we present extended work on the taxonomy for safety that incorporates the additional issues inherent in the development and maintenance of safety-critical systems with software. An instrument called a Software Safety Risk Taxonomy Based Questionnaire (TBQ) is generated containing questions addressing each safety attribute in the Software Safety Risk Taxonomy. Software safety risks are surfaced using the new TBQ and then analyzed. In this paper we give the definitions for the specialized Product Engineering Class within the Software Safety Risk Taxonomy. At the end of the paper, we present the tool known as the 'Legacy Systems Risk Database Tool' that is used to collect and analyze the data required to show traceability to a particular safety standard

  15. Method for Pedestrian Crossing Risk Assessment and Safety Level Determination: the Case Study of Tallinn

    Energy Technology Data Exchange (ETDEWEB)

    Pashkevich, M.; Krasilnikova, A.; Antov, D.

    2016-07-01

    Pedestrians are a part of vulnerable road users which safety requires a special attention. Official statistics in Estonia from the last decade returns the following numbers: around 30 % of all road traffic accidents in the country were accidents with pedestrians, 32 % of all traffic fatalities were finished with pedestrian death. Pedestrian crossing has the biggest risk level between all kinds of pedestrian facilities, because it includes a direct conflict point between vehicle and pedestrian traffics. The article presents a method to assess risk of pedestrian crossing users and to determine safety level of this road infrastructure element. This approach is based on observation and collection of infrastructural as well as traffic data, which includes: (1) information about each pedestrian crossing facility, its location and state, (2) data about accidents with pedestrians and their features, (3) data from road traffic measurements. The main advantages of the described method are universality and comprehensiveness. The case study was done in Kristiine district of the city Tallinn, which was chosen as the most typical average district of Estonian capital. Results of this study are also presented in the article. (Author)

  16. Hazard Identification, Risk Assessment and Risk Control (HIRARC Accidents at Power Plant

    Directory of Open Access Journals (Sweden)

    Ahmad Asmalia Che

    2016-01-01

    Full Text Available Power plant had a reputation of being one of the most hazardous workplace environments. Workers in the power plant face many safety risks due to the nature of the job. Although power plants are safer nowadays since the industry has urged the employer to improve their employees’ safety, the employees still stumble upon many hazards thus accidents at workplace. The aim of the present study is to investigate work related accidents at power plants based on HIRARC (Hazard Identification, Risk Assessment and Risk Control process. The data were collected at two coal-fired power plant located in Malaysia. The finding of the study identified hazards and assess risk relate to accidents occurred at the power plants. The finding of the study suggested the possible control measures and corrective actions to reduce or eliminate the risk that can be used by power plant in preventing accidents from occurred

  17. A Framework for Assessment of Aviation Safety Technology Portfolios

    Science.gov (United States)

    Jones, Sharon M.; Reveley, Mary S.

    2014-01-01

    The programs within NASA's Aeronautics Research Mission Directorate (ARMD) conduct research and development to improve the national air transportation system so that Americans can travel as safely as possible. NASA aviation safety systems analysis personnel support various levels of ARMD management in their fulfillment of system analysis and technology prioritization as defined in the agency's program and project requirements. This paper provides a framework for the assessment of aviation safety research and technology portfolios that includes metrics such as projected impact on current and future safety, technical development risk and implementation risk. The paper also contains methods for presenting portfolio analysis and aviation safety Bayesian Belief Network (BBN) output results to management using bubble charts and quantitative decision analysis techniques.

  18. Safety assessment for facilities and activities. General safety requirements. Pt. 4

    International Nuclear Information System (INIS)

    2009-01-01

    The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF 6 ; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

  19. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    International Nuclear Information System (INIS)

    2009-01-01

    The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

  20. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    International Nuclear Information System (INIS)

    2010-01-01

    The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

  1. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    International Nuclear Information System (INIS)

    2009-01-01

    The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation.? read more The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are

  2. LWR safety studies. Analyses and further assessments relating to the German Risk Assessment Study on Nuclear Power Plants. Vol. 3

    International Nuclear Information System (INIS)

    1983-01-01

    Critical review of the analyses of the German Risk Assessment Study on Nuclear Power Plants (DRS) concerning the reliability of the containment under accident conditions and the conditions of fission product release (transport and distribution in the environment). Main point of interest in this context is an explosion in the steam section and its impact on the containment. Critical comments are given on the models used in the DRS for determining the accident consequences. The analyses made deal with the mathematical models and database for propagation calculations, the methods of dose computation and assessment of health hazards, and the modelling of protective and safety measures. Social impacts of reactor accidents are also considered. (RF) [de

  3. Risk assessment principle for engineered nanotechnology in food and drug.

    Science.gov (United States)

    Hwang, Myungsil; Lee, Eun Ji; Kweon, Se Young; Park, Mi Sun; Jeong, Ji Yoon; Um, Jun Ho; Kim, Sun Ah; Han, Bum Suk; Lee, Kwang Ho; Yoon, Hae Jung

    2012-06-01

    While the ability to develop nanomaterials and incorporate them into products is advancing rapidly worldwide, understanding of the potential health safety effects of nanomaterials has proceeded at a much slower pace. Since 2008, Korea Food and Drug Administration (KFDA) started an investigation to prepare "Strategic Action Plan" to evaluate safety and nano risk management associated with foods, drugs, medical devices and cosmetics using nano-scale materials. Although there are some studies related to potential risk of nanomaterials, physical-chemical characterization of nanomaterials is not clear yet and these do not offer enough information due to their limitations. Their uncertainties make it impossible to determine whether nanomaterials are actually hazardous to human. According to the above mention, we have some problems to conduct the human exposure risk assessment currently. On the other hand, uncertainty about safety may lead to polarized public debate and to businesses unwillingness for further nanotechnology investigation. Therefore, the criteria and methods to assess possible adverse effects of nanomaterials have been vigorously taken into consideration by many international organizations: the World Health Organization, the Organization for Economic and Commercial Development and the European Commission. The object of this study was to develop risk assessment principles for safety management of future nanoproducts and also to identify areas of research to strengthen risk assessment for nanomaterials. The research roadmaps which were proposed in this study will be helpful to fill up the current gaps in knowledge relevant nano risk assessment.

  4. Food and feed safety assessment: the importance of proper sampling.

    Science.gov (United States)

    Kuiper, Harry A; Paoletti, Claudia

    2015-01-01

    The general principles for safety and nutritional evaluation of foods and feed and the potential health risks associated with hazardous compounds are described as developed by the Food and Agriculture Organization (FAO) and the World Health Organization (WHO) and further elaborated in the European Union-funded project Safe Foods. We underline the crucial role of sampling in foods/feed safety assessment. High quality sampling should always be applied to ensure the use of adequate and representative samples as test materials for hazard identification, toxicological and nutritional characterization of identified hazards, as well as for estimating quantitative and reliable exposure levels of foods/feed or related compounds of concern for humans and animals. The importance of representative sampling is emphasized through examples of risk analyses in different areas of foods/feed production. The Theory of Sampling (TOS) is recognized as the only framework within which to ensure accuracy and precision of all sampling steps involved in the field-to-fork continuum, which is crucial to monitor foods and feed safety. Therefore, TOS must be integrated in the well-established FAO/WHO risk assessment approach in order to guarantee a transparent and correct frame for the risk assessment and decision making process.

  5. The impact of discontinuation of 7-day storage of apheresis platelets (PASSPORT) on recipient safety: an illustration of the need for proper risk assessments.

    Science.gov (United States)

    Kleinman, Steven; Dumont, Larry J; Tomasulo, Peter; Bianco, Celso; Katz, Louis; Benjamin, Richard J; Gajic, Ognjen; Brecher, Mark E

    2009-05-01

    Seven-day stored apheresis platelets (APs) were withdrawn from the US market after detection of two culture-positive units from 2571 tested at outdate in the PASSPORT surveillance study. The impact of this discontinuation on recipient safety was explored using mathematical modeling. Risk models for septic transfusion reactions (STRs) and transfusion-related acute lung injury (TRALI) were developed. Key assumptions were 400,000 annual APs transfused, equivalent STR risk for platelets (PLTs) stored for 5 days or more and zero for PLTs stored for less than 5 days, whole blood-derived PLTs (WBplts) administered in 5-unit pools, a 4.6-fold higher risk of false-negatives with surrogate versus culture-based bacterial testing, an AP TRALI risk between 1 per 1000 and 1 per 10,000, and a delay in TRALI risk reduction implementation in some centers by 6 to 12 months due to limited PLT availability. STR risk could increase, decrease, or remain the same depending on the percentage of inventory replaced by surrogate-tested WBplts versus culture-tested apheresis or whole blood PLTs. A delay in TRALI risk reduction implementation is likely to result in a comparable or greater risk during the delayed implementation period than the safety achieved with regard to STRs, even in the most favorable case scenario. A comprehensive risk assessment should have been conducted before the decision to discontinue PASSPORT. Risk assessments using accepted methods (and actual data when available) should precede any major blood safety decisions.

  6. Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    2002-01-01

    A well performed and adequately documented safety assessment of a nuclear facility will serve as a basis to determine whether the facility complies with the safety objectives, principles and criteria as stipulated by the national regulatory body of the country where the facility is in operation. International experience shows that the practices and methodologies used to perform safety assessments and periodic safety re-assessment for non-reactor nuclear facilities differ significantly from county to country. Most developing countries do not have methods and guidance for safety assessment that are prescribed by the regulatory body. Typically the safety evaluation for the facility is based on a case by case assessment. Whilst conservative deterministic analyses are predominantly used as a licensing basis in many countries, recently probabilistic safety assessment (PSA) techniques have been applied as a useful complementary tool to support safety decision making. The main benefit of PSA is to provide insights into the safety aspects of facility design and operation. PSA points up the potential environmental impacts of postulated accidents, including the dominant risk contributors, and enables safety analysts to compare options for reducing risk. In order to advise on how to apply PSA methodology for the safety assessment of non-reactor nuclear facilities, the IAEA organized several consultants meetings, which led to the preparation of this TECDOC. This document is intended as guidance for the conduct of PSA in non-nuclear facilities. The main emphasis here is on the general procedural steps of a PSA that is specific for a non-reactor nuclear facility, rather than the details of the specific methods. The report is directed at technical staff managing or performing such probabilistic assessments and to promote a standardized framework, terminology and form of documentation for these PSAs. It is understood that the level of detail implied in the tasks presented in this

  7. Safety Assessment for Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum

  8. Development of a system utilizing data of risk assessment

    International Nuclear Information System (INIS)

    Nagasaka, Akihiko; Takano, Kenichi; Ebisu, Mitsuhiro; Aikawa, Tadashi; Hayase, Kenichi

    2004-01-01

    This report deals with a concrete method of utilizing data of risk assessment. First, the authors point out the necessity to assess all stages of jobs (planning, meeting with contractors, performing phase of task, etc.) in risk assessment bout jobs in electric power company, because most jobs are performed by contract system and risks of a job are distributed over electric company, contractors and subcontractors. Secondly, risks estimated from past accidents and near-miss events must be included. If these 2 requirements are fulfilled, data of risk assessment can be more useful. Then below 4 forms of present data of risk assessment were developed. A form to be used in job planning stage in electric companies for efficient investment planning in safety measures. A form to be used in meetings between electric companies and contractors for checking accident prevention methods. A form to be used in meetings between contractors and subcontractors for enhancing a shared awareness of risk. A form to be used in tool box meetings for confirming safe condition and inheriting of ability of risk perception. Additionally, a data base system of risk assessment about 4 jobs was developed. This system prints out about 4 forms for each job and is useful for PDCA of safety activities. (author)

  9. The implications of probabilistic risk assessment for safety policy

    International Nuclear Information System (INIS)

    Hayns, M.R.

    1987-01-01

    The use of PRA results in decision making requires a level of understanding on the part of the decision maker which is higher than that obtaining previously. The most important application of PRA lies not in the final results but in the intermediate results which refer to specific systems and operations. Such intermediate results are of great value either at the design stage or later during operation. One of the most 'visible' uses of PRA results is in comparing calculated plant risks with either proposed acceptability criteria, or with other plant, or even natural events. The capability to perform PRA has been established. Only the incorporation of PRA into the licensing process is lacking. The principal conclusions on the implications of PRA for safety policy are as follows: regardless of its state of development, PRA is the only means available for calculating public risk, being able to quantify risk is important in policy related to risk acceptability and to national energy policy. PRAs will be used to establish research and development priorities. Any hazardous plant can be treated using the same methods. More sophisticated methods will be used for solving engineering problems. (author)

  10. Risk assessment of mitigated domino scenarios in process facilities

    International Nuclear Information System (INIS)

    Landucci, Gabriele; Necci, Amos; Antonioni, Giacomo; Argenti, Francesca; Cozzani, Valerio

    2017-01-01

    The propagation of accidents among process units may lead to severe cascading events or domino effects with catastrophic consequences. Prevention, mitigation and management of domino scenarios is of utmost importance and may be achieved in industrial facilities through the adoption of multiple safety layers. The present study was aimed at developing an innovative methodology to address the quantitative risk assessment (QRA) of domino scenarios accounting for the presence and role of safety barriers. Based on the expected performance of safety barriers, a dedicated event tree analysis allowed the identification and the assessment of the frequencies of the different end-point events deriving from unmitigated and partially mitigated domino chains. Specific criteria were introduced in consequence analysis to consider the mitigation effects of end-point scenarios deriving from safety barriers. Individual and societal risk indexes were calculated accounting for safety barriers and the mitigated scenarios that may result from their actions. The application of the methodology to case-studies of industrial interest proved the importance of introducing a specific systematic and quantitative analysis of safety barrier performance when addressing escalation leading to domino effect. - Highlights: • A methodology was developed to account for safety barrier performance in escalation prevention. • The methodology allows quantitative assessment accounting for safety barrier performance. • A detailed analysis of transient mitigated scenarios is allowed by the developed procedure. • The procedure allows accounting for safety barrier performance in QRA of domino scenarios. • An important reduction in the risk due to domino scenarios is evidenced when considering safety barriers.

  11. Consideration of the FQPA Safety Factor and Other Uncertainty Factors in Cumulative Risk Assessment of Chemicals Sharing a Common Mechanism of Toxicity

    Science.gov (United States)

    This guidance document provides OPP's current thinking on application of the provision in FFDCA about an additional safety factor for the protection of infants and children in the context of cumulative risk assessments.

  12. Use of the Home Safety Self-Assessment Tool (HSSAT) within Community Health Education to Improve Home Safety.

    Science.gov (United States)

    Horowitz, Beverly P; Almonte, Tiffany; Vasil, Andrea

    2016-10-01

    This exploratory research examined the benefits of a health education program utilizing the Home Safety Self-Assessment Tool (HSSAT) to increase perceived knowledge of home safety, recognition of unsafe activities, ability to safely perform activities, and develop home safety plans of 47 older adults. Focus groups in two senior centers explored social workers' perspectives on use of the HSSAT in community practice. Results for the health education program found significant differences between reported knowledge of home safety (p = .02), ability to recognize unsafe activities (p = .01), safely perform activities (p = .04), and develop a safety plan (p = .002). Social workers identified home safety as a major concern and the HSSAT a promising assessment tool. Research has implications for reducing environmental fall risks.

  13. Risk-informed regulation: handling uncertainty for a rational management of safety

    International Nuclear Information System (INIS)

    Zio, Enrico

    2008-01-01

    A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated

  14. Risk-targeted safety distance of reinforced concrete buildings from natural-gas transmission pipelines

    International Nuclear Information System (INIS)

    Russo, Paola; Parisi, Fulvio

    2016-01-01

    Natural-gas pipeline accidents mostly result in major damage even to buildings located far away. Therefore, proper safety distances should be observed in land use planning to ensure target safety levels for both existing and new buildings. In this paper, a quantitative risk assessment procedure is presented for the estimation of the annual probability of direct structural damage to reinforced concrete buildings associated with high-pressure natural-gas pipeline explosions. The procedure is based on Monte Carlo simulation and takes into account physical features of blast generation and propagation, as well as damage to reinforced concrete columns. The natural-gas jet release process and the flammable cloud size are estimated through SLAB one-dimensional integral model incorporating a release rate model. The explosion effects are evaluated by a Multi-Energy Method. Damage to reinforced concrete columns is predicted by means of pressure–impulse diagrams. The conditional probability of damage was estimated at multiple pressure–impulse levels, allowing blast fragility surfaces to be derived at different performance limit states. Finally, blast risk was evaluated and allowed the estimation of minimum pipeline-to-building safety distances for risk-informed urban planning. The probabilistic procedure presented herein may be used for performance-based design/assessment of buildings and to define the path of new natural-gas pipeline networks. - Highlights: • The safety of buildings against blast loads due to pipeline accidents is assessed. • A probabilistic risk assessment procedure is presented for natural-gas pipelines. • The annual risk of collapse of reinforced concrete building columns is evaluated. • Monte Carlo simulation was carried out considering both pipeline and column features. • A risk-targeted safety distance is proposed for blast strength class 9.

  15. An integrated risk sensing system for geo-structural safety

    Institute of Scientific and Technical Information of China (English)

    H.W. Huang; D.M. Zhang; B.M. Ayyub

    2017-01-01

    Over the last decades, geo-structures are experiencing a rapid development in China. The potential risks inherent in the huge amount of construction and asset operation projects in China were well managed in the major project, i.e. the project of Shanghai Yangtze tunnel in 2002. Since then, risk assessment of geo-structures has been gradually developed from a qualitative manner to a quantitative manner. However, the current practices of risk management have been paid considerable attention to the assessment, but little on risk control. As a result, the responses to risks occurrences after a comprehensive assessment are basically too late. In this paper, a smart system for risk sensing incorporating the wireless sensor network (WSN) on-site visualization techniques and the resilience-based repair strategy was proposed. The merit of this system is the real-time monitoring for geo-structural performance and dynamic pre-warning for safety of on-site workers. The sectional convergence, joint opening, and seepage of segmental lining of shield tunnel were monitored by the micro-electro-mechanical systems (MEMS) based sensors. The light emitting diode (LED) coupling with the above WSN system was used to indicate different risk levels on site. By sensing the risks and telling the risks in real time, the geo-risks could be controlled and the safety of geo-structures could be assured to a certain degree. Finally, a resilience-based analysis model was proposed for designing the repair strategy by using the measured data from the WSN system. The application and efficiency of this system have been validated by two cases including Shanghai metro tunnel and underwater road tunnel.

  16. The Research on Safety Management Information System of Railway Passenger Based on Risk Management Theory

    Science.gov (United States)

    Zhu, Wenmin; Jia, Yuanhua

    2018-01-01

    Based on the risk management theory and the PDCA cycle model, requirements of the railway passenger transport safety production is analyzed, and the establishment of the security risk assessment team is proposed to manage risk by FTA with Delphi from both qualitative and quantitative aspects. The safety production committee is also established to accomplish performance appraisal, which is for further ensuring the correctness of risk management results, optimizing the safety management business processes and improving risk management capabilities. The basic framework and risk information database of risk management information system of railway passenger transport safety are designed by Ajax, Web Services and SQL technologies. The system realizes functions about risk management, performance appraisal and data management, and provides an efficient and convenient information management platform for railway passenger safety manager.

  17. Evaluation model for safety capacity of chemical industrial park based on acceptable regional risk

    Institute of Scientific and Technical Information of China (English)

    Guohua Chen; Shukun Wang; Xiaoqun Tan

    2015-01-01

    The paper defines the Safety Capacity of Chemical Industrial Park (SCCIP) from the perspective of acceptable regional risk. For the purpose of exploring the evaluation model for the SCCIP, a method based on quantitative risk assessment was adopted for evaluating transport risk and to confirm reasonable safety transport capacity of chemical industrial park, and then by combining with the safety storage capacity, a SCCIP evaluation model was put forward. The SCCIP was decided by the smaller one between the largest safety storage capacity and the maximum safety transport capacity, or else, the regional risk of the park will exceed the acceptable level. The developed method was applied to a chemical industrial park in Guangdong province to obtain the maximum safety transport capacity and the SCCIP. The results can be realized in the regional risk control of the park effectively.

  18. Research on Occupational Safety, Health Management and Risk Control Technology in Coal Mines.

    Science.gov (United States)

    Zhou, Lu-Jie; Cao, Qing-Gui; Yu, Kai; Wang, Lin-Lin; Wang, Hai-Bin

    2018-04-26

    This paper studies the occupational safety and health management methods as well as risk control technology associated with the coal mining industry, including daily management of occupational safety and health, identification and assessment of risks, early warning and dynamic monitoring of risks, etc.; also, a B/S mode software (Geting Coal Mine, Jining, Shandong, China), i.e., Coal Mine Occupational Safety and Health Management and Risk Control System, is developed to attain the aforementioned objectives, namely promoting the coal mine occupational safety and health management based on early warning and dynamic monitoring of risks. Furthermore, the practical effectiveness and the associated pattern for applying this software package to coal mining is analyzed. The study indicates that the presently developed coal mine occupational safety and health management and risk control technology and the associated software can support the occupational safety and health management efforts in coal mines in a standardized and effective manner. It can also control the accident risks scientifically and effectively; its effective implementation can further improve the coal mine occupational safety and health management mechanism, and further enhance the risk management approaches. Besides, its implementation indicates that the occupational safety and health management and risk control technology has been established based on a benign cycle involving dynamic feedback and scientific development, which can provide a reliable assurance to the safe operation of coal mines.

  19. Developing guidance in the nuclear criticality safety assessment for fuel cycle facilities

    International Nuclear Information System (INIS)

    Galet, C.; Evo, S.

    2012-01-01

    In this poster IRSN (Institute for radiation protection and nuclear safety) presents its safety guides whose purpose is to transmit the safety assessment know-how to any 'junior' staff or even to give a view of the safety approach on the overall risks to any staff member. IRSN has written a first version of such a safety guide for fuel cycle facilities and laboratories. It is organized into several chapters: some refer to types of assessments, others concern the types of risks. Currently, this guide contains 13 chapters and each chapter consists of three parts. In parallel to the development of criticality chapter of this guide, the IRSN criticality department has developed a nuclear criticality safety guide. It follows the structure of the three parts fore-mentioned, but it presents a more detailed first part and integrates, in the third part, the experience feedback collected on nuclear facilities. The nuclear criticality safety guide is online on the IRSN's web site

  20. Do we see how they perceive risk? An integrated analysis of risk perception and its effect on workplace safety behavior.

    Science.gov (United States)

    Xia, Nini; Wang, Xueqing; Griffin, Mark A; Wu, Chunlin; Liu, Bingsheng

    2017-09-01

    While risk perception is a key factor influencing safety behavior, the academia lacks specific attention to the ways that workers perceive risk, and thus little is known about the mechanisms through which different risk perceptions influence safety behavior. Most previous research in the workplace safety domain argues that people tend to perceive risk based on rational formulations of risk criticality. However, individuals' emotions can be also useful in understanding their perceptions. Therefore, this research employs an integrated analysis concerning the rational and emotional perspectives. Specifically, it was expected that the identified three rational ways of perceiving risk, i.e., perceived probability, severity, and negative utility, would influence the direct emotional risk perception. Furthermore, these four risk perceptions were all expected to positively but differently influence safety behavior. The hypotheses were tested using a sample of 120 construction workers. It was found that all the three rational risk perceptions significantly influenced workers' direct perception of risk that is mainly based on emotions. Furthermore, safety behavior among workers relied mainly on emotional perception but not rational calculations of risk. This research contributes to workplace safety research by highlighting the importance of integrating the emotional assessment of risk, especially when workers' risk perception and behavior are concerned. Suggested avenues for improving safety behavior through improvement in risk perception include being aware of the possibility of different ways of perceiving risk, promoting experience sharing and accident simulation, and uncovering risk information. Copyright © 2017 Elsevier Ltd. All rights reserved.

  1. Evaluation of severe accident safety system value based on averting financial risks

    International Nuclear Information System (INIS)

    Hatch, S.W.; Benjamin, A.S.; Bennett, P.R.

    1983-01-01

    The Severe Accident Risk Reduction Program is being performed to benchmark the risks from nuclear power plants and to assess the benefits and impacts of a set of severe accident safety features. This paper describes the program in general and presents some preliminary results. These results include estimates of the financial risks associated with the operation of six reference plants and the value of severe accident prevention and mitigation safety systems in averting these risks. The results represent initial calculations and will be iterated before being used to support NRC decisions

  2. Transportation System Risk Assessment on DOE Defense Program shipments

    International Nuclear Information System (INIS)

    Brumburgh, G.P.; Kimura, C.Y.; Alesso, H.P.; Prassinos, P.G.

    1992-01-01

    Substantial effort has been expended concerning the level of safety provided to persons, property, and the environment from the hazards associated with transporting radioactive material. This work provided an impetus for the Department of Energy to investigate the use of probabilistic risk assessment techniques to supplement the deterministic approach to transportation safety. The DOE recently decided to incorporate the methodologies associated with PRAs in the process for authorizing the transportation of nuclear components, special assemblies, and radioactive materials affiliated with the DOE Defense Program. Accordingly, the LLNL, sponsored by the DOE/AL, is tasked with developing a safety guide series to provide guidance to preparers performing a transportation system risk assessment

  3. Learning Safety Assessment from Accidents in a University Environment

    OpenAIRE

    Jensen, Niels; Jørgensen, Sten Bay

    2013-01-01

    This contribution describes how a chemical engineering department started learning from accidents during experimental work and ended up implementing an industrially inspired system for risk assessment of new and existing experimental setups as well as a system for assessing potential risk from the chemicals used in the experimental work. These experiences have led to recent developments which focus increasingly on the a theoretical basis for modeling and reasoning on safety as well as operati...

  4. Achieving safety/risk goals for less ATR backup power upgrades

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1995-01-01

    The Advanced Test Reactor probabilistic risk assessment for internal fire and flood events defined a relatively high risk for a total loss of electric power possibly leading to core damage. Backup power sources were disabled due to fire and flooding in the diesel generator area with propagation of the flooding to a common switchgear room. The ATR risk assessment was employed to define options for relocation of backup power system components to achieve needed risk reduction while minimizing costs. The risk evaluations were performed using sensitivity studies and importance measures. The risk-based evaluations of relocation options for backup power systems saved over $3 million from what might have been otherwise considered open-quotes necessaryclose quotes for safety/risk improvement. The ATR experience shows that the advantages of a good risk assessment are to define risk significance, risk specifics, and risk solutions which enable risk goals to be achieved at the lowest cost

  5. Risk Assessment in Finland: Theory and Practice

    Directory of Open Access Journals (Sweden)

    Hannu Anttonen

    2010-09-01

    Full Text Available The Finnish risk assessment practice is based on the Occupational Safety and Health Act aiming to improve working conditions in order maintain the employees' work ability, and to prevent occupational accidents and diseases. In practice there are hundreds of risk assessment methods in use. A simple method is used in SME's and more complex risk evaluation methods in larger work places. Does the risk management function in the work places in Finland? According to our experience something more is needed. That is, understanding of common and company related benefits of risk management. The wider conclusion is that commitment for risk assessment in Finland is high enough. However, in those enterprises where OSH management was at an acceptable level or above it, there were also more varied and more successfully accomplished actions to remove or reduce the risks than in enterprises, where OSH management was in lower level. In risk assessment it is important to process active technical prevention and exact communication, increase work place attraction and increase job satisfaction and motivation. Investments in occupational safety and health are also good business. Low absenteeism due to illness or accidents increases directly the production results by improved quality and quantity of the product. In general Finnish studies have consistently shown that the return of an invested euro is three to seven-old. In national level, according to our calculations the savings could be even 20% of our gross national product.

  6. The role of hazard- and risk-based approaches in ensuring food safety

    DEFF Research Database (Denmark)

    Barlow, Susan M.; Boobis, Alan R.; Bridges, Jim

    2015-01-01

    action. Risk-based approaches allow consideration of exposure in assessing whether there may be unacceptable risks to health. Scope and approach The advantages and disadvantages of hazard- and risk-based approaches for ensuring the safety of food chemicals, allergens, ingredients and microorganisms were...

  7. Risk assessment, session 1-4. International conference 1992. Part 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    The international conference on Risk Assessment, 5-9 October 1992, London was organised by the Health and Safety Commission of the UK and co-sponsored by a number of regional and international organizations namely: the European Commission, the ILO, the OECD and WHO. The main sessions of the conference cover what risk assessment means, the role of risk assessment in devising policies and regulations; and risk assessment in practice.

  8. Risk assessment, session 1-4. International conference 1992. Part 1

    International Nuclear Information System (INIS)

    1992-01-01

    The international conference on Risk Assessment, 5-9 October 1992, London was organised by the Health and Safety Commission of the UK and co-sponsored by a number of regional and international organizations namely: the European Commission, the ILO, the OECD and WHO. The main sessions of the conference cover what risk assessment means, the role of risk assessment in devising policies and regulations; and risk assessment in practice

  9. Risk assessment - black art or science?

    International Nuclear Information System (INIS)

    Moore, G.

    1988-01-01

    Measures of risk can be divided into two categories, those that observe or calculate the risk of a process or project, and those that rely on the level of risk as perceived by the people during the assessment. Collection of data of accidents (where cause and effect are obvious) and experiments on animals which can then be extrapolated to humans, are two ways of risk assessment. Mathematical models and computerized simulations, using either fault tree analysis or Monte Carlo methods are explained simply. Using these methods, experts are able to perceive risk fairly realistically. However, the general public's perception of risk is often quite different, as potential risk is assessed in different ways. The concept of tolerable risk is considered, particularly with reference to nuclear reactors such as Sizewell-B. The need to inform the public of safeguards and safety procedures so they have a better understanding of the risks of nuclear power is stressed. (U.K.)

  10. Meeting on risk and monitoring analysis techniques for food safety - RLA/5/060/ARCAL Project (ARCAL CXXVIII): sampling plans and introduction to chemical risk assessment in food innocuousness

    International Nuclear Information System (INIS)

    2013-03-01

    Some of the Latinoamerican countries such us Bolivia, Colombia, Uruguay and Venezuela participant in the meeting gave an exposition about the risk analysis and monitoring techniques in food safety in their countyries. With the aim to study components of risk analysis, food innocuousness, evaluation and chemical dangers, toxicity, exposure, change of paradigms in the global food system, data sources, study in animals and in vitro, sensitivity analysis, risk assessment in health it carried out the meeting

  11. The role of risk assessment in the nuclear regulatory process

    International Nuclear Information System (INIS)

    Levine, S.

    1979-01-01

    Since the publication of the Reactor Safety Study in the USA, the basic tasks of which are summarised, the use of quantitative risk-assessment techniques for the safety of nuclear power plants has increased considerably. Some of the viewpoints expressed on the use of these techniques are examined, and their limitations are discussed. Areas where risk-assessment techniques are applied by the NRC are listed and some recent examples are discussed. Risk assessment has also been used as a criteria for deciding the topics for the NRC's recommendations for research programs. It is concluded that the major contribution of risk assessment techniques should be in the form of background analyses that will aid decision making and could also significantly affect the scope and content of regulatory reviews. (UK)

  12. Business managers turn to risk assessment

    International Nuclear Information System (INIS)

    Allen, Frank

    1993-01-01

    Risk assessments have evolved to help technical managers in nuclear and other industries to design and operate plant with safety in mind. However, they are now developing into the area of business management. (author)

  13. Approaches to quantitative risk assessment with applications to PP

    International Nuclear Information System (INIS)

    Geiger, G.; Schaefer, A.

    2002-01-01

    Full text: Experience with accidents such as Goiania in Brazil and indications of a considerable number of orphan sources suggest that improved protection would be desirable for some types of radioactive material of wide-spread use such as radiation sources for civil purposes. Regarding large potential health and economic consequences (in particular, if terrorists attacks cannot be excluded), significant costs of preventive actions, and large uncertainties about both the likelihood of occurrence and the potential consequences of PP safety and security incidents, an optimum relationship between preventive and mitigative efforts is likely to be a key issue for successful risk management in this field. Thus, possible violations of physical protection combined with threats of misuse of nuclear materials, including terrorist attack, pose considerable challenges to global security from various perspectives. In view of these challenges, recent advance in applied risk and decision analysis suggests methodological and procedural improvements in quantitative risk assessment, the demarcation of acceptable risk, and risk management. Advance is based on a recently developed model of optimal risky choice suitable for assessing and comparing the cumulative probability distribution functions attached to safety and security risks. Besides quantification of risk (e. g., in economic terms), the standardization of various risk assessment models frequently used in operations research can be approached on this basis. The paper explores possible applications of these improved methods to the safety and security management of nuclear materials, cost efficiency of risk management measures, and the establishment international safety and security standards of PP. Examples will be presented that are based on selected scenarios of misuse involving typical radioactive sources. (author)

  14. Selected component failure rate values from fusion safety assessment tasks

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, L.C.

    1998-09-01

    This report is a compilation of component failure rate and repair rate values that can be used in magnetic fusion safety assessment tasks. Several safety systems are examined, such as gas cleanup systems and plasma shutdown systems. Vacuum system component reliability values, including large vacuum chambers, have been reviewed. Values for water cooling system components have also been reported here. The report concludes with the examination of some equipment important to personnel safety, atmospheres, combustible gases, and airborne releases of radioactivity. These data should be useful to system designers to calculate scoping values for the availability and repair intervals for their systems, and for probabilistic safety or risk analysts to assess fusion systems for safety of the public and the workers.

  15. Selected Component Failure Rate Values from Fusion Safety Assessment Tasks

    Energy Technology Data Exchange (ETDEWEB)

    Cadwallader, Lee Charles

    1998-09-01

    This report is a compilation of component failure rate and repair rate values that can be used in magnetic fusion safety assessment tasks. Several safety systems are examined, such as gas cleanup systems and plasma shutdown systems. Vacuum system component reliability values, including large vacuum chambers, have been reviewed. Values for water cooling system components have also been reported here. The report concludes with the examination of some equipment important to personnel safety, atmospheres, combustible gases, and airborne releases of radioactivity. These data should be useful to system designers to calculate scoping values for the availability and repair intervals for their systems, and for probabilistic safety or risk analysts to assess fusion systems for safety of the public and the workers.

  16. Selected component failure rate values from fusion safety assessment tasks

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1998-01-01

    This report is a compilation of component failure rate and repair rate values that can be used in magnetic fusion safety assessment tasks. Several safety systems are examined, such as gas cleanup systems and plasma shutdown systems. Vacuum system component reliability values, including large vacuum chambers, have been reviewed. Values for water cooling system components have also been reported here. The report concludes with the examination of some equipment important to personnel safety, atmospheres, combustible gases, and airborne releases of radioactivity. These data should be useful to system designers to calculate scoping values for the availability and repair intervals for their systems, and for probabilistic safety or risk analysts to assess fusion systems for safety of the public and the workers

  17. The Safety Assessment of OPR-1000 for Station Blackout Applying Combined Deterministic and Probabilistic Procedure

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dong Gu; Ahn, Seung-Hoon; Cho, Dae-Hyung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    This is termed station blackout (SBO). However, it does not generally include the loss of available AC power to safety buses fed by station batteries through inverters or by alternate AC sources. Historically, risk analysis results have indicated that SBO was a significant contributor to overall core damage frequency. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident, which is a typical beyond design basis accident and important contributor to overall plant risk, is performed by applying the combined deterministic and probabilistic procedure (CDPP). In addition, discussions are made for reevaluation of SBO risk at OPR-1000 by eliminating excessive conservatism in existing PSA. The safety assessment of OPR-1000 for SBO accident, which is a typical BDBA and significant contributor to overall plant risk, was performed by applying the combined deterministic and probabilistic procedure. However, the reference analysis showed that the CDF and CCDP did not meet the acceptable risk, and it was confirmed that the SBO risk should be reevaluated. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it was demonstrated that the proposed CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

  18. Review of the Brunswick Steam Electric Plant Probabilistic Risk Assessment

    International Nuclear Information System (INIS)

    Sattison, M.B.; Davis, P.R.; Satterwhite, D.G.; Gilmore, W.E.; Gregg, R.E.

    1989-11-01

    A review of the Brunswick Steam Electric Plant probabilistic risk Assessment was conducted with the objective of confirming the safety perspectives brought to light by the probabilistic risk assessment. The scope of the review included the entire Level I probabilistic risk assessment including external events. This is consistent with the scope of the probabilistic risk assessment. The review included an assessment of the assumptions, methods, models, and data used in the study. 47 refs., 14 figs., 15 tabs

  19. Navigation safety and risk assessment challenges in the High North

    DEFF Research Database (Denmark)

    Marchenko, N.A.; Borch, O.J.; Andreassen, N.

    2017-01-01

    marine accidents. Therefore, in this study a mostly qualitative analysis and expert judgement is the basis for the risk assessments. Implications for the emergency preparedness system of the region are discussed. The consequences of incidents depend on the incident type, scale and location,....... In this paper we look into the risks of accidents in the Atlantic Arctic based on previous ship accidents and the changes in maritime activity. The risk has to be assessed to ensure a proper level of response in emergency situations. As accidents are rare, there are limited statistics available for Arctic...

  20. Magnetic resonance imaging: hazard, risk and safety

    International Nuclear Information System (INIS)

    Narayan, Pradeep; Suri, S.; Singh, P.

    2001-01-01

    The hazard and risk associated with magnetic resonance imaging is a matter of concern. In 1982, the Food and Drug Administration (FDA), USA issued guidelines to Hospital's Investigational Review Board (IRBs) in 'Guidelines for Evaluating Electromagnetic Exposure Risks for Trials of Clinical Nuclear Magnetic Resonance (NMR)'. In 1997, the Berufsgenossenschaft (BG), professional association for precision engineering and electronics of Germany, in their preliminary proposal for safety limits extended their concerns on static magnetic field. Owing to both time varying and static magnetic fields applied in Magnetic Resonance Imaging (MRI) this became of immediate concern to user community to assess the potential hazard and risk associated with the NMR system

  1. Assessment of radiation safety in well logging

    International Nuclear Information System (INIS)

    Alles, A.; Pérez, Y.; Duménigo, C.

    2015-01-01

    Radiation safety assessments required by current regulations are a means to verify compliance with the requirements. Different methods have been used for this purpose. In the paper the results of applying the method of risk matrices, applied for the first time in the practice of well logging are exposed. For each initiating event frequency of occurrence, the severity of its consequences and the probability of failure of the barriers identified were evaluated. Starting from these assumptions, the risk associated is determined for each of the identified accident sequences, using for this the SEVRRA code 'Risk Assessment System', originally designed for use in radiotherapy. As an result sequences increased risk associated with the practice of well logging were identified, which is the starting point for the further implementation of a coherent program of dose optimization in practice. [es

  2. Economic Risk Assessment Taking Into Account the Volume Oscillator Indicators

    Directory of Open Access Journals (Sweden)

    Loredana Mihaela LAPADUSI

    2016-09-01

    Full Text Available Economic risk can be assessed from many points of view, but generally speaking it means the firm's inability to match workload with cost structure. Expansion of production capacity, adaptation to new technologies, diversification of products are only a few factors influencing risk. These, along with financial risk and bankruptcy risk constitute the most important category of risk which presents a great interest for the banks, shareholders, managers, business partners, etc. The purpose of this article is to provide a brief overview of tje oscillation of your company's activity from the point of view of economic risk. The main objective of this research lies in economic risk assessment by means of the margin of safety, the safety index and critical time point.

  3. Occupational health policies on risk assessment in Japan.

    Science.gov (United States)

    Horie, Seichi

    2010-09-01

    Industrial Safety and Health Law (ISH Law) of Japan requires abnormalities identified in evaluations of worker health and working environments are reported to occupational physicians, and employers are advised of measures to ensure appropriate accommodations in working environments and work procedures. Since the 1980s, notions of a risk assessment and occupational safety and health management system were expected to further prevent industrial accidents. In 2005, ISH Law stipulated workplace risk assessment using the wording "employers shall endeavor." Following the amendment, multiple documents and guidelines for risk assessment for different work procedures were developed. They require ISH Laws to be implemented fully and workplaces to plan and execute measures to reduce risks, ranking them from those addressing potential hazards to those requiring workers to wear protective articles. A governmental survey in 2005 found the performance of risk assessment was 20.4% and common reasons for not implementing risk assessments were lack of adequate personnel or knowledge. ISH Law specifies criminal penalties for both individuals and organizations. Moreover, under the Labor Contract Law promulgated in 2007, employers are obliged to make reasonable efforts to ensure employee health for foreseeable and avoidable risks. Therefore, enterprises neglecting even the non-binding provisions of guidelines are likely to suffer significant business impact if judged to be responsible for industrial accidents or occupational disease. To promote risk assessment, we must strengthen technical, financial, and physical support from public-service organizations, encourage the dissemination of good practices to reduce risks, and consider additional employer incentives, including relaxed mandatory regulations.

  4. Occupational Health Policies on Risk Assessment in Japan

    Directory of Open Access Journals (Sweden)

    Seichi Horie

    2010-09-01

    Full Text Available Industrial Safety and Health Law (ISH Law of Japan requires abnormalities identifi ed in evaluations of worker health and working environments are reported to occupational physicians, and employers are advised of measures to ensure appropriate accommodations in working environments and work procedures. Since the 1980s, notions of a risk assessment and occupational safety and health management system were expected to further prevent industrial accidents. In 2005, ISH Law stipulated workplace risk assessment using the wording “employers shall endeavor.” Following the amendment, multiple documents and guidelines for risk assessment for different work procedures were developed. They require ISH Laws to be implemented fully and workplaces to plan and execute measures to reduce risks, ranking them from those addressing potential hazards to those requiring workers to wear protective articles. A governmental survey in 2005 found the performance of risk assessment was 20.4% and common reasons for not implementing risk assessments were lack of adequate personnel or knowledge. ISH Law specifi es criminal penalties for both individuals and organizations. Moreover, under the Labor Contract Law promulgated in 2007, employers are obliged to make reasonable efforts to ensure employee health for foreseeable and avoidable risks. Therefore, enterprises neglecting even the non-binding provisions of guidelines are likely to suffer signifi cant business impact if judged to be responsible for industrial accidents or occupational disease. To promote risk assessment, we must strengthen technical, fi nancial, and physical support from public-service organizations, encourage the dissemination of good practices to reduce risks, and consider additional employer incentives, including relaxed mandatory regulations.

  5. Risk perception, safety goals and regulatory decision-making

    International Nuclear Information System (INIS)

    Hoegberg, Lars

    1998-01-01

    Deciding on 'how safe is safe enough?' includes value judgements with implications of an ethical and political nature. As regulators are accountable to governments, parliaments and the general public, regulatory decision-making should be characterized by transparency with respect to how such value judgements are reflected in risk assessments and regulatory decisions. Some approaches in this respect are discussed in the paper, based on more than fifteen years of experience in nuclear regulatory decision-making. Issues discussed include: (1) risk profiles and safety goals associated with severe reactor accidents--individual health risks, societal risks and risk of losing investments; (2) risk profile-based licensing of the Swedish SFR final disposal facility for low and intermediate level radioactive waste

  6. Approaches to risk assessment in food allergy

    DEFF Research Database (Denmark)

    Madsen, Charlotte Bernhard; Hattersley, S.; Buck, J.

    2009-01-01

    modelling is considered to be the most promising approach for use in population risk assessment (which is a particular focus for risk managers). For all approaches, further improvement of input data is desirable, particularly data on consumption patterns/food choices in food allergic consumers, data...... models. The workshop concluded that all the three approaches to safety and risk assessment of allergenic foods should continue to be considered. A particular strength of the MoE and probabilistic approaches is that they do not rely on low-dose extrapolations with its inherent issues. Probabilistic......A workshop was organised to investigate whether risk assessment strategies and methodologies used in classical/conventional toxicology may be used for risk assessment of allergenic foods. to discuss the advantages and limitations of different approaches and to determine the research needed to move...

  7. Principle considerations for the risk assessment of sprayed consumer products.

    Science.gov (United States)

    Steiling, W; Bascompta, M; Carthew, P; Catalano, G; Corea, N; D'Haese, A; Jackson, P; Kromidas, L; Meurice, P; Rothe, H; Singal, M

    2014-05-16

    In recent years, the official regulation of chemicals and chemical products has been intensified. Explicitly for spray products enhanced requirements to assess the consumers'/professionals' exposure to such product type have been introduced. In this regard the Aerosol-Dispensers-Directive (75/324/EEC) with obligation for marketing aerosol dispensers, and the Cosmetic-Products-Regulation (1223/2009/EC) which obliges the insurance of a safety assessment, have to be mentioned. Both enactments, similar to the REACH regulation (1907/2006/EC), require a robust chemical safety assessment. From such assessment, appropriate risk management measures may be identified to adequately control the risk of these chemicals/products to human health and the environment when used. Currently, the above-mentioned regulations lack the guidance on which data are needed for preparing a proper hazard analysis and safety assessment of spray products. Mandatory in the process of inhalation risk and safety assessment is the determination and quantification of the actual exposure to the spray product and more specifically, its ingredients. In this respect the current article, prepared by the European Aerosol Federation (FEA, Brussels) task force "Inhalation Toxicology", intends to introduce toxicological principles and the state of the art in currently available exposure models adapted for typical application scenarios. This review on current methodologies is intended to guide safety assessors to better estimate inhalation exposure by using the most relevant data. Copyright © 2014 The Authors. Published by Elsevier Ireland Ltd.. All rights reserved.

  8. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

  9. Communicating on risk and safety in terms of awareness

    International Nuclear Information System (INIS)

    Hammar, L.; Andersson, Kjell

    1999-01-01

    'Safety awareness' is proposed as a possibly constructive concept for the purpose of promoting initiatives in nuclear safety work and gaining improved understanding when communicating on nuclear safety. Safety is thus conceived as resulting essentially from and actually constituting awareness of critical factors in regard of safety. The concept aims specifically at promoting the view of 'safety' as 'awareness of required conditions for being in control of risk'. It aims as well at making clearer sense in calling for constant improvement of safety, according to practice in a safety culture. This proposed view would be expected to lead to applying the usual types of safety criteria but offers the merit of attracting due attention to 'awareness goals' in process oriented safety management which are fundamental to maintaining and improving safety. Applications are discussed in regard of communicating on nuclear safety between decision-makers and the general public, developing and maintaining safety culture, integrating specialist expert contributions in over-all safety assessment, setting safety goals and using safety indicators

  10. Implementing Toxicity Testing in the 21st Century (TT21C): Making safety decisions using toxicity pathways, and progress in a prototype risk assessment

    International Nuclear Information System (INIS)

    Adeleye, Yeyejide; Andersen, Melvin; Clewell, Rebecca; Davies, Michael; Dent, Matthew; Edwards, Sue; Fowler, Paul; Malcomber, Sophie; Nicol, Beate; Scott, Andrew; Scott, Sharon; Sun, Bin; Westmoreland, Carl; White, Andrew; Zhang, Qiang; Carmichael, Paul L.

    2015-01-01

    Risk assessment methodologies in toxicology have remained largely unchanged for decades. The default approach uses high dose animal studies, together with human exposure estimates, and conservative assessment (uncertainty) factors or linear extrapolations to determine whether a specific chemical exposure is ‘safe’ or ‘unsafe’. Although some incremental changes have appeared over the years, results from all new approaches are still judged against this process of extrapolating high-dose effects in animals to low-dose exposures in humans. The US National Research Council blueprint for change, entitled Toxicity Testing in the 21st Century: A Vision and Strategy called for a transformation of toxicity testing from a system based on high-dose studies in laboratory animals to one founded primarily on in vitro methods that evaluate changes in normal cellular signalling pathways using human-relevant cells or tissues. More recently, this concept of pathways-based approaches to risk assessment has been expanded by the description of ‘Adverse Outcome Pathways’ (AOPs). The question, however, has been how to translate this AOP/TT21C vision into the practical tools that will be useful to those expected to make safety decisions. We have sought to provide a practical example of how the TT21C vision can be implemented to facilitate a safety assessment for a commercial chemical without the use of animal testing. To this end, the key elements of the TT21C vision have been broken down to a set of actions that can be brought together to achieve such a safety assessment. Such components of a pathways-based risk assessment have been widely discussed, however to-date, no worked examples of the entire risk assessment process exist. In order to begin to test the process, we have taken the approach of examining a prototype toxicity pathway (DNA damage responses mediated by the p53 network) and constructing a strategy for the development of a pathway based risk assessment for a

  11. Implementing Toxicity Testing in the 21st Century (TT21C): Making safety decisions using toxicity pathways, and progress in a prototype risk assessment.

    Science.gov (United States)

    Adeleye, Yeyejide; Andersen, Melvin; Clewell, Rebecca; Davies, Michael; Dent, Matthew; Edwards, Sue; Fowler, Paul; Malcomber, Sophie; Nicol, Beate; Scott, Andrew; Scott, Sharon; Sun, Bin; Westmoreland, Carl; White, Andrew; Zhang, Qiang; Carmichael, Paul L

    2015-06-05

    Risk assessment methodologies in toxicology have remained largely unchanged for decades. The default approach uses high dose animal studies, together with human exposure estimates, and conservative assessment (uncertainty) factors or linear extrapolations to determine whether a specific chemical exposure is 'safe' or 'unsafe'. Although some incremental changes have appeared over the years, results from all new approaches are still judged against this process of extrapolating high-dose effects in animals to low-dose exposures in humans. The US National Research Council blueprint for change, entitled Toxicity Testing in the 21st Century: A Vision and Strategy called for a transformation of toxicity testing from a system based on high-dose studies in laboratory animals to one founded primarily on in vitro methods that evaluate changes in normal cellular signalling pathways using human-relevant cells or tissues. More recently, this concept of pathways-based approaches to risk assessment has been expanded by the description of 'Adverse Outcome Pathways' (AOPs). The question, however, has been how to translate this AOP/TT21C vision into the practical tools that will be useful to those expected to make safety decisions. We have sought to provide a practical example of how the TT21C vision can be implemented to facilitate a safety assessment for a commercial chemical without the use of animal testing. To this end, the key elements of the TT21C vision have been broken down to a set of actions that can be brought together to achieve such a safety assessment. Such components of a pathways-based risk assessment have been widely discussed, however to-date, no worked examples of the entire risk assessment process exist. In order to begin to test the process, we have taken the approach of examining a prototype toxicity pathway (DNA damage responses mediated by the p53 network) and constructing a strategy for the development of a pathway based risk assessment for a specific

  12. Exploration Health Risks: Probabilistic Risk Assessment

    Science.gov (United States)

    Rhatigan, Jennifer; Charles, John; Hayes, Judith; Wren, Kiley

    2006-01-01

    Maintenance of human health on long-duration exploration missions is a primary challenge to mission designers. Indeed, human health risks are currently the largest risk contributors to the risks of evacuation or loss of the crew on long-duration International Space Station missions. We describe a quantitative assessment of the relative probabilities of occurrence of the individual risks to human safety and efficiency during space flight to augment qualitative assessments used in this field to date. Quantitative probabilistic risk assessments will allow program managers to focus resources on those human health risks most likely to occur with undesirable consequences. Truly quantitative assessments are common, even expected, in the engineering and actuarial spheres, but that capability is just emerging in some arenas of life sciences research, such as identifying and minimize the hazards to astronauts during future space exploration missions. Our expectation is that these results can be used to inform NASA mission design trade studies in the near future with the objective of preventing the higher among the human health risks. We identify and discuss statistical techniques to provide this risk quantification based on relevant sets of astronaut biomedical data from short and long duration space flights as well as relevant analog populations. We outline critical assumptions made in the calculations and discuss the rationale for these. Our efforts to date have focussed on quantifying the probabilities of medical risks that are qualitatively perceived as relatively high risks of radiation sickness, cardiac dysrhythmias, medically significant renal stone formation due to increased calcium mobilization, decompression sickness as a result of EVA (extravehicular activity), and bone fracture due to loss of bone mineral density. We present these quantitative probabilities in order-of-magnitude comparison format so that relative risk can be gauged. We address the effects of

  13. Nuclear power and probabilistic safety assessment (PSA): past through future applications

    Science.gov (United States)

    Stamatelatos, M. G.; Moieni, P.; Everline, C. J.

    1995-03-01

    Nuclear power reactor safety in the United States is about to enter a new era -- an era of risk- based management and risk-based regulation. First, there was the age of `prescribed safety assessment,' during which a series of design-basis accidents in eight categories of severity, or classes, were postulated and analyzed. Toward the end of that era, it was recognized that `Class 9,' or `beyond design basis,' accidents would need special attention because of the potentially severe health and financial consequences of these accidents. The accident at Three Mile Island showed that sequences of low-consequence, high-frequency events and human errors can be much more risk dominant than the Class 9 accidents. A different form of safety assessment, PSA, emerged and began to gain ground against the deterministic safety establishment. Eventually, this led to the current regulatory requirements for individual plant examinations (IPEs). The IPEs can serve as a basis for risk-based regulation and management, a concept that may ultimately transform the U.S. regulatory process from its traditional deterministic foundations to a process predicated upon PSA. Beyond the possibility of a regulatory environment predicated upon PSA lies the possibility of using PSA as the foundation for managing daily nuclear power plant operations.

  14. Safety assessment of genetically modified crops

    International Nuclear Information System (INIS)

    Atherton, Keith T.

    2002-01-01

    The development of genetically modified (GM) crops has prompted widespread debate regarding both human safety and environmental issues. Food crops produced by modern biotechnology using recombinant techniques usually differ from their conventional counterparts only in respect of one or a few desirable genes, as opposed to the use of traditional breeding methods which mix thousands of genes and require considerable efforts to select acceptable and robust hybrid offspring. The difficulties of applying traditional toxicological testing and risk assessment procedures to whole foods are discussed along with the evaluation strategies that are used for these new food products to ensure the safety of these products for the consumer

  15. [International trend of guidance for nanomaterial risk assessment].

    Science.gov (United States)

    Hirose, Akihiko

    2013-01-01

    In the past few years, several kinds of opinions or recommendations on the nanomaterial safety assessment have been published from international or national bodies. Among the reports, the first practical guidance of risk assessment from the regulatory body was published from the European Food Safety Authorities in May 2011, which included the determination of exposure scenario and toxicity testing strategy. In October 2011, European Commission (EC) adopted the definition of "nanomaterial" for regulation. And more recently, Scientific Committee on Consumer Safety of EC released guidance for assessment of nanomaterials in cosmetics in June 2012. A series of activities in EU marks an important step towards realistic safety assessment of nanomaterials. On the other hand, the US FDA announced a draft guidance for industry in June 2011, and then published draft guidance documents for both "Cosmetic Products" and "Food Ingredients and Food Contact Substances" in April 2012. These draft documents do not restrictedly define the physical properties of nanomaterials, but when manufacturing changes alter the dimensions, properties, or effects of an FDA-regulated product, the products are treated as new products. Such international movements indicate that most of nanomaterials with any new properties would be assessed or regulated as new products by most of national authorities in near future, although the approaches are still case by case basis. We will introduce such current international activities and consideration points for regulatory risk assessment.

  16. Risk-assessment techniques and the reactor licensing process

    International Nuclear Information System (INIS)

    Levine, S.

    1979-01-01

    A brief description of the Reactor Safety Study (WASH-1400), concentrating on the engineering aspects of the contribution to reactor accident risks is followed by some comments on how we have applied the insights and techniques developed in this study to prepare a program to improve the safety of nuclear power plants. Some new work we are just beginning on the application of risk-assessment techniques to stablize the reactor licensing process is also discussed

  17. Identification and evaluation of priorities in the business process of a risk or safety organization

    International Nuclear Information System (INIS)

    Teng, Kuei-Yung; Thekdi, Shital A.; Lambert, James H.

    2012-01-01

    Agencies are increasingly following principles and guidelines for the coordination of risk assessment, risk management, and risk communication in large-scale programs. In particular, there is a challenge to comply with the U.S. Office of Management and Budget (OMB) memorandum “Updated Principles for Risk Analysis” among other guidelines. This paper demonstrates a systemic approach to achieve compliance of a risk program with administrative and organizational principles and guidelines for risk analysis. The paper suggests three canonical questions as the mission of such a program: (i) what sources of risks are to be managed by the program, (ii) how should multiple risk assessment, risk management, and risk communication activities be administered and coordinated, and what should be the basis for resource allocation to these activities, and (iii) how will the performance of the program be monitored and evaluated. The paper demonstrates a re-prioritization of policy initiatives of the program based on emergent and future conditions. The approach is useful to agencies implementing risk or safety organizational guidelines such as those of the OMB, the US Government Accountability Office, the US Department of Homeland Security, the US Department of Defense, and others. This paper will be of interest to risk managers; agencies; and risk and safety analysts engaged in the conception, implementation, and evaluation of risk or safety programs. - Highlights: ► We develop a systemic approach for management of a risk or safety program. ► The approach includes business process models and policy prioritization. ► The results support organizations to implement risk and safety programs.

  18. Human reliability assessment and probabilistic risk assessment

    International Nuclear Information System (INIS)

    Embrey, D.E.; Lucas, D.A.

    1989-01-01

    Human reliability assessment (HRA) is used within Probabilistic Risk Assessment (PRA) to identify the human errors (both omission and commission) which have a significant effect on the overall safety of the system and to quantify the probability of their occurrence. There exist a variey of HRA techniques and the selection of an appropriate one is often difficult. This paper reviews a number of available HRA techniques and discusses their strengths and weaknesses. The techniques reviewed include: decompositional methods, time-reliability curves and systematic expert judgement techniques. (orig.)

  19. Risk assessment approach for Rokkasho reprocessing plant

    International Nuclear Information System (INIS)

    Ootou, Y.; Tamauchi, Y.; Hayashi, Y.; Takebe, K.; Miyata, T.

    2006-01-01

    Full text: It is desirable that the operation and maintenance of Rokkasho Reprocessing Plant (RRP) be established and conducted with maximum effectiveness and efficiency, making the best use of risk information to help the plant achieve further enhanced safety. Risk assessment is applied for RRP, and upgraded risk information is established. In the basic design phase, the potential incidents and accidents that might occur in the plant were identified systematically and exhaustively adopting the HAZOP method. After screening the potential for occurrence, the design basis accidents (DBAs) were identified and it was confirmed that the plant would not put the general public at risk of significant radiation exposure in the case of such accidents, even when assuming the single failure of dynamic apparatus in the prevention and mitigation systems. To support the deterministic safety assessment mentioned above, the risk assessment was conducted during the basic design phase. Of the DBAs and out-of-design basis accidents excluded from DBAs because of extremely rare occurrence possibilities, the risk assessment was conducted for such accidents which might cause relatively high consequence for the general public. The risk assessment was conducted using the PSA method generally used for nuclear power plants. After that, a review of the occurrence frequency assessment for some of the accidents was made, taking into account information relating to detailed design and operation procedures. Typical examples are a loss of the hydrogen scavenging function in the plutonium solution tank and a loss of cooling capability in the high-active liquid waste storage tank. The occurrence frequency for a loss of the hydrogen scavenging function was less than 10 -5 /year. The occurrence frequency for a loss of cooling capability was less than 10 -7 /year. In addition, an importance assessment (FV index, Risk Achievement Worth) was conducted, such as a contribution to the occurrence frequency

  20. Mitigating construction safety risks using prevention through design.

    Science.gov (United States)

    Gangolells, Marta; Casals, Miquel; Forcada, Núria; Roca, Xavier; Fuertes, Alba

    2010-04-01

    Research and practice have demonstrated that decisions made prior to work at construction sites can influence construction worker safety. However, it has also been argued that most architects and design engineers possess neither the knowledge of construction safety nor the knowledge of construction processes necessary to effectively perform Construction Hazards Prevention through Design (CHPtD). This paper introduces a quantitative methodology that supports designers by providing a way to evaluate the safety-related performance of residential construction designs using a risk analysis-based approach. The methodology compares the overall safety risk level of various construction designs and ranks the significance of the various safety risks of each of these designs. The methodology also compares the absolute importance of a particular safety risk in various construction designs. Because the methodology identifies the relevance of each safety risk at a particular site prior to the construction stage, significant risks are highlighted in advance. Thus, a range of measures for mitigating safety risks can then be implemented during on-site construction. The methodology is specially worthwhile for designers, who can compare construction techniques and systems during the design phase and determine the corresponding level of safety risk without their creative talents being restricted. By using this methodology, construction companies can improve their on-site safety performance. Copyright 2010 Elsevier Ltd. All rights reserved.

  1. Discounting the value of safety: effects of perceived risk and effort.

    Science.gov (United States)

    Sigurdsson, Sigurdur O; Taylor, Matthew A; Wirth, Oliver

    2013-09-01

    Although falls from heights remain the most prevalent cause of fatalities in the construction industry, factors impacting safety-related choices associated with work at heights are not completely understood. Better tools are needed to identify and study the factors influencing safety-related choices and decision making. Using a computer-based task within a behavioral economics paradigm, college students were presented a choice between two hypothetical scenarios that differed in working height and effort associated with retrieving and donning a safety harness. Participants were instructed to choose the scenario in which they were more likely to wear the safety harness. Based on choice patterns, switch points were identified, indicating when the perceived risk in both scenarios was equivalent. Switch points were a systematic function of working height and effort, and the quantified relation between perceived risk and effort was described well by a hyperbolic equation. Choice patterns revealed that the perceived risk of working at heights decreased as the effort to retrieve and don a safety harness increased. Results contribute to the development of computer-based procedure for assessing risk discounting within a behavioral economics framework. Such a procedure can be used as a research tool to study factors that influence safety-related decision making with a goal of informing more effective prevention and intervention strategies. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  2. Operationalization Of The Professional Risks Assessment Activity

    Science.gov (United States)

    Ivascu, Victoria Larisa; Cirjaliu, Bianca; Draghici, Anca

    2015-07-01

    Professional risks assessment approach (integration of analysis and evaluation processes) is linked with the general concerns of nowadays companies for their employees' health and safety assurances, in the context of organizations sustainable development. The paper presents an approach for the operationalization of the professional risk assessment activity in companies through the implementation and use of the OnRisk platform (this have been tested in some industrial companies). The short presentation of the relevant technical reports and statistics on OSH management at the European Union level underlines the need for the development of a professional risks assessment. Finally, there have been described the designed and developed OnRisk platform as a web platform together with some case studies that have validate the created tool.

  3. Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

  4. Quantified reliability and risk assessment methodology in safety evaluation and licensing: survey of practice and trends in E.C. countries; partial contribution in decision making, perpective of safety goals

    International Nuclear Information System (INIS)

    Vinck, W.F.

    1982-01-01

    Quantified reliability analysis of structures and systems and the quantified risk-concept is increasingly developed and applied in safety evaluation and in the licensing/regulatory process where deterministic approaches are however still predominant. A description of the types of application and a survey of the diversified opinions and the problem areas (e.g. the validity of input data, uncertainties in consequence modelling, human factors, common mode failures, etc.) are given. The significance of quantified risk assessment and comparisons, as one of the contributors in the solution to acceptability of modern technology such as nuclear power production, is discussed. Other contributions, such as benefit assessment and cost-efficiency of risk reduction, are also put into perspective within the decision-making process and in the problem of actual acceptance of new technologies. The growing need of developing and agreeing on overall safety objectives (how safe is safe enough) is finally discussed, in the light of the increasing diversity of approaches in the interconnected areas of accident hypotheses/sequences, siting parameters and technical bases for emergency planning; the latter problem being also closely connected to decisional processes for acceptability and to actual acceptance

  5. The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dong Gu, E-mail: littlewing@kins.re.kr [Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon 305-338 (Korea, Republic of); Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Chang, Soon Heung [Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

    2014-08-15

    Highlights: • The combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the BDBAs. • The safety assessment of OPR-1000 nuclear power plant for SBO accident is performed by applying the CDPP. • By estimating the offsite power restoration time appropriately, the SBO risk is reevaluated. • It is concluded that the CDPP is applicable to safety assessment of BDBAs without significant erosion of the safety margin. - Abstract: Station blackout (SBO) is a typical beyond design basis accident (BDBA) and significant contributor to overall plant risk. The risk analysis of SBO could be important basis of rulemaking, accident mitigation strategy, etc. Recently, studies on the integrated approach of deterministic and probabilistic method for nuclear safety in nuclear power plants have been done, and among them, the combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the BDBAs. In the CDPP, the conditional exceedance probability obtained by the best estimate plus uncertainty method acts as go-between deterministic and probabilistic safety assessments, resulting in more reliable values of core damage frequency and conditional core damage probability. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident was performed by applying the CDPP. It was confirmed that the SBO risk should be reevaluated by eliminating excessive conservatism in existing probabilistic safety assessment to meet the targeted core damage frequency and conditional core damage probability. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it is concluded that the CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

  6. The practice of pre-marketing safety assessment in drug development.

    Science.gov (United States)

    Chuang-Stein, Christy; Xia, H Amy

    2013-01-01

    The last 15 years have seen a substantial increase in efforts devoted to safety assessment by statisticians in the pharmaceutical industry. While some of these efforts were driven by regulations and public demand for safer products, much of the motivation came from the realization that there is a strong need for a systematic approach to safety planning, evaluation, and reporting at the program level throughout the drug development life cycle. An efficient process can help us identify safety signals early and afford us the opportunity to develop effective risk minimization plan early in the development cycle. This awareness has led many pharmaceutical sponsors to set up internal systems and structures to effectively conduct safety assessment at all levels (patient, study, and program). In addition to process, tools have emerged that are designed to enhance data review and pattern recognition. In this paper, we describe advancements in the practice of safety assessment during the premarketing phase of drug development. In particular, we share examples of safety assessment practice at our respective companies, some of which are based on recommendations from industry-initiated working groups on best practice in recent years.

  7. Safety assessment of cast steel valve housing using NDE- and FM-methods

    Energy Technology Data Exchange (ETDEWEB)

    Blauel, J G; Hodulak, L [Fraunhofer-Institut fuer Werkstoffmechanik, Freiburg im Breisgau (Germany)

    1988-12-31

    This document presents some results concerning the safety assessment of cast steel valve housing. This risk assessment is performed through the Non Destructive Examination and Fracture Mechanics methods. (TEC).

  8. Risk-based assessment of the surety of information systems

    Energy Technology Data Exchange (ETDEWEB)

    Jansma, R.M.; Fletcher, S.K.; Murphy, M.D.; Lim, J.J.; Wyss, G.D.

    1996-07-01

    When software is used in safety-critical, security-critical, or mission-critical situations, it is imperative to understand and manage the risks involved. A risk assessment methodology and toolset have been developed which are specific to software systems and address a broad range of risks including security, safety, and correct operation. A unique aspect of this methodology is the use of a modeling technique that captures interactions and tradeoffs among risk mitigators. This paper describes the concepts and components of the methodology and presents its application to example systems.

  9. An integrated framework for health and ecological risk assessment

    International Nuclear Information System (INIS)

    Suter, Glenn W.; Vermeire, Theo; Munns, Wayne R.; Sekizawa, Jun

    2005-01-01

    The worldHealth Organization's (WHO's) International Program for Chemical Safety has developed a framework for performing risk assessments that integrate the assessment of risks to human health and risks to nonhuman organisms and ecosystems. The WHO's framework recognizes that stakeholders and risk managers have their own processes that are parallel to the scientific process of risk assessment and may interact with the risk assessment at various points, depending on the context. Integration of health and ecology provides consistent expressions of assessment results, incorporates the interdependence of humans and the environment, uses sentinel organisms, and improves the efficiency and quality of assessments relative to independent human health and ecological risk assessments. The advantage of the framework to toxicologists lies in the opportunity to use understanding of toxicokinetics and toxicodynamics to inform the integrated assessment of all exposed species

  10. Safety analysis and risk assessment of the National Ignition Facility

    International Nuclear Information System (INIS)

    Brereton, S.; McLouth, L.; Odell, B.

    1996-01-01

    The National Ignition Facility (NIF) is a proposed U.S. Department of Energy inertial confinement laser fusion facility. The candidate sites for locating the NIF are: Los Alamos National Laboratory, Sandia National Laboratory, the Nevada Test Site, and Lawrence Livermore National Laboratory (LLNL), the preferred site. The NIF will operate by focusing 192 laser beams onto a tiny deuterium-tritium target located at the center of a spherical target chamber. The NIF mission is to achieve inertial confinement fusion (ICF) ignition, access physical conditions in matter of interest to nuclear weapons physics, provide an above ground simulation capability for nuclear weapons effects testing, and contribute to the development of inertial fusion for electrical power production. The NIF has been classified as a radiological, low hazard facility on the basis of a preliminary hazards analysis and according to the DOE methodology for facility classification. This requires that a safety analysis be prepared under DOE Order 5481.1B, Safety Analysis and Review System. A draft Preliminary Safety Analysis Report (PSAR) has been written, and this will be finalized later in 1996. This paper summarizes the safety issues associated with the operation of the NIF and the methodology used to study them. It provides a summary of the methodology, an overview of the hazards, estimates maximum routine and accidental exposures for the preferred site of LLNL, and concludes that the risks from NIF operations are low

  11. A novel safety assessment strategy applied to non-selective extracts.

    Science.gov (United States)

    Koster, Sander; Leeman, Winfried; Verheij, Elwin; Dutman, Ellen; van Stee, Leo; Nielsen, Lene Munch; Ronsmans, Stefan; Noteborn, Hub; Krul, Lisette

    2015-06-01

    A main challenge in food safety research is to demonstrate that processing of foodstuffs does not lead to the formation of substances for which the safety upon consumption might be questioned. This is especially so since food is a complex matrix in which the analytical detection of substances, and consequent risk assessment thereof, is difficult to determine. Here, a pragmatic novel safety assessment strategy is applied to the production of non-selective extracts (NSEs), used for different purposes in food such as for colouring purposes, which are complex food mixtures prepared from reference juices. The Complex Mixture Safety Assessment Strategy (CoMSAS) is an exposure driven approach enabling to efficiently assess the safety of the NSE by focussing on newly formed substances or substances that may increase in exposure during the processing of the NSE. CoMSAS enables to distinguish toxicologically relevant from toxicologically less relevant substances, when related to their respective levels of exposure. This will reduce the amount of work needed for identification, characterisation and safety assessment of unknown substances detected at low concentration, without the need for toxicity testing using animal studies. In this paper, the CoMSAS approach has been applied for elderberry and pumpkin NSEs used for food colouring purposes. Copyright © 2015 Elsevier Ltd. All rights reserved.

  12. Bayesian-network-based safety risk analysis in construction projects

    International Nuclear Information System (INIS)

    Zhang, Limao; Wu, Xianguo; Skibniewski, Miroslaw J.; Zhong, Jingbing; Lu, Yujie

    2014-01-01

    This paper presents a systemic decision support approach for safety risk analysis under uncertainty in tunnel construction. Fuzzy Bayesian Networks (FBN) is used to investigate causal relationships between tunnel-induced damage and its influential variables based upon the risk/hazard mechanism analysis. Aiming to overcome limitations on the current probability estimation, an expert confidence indicator is proposed to ensure the reliability of the surveyed data for fuzzy probability assessment of basic risk factors. A detailed fuzzy-based inference procedure is developed, which has a capacity of implementing deductive reasoning, sensitivity analysis and abductive reasoning. The “3σ criterion” is adopted to calculate the characteristic values of a triangular fuzzy number in the probability fuzzification process, and the α-weighted valuation method is adopted for defuzzification. The construction safety analysis progress is extended to the entire life cycle of risk-prone events, including the pre-accident, during-construction continuous and post-accident control. A typical hazard concerning the tunnel leakage in the construction of Wuhan Yangtze Metro Tunnel in China is presented as a case study, in order to verify the applicability of the proposed approach. The results demonstrate the feasibility of the proposed approach and its application potential. A comparison of advantages and disadvantages between FBN and fuzzy fault tree analysis (FFTA) as risk analysis tools is also conducted. The proposed approach can be used to provide guidelines for safety analysis and management in construction projects, and thus increase the likelihood of a successful project in a complex environment. - Highlights: • A systemic Bayesian network based approach for safety risk analysis is developed. • An expert confidence indicator for probability fuzzification is proposed. • Safety risk analysis progress is extended to entire life cycle of risk-prone events. • A typical

  13. Review of Risk Reduction Methods using Probabilistic Safety Assessment Insights and Improved Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eun-Chan; Choi, Byung-Pil [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2016-10-15

    As seen in the process of the periodic safety review of domestic nuclear power plants, the risk management objectives such as core damage frequency and large early release frequency are not easy to be met without continuous safety improvements and the integratoin of the improved technologies into the PSA evaluation methodologies. Because external event analyses have a protion of uncertainty factors in the current analysis methodologies, the technical efforts in various perspectives.

  14. [Endorsement of risk management and patient safety by certification of conformity in health care quality assessment].

    Science.gov (United States)

    Waßmuth, Ralf

    2015-01-01

    Certification of conformity in health care should provide assurance of compliance with quality standards. This also includes risk management and patient safety. Based on a comprehensive definition of quality, beneficial effects on the management of risks and the enhancement of patient safety can be expected from certification of conformity. While these effects have strong face validity, they are currently not sufficiently supported by evidence from health care research. Whether this relates to a lack of evidence or a lack of investigation remains open. Advancing safety culture and "climate", as well as learning from adverse events rely in part on quality management and are at least in part reflected in the certification of healthcare quality. However, again, evidence of the effectiveness of such measures is limited. Moreover, additional factors related to personality, attitude and proactive action of healthcare professionals are crucial factors in advancing risk management and patient safety which are currently not adequately reflected in certification of conformity programs.

  15. Deterministic quantitative risk assessment development

    Energy Technology Data Exchange (ETDEWEB)

    Dawson, Jane; Colquhoun, Iain [PII Pipeline Solutions Business of GE Oil and Gas, Cramlington Northumberland (United Kingdom)

    2009-07-01

    Current risk assessment practice in pipeline integrity management is to use a semi-quantitative index-based or model based methodology. This approach has been found to be very flexible and provide useful results for identifying high risk areas and for prioritizing physical integrity assessments. However, as pipeline operators progressively adopt an operating strategy of continual risk reduction with a view to minimizing total expenditures within safety, environmental, and reliability constraints, the need for quantitative assessments of risk levels is becoming evident. Whereas reliability based quantitative risk assessments can be and are routinely carried out on a site-specific basis, they require significant amounts of quantitative data for the results to be meaningful. This need for detailed and reliable data tends to make these methods unwieldy for system-wide risk k assessment applications. This paper describes methods for estimating risk quantitatively through the calibration of semi-quantitative estimates to failure rates for peer pipeline systems. The methods involve the analysis of the failure rate distribution, and techniques for mapping the rate to the distribution of likelihoods available from currently available semi-quantitative programs. By applying point value probabilities to the failure rates, deterministic quantitative risk assessment (QRA) provides greater rigor and objectivity than can usually be achieved through the implementation of semi-quantitative risk assessment results. The method permits a fully quantitative approach or a mixture of QRA and semi-QRA to suit the operator's data availability and quality, and analysis needs. For example, consequence analysis can be quantitative or can address qualitative ranges for consequence categories. Likewise, failure likelihoods can be output as classical probabilities or as expected failure frequencies as required. (author)

  16. Risk assessment and management in IOR projects

    International Nuclear Information System (INIS)

    Goodyear, S.G.; Gregory, A.T.

    1994-01-01

    The application of IOR techniques is one of the investment opportunities open to Exploration and Production companies. A project will only go forward if the perceived balance between the rewards and the risks is acceptable. IOR projects may be ruled out because they are considered to involve significantly higher risks than conventional developments. Therefore, some means of evaluating the actual level of risk may be required if the full economic benefits from IOR techniques are to be realized. Risk assessment is a key element in safety cases, where a well-established methodology for quantifying risk exists. This paper discusses the extension of these methods to IOR project risk assessment. Combining reservoir and IOR technique uncertainties with their impact on project performance allows project risk to be better quantified. The results of the risk assessment are presented in terms of a risk-reward diagram that plots the probability surface for possible project outcomes as a function of NPV (reward) and exposure (risk)

  17. Proposing a model for safety risk assessment in the construction industry using gray multi-criterion decision-making

    Directory of Open Access Journals (Sweden)

    S. M. Abootorabi

    2014-09-01

    Full Text Available Introduction: Statistical Report of the Social Security Organization indicate that among the various industries, the construction industry has the highest number of work-related accidents so that in addition to frequency, it has high intensity, as well. On the other hand, a large number of human resources are working in this whish shows they necessity for paying special attention to these workers. Therefore, risk assessment of the safety in the construction industry is an effective step in this regard. In this study, a method for ranking safety risks in conditions of low number of samples and uncertainty is presented, using gray multi-criterion decision-making. .Material and Method: In this study, we first identified the factors affecting the occurrence of hazards in the construction industry. Then, appropriate for ranking the risks were determined and the problem was defined as a multi-criterion decision-making. In order to weight the criteria and to evaluate alternatives based on each criterion, gray numbers were used. In the last stage, the problem was solved using the gray possibility degree. .Results: The results show that the method of gray multi-criterion decision-making is an effective method for ranking risks in situations of low samples compared with other methods of MCDM. .Conclusion: The proposed method is preferred to fuzzy methods and statistics in uncertain and low sample size, due to simple calculations and no need to define the membership function.

  18. Thermonuclear generation program: risks and safety

    International Nuclear Information System (INIS)

    Goes, Alexandre Gromann de Araujo

    1999-01-01

    This work deals with the fundamental concepts of risk and safety related to nuclear power generation. In the first chapter, a general evaluation of the various systems for energy generation and their environmental impacts is made. Some definitions for safety and risk are suggested, based on the already existing regulatory processes and also on the current tendencies of risk management. Aspects regarding the safety culture are commented. The International Nuclear Event Scale (INES), a coherent and clear mechanism of communication between nuclear specialists and the general public, is analyzed. The second chapter examines the thermonuclear generation program in Brazil and the role of the National Nuclear Energy Commission. The third chapter presents national and international scenarios in terms of safety and risks, available policies and the main obstacles for future development of nuclear energy and nuclear engineering, and strategies are proposed. In the last chapter, comments about possible trends and recommendations related to practical risk management procedures, taking into account rational criteria for resources distribution and risk reduction are made, envisaging a closer integration between nuclear specialists and the society as a whole, thus decreasing the conflicts in a democratic decision-making process

  19. A Real-Time Location-Based Services System Using WiFi Fingerprinting Algorithm for Safety Risk Assessment of Workers in Tunnels

    Directory of Open Access Journals (Sweden)

    Peng Lin

    2014-01-01

    Full Text Available This paper investigates the feasibility of a real-time tunnel location-based services (LBS system to provide workers’ safety protection and various services in concrete dam site. In this study, received signal strength- (RSS- based location using fingerprinting algorithm and artificial neural network (ANN risk assessment is employed for position analysis. This tunnel LBS system achieves an online, real-time, intelligent tracking identification feature, and the on-site running system has many functions such as worker emergency call, track history, and location query. Based on ANN with a strong nonlinear mapping, and large-scale parallel processing capabilities, proposed LBS system is effective to evaluate the risk management on worker safety. The field implementation shows that the proposed location algorithm is reliable and accurate (3 to 5 meters enough for providing real-time positioning service. The proposed LBS system is demonstrated and firstly applied to the second largest hydropower project in the world, to track workers on tunnel site and assure their safety. The results show that the system is simple and easily deployed.

  20. Radiation safety assessment of treatment teletherapy linear accelerators using the method of the risk matrix

    International Nuclear Information System (INIS)

    Dumenigo Gonzalez, Cruz; Vilaragut Llanes, Juan J.; Morales Lopez, Jorge L.

    2009-01-01

    Accidents in the world of radiation, demonstrating the need for deepen security assessments. This study evaluates the safety of the treatment of teletherapy linear accelerator (LINAC) at a hospital in Cuba, based on applying the method Risk Matrix. This method has been used for many years in conventional industry, is simple, easy to apply and is based on the equation General risk R = f * P * C (where: f frequency of occurrence of the initiating event, P probability of failure of all barriers and magnitude of the consequences C expected). We have evaluated 140 accident sequences that were identified during the analysis of the treatment process. It was identified that 5 sequences are associated with the level of risk is very low, 96 low-risk, high risk and 39 with no very high risk. All accident sequences associated with high risk (considered unacceptable), have an impact on patients, and no concerns workers and public, which reaffirms that major security problems are related to radiation protection of patients. 34 sequences accidental high risk are associated with human errors and failures only 5 to equipment (LINAC, TPS, TAC, etc.). demonstrating the importance of human error. It shows that 35 of the 39 high-risk accident sequences leading to serious or very serious consequences for patients, which would mean the death of one or more patients, making specific recommendations to reduce risk in these cases. The findings of this work and regulators allow users to refine their programs quality assurance and inspection and suggest the hospital management, prioritize material resources according to criteria of irrigation management. (author)

  1. Emerging Infectious Diseases and Blood Safety: Modeling the Transfusion-Transmission Risk.

    Science.gov (United States)

    Kiely, Philip; Gambhir, Manoj; Cheng, Allen C; McQuilten, Zoe K; Seed, Clive R; Wood, Erica M

    2017-07-01

    While the transfusion-transmission (TT) risk associated with the major transfusion-relevant viruses such as HIV is now very low, during the last 20 years there has been a growing awareness of the threat to blood safety from emerging infectious diseases, a number of which are known to be, or are potentially, transfusion transmissible. Two published models for estimating the transfusion-transmission risk from EIDs, referred to as the Biggerstaff-Petersen model and the European Upfront Risk Assessment Tool (EUFRAT), respectively, have been applied to several EIDs in outbreak situations. We describe and compare the methodological principles of both models, highlighting their similarities and differences. We also discuss the appropriateness of comparing results from the two models. Quantitating the TT risk of EIDs can inform decisions about risk mitigation strategies and their cost-effectiveness. Finally, we present a qualitative risk assessment for Zika virus (ZIKV), an EID agent that has caused several outbreaks since 2007. In the latest and largest ever outbreak, several probable cases of transfusion-transmission ZIKV have been reported, indicating that it is transfusion-transmissible and therefore a risk to blood safety. We discuss why quantitative modeling the TT risk of ZIKV is currently problematic. Crown Copyright © 2017. Published by Elsevier Inc. All rights reserved.

  2. Mastery of risks and operating safety, risks and efficiencies

    International Nuclear Information System (INIS)

    2006-01-01

    A proper management of ones risks consists in acting to exert prevention and protection capacities against the negative consequences of an event, but also by committing oneself into an offensive approach allowing to improve efficiency, quality and availability. Safety and efficiencies are mutual reinforcing goals aiming at ensuring the perenniality of industries and services. The implementation of a risk management approach in an industrial environment allows to reach a better reactiveness and to increase the efficiency of a system by the mastery of organization and processes. The activities in concern are those of industries and services: transports, energy and environment, automotive industry, petrochemistry, chemistry, food, space, health, defense industries, telecommunication, mining industry, information systems, textile industry, finances.. The topics approached during this meeting treat of: the relevance of risk-abatement resources with respect to risks criticality; the consistent management of uncertainties with respect to stakes; the mastery of components aging and the expression of aging-dependent availability, maintenance and safety policies; the expression of obsolescence-related renewing policies; the operating safety tools and methods applied to complex and computerized-controlled systems; the integration of social, organizational and human factors in technical decisions and companies management; transverse and global risk analysis and decision-aid approaches; the vigilance culture; crisis anticipation and management; the experience feedback on technical and organisational aspects; efficiency and risk mastery indicators; cost/benefit approach in risk management, and economic intelligence approaches. Nineteen presentations have been selected which deal with the mastery of risks and the operating safety at nuclear facilities. (J.S.)

  3. Legal basis for risk analysis methodology while ensuring food safety in the Eurasian Economic union and the Republic of Belarus

    Directory of Open Access Journals (Sweden)

    E.V. Fedorenko

    2015-09-01

    Full Text Available Health risk analysis methodology is an internationally recognized tool for ensuring food safety. Three main elements of risk analysis are risk assessment, risk management and risk communication to inform the interested parties on the risk, are legislated and implemented in the Eurasian Economic Union and the Republic of Belarus. There is a corresponding organizational and functional framework for the application of risk analysis methodology as in the justification of production safety indicators and the implementation of public health surveillance. Common methodological approaches and criteria for evaluating public health risk are determined, which are used in the development and application of food safety requirements. Risk assessment can be used in justifying the indicators of safety (contaminants, food additives, and evaluating the effectiveness of programs on enrichment of food with micronutrients.

  4. Safety assessment in schools: beyond risk: the role of child psychiatrists and other mental health professionals.

    Science.gov (United States)

    Rappaport, Nancy; Pollack, William S; Flaherty, Lois T; Schwartz, Sarah E O; McMickens, Courtney

    2015-04-01

    This article presents an overview of a comprehensive school safety assessment approach for students whose behavior raises concern about their potential for targeted violence. Case vignettes highlight the features of 2 youngsters who exemplify those seen, the comprehensive nature of the assessment, and the kind of recommendations that enhance a student's safety, connection, well-being; engage families; and share responsibility of assessing safety with the school. Copyright © 2015 Elsevier Inc. All rights reserved.

  5. Assessing reservoir performance risk in CO2 storage projects

    International Nuclear Information System (INIS)

    Bowden, A.R.; Rigg, A.

    2005-01-01

    One of the main issues for researchers involved with geological storage of carbon dioxide (CO 2 ) has been the development of a proper methodology to assess and compare alternative CO 2 injection projects on the basis of risk. Consideration needs to be given to technical aspects, such as the risk of leakage and the effectiveness of the intended reservoir, as well as less tangible aspects such as the value and safety of geological storage of CO 2 , and potential impacts on the community and environment. The Geological Disposal of Carbon Dioxide (GEODISC), was a research program of the Australian Petroleum Cooperative Research Centre which identified 56 potential environmentally sustainable sites for CO 2 injection (ESSCIs) within Australia. Several studies were carried out, involving detailed evaluation of the suitability of 4 selected sites, including Dongara, Petrel, Gippsland and Carnarvon. The GEODISC program included a risk assessment research module which required a complete and quantified risk assessment of CO 2 injection as a storage option. Primary goals were to assess the risk of leakage, to assess the effectiveness of the intended reservoir, and to assess negative consequences to facilitate comparison of alternative sites. This paper discussed the background and risk assessment model. Key performance indicators (KPIs) were also developed to address the purpose of risk assessment. It was concluded that the RISQUE method is an appropriate approach and that potential injection projects can be measured against six KPIs including containment; effectiveness; self-funding potential; wider community benefits; community safety and community amenity. 6 refs., 3 tabs., 3 figs

  6. Harmonization of international risk assessment protocol

    International Nuclear Information System (INIS)

    Toyofuku, Hajime . E-mail toyofuku@nihs.go.jp

    2006-01-01

    For over centuries developments in food production and new food safety management systems in most developed countries have been perceived by many to be efficient in the prevention of food-borne disease. Nevertheless a number of problems remain dominant, one of these being the high level of food-borne microbiological disease which seems, for some pathogens, to have increased over the last decades. The development of an interdisciplinary approach with direct interaction between surveillance and risk analysis systems is described as a potential basis for improved prevention of food-borne disease. Quantitative microbiological risk assessment is a relatively new scientific approach, able to link data from food within the entire food chain and the various data on human disease to provide a clear estimation of risk. Today food safety is one of the WHOs top eleven priorities; the Organization calls for more systematic and aggressive steps to be taken to reduce significantly the risk of microbiological food-borne diseases. Dealing with this challenge is one of the major challenges for the 21st century in regard to food safety, implying a significant re-direction of food microbiology efforts in many parts of the world

  7. The MARINA Risk Assessment Strategy: A Flexible Strategy for Efficient Information Collection and Risk Assessment of Nanomaterials.

    Science.gov (United States)

    Bos, Peter M J; Gottardo, Stefania; Scott-Fordsmand, Janeck J; van Tongeren, Martie; Semenzin, Elena; Fernandes, Teresa F; Hristozov, Danail; Hund-Rinke, Kerstin; Hunt, Neil; Irfan, Muhammad-Adeel; Landsiedel, Robert; Peijnenburg, Willie J G M; Sánchez Jiménez, Araceli; van Kesteren, Petra C E; Oomen, Agnes G

    2015-11-27

    An engineered nanomaterial (ENM) may actually consist of a population of primary particles, aggregates and agglomerates of various sizes. Furthermore, their physico-chemical characteristics may change during the various life-cycle stages. It will probably not be feasible to test all varieties of all ENMs for possible health and environmental risks. There is therefore a need to further develop the approaches for risk assessment of ENMs. Within the EU FP7 project Managing Risks of Nanoparticles (MARINA) a two-phase risk assessment strategy has been developed. In Phase 1 (Problem framing) a base set of information is considered, relevant exposure scenarios (RESs) are identified and the scope for Phase 2 (Risk assessment) is established. The relevance of an RES is indicated by information on exposure, fate/kinetics and/or hazard; these three domains are included as separate pillars that contain specific tools. Phase 2 consists of an iterative process of risk characterization, identification of data needs and integrated collection and evaluation of data on the three domains, until sufficient information is obtained to conclude on possible risks in a RES. Only data are generated that are considered to be needed for the purpose of risk assessment. A fourth pillar, risk characterization, is defined and it contains risk assessment tools. This strategy describes a flexible and efficient approach for data collection and risk assessment which is essential to ensure safety of ENMs. Further developments are needed to provide guidance and make the MARINA Risk Assessment Strategy operational. Case studies will be needed to refine the strategy.

  8. The MARINA Risk Assessment Strategy: A Flexible Strategy for Efficient Information Collection and Risk Assessment of Nanomaterials

    Directory of Open Access Journals (Sweden)

    Peter M. J. Bos

    2015-11-01

    Full Text Available An engineered nanomaterial (ENM may actually consist of a population of primary particles, aggregates and agglomerates of various sizes. Furthermore, their physico-chemical characteristics may change during the various life-cycle stages. It will probably not be feasible to test all varieties of all ENMs for possible health and environmental risks. There is therefore a need to further develop the approaches for risk assessment of ENMs. Within the EU FP7 project Managing Risks of Nanoparticles (MARINA a two-phase risk assessment strategy has been developed. In Phase 1 (Problem framing a base set of information is considered, relevant exposure scenarios (RESs are identified and the scope for Phase 2 (Risk assessment is established. The relevance of an RES is indicated by information on exposure, fate/kinetics and/or hazard; these three domains are included as separate pillars that contain specific tools. Phase 2 consists of an iterative process of risk characterization, identification of data needs and integrated collection and evaluation of data on the three domains, until sufficient information is obtained to conclude on possible risks in a RES. Only data are generated that are considered to be needed for the purpose of risk assessment. A fourth pillar, risk characterization, is defined and it contains risk assessment tools. This strategy describes a flexible and efficient approach for data collection and risk assessment which is essential to ensure safety of ENMs. Further developments are needed to provide guidance and make the MARINA Risk Assessment Strategy operational. Case studies will be needed to refine the strategy.

  9. The use of safety indicators in the assessment of radioactive waste disposal

    International Nuclear Information System (INIS)

    Wingefors, S.; Westerlind, M.; Gera, F.

    1999-01-01

    The most widely used criteria for disposal are limits or constraints on individual dose or risk, and these have been introduced in most national legal frameworks. There is general agreement that future generations have the right to the same level of protection as the current generation. Even if quantitative criteria corresponding to the required level of protection can be (and have been) defined, it is a great challenge to demonstrate compliance with these criteria. The difficulties are to large extent due to the long time-scales needed to be considered in radioactive waste disposal. The future cannot be predicted in detail but instead different scenarios, with different probabilities of occurrence, must be assessed. Some parts of a disposal system can be predicted or analysed with high confidence for very long periods of time, e.g. geological formations, while for example the evolution of the biosphere, and in particular the society, become quite uncertain within less than one thousand years. Thus, there may be considerable uncertainty in doses (or risks) derived from the safety assessment of a repository. Due to these unavoidable uncertainties it is believed advantageous to use multiple approaches in the safety assessment and to identify different indicators for the repository safety ('multiple-lines-of-reasoning'). The most fundamental safety indicators are dose/risk but complementary indicators have been suggested, in particular flux and environmental concentration of radionuclides. This presentation is focussed on fluxes and concentrations as complementary safety indicators. Other safety indicators, e.g. transfer times, are mentioned only briefly

  10. Learning Safety Assessment from Accidents in a University Environment

    DEFF Research Database (Denmark)

    Jensen, Niels; Jørgensen, Sten Bay

    2013-01-01

    This contribution describes how a chemical engineering department started learning from accidents during experimental work and ended up implementing an industrially inspired system for risk assessment of new and existing experimental setups as well as a system for assessing potential risk from...... the chemicals used in the experimental work. These experiences have led to recent developments which focus increasingly on the a theoretical basis for modeling and reasoning on safety as well as operational aspects within a common framework. Presently this framework is being extended with barrier concepts both...

  11. Probabilistic safety assessment goals in Canada

    International Nuclear Information System (INIS)

    Snell, V.G.

    1986-01-01

    CANDU safety philosphy, both in design and in licensing, has always had a strong bias towards quantitative probabilistically-based goals derived from comparative safety. Formal probabilistic safety assessment began in Canada as a design tool. The influence of this carried over later on into the definition of the deterministic safety guidelines used in CANDU licensing. Design goals were further developed which extended the consequence/frequency spectrum of 'acceptable' events, from the two points defined by the deterministic single/dual failure analysis, to a line passing through lower and higher frequencies. Since these were design tools, a complete risk summation was not necessary, allowing a cutoff at low event frequencies while preserving the identification of the most significant safety-related events. These goals gave a logical framework for making decisions on implementing design changes proposed as a result of the Probabilistic Safety Analysis. Performing this analysis became a regulatory requirement, and the design goals remained the framework under which this was submitted. Recently, there have been initiatives to incorporate more detailed probabilistic safety goals into the regulatory process in Canada. These range from far-reaching safety optimization across society, to initiatives aimed at the nuclear industry only. The effectiveness of the latter is minor at very low and very high event frequencies; at medium frequencies, a justification against expenditures per life saved in other industries should be part of the goal setting

  12. Scientific Opinion on Risk Assessment of Synthetic Biology.

    Science.gov (United States)

    Epstein, Michelle M; Vermeire, Theo

    2016-08-01

    In 2013, three Scientific Committees of the European Commission (EC) drafted Scientific Opinions on synthetic biology that provide an operational definition and address risk assessment methodology, safety aspects, environmental risks, knowledge gaps, and research priorities. These Opinions contribute to the international discussions on the risk governance for synthetic biology developments. Copyright © 2016 Elsevier Ltd. All rights reserved.

  13. Pushing and pulling: an assessment tool for occupational health and safety practitioners.

    Science.gov (United States)

    Lind, Carl Mikael

    2018-03-01

    A tool has been developed for supporting practitioners when assessing manual pushing and pulling operations based on an initiative by two global companies in the manufacturing industry. The aim of the tool is to support occupational health and safety practitioners in risk assessment and risk management of pushing and pulling operations in the manufacturing and logistics industries. The tool is based on a nine-multiplier equation that includes a wide range of factors affecting an operator's health risk and capacity in pushing and pulling. These multipliers are based on psychophysical, physiological and biomechanical studies in combination with judgments from an expert group consisting of senior researchers and ergonomists. In order to consider usability, more than 50 occupational health and safety practitioners (e.g., ergonomists, managers, safety representatives and production personnel) participated in the development of the tool. An evaluation by 22 ergonomists supports that the push/pull tool is user friendly in general.

  14. Assessment of food safety practices of food service food handlers (risk assessment data): testing a communication intervention (evaluation of tools).

    Science.gov (United States)

    Chapman, Benjamin; Eversley, Tiffany; Fillion, Katie; Maclaurin, Tanya; Powell, Douglas

    2010-06-01

    Globally, foodborne illness affects an estimated 30% of individuals annually. Meals prepared outside of the home are a risk factor for acquiring foodborne illness and have been implicated in up to 70% of traced outbreaks. The Centers for Disease Control and Prevention has called on food safety communicators to design new methods and messages aimed at increasing food safety risk-reduction practices from farm to fork. Food safety infosheets, a novel communication tool designed to appeal to food handlers and compel behavior change, were evaluated. Food safety infosheets were provided weekly to food handlers in working food service operations for 7 weeks. It was hypothesized that through the posting of food safety infosheets in highly visible locations, such as kitchen work areas and hand washing stations, that safe food handling behaviors of food service staff could be positively influenced. Using video observation, food handlers (n = 47) in eight food service operations were observed for a total of 348 h (pre- and postintervention combined). After the food safety infosheets were introduced, food handlers demonstrated a significant increase (6.7%, P < 0.05, 95% confidence interval) in mean hand washing attempts, and a significant reduction in indirect cross-contamination events (19.6%, P < 0.05, 95% confidence interval). Results of the research demonstrate that posting food safety infosheets is an effective intervention tool that positively influences the food safety behaviors of food handlers.

  15. Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

    International Nuclear Information System (INIS)

    Samanta, P.K.; Kim, I.S.; Vesely, W.E.

    1992-01-01

    Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation

  16. Safety assessment principles for reactor protection systems in the United Kingdom

    International Nuclear Information System (INIS)

    Philp, W.

    1990-01-01

    The duty of Nuclear Installations Inspectorate (NII) is to see that the appropriate standards are developed, achieved and maintained by the plant operators, and to monitor and regulate the safety of the plant by means of its powers under the licence. It does not issue standards or codes of practice for NPPs, but it requires each plant operator to develop its own safety criteria and requirements. The following relevant issues are described: NII assessment principles and societal risks; principles and guidance for the assessment of rector protection systems; assessment of reactor shutdown systems

  17. Safety assessment principles for reactor protection systems in the United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Philp, W

    1990-07-01

    The duty of Nuclear Installations Inspectorate (NII) is to see that the appropriate standards are developed, achieved and maintained by the plant operators, and to monitor and regulate the safety of the plant by means of its powers under the licence. It does not issue standards or codes of practice for NPPs, but it requires each plant operator to develop its own safety criteria and requirements. The following relevant issues are described: NII assessment principles and societal risks; principles and guidance for the assessment of rector protection systems; assessment of reactor shutdown systems.

  18. Risk assessment of medical devices: evaluation of microbiological and toxicological safety

    International Nuclear Information System (INIS)

    Dorpema, J.W.

    1995-01-01

    Safety assessment of medical devices includes sterilization and biological evaluation or biocompatability testing. Sterilization by ETO gas is criticised for their carcinogenic potency or even banned. Mutual acceptance of biological evaluation test results is promoted by a laboratory accreditation and qualification program. (Author)

  19. Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature

    International Nuclear Information System (INIS)

    Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

    1982-10-01

    The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included

  20. A Study on Safety and Risk Assessment of Dangerous Cargo Operations in Oil/Chemical Tankers

    Directory of Open Access Journals (Sweden)

    Cenk ŞAKAR

    2017-12-01

    Full Text Available The safety and risk assessment of dangerous cargo operations in oil and chemical tankers is a necessary process to prevent possible accidents during these operations. Fire and explosion are the major accidents encountered in tanker operations. In this study, a model was constructed through the Fuzzy Bayes Network Method for the probabilistic relationships between the causes of fire and explosion accidents that could occur during the tank cleaning process. The study is composed of two stages. Firstly, the variables that are the subject of the problem and that constitute the graphical structure of the Bayes Networks are identified. Then, expert opinion was sought as the statistical data on accident reports were not recorded properly while identifying the conditional probability of the relationships between the variables. Linguistic variables whose fuzzy membership functions were identified were used in detecting the probabilities. The findings of the sensitivity test revealed that the major reasons that could lead to fire and explosion during the tank cleaning process are ignition sources, reaction and safety culture.

  1. NASA Aviation Safety Program Systems Analysis/Program Assessment Metrics Review

    Science.gov (United States)

    Louis, Garrick E.; Anderson, Katherine; Ahmad, Tisan; Bouabid, Ali; Siriwardana, Maya; Guilbaud, Patrick

    2003-01-01

    The goal of this project is to evaluate the metrics and processes used by NASA's Aviation Safety Program in assessing technologies that contribute to NASA's aviation safety goals. There were three objectives for reaching this goal. First, NASA's main objectives for aviation safety were documented and their consistency was checked against the main objectives of the Aviation Safety Program. Next, the metrics used for technology investment by the Program Assessment function of AvSP were evaluated. Finally, other metrics that could be used by the Program Assessment Team (PAT) were identified and evaluated. This investigation revealed that the objectives are in fact consistent across organizational levels at NASA and with the FAA. Some of the major issues discussed in this study which should be further investigated, are the removal of the Cost and Return-on-Investment metrics, the lack of the metrics to measure the balance of investment and technology, the interdependencies between some of the metric risk driver categories, and the conflict between 'fatal accident rate' and 'accident rate' in the language of the Aviation Safety goal as stated in different sources.

  2. The Development of a Risk Management System in the Field of Industrial Safety in the Republic of Kazakhstan

    Directory of Open Access Journals (Sweden)

    Sergey S. Kudryavtsev

    2018-03-01

    Full Text Available Background: The purpose of the work is to develop a system that allows processing of information for analysis and industrial risk management, to monitor the level of industrial safety and to perform necessary measures aimed at the prevention of accidents, casualties, and development of professional diseases for effective management of industrial safety at hazardous industrial sites. Methods: Risk assessment of accidents and incidents is based on expert evaluations. Based on the lists of criteria parameters and their possible values, provided by the experts, a unified information and analytical database is compiled, which is included in the final interrogation questionnaires. Risk assessment of industrial injuries and occupational diseases is based on statistical methods. Results: The result of the research is the creation of Guidelines for risk management on hazardous industrial sites of the Republic of Kazakhstan. The Guidelines determine the directions and methods of complex assessment of the state of industrial safety and labor protection and they could be applied as methodological basis at the development of preventive measures for emergencies, casualties, and incidents at hazardous industrial sites. Conclusion: Implementation of the information-analytical system of risk level assessment allows to analyze the state of risk of a possible accident at industrial sites, make valid management decisions aimed at the prevention of emergencies, and monitor the effectiveness of accident prevention measures. Keywords: industrial safety, industrial trauma, professional sickness rate, risk assessment, risk management

  3. Aspects regarding explosion risk assessment

    Directory of Open Access Journals (Sweden)

    Părăian Mihaela

    2017-01-01

    Full Text Available Explosive risk occurs in all activities involving flammable substances in the form of gases, vapors, mists or dusts which, in mixture with air, can generate an explosive atmosphere. As explosions can cause human losses and huge material damage, the assessment of the explosion risk and the establishment of appropriate measures to reduce it to acceptable levels according to the standards and standards in force is of particular importance for the safety and health of people and goods.There is no yet a recognized method of assessing the explosion risk, but regardless of the applied method, the likelihood of an explosive atmosphere occurrence has to be determined, together with the occurrence of an efficient ignition source and the magnitude of foreseeable consequences. In assessment processes, consequences analysis has a secondary importance since it’s likely that explosions would always involve considerable damage, starting from important material damages and up to human damages that could lead to death.The purpose of the work is to highlight the important principles and elements to be taken into account for a specific risk assessment. An essential element in assessing the risk of explosion in workplaces where explosive atmospheres may occur is technical installations and personal protective equipment (PPE that must be designed, manufactured, installed and maintained so that they cannot generate a source of ignition. Explosion prevention and protection requirements are governed by specific norms and standards, and a main part of the explosion risk assessment is related to the assessment of the compliance of the equipment / installation with these requirements.

  4. Safety assessment input for site selection - the Swedish example - 59031

    International Nuclear Information System (INIS)

    Andersson, Johan

    2012-01-01

    Svensk Kaernbraenslehantering AB (SKB) has performed comprehensive investigations of two candidate sites for a final repository for Sweden's spent nuclear fuel. In March 2011 SKB decided to submit licence applications for a final repository at Forsmark. Before selection, SKB stated that the site that offers the best prospects for achieving long-term safety in practice would be selected. Based on experiences previous safety assessments, a number of issues related to long-term safety need to be considered in the context of site comparison. The factors include sensitivity to climate change such as periods of permafrost and glaciations, rock mechanics evolution including the potential for thermally induced spalling and sensitivity to potential future earthquakes, current and future groundwater flow, evolution of groundwater composition and proximity to mineral resources. Each of these factors related to long-term safety for the two candidate sites is assessed in a comparative analysis of site characteristics. The assessment also considers differences in biosphere conditions and in the confidence of the site descriptions. The comparison is concluded by an assessment on how the identified differences would affect the estimated radiological risk from a repository located at either of the sites. The assessment concludes that there are a number of safety related site characteristics for which the analyses do not show any decisive differences in terms of implications on safety, between the sites Forsmark and Laxemar. However, the frequency of water conducting fractures at repository depth is much smaller at Forsmark than at Laxemar. This difference, in turn, affects the future stability of the current favourable groundwater composition, which combined with the much higher flows at Laxemar would, for the current repository design, lead to a breach in the safety functions for the buffer and the canister for many more deposition positions at Laxemar than at Forsmark. Thereby

  5. Problems of making decisions with account of risk and safety factors

    Energy Technology Data Exchange (ETDEWEB)

    Larichev, O I

    1987-01-01

    New trends in making decisions on accidents when using large-scale technologies-NPPs, chemical plants etc., are considered. Three main directions in the investigations in this field are distinguished. One of them consists in risk measuring (its perception by people, ways of its quantitative determination). The second direction consists in increasing the safety of large-scale production systems. Here the following questions are considered: risk assessment (the safety standard statement), site selection for new systems, man-machine interaction problems, development of safer technologies, cost benefit safety analysis. The third direction is connected with the problem of accidents and their analysis. This direction includes considering the reasons and process of the accident development, preparing for the possible accidents, monitoring under extreme conditions, accident effect analysis.

  6. Problems of making decisions with account of risk and safety factors

    International Nuclear Information System (INIS)

    Larichev, O.I.

    1987-01-01

    New trends in making decisions on accidents when using large-scale technologies-NPPs, chemical plants etc., are considered. Three main directions in the investigations in this field are distinguished. One of them consists in risk measuring (its perception by people, ways of its quantitative determination). The second direction consists in increasing the safety of large-scale production systems. Here the following questions are considered: risk assessment (the safety standard statement), site selection for new systems, man-machine interaction problems, development of safer technologies, cost benefit safety analysis. The third direction is connected with the problem of accidents and their analysis. This direction includes considering the reasons and process of the accident development, preparing for the possible accidents, monitoring under extreme conditions, accident effect analysis

  7. Discussion about risk-informed regulations on the nuclear safety

    International Nuclear Information System (INIS)

    Gu Yeyi

    2008-01-01

    The article introduces the background and status quo of regulations on the nuclear safety in China, and points out the inadequacies existing with the current regulations. The author explains the risk-informed safety management concerning its development, status quo, and achievements made, in an attempt to make out the trend of improving regulations on the nuclear safety through risk-informed methods. Combining the U.S. development program of establishing risk-informed regulations on the nuclear safety, the author narrates principles and features of the new regulations system, and provides suggestions for the promotion of risk-informed safety management and establishment of risk-informed regulations on the nuclear safety. (author)

  8. Assessment of Safety Culture

    International Nuclear Information System (INIS)

    Bilic Zabric, T.; Kavsek, D.

    2006-01-01

    A strong safety culture leads to more effective conduct of work and a sense of accountability among managers and employees, who should be given the opportunity to expand skills by training. The resources expended would thus result in tangible improvements in working practices and skills, which encourage further improvement of safety culture. In promoting an improved safety culture, NEK has emphasized both national and organizational culture with an appropriate balance of behavioural sciences and quality management systems approaches. In recent years there has been particular emphasis put on an increasing awareness of the contribution that human behavioural sciences can make to develop good safety practices. The purpose of an assessment of safety culture is to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. There is, however, no single approach that is suitable for all purposes and which can measure, simultaneously, all the intangible aspects of safety culture, i.e. the norms, values, beliefs, attitudes or the behaviours reflecting the culture. Various methods have their strengths and weaknesses. To prevent significant performance problems, self-assessment is used. Self-assessment is the process of identifying opportunities for improvement actively or, in some cases, weaknesses that could cause more serious errors or events. Self-assessments are an important input to the corrective action programme. NEK has developed questionnaires for safety culture self-assessment to obtain information that is representative of the whole organization. Questionnaires ensure a greater degree of anonymity, and create a less stressful situation for the respondent. Answers to questions represent the more apparent and conscious values and attitudes of the respondent. NEK proactively co-operates with WANO, INPO, IAEA in the areas of Safety Culture and Human

  9. Innovative Modelling Approach of Safety Culture Assessment in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ahn, N.

    2016-01-01

    A culture is commonly defined as the shared set of norms and values that govern appropriate individual behavior. Safety culture is the subset of organizational culture that reflects the general attitude and approaches to safety and risk management. While safety is sometimes narrowly defined in terms of human death and injury, we use a more inclusive definition that also considers mission loss as a safety problem and is thus applicable to nuclear power plants and missions. The recent accident reports and investigations of the nuclear power plant mission failures (i.e., TMI, Chernobyl, and Fukushima) point to safety cultural problems in nuclear power plants. Many assessment approaches have been developed by organizations such as IAEA and INPO based on the assessment of parameters at separate levels — individuals, groups, and organizations.

  10. Next generation of microbiological risk assessment

    NARCIS (Netherlands)

    Besten, den Heidy M.W.; Amézquita, Alejandro; Bover-Cid, Sara; Dagnas, Stéphane; Ellouze, Mariem; Guillou, Sandrine; Nychas, George; O'Mahony, Cian; Pérez-Rodriguez, Fernando; Membré, Jeanne Marie

    2017-01-01

    In food safety and public health risk evaluations, microbiological exposure assessment plays a central role as it provides an estimation of both the likelihood and the level of the microbial hazard in a specified consumer portion of food and takes microbial behaviour into account. While until now

  11. 77 FR 28406 - Spent Fuel Transportation Risk Assessment

    Science.gov (United States)

    2012-05-14

    ... the release of some quantity of radioactive material during a severe accident. This investigation... assessment, the measure of safety was the risk of radiation doses to the public under routine and accident... assumptions has made the estimate of accident risk from the release of radioactive material in this study...

  12. Preliminary risk assessments of the small HTGR

    International Nuclear Information System (INIS)

    Everline, C.J.; Bellis, E.A.

    1985-05-01

    Preliminary investment and safety risk assessments were performed for a preconceptual design of a four-module 250-MW(t) side-by-side steel-vessel pebble bed HTGR plant. Broad event spectra were analyzed involving component damage resulting in unscheduled plant outages and fission product releases resulting in offsite doses. The preliminary assessment indicates at this stage of the design that two categories of events govern the investment risk envelope: primary coolant leaks which release some circulating and plate-out activity that contaminates the confinement and turbogenerator damage which involves extensive turbine blade failure. Primary coolant leaks are important contributors because associated cleanup and decontamination requirements result in longer outages that arise from other events with comparable frequencies. Turbogenerator damage is the salient low-frequency investment risk accident due to the relatively long outages being experienced in the industry. Thermal transients are unimportant investment risk contributors because pressurized core heatups cause little damage, and depressurized core heatups occur at negligible frequencies relative to the forced outage goal. These preliminary results demonstrate investment and safety risk goal compliance at this stage in the design process. Studies are continuing in order to provide valuable insights into risk-significant events to assure a balanced approach to meeting user and regulatory requirements

  13. Occupational health and safety: Designing and building with MACBETH a value risk-matrix for evaluating health and safety risks

    Science.gov (United States)

    Lopes, D. F.; Oliveira, M. D.; Costa, C. A. Bana e.

    2015-05-01

    Risk matrices (RMs) are commonly used to evaluate health and safety risks. Nonetheless, they violate some theoretical principles that compromise their feasibility and use. This study describes how multiple criteria decision analysis methods have been used to improve the design and the deployment of RMs to evaluate health and safety risks at the Occupational Health and Safety Unit (OHSU) of the Regional Health Administration of Lisbon and Tagus Valley. ‘Value risk-matrices’ (VRMs) are built with the MACBETH approach in four modelling steps: a) structuring risk impacts, involving the construction of descriptors of impact that link risk events with health impacts and are informed by scientific evidence; b) generating a value measurement scale of risk impacts, by applying the MACBETH-Choquet procedure; c) building a system for eliciting subjective probabilities that makes use of a numerical probability scale that was constructed with MACBETH qualitative judgments on likelihood; d) and defining a classification colouring scheme for the VRM. A VRM built with OHSU members was implemented in a decision support system which will be used by OHSU members to evaluate health and safety risks and to identify risk mitigation actions.

  14. Risk as a target of safety research

    International Nuclear Information System (INIS)

    Krueger, W.

    1986-01-01

    Job creation is not the idea behind the demand for risk studies to be intensified in safety research. Risks are not only a target safety research should investigate, they are a subject that actually can be most adequately investigated by safety research. Assuming a neutral position between irrational fears and interest-minded problem minimization, that is the central approach and the ethics of a safety scientist. The Babylonian confusion of terminology experienced after the Chernobyl accident is a good example proving the necessity of fostering the neutral professionalism in safety research. (orig./DG) [de

  15. Probabilistic safety assessment technology for commercial nuclear power plant security evaluation

    International Nuclear Information System (INIS)

    Liming, J.K.; Johnson, D.H.; Dykes, A.A.

    2004-01-01

    Commercial nuclear power plant physical security has received much more intensive treatment and regulatory attention since September 11, 2001. In light of advancements made by the nuclear power industry in the field of probabilistic safety assessment (PSA) for its power plants over that last 30 years, and given the many examples of successful applications of risk-informed regulation at U. S. nuclear power plants during recent years, it may well be advisable to apply a 'risk-informed' approach to security management at nuclear power plants from now into the future. In fact, plant PSAs developed in response to NRC Generic Letter 88-20 and related requirements are used to help define target sets of critical plant safety equipment in our current security exercises for the industry. With reasonable refinements, plant PSAs can be used to identify, analyze, and evaluate reasonable and prudent approaches to address security issues and associated defensive strategies at nuclear power plants. PSA is the ultimate scenario-based approach to risk assessment, and thus provides a most powerful tool in identifying and evaluating potential risk management decisions. This paper provides a summary of observations of factors that are influencing or could influence cost-effective or 'cost-reasonable' security management decision-making in the current political environment, and provides recommendations for the application of PSA tools and techniques to the nuclear power plant operational safety response exercise process. The paper presents a proposed framework for nuclear power plant probabilistic terrorist risk assessment that applies these tools and techniques. (authors)

  16. An Autopsy Checklist: A Monitor of Safety and Risk Management.

    Science.gov (United States)

    Shkrum, Michael James; Kent, Jessica

    2016-09-01

    Any autopsy has safety and risk management issues, which can arise in the preautopsy, autopsy, and postautopsy phases. The London Health Sciences Department of Pathology and Laboratory Medicine Autopsy Checklist was developed to address these issues. The current study assessed 1 measure of autopsy safety: the effectiveness of the checklist in documenting pathologists' communication of the actual or potential risk of blood-borne infections to support staff. Autopsy checklists for cases done in 2012 and 2013 were reviewed. The frequency of communication, as recorded in checklists, by pathologists to staff of previously diagnosed blood-borne infections (hepatitis B/C and human immunodeficiency virus) or the risk of infection based on lifestyle (eg, intravenous drug abuse) was tabulated. These data were compared with medical histories of the deceased and circumstances of their deaths described in the final autopsy reports. Information about blood-borne infections was recorded less frequently in the checklists compared with the final reports. Of 4 known human immunodeficiency virus cases, there was no checklist documentation in 3. All 11 hand injuries were documented. None of these cases had known infectious risks. The Autopsy Checklist is a standardized means of documenting safety and risk issues arising during the autopsy process, but its effectiveness relies on accurate completion.

  17. Safety assessment of HLW geological disposal system

    International Nuclear Information System (INIS)

    Naito, Morimasa

    2006-01-01

    In accordance with the Japanese nuclear program, the liquid waste with a high level of radioactivity arising from reprocessing is solidified in a stable glass matrix (vitrification) in stainless steel fabrication containers. The vitrified waste is referred to as high-level radioactive waste (HLW), and is characterized by very high initial radioactivity which, even though it decreases with time, presents a potential long-term risk. It is therefore necessary to thoroughly manage HLW from human and his environment. After vitrification, HLW is stored for a period of 30 to 50 years to allow cooling, and finally disposed of in a stable geological environment at depths greater than 300 m below surface. The deep underground environment, in general, is considered to be stable over geological timescales compared with surface environment. By selecting an appropriate disposal site, therefore, it is considered to be feasible to isolate the waste in the repository from man and his environment until such time as radioactivity levels have decayed to insignificance. The concept of geological disposal in Japan is similar to that in other countries, being based on a multibarrier system which combines the natural geological environment with engineered barriers. It should be noted that geological disposal concept is based on a passive safety system that does not require any institutional control for assuring long term environmental safety. To demonstrate feasibility of safe HLW repository concept in Japan, following technical steps are essential. Selection of a geological environment which is sufficiently stable for disposal (site selection). Design and installation of the engineered barrier system in a stable geological environment (engineering measures). Confirmation of the safety of the constructed geological disposal system (safety assessment). For site selection, particular consideration is given to the long-term stability of the geological environment taking into account the fact

  18. Team based risk assessment in the South African mining industry

    Energy Technology Data Exchange (ETDEWEB)

    Turner, J.; Ashworth, G.; Webger, S.; Protheroe, B. [CSIR, Auckland Park (South Africa). MineRisk Africa Division

    1996-12-31

    Improved health and safety for the large mining workforce in South Africa is a priority. Risk Assessments will be mandatory following the promulgation of the new health and safety act, due out in mid 1996. There is also a strong demand for employee organizations for participation in regulating the work process, particularly in the aspects of health and safety. The concept of system safety is that safe production is achieved through four ingredients, being, competent and trained personnel working according to appropriate standard operating practices using fit-for-purpose equipment in a well-controlled environment. A deficiency in any one of these areas will lead to an increased chance of operating problems and consequently accidents. The Mine Risk processes for risk assessment and management provide a mechanism for adopting this concept in practical mining operations; they provide a framework for identifying the root cause of safety problems as a basis for defining changes which will contribute significantly towards improving safety. The Mine Risk processes are applied practively and systematically to identify hazards and evaluate the magnitude of the associated risk in a defined aspect of the mining operation using a participative team based approach. The team, whose membership consists of highly experienced personnel drawn from all relevant departments and from positions ranging from manager to operator, then determines practical controls to reduce priority risks to acceptable levels. Team building is a natural product of this process, and should lead to higher productivity levels which is also a cause for concern. By using this process, a number of objectives of all the stakeholders in the South African Mining industry are addressed. 3 tabs.

  19. Safety assessment, safety performance indicators at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Baji, C.; Vamos, G.; Toth, J.

    2001-01-01

    The Paks Nuclear Power Plant has been using different methods of safety assessment (event analysis, self-assessment, probabilistic safety analysis), including performance indicators characterizing both operational and safety performance since the early years of operation of the plant. Regarding the safety performance, the indicators include safety system performance, number of scrams, release of radioactive materials, number of safety significant events, industrial safety indicator, etc. The Paks NPP also reports a set of ten indicators to WANO Performance Indicator Programme which, among others, include safety related indicators as well. However, a more systematic approach to structuring and trending safety indicators is needed so that they can contribute to the enhancement of the operational safety. A more comprehensive set of indicators and a systematic evaluation process was introduced in 1996. The performance indicators framework proposed by the IAEA was adapted to Paks in this year to further improve the process. Safety culture assessment and characterizing safety culture is part of the assessment process. (author)

  20. Risk assessment of pesticides and other stressors in bees: Principles, data gaps and perspectives from the European Food Safety Authority.

    Science.gov (United States)

    Rortais, Agnès; Arnold, Gérard; Dorne, Jean-Lou; More, Simon J; Sperandio, Giorgio; Streissl, Franz; Szentes, Csaba; Verdonck, Frank

    2017-06-01

    Current approaches to risk assessment in bees do not take into account co-exposures from multiple stressors. The European Food Safety Authority (EFSA) is deploying resources and efforts to move towards a holistic risk assessment approach of multiple stressors in bees. This paper describes the general principles of pesticide risk assessment in bees, including recent developments at EFSA dealing with risk assessment of single and multiple pesticide residues and biological hazards. The EFSA Guidance Document on the risk assessment of plant protection products in bees highlights the need for the inclusion of an uncertainty analysis, other routes of exposures and multiple stressors such as chemical mixtures and biological agents. The EFSA risk assessment on the survival, spread and establishment of the small hive beetle, Aethina tumida, an invasive alien species, is provided with potential insights for other bee pests such as the Asian hornet, Vespa velutina. Furthermore, data gaps are identified at each step of the risk assessment, and recommendations are made for future research that could be supported under the framework of Horizon 2020. Finally, the recent work conducted at EFSA is presented, under the overarching MUST-B project ("EU efforts towards the development of a holistic approach for the risk assessment on MUltiple STressors in Bees") comprising a toolbox for harmonised data collection under field conditions and a mechanistic model to assess effects from pesticides and other stressors such as biological agents and beekeeping management practices, at the colony level and in a spatially complex landscape. Future perspectives at EFSA include the development of a data model to collate high quality data to calibrate and validate the model to be used as a regulatory tool. Finally, the evidence collected within the framework of MUST-B will support EFSA's activities on the development of a holistic approach to the risk assessment of multiple stressors in bees. In

  1. Advancing environmental risk assessment for transgenic biofeedstock crops

    Directory of Open Access Journals (Sweden)

    Wolt Jeffrey D

    2009-11-01

    Full Text Available Abstract Transgenic modification of plants is a key enabling technology for developing sustainable biofeedstocks for biofuels production. Regulatory decisions and the wider acceptance and development of transgenic biofeedstock crops are considered from the context of science-based risk assessment. The risk assessment paradigm for transgenic biofeedstock crops is fundamentally no different from that of current generation transgenic crops, except that the focus of the assessment must consider the unique attributes of a given biofeedstock crop and its environmental release. For currently envisioned biofeedstock crops, particular emphasis in risk assessment will be given to characterization of altered metabolic profiles and their implications relative to non-target environmental effects and food safety; weediness and invasiveness when plants are modified for abiotic stress tolerance or are domesticated; and aggregate risk when plants are platforms for multi-product production. Robust risk assessments for transgenic biofeedstock crops are case-specific, initiated through problem formulation, and use tiered approaches for risk characterization.

  2. Managing health and safety risks: Implications for tailoring health and safety management system practices.

    Science.gov (United States)

    Willmer, D R; Haas, E J

    2016-01-01

    As national and international health and safety management system (HSMS) standards are voluntarily accepted or regulated into practice, organizations are making an effort to modify and integrate strategic elements of a connected management system into their daily risk management practices. In high-risk industries such as mining, that effort takes on added importance. The mining industry has long recognized the importance of a more integrated approach to recognizing and responding to site-specific risks, encouraging the adoption of a risk-based management framework. Recently, the U.S. National Mining Association led the development of an industry-specific HSMS built on the strategic frameworks of ANSI: Z10, OHSAS 18001, The American Chemistry Council's Responsible Care, and ILO-OSH 2001. All of these standards provide strategic guidance and focus on how to incorporate a plan-do-check-act cycle into the identification, management and evaluation of worksite risks. This paper details an exploratory study into whether practices associated with executing a risk-based management framework are visible through the actions of an organization's site-level management of health and safety risks. The results of this study show ways that site-level leaders manage day-to-day risk at their operations that can be characterized according to practices associated with a risk-based management framework. Having tangible operational examples of day-to-day risk management can serve as a starting point for evaluating field-level risk assessment efforts and their alignment to overall company efforts at effective risk mitigation through a HSMS or other processes.

  3. A methodology for assessment seismic risk in PSAs

    International Nuclear Information System (INIS)

    Jae, Moo Sung

    2001-01-01

    This paper suggested a new framework for assessing seismic risk in PSAs. The framework used the concepts of requirement and achievement in the reliability physics. The quantified correlation which is a function of the requirement variable (hazard curve) and the achievement variable (fragility curve) results in a quantity, the unconditional frequency of exceeding a damage lelvel. This framework can be applied to any other external safety assessment, such as Fire and Flood Risk in PSAs

  4. New developments in quantitative risk assessment of campylobacteriosis

    DEFF Research Database (Denmark)

    Havelaar, Arie; Nauta, Maarten

    meat to ready-to-eat foods is the main pathway of consumer exposure. Undercooking appears to be of minor importance. However, this conclusion may need to be reconsidered in the light of increasing consumption of minced meat preparations. Five QMRA models have been compared in detail, and detailed......Quantitative microbiological risk assessment (QMRA) is now broadly accepted as an important decision support tool in food safety risk management. It has been used to support decision making at the global level (Codex Alimentarius, FAO and WHO), at the European level (European Food Safety Authority...

  5. Safety assessment of geologic repositories for nuclear waste

    International Nuclear Information System (INIS)

    Bartlett, J.W.; Burkholder, H.C.; Winegardner, W.K.

    1977-01-01

    Consideration of geologic isolation for final disposition of radioactive wastes has led to the need for evaluation of the safety of the concept. Such evaluations require consideration of factors not encountered in conventional risk analysis: consequences at times and places far removed from the repository site; indirect, complex, and alternative pathways between the waste and the point of potential consequences; a highly limited data base; and limited opportunity for experimental verification of results. R and D programs to provide technical safety evaluations are under way. Three methods are being considered for the probabilistic aspects of the evaluations: fault tree analysis, repository simulation analysis, and system stability analysis. Nuclide transport models, currently in a relatively advanced state of development, are used to evaluate consequences of postulated loss of geologic isolation. This paper outlines the safety assessment methods, unique features of the assessment problem that affect selection of methods and reliability of results, and available results. It also discusses potential directions for future work

  6. Use of probabilistic risk assessment in expert system usage for nuclear power plant safety

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1987-01-01

    The introduction of probability risk assessments (PRA's) to nuclear power plants in the Rasmussen Report (WASH-1400) gave us a means of evaluating the risk to the public associated with the operation of nuclear power plants, at least on a relative basis. While the choice of the ''source term'' and methodology in a PRA significantly influence the absolute probability and the consequences of core melt, comparison of two PRA calculations for two configurations of the same plant, carried out on a consistent basis, can be readily identify the increase in risk associated with going from one configuration of a plant to another by removing components or systems from service. This ratio of core melt probabilities (assuming no recovery of failed systems) obtained from two PRA calculations for different configurations was the criterion (called ''risk factor'') chosen as a basis for making a decision in an expert system as to what mitigating action, if any, would be taken to avoid a trip situation from developing. PRISIM was developed by JBF Associates of Knoxville under the sponsorship of the NRC as a system for Resident Inspectors at nuclear power plants to provide them with a relative safety status of the plant under all configurations. PRISIM calculated the risk factor---the ration of core melt probabilities of the plant under the current configuration relative to the normal configuration with all systems functioning---using an algorithm that emulates the results of the original PRA. It also presents time and core melt (assuming no recovery of systems or components)

  7. Research on risk assessment for maritime transport of radioactive materials. Preparation of maritime accident data for risk assessment

    International Nuclear Information System (INIS)

    Odano, Naoteru; Sawada, Ken-ichi; Mochiduki, Hiromitsu; Hirao, Yoshihiro; Asami, Mitsufumi

    2010-01-01

    Maritime transport of radioactive materials has been playing an important role in the nuclear fuel cycle in Japan. Due to recent increase of transported radioactive materials and diversification of transport packages with enlargement of nuclear research, development and utilization, safety securement for maritime transport of radioactive materials is one of important issues in the nuclear fuel cycle. Based squarely on the current circumstances, this paper summarizes discussion on importance of utilization of results of risk assessment for maritime transport of radioactive materials. A plan for development of comprehensive methodology to assess risks in maritime transport of radioactive materials is also described. Preparations of database of maritime accident to be necessary for risk assessment are also summarized. The prepared data could be utilized for future quantitative risk assessment, such as the event trees and fault trees analyses, for maritime transport of radioactive materials. The frequency of severe accident that the package might be damaged is also estimated using prepared data. (author)

  8. Subjective Risk Assessment and Perception in the Greek and English Bakery Industries

    Directory of Open Access Journals (Sweden)

    Evangelos C. Alexopoulos

    2009-01-01

    Full Text Available Several factors influencing risk perception in the area of occupational health and safety are known, but there is still lack of a full understanding of the ways in which people characterize risk. This study aimed to provide an insight of employee risk assessment and perception in the bakery industry. 87 British and 64 Greek employees in two comparable bakery companies were asked to estimate and evaluate hazards at their workplace. The participants' judgments of 12 hazards—according to 7 risk aspects—were collected and analyzed. Subjective assessment on important occupational hazards included handling heavy loads, repetitiveness, high temperatures, high rate of work, stressful deadlines, and noise. Although limited in the population involved, our findings revealed strong cross-national differences in employee risk perception of specific groups of hazards in the bakery industry. Additional interviews revealed evidence that Greek employees' risk perception depends mostly on work experience while British employees were aware of risks due to company health and safety policy, recognizing that safety is the responsibility of both the management and the worker. Cross-national (cultural factors that influence workforce risk perception and attitudes towards safety have to be taken into account by technical experts and policy makers in the designing of prevention strategies and risk communication.

  9. Subjective Risk Assessment and Perception in the Greek and English Bakery Industries

    International Nuclear Information System (INIS)

    Alexopoulos, E.C.; Kavadi, Z.; Bakoyannis, G.; Papantonopoulos, S.

    2010-01-01

    Several factors influencing risk perception in the area of occupational health and safety are known, but there is still lack of a full understanding of the ways in which people characterize risk. This study aimed to provide an insight of employee risk assessment and perception in the bakery industry. 87 British and 64 Greek employees in two comparable bakery companies were asked to estimate and evaluate hazards at their workplace. The participants judgments of 12 hazards according to 7 risk aspects were collected and analyzed. Subjective assessment on important occupational hazards included handling heavy loads, repetitiveness, high temperatures, high rate of work, stressful deadlines, and noise. Although limited in the population involved, our findings revealed strong cross-national differences in employee risk perception of specific groups of hazards in the bakery industry. Additional interviews revealed evidence that Greek employees risk perception depends mostly on work experience while British employees were aware of risks due to company health and safety policy, recognizing that safety is the responsibility of both the management and the worker. Cross-national (cultural) factors that influence workforce risk perception and attitudes towards safety have to be taken into account by technical experts and policy makers in the designing of prevention strategies and risk communication.

  10. Applicability of the Reactor Safety Study (WASH-1400) to LMFBR risk assessments

    International Nuclear Information System (INIS)

    El-Sheikh, K.A.; Feller, K.G.; Fleischer, L.; Greebler, P.; McDonald, A.; Sultan, P.; Temme, M.I.; Fullwood, R.R.

    1976-01-01

    The feasibility of applying the WASH-1400 methods and data to LMFBR risk assessment is evaluated using the following approach for a selected LMFBR: (1) Structuring the LMFBR risk assessment problem in a modular form similar to WASH-1400; (2) Comparing the predictive tools applicable to each module; (3) Comparing the dependencies among the various modules. It is concluded that the WASH-1400 applicability is limited due to LWR-LMFBR differences in operating environments and accident phenomena. WASH-1400 and LMFBR specific methods applicable to LMFBR risk assessments are indicated

  11. Risk and safety perception on urban and rural roads: Effects of environmental features, driver age and risk sensitivity.

    Science.gov (United States)

    Cox, Jolene A; Beanland, Vanessa; Filtness, Ashleigh J

    2017-10-03

    impact changes; however, the effect was larger for urban environments. There were also effects of object type, with certain objects rated as consistently more safety relevant. In urban scenes, changes involving pedestrians were rated significantly more hazardous than all other objects, and in rural scenes, changes involving animals were rated as significantly more hazardous. Notably, hazard ratings were found to be higher in urban compared with rural driving environments, even when changes were matched between environments. This study demonstrates that drivers perceive rural roads as less risky than urban roads, even when similar scenarios occur in both environments. Age did not affect hazard ratings. Instead, the findings suggest that the assessment of risk posed by hazards is influenced more by individual differences in risk sensitivity. This highlights the need for driver education to account for appraisal of hazards' risk and relevance, in addition to hazard detection, when considering factors that promote road safety.

  12. Current status and future expectation concerning probabilistic risk assessment of NPPs. 1. Features and issues of probabilistic risk assessment methodology

    International Nuclear Information System (INIS)

    Yamashita, Masahiro

    2012-01-01

    Probabilistic risk assessment (PRA) of Nuclear Power Plants (NPPs) could play an important role in assuring safety of NPPs. However PRA had not always effectively used, which was indicated in Japanese government's report on Fukushima Daiichi NPP accident. At the Risk Technical Committee (RTC) of Standards Committee of Atomic Energy Society of Japan, preparation of standards (implementing criteria) focusing on PRA methodology and investigation on basic philosophy for use of PRA had been in progress. Based on activities of RTC, a serial in three articles including this described current status and future expectation concerning probabilistic risk assessment of NPPs. This article introduced features and issues of PRA methodology related to the use of PRA. Features of PRA methodology could be shown as (1) systematic and comprehensive understanding of risk, (2) support of grading approach, (3) identification of effective safety upgrade measures and (4) quantitative understanding of effects of uncertainty. Issues of PRA methodology were (1) extension of PRA application area, (2) upgrade of PRA methodology, (3) quality assurance of PRA, (4) treatment of uncertainty and (5) quantitative evaluation criteria. (T. Tanaka)

  13. Experiences in assessing safety culture

    International Nuclear Information System (INIS)

    Spitalnik, J.

    2002-01-01

    Based on several Safety Culture self-assessment applications in nuclear organisations, the paper stresses relevant aspects to be considered when programming an assessment of this type. Reasons for assessing Safety Culture, basic principles to take into account, necessary resources, the importance of proper statistical analyses, the feed-back of results, and the setting up of action plans to enhance Safety Culture are discussed. (author)

  14. New safety performance indicators for safety assessment of radioactive waste disposal facilities. Cuban experience

    International Nuclear Information System (INIS)

    Peralta Vital, J.L.; Castillo, R.G.; Olivera, J.

    2002-01-01

    The paper shows the Cuban experience on implementing geological disposal of radioactive waste and the necessity for identifying new safety performance indicators for the safety assessment (SA) of radioactive waste disposal facilities. The selected indicator was the concentration of natural radioactive elements (U, Ra, Th, K) in the Cuban geologic environment. We have carried out a group of investigations, which have allowed characterising the concentration for the whole Country, creating a wide database where this indicator is associated with the lithology. The main lithologies in Cuba are: the sedimentary rocks (70 percent of national occurrence), which are present in the three regions (limestone and lutite), and finally the igneous and metamorphic rocks. The results show the concentrations ranges of the natural radionuclides associated fundamentally to the variation in the lithology and geographical area of the Country. In Cuba, the higher concentration (ppm) of Uranium and Radium are referenced to the Central region associated to Skarn, while for Thorium (ppm) and Potassium (%), in the East region the concentration peaks in Tuffs have been found. The concentrations ranges obtained are preliminary, they characterise the behaviour of this parameter for the Cuban geology, but they do not represent limits for safety assessment purposes yet. Also other factors should be taken into account as the assessment context, time scales and others assumptions before establishing the final concentration limits for the natural radionuclides as a radiological and nuclear safety performance indicator complementary to dose and risk for safety assessment for radiological and nuclear facilities. (author)

  15. Ex-ante assessment of the safety effects of intelligent transport systems.

    Science.gov (United States)

    Kulmala, Risto

    2010-07-01

    There is a need to develop a comprehensive framework for the safety assessment of Intelligent Transport Systems (ITS). This framework should: (1) cover all three dimensions of road safety-exposure, crash risk and consequence, (2) cover, in addition to the engineering effect, also the effects due to behavioural adaptation and (3) be compatible with the other aspects of state of the art road safety theories. A framework based on nine ITS safety mechanisms is proposed and discussed with regard to the requirements set to the framework. In order to illustrate the application of the framework in practice, the paper presents a method based on the framework and the results from applying that method for twelve intelligent vehicle systems in Europe. The framework is also compared to two recent frameworks applied in the safety assessment of intelligent vehicle safety systems. Copyright 2010 Elsevier Ltd. All rights reserved.

  16. Assessment of Tolerability and Safety of Monocomponent Complementary Food Products in the Diet of Infants With Risk for Allergic Diseases

    Directory of Open Access Journals (Sweden)

    L. S. Namazova-Baranova

    2016-01-01

    Full Text Available Background: Children with burdened allergological history and/or having preliminary allergy manifestations need the effective prevention of allergy from the first months of life.Objective: Our aim was to assess the tolerability, safety, and efficacy of monocomponent complementary food products in the diet of infants with high risk for allergic diseases.Methods: Tolerability, safety, and efficacy of monocomponent complementary food products (vegetable puree, fruit juices, and after 6 months — meat sauce were studied in a singlecentre, prospective, comparative study. The symptoms of indigestion, skin allergy symptoms were registered, the results of coprological research and immunogenicity of complementary food products were assessed.Results: The study included 200 children in the age from 5 months from the risk group of allergy developing. Children were divided into 4 groups of 50 people. It was found that complementary food products were well tolerated and assimilated by children, did not cause skin and gastrointestinal allergic reactions in healthy children with risk of allergy developing. Food antigens of complementary food components (pumpkin, rabbit meat, turkey meat, apples, pears, plums were characterized by low immunogenicity: the level of specific IgE to the specified products did not change in blood serum and remained at a low level at the beginning and at the end of the study (ranging from 0.01 to 0.03 kE/l.Conclusion: Studied complementary food products (vegetable-, fruit- and meat-based can be used in the diet of children with high risk for allergy.

  17. The importance of data collection for timely and accurate risk assessment

    Science.gov (United States)

    Gilsenan, MB

    2017-09-01

    The European Food Safety Authority (EFSA) is responsible for food safety risk assessments at EU level. It provides independent scientific advice on risks associated with the food chain to support EU risk management decisions. Since its establishment, EFSA has amassed a wealth of data to underpin its risk assessments, such as food consumption data, monitoring data and experimental data. Increasing transparency of its risk assessments is a core objective of EFSA. EFSA aims to enhance the quality and transparency of its outputs by giving insofar as possible access to data and methods underpinning its scientific outputs. This paper provides an overview of the role of EFSA, its core data collections and their regulatory framework, as well as data quality and standardisation aspects. Finally, the paper elaborates on EFSA’s 2020 strategy in relation to data, and describes EFSA scientific data warehouse and Knowledge Junction in this regard.

  18. Review insights on the probabilistic risk assessment for the Limerick Generating Station

    International Nuclear Information System (INIS)

    1984-08-01

    In recognition of the high population density around the Limerick Generating Station site and the proposed power level, the Philadelphia Electric Company, in response to NRC staff requests, conducted and submitted between March 1981 and November 1983 a probabilistic risk assessment (PRA) on internal event contributors and a severe accident risk assessment on external event contributors to assess risks posed by operation of the plant. The applicant has developed perspectives using PRA models on the safety profile of the Limerick plant and has altered the plant design to reduce accident vulnerabilities identified in these PRAs. The staff's review of the Limerick PRA has particularly emphasized the dominant accident sequences and the resulting insights into demonstration of compliance with regulatory requirments, unique design features and major plant vulnerabilities to assess the need for any additional measures to further improve the safety of the LGS. The staff's review insights and PRA safety review conclusions are presented in this report

  19. Climate Change Impact Assessment of Dike Safety and Flood Risk in the Vidaa River System

    DEFF Research Database (Denmark)

    Madsen, H.; Sunyer Pinya, Maria Antonia; Larsen, J.

    2013-01-01

    The impact of climate change on the flood risk and dike safety in the Vidaa River system, a cross-border catchment located in the southern part of Jutland, Denmark and northern Germany, is analysed. The river discharges to the Wadden Sea through a tidal sluice, and extreme water level conditions...... in the river system occur in periods of high sea water levels where the sluice is closed and increased catchment run-off take place. Climate model data from the ENSEMBLES data archive are used to assess the changes in climate variables and the resulting effect on catchment run-off. Extreme catchment run......-off is expected to increase about 8 % in 2050 and 14 % in 2100. The changes in sea water level is assessed considering climate projections of mean sea level rise, isostatic changes, and changes in storm surge statistics. At the Vidaa sluice a mean sea level rise of 0.15–0.39 m in 2050 and 0.41–1.11 m in 2010...

  20. Risk assessment of supply chain for pharmaceutical excipients with AHP-fuzzy comprehensive evaluation.

    Science.gov (United States)

    Li, Maozhong; Du, Yunai; Wang, Qiyue; Sun, Chunmeng; Ling, Xiang; Yu, Boyang; Tu, Jiasheng; Xiong, Yerong

    2016-04-01

    As the essential components in formulations, pharmaceutical excipients directly affect the safety, efficacy, and stability of drugs. Recently, safety incidents of pharmaceutical excipients posing seriously threats to the patients highlight the necessity of controlling the potential risks. Hence, it is indispensable for the industry to establish an effective risk assessment system of supply chain. In this study, an AHP-fuzzy comprehensive evaluation model was developed based on the analytic hierarchy process and fuzzy mathematical theory, which quantitatively assessed the risks of supply chain. Taking polysorbate 80 as the example for model analysis, it was concluded that polysorbate 80 for injection use is a high-risk ingredient in the supply chain compared to that for oral use to achieve safety application in clinic, thus measures should be taken to control and minimize those risks.

  1. Edible safety requirements and assessment standards for agricultural genetically modified organisms.

    Science.gov (United States)

    Deng, Pingjian; Zhou, Xiangyang; Zhou, Peng; Du, Zhong; Hou, Hongli; Yang, Dongyan; Tan, Jianjun; Wu, Xiaojin; Zhang, Jinzhou; Yang, Yongcun; Liu, Jin; Liu, Guihua; Li, Yonghong; Liu, Jianjun; Yu, Lei; Fang, Shisong; Yang, Xiaoke

    2008-05-01

    This paper describes the background, principles, concepts and methods of framing the technical regulation for edible safety requirement and assessment of agricultural genetically modified organisms (agri-GMOs) for Shenzhen Special Economic Zone in the People's Republic of China. It provides a set of systematic criteria for edible safety requirements and the assessment process for agri-GMOs. First, focusing on the degree of risk and impact of different agri-GMOs, we developed hazard grades for toxicity, allergenicity, anti-nutrition effects, and unintended effects and standards for the impact type of genetic manipulation. Second, for assessing edible safety, we developed indexes and standards for different hazard grades of recipient organisms, for the influence of types of genetic manipulation and hazard grades of agri-GMOs. To evaluate the applicability of these criteria and their congruency with other safety assessment systems for GMOs applied by related organizations all over the world, we selected some agri-GMOs (soybean, maize, potato, capsicum and yeast) as cases to put through our new assessment system, and compared our results with the previous assessments. It turned out that the result of each of the cases was congruent with the original assessment.

  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. Guidance on the environmental risk assessment of plant pests

    DEFF Research Database (Denmark)

    Baker, R.; Candresse, T.; Dormannsne Simon, E.

    2011-01-01

    The European Food Safety Authority (EFSA) requested the Panel on Plant Health to develop a methodology for assessing the environmental risks posed by harmful organisms that may enter, establish and spread in the European Union. To do so, the Panel first reviewed the methods for assessing...... the environmental risks of plant pests that have previously been used in pest risk assessment. The limitations identified by the review led the Panel to define the new methodology for environmental risk assessment which is described in this guidance document. The guidance is primarily addressed to the EFSA PLH...... (biodiversity) and the functional (ecosystem services) aspects of the environment, this new approach includes methods for assessing both aspects for the first time in a pest risk assessment scheme. A list of questions has been developed for the assessor to evaluate the consequences for structural biodiversity...

  4. Risk-assessment methodology for fast breeder reactors

    International Nuclear Information System (INIS)

    Ott, K.O.

    1976-04-01

    The methods applied or proposed for risk assessment of nuclear reactors are reviewed, particularly with respect to their applicability for risk assessment of future commercial fast breeder reactors. All methods are based on the calculation of accident consequences for relatively few accident scenarios. The role and general impact of uncertainties in fast-reactor accident analysis are discussed. The discussion shows the need for improvement of the methodology. A generalized and improved risk-assessment methodology is outlined and proposed (accident-spectra-progression approach). The generalization consists primarily of an explicit treatment of uncertainties throughout the accident progression. The results of this method are obtained in form of consequence distributions. The width and shape of the distributions depend in part on the superposition of the uncertainties. The first moment of the consequence distribution gives an improved prediction of the ''average'' consequence. The higher-consequence moments can be used for consideration of risk aversion. The assessment of the risk of one or a certain number of nuclear reactors can only provide an ''isolated'' risk assessment. The general problem of safety risk assessment and its relation to public acceptance of certain modes of power production is a much broader problem area, which is also discussed

  5. Assessment of risk of potential exposures on facilities industries

    International Nuclear Information System (INIS)

    Leocadio, Joao Carlos

    2007-03-01

    This work develops a model to evaluate potential exposures on open facilities of industrial radiography in Brazil. This model will decisively contribute to optimize operational, radiological protection and safety procedures, to prevent radiation accidents and to reduce human errors in industrial radiography. The probabilistic safety assessment (PSA) methodology was very useful to assess potential exposures. The open facilities of industrial radiography were identified as the scenario to be analyzed in what concerns the evaluation of potential exposures, due to their high accidents indices. The results of the assessment of potential exposures confirm that the industrial radiography in Brazil is a high-risk practice as classified by the IAEA. The risk of potential exposure was estimated to be 40,5 x 10 -2 per year in Brazil, having as main consequences injuries to the workers' hands and arms. In the world scene, the consequences are worst, leading to fatalities of people, thus emphasizing the high risk of industrial radiography. (author)

  6. The role of hazard- and risk-based approaches in ensuring food safety

    OpenAIRE

    Barlow, Susan M.; Boobis, Alan R.; Bridges, Jim; Cockburn, Andrew; Dekant, Wolfgang; Hepburn, Paul; Houben, Geert F.; König, Jürgen; Nauta, Maarten; Schuermans, Jeroen; Bánáti, Diána

    2015-01-01

    BackgroundFood legislation in the European Union and elsewhere includes both hazard- and risk-based approaches for ensuring safety. In hazard-based approaches, simply the presence of a potentially harmful agent at a detectable level in food is used as a basis for legislation and/or risk management action. Risk-based approaches allow consideration of exposure in assessing whether there may be unacceptable risks to health.Scope and approachThe advantages and disadvantages of hazard- and risk-ba...

  7. Assessing reservoir performance risk in CO{sub 2} storage projects

    Energy Technology Data Exchange (ETDEWEB)

    Bowden, A.R. [URS Corp., San Francisco, CA (United States); Rigg, A. [CRC for Greenhouse Gas Technologies, Canberra (Australia)

    2005-07-01

    One of the main issues for researchers involved with geological storage of carbon dioxide (CO{sub 2}) has been the development of a proper methodology to assess and compare alternative CO{sub 2} injection projects on the basis of risk. Consideration needs to be given to technical aspects, such as the risk of leakage and the effectiveness of the intended reservoir, as well as less tangible aspects such as the value and safety of geological storage of CO{sub 2}, and potential impacts on the community and environment. The Geological Disposal of Carbon Dioxide (GEODISC), was a research program of the Australian Petroleum Cooperative Research Centre which identified 56 potential environmentally sustainable sites for CO{sub 2} injection (ESSCIs) within Australia. Several studies were carried out, involving detailed evaluation of the suitability of 4 selected sites, including Dongara, Petrel, Gippsland and Carnarvon. The GEODISC program included a risk assessment research module which required a complete and quantified risk assessment of CO{sub 2} injection as a storage option. Primary goals were to assess the risk of leakage, to assess the effectiveness of the intended reservoir, and to assess negative consequences to facilitate comparison of alternative sites. This paper discussed the background and risk assessment model. Key performance indicators (KPIs) were also developed to address the purpose of risk assessment. It was concluded that the RISQUE method is an appropriate approach and that potential injection projects can be measured against six KPIs including containment; effectiveness; self-funding potential; wider community benefits; community safety and community amenity. 6 refs., 3 tabs., 3 figs.

  8. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  9. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    International Nuclear Information System (INIS)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-01-01

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  10. Tech assist/fire safety assessment of 100K area facilities

    International Nuclear Information System (INIS)

    Johnson, B.H.

    1994-01-01

    This Tech Assist/Fire Safety Assessment provides a comprehensive assessment of the 100K Area Facilities at the U.S. Department of Energy's Hanford Site for fire protection upgrades that may be needed given the limited remaining service life of these facilities. This assessment considers the relative nature of observed fire risks and whether the installed fire protection systems adequately control this risk. The analysis is based on compliance with DOE Orders, NFPA Codes and Standards, and recognized industry practice. Limited remaining service life (i.e., 6 to 12 years), current value of each facility, comparison to the best protected class of industrial risk, and the potential for exemptions from DOE requirements are key factors for recommendations presented in this report

  11. Application and problems of probability methods in technical safety assessment in the field of nuclear engineering and other technologies

    International Nuclear Information System (INIS)

    Heuser, F.W.

    1980-01-01

    On the basis of a deterministic safety concept that has been developed in nuclear engineering, approaches for a probabilistic interpretation of existing safety requirements and for a further risk assessment are described. The procedures in technical reliability analysis and its application in nuclear engineering are discussed. By the example of a reliability analysis for a reactor protection system the author discusses the question as to what extent methods of reliability analysis can be used to interpret deterministically derived safety requirements. The the author gives a survey of the current value and application of probabilistic reliability assessments in non-nuclear technology. The last part of this report deals with methods of risk analysis and its use for safety assessment in nuclear engineering. On the basis of WASH 1,400 the most important phases and tasks of research work in risk assessment are explained, showing the basic criteria and the methods to be applied in risk analysis. (orig./HSCH) [de

  12. Assessing safety risk in electricity distribution processes using ET & BA improved technique and its ranking by VIKOR and TOPSIS models in fuzzy environment

    OpenAIRE

    S. Rahmani; M. Omidvari

    2016-01-01

    Introduction: Electrical industries are among high risk industries. The present study aimed to assess safety risk in electricity distribution processes using  ET&BA technique and also to compare with both VIKOR & TOPSIS methods in fuzzy environments.   Material and Methods: The present research is a descriptive study and ET&BA worksheet is the main data collection tool. Both Fuzzy TOPSIS and Fuzzy VIKOR methods were used for the worksheet analysis.   Result: Findi...

  13. Food safety in the domestic environment: the effect of consumer risk information on human disease risks.

    Science.gov (United States)

    Nauta, Maarten J; Fischer, Arnout R H; van Asselt, Esther D; de Jong, Aarieke E I; Frewer, Lynn J; de Jonge, Rob

    2008-02-01

    The improvement of food safety in the domestic environment requires a transdisciplinary approach, involving interaction between both the social and natural sciences. This approach is applied in a study on risks associated with Campylobacter on broiler meat. First, some web-based information interventions were designed and tested on participant motivation and intentions to cook more safely. Based on these self-reported measures, the intervention supported by the emotion "disgust" was selected as the most promising information intervention. Its effect on microbial cross-contamination was tested by recruiting a set of participants who prepared a salad with chicken breast fillet carrying a known amount of tracer bacteria. The amount of tracer that could be recovered from the salad revealed the transfer and survival of Campylobacter and was used as a measure of hygiene. This was introduced into an existing risk model on Campylobacter in the Netherlands to assess the effect of the information intervention both at the level of exposure and the level of human disease risk. We showed that the information intervention supported by the emotion "disgust" alone had no measurable effect on the health risk. However, when a behavioral cue was embedded within the instruction for the salad preparation, the risk decreased sharply. It is shown that a transdisciplinary approach, involving research on risk perception, microbiology, and risk assessment, is successful in evaluating the efficacy of an information intervention in terms of human health risks. The approach offers a novel tool for science-based risk management in the area of food safety.

  14. OSART Independent Safety Culture Assessment (ISCA) Guidelines

    International Nuclear Information System (INIS)

    2016-01-01

    Safety culture is understood as an important part of nuclear safety performance. This has been demonstrated by the analysis of significant events such as Chernobyl, Davis Besse, Vandellos II, Asco, Paks, Mihamma and Forsmark, among others. In order to enhance safety culture, one essential activity is to perform assessments. IAEA Safety Standard Series No. GS-R-3, The Management System for Facilitites and Activities, states requirements for continuous improvement of safety culture, of which self, peer and independent safety culture assessments constitute an essential part. In line with this requirement, the Independent Safety Culture Assessment (ISCA) module is offered as an add-on module to the IAEA Operational Safety Review Team (OSART) programme. The OSART programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. By including the ISCA module in an OSART mission, the receiving organization benefits from the synergy between the technical and the safety culture aspects of the safety review. The joint operational safety and safety culture assessment provides the organization with the opportunity to better understand the interactions between technical, human, organizational and cultural aspects, helping the organization to take a systemic approach to safety through identifying actions that fully address the root causes of any identified issue. Safety culture assessments provide insight into the fundamental drivers that shape organizational patterns of behaviour, safety consciousness and safety performance. The complex nature of safety culture means that the analysis of the results of such assessments is not as straightforward as for other types of assessment. The benefits of the results of nuclear safety culture assessments are maximized only if appropriate tools and guidance for these assessments is used; hence, this comprehensive guideline has been developed. The methodology explained

  15. Preliminary results from the application of risk matrix method for safety assessment in industrial radiography

    International Nuclear Information System (INIS)

    Lopez G, A.; Cruz, D.; Truppa, W.; Aravena, M.; Tamayo, B.

    2015-09-01

    Although the uses of ionizing radiation in industry are subject to procedures that provide a high level of safety, experience has shown that equipment failure, human errors, or the combination of both that can trigger accidental exposures may occur. Traditionally, the radiation safety checks whether these industrial practices (industrial radiography, industrial irradiators, among others) are sufficiently safe to prevent similar accidental exposures already occurred, so that becomes dependent on the published information and not always answers questions like: What other events can occur, or what other risks are present? Taking into account the results achieved by the Foro Iberoamericano de Organismos Reguladores Radiologicos y Nucleares, its leading position in the use of techniques of risk analysis in radioactive facilities and the need to develop a proactive approach to the prevention of accidents arising from the use of ionizing radiations in the industry, it intends to apply the risk analysis technique known as Risk Matrix to a hypothetical reference entity for the region in which industrial radiography is performed. In this paper the results of the first stage of this study are shown, that is the identification of initiating events (IE) and barriers that help mitigate the consequences of such IE, so that can appreciate the applicability of this method to industrial radiography services, to reduce the risk to acceptable levels. The fundamental advantage associated with the application of this methodology is that can be applied by the professionals working in the service and identifies specific weaknesses that from the point of view of safety there, so they can be prioritized resources depending on risk reduction. (Author)

  16. Use of risk assessment in the nuclear industry with specific reference to the Australian situation

    International Nuclear Information System (INIS)

    Cameron, R.F.; Willers, A.

    2001-01-01

    The use of risk assessment in the nuclear industry began in the 1970s as a complementary approach to the deterministic methods used to assess the safety of nuclear facilities. As experience with the theory and application of probabilistic methods has grown, so too has its application. In the last decade, the use of probabilistic safety assessment has become commonplace for all phases of the life of a plant, including siting, design, construction, operation and decommissioning. In the particular case of operation of plant, the use of a 'living' safety case or probabilistic safety assessment, building upon operational experience, is becoming more widespread, both as an operational tool and as a basis for communication with the regulator. In the case of deciding upon a site for a proposed reactor, use is also being made of probabilistic methods in defining the effect of design parameters. Going hand in hand with this increased use of risk based methods has been the development of assessment criteria against which to judge the results being obtained from the risk analyses. This paper reviews the use of risk assessment in the light of the need for acceptability criteria and shows how these tools are applied in the Australian nuclear industry, with specific reference to the probabilistic safety assessment (PSA) performed of HIFAR

  17. A methodology for reviewing probabilistic risk assessments

    International Nuclear Information System (INIS)

    Derby, S.L.

    1983-01-01

    The starting point for peer review of a Probabilistic Risk Assessment (PRA) is a clear understanding of how the risk estimate was prepared and of what contributions dominate the calculation. The problem facing the reviewers is how to cut through the complex details of a PRA to gain this understanding. This paper presents a structured, analytical procedure that solves this problem. The effectiveness of this solution is demonstrated by an application on the Zion Probabilistic Safety Study. The procedure found the three dominant initiating events and provided a simplified reconstruction of the calculation of the risk estimate. Significant assessments of uncertainty were also identified. If peer review disputes the accuracy of these judgments, then the revised risk estimate could significantly increase

  18. Implementation of the safety assessment in the practice of industrial radiography

    International Nuclear Information System (INIS)

    Alfonso Pallarés, C.; Pérez Reyes, Y.

    2015-01-01

    The CNSN as regulatory authority has regulatory control processes based on regulations, permits, inspections and limitation to ensure the supervision and control of the practice of industrial radiography. On the other hand in the light of the new regulations approved and being implemented such as: Resolution 334/2011 CITMA 'Regulation on Notification and authorization of practices and activities associated with the use of ionizing radiation sources' and Resolution 17 / 2012, Security Guide: Security Assessment Practices and Activities associated with the use of ionizing radiation (recommendatory), it is necessary for compliance with regulatory requirements concerning the safety assessment. Since 2009 it has been applied this experience in different medical practices and industry, providing a systematic and consistent basis, to the safety assessment of all facilities and activities, which has helped increase the confidence that has been achieved an adequate level of security. The work was able to identify that there is a group of barriers operating in the risk reduction in various accident sequences and therefore have a relative importance in risk reduction, recommendations in this regard to improve the program management of safety in the practice of industrial radiography. [es

  19. Risk Communication: A Key for Fostering a More Resilient Safety Culture

    International Nuclear Information System (INIS)

    Nishizawa, M.

    2016-01-01

    It is widely agreed that the accident of the Fukushima Daiichi nuclear power plant was not only triggered by natural events combined with technical failures, but was a human induced disaster. From the bitter lessons, we have learned that human and organizational factors associated with emergency planning, response and decision-making for nuclear safety need to be more carefully reviewed and enhanced. Elements of social sciences, especially, risk management and risk communication here play a key role. Risk communication is an established concept within risk analysis frameworks. It is a vital tool to convey the meaning of scientific assessment and risk management, share safety related information, and exchange views and values amongst varying stakeholder groups. Risk communication aims at building trust through this process and human interactions. However, it would not be an overstatement that the essence of risk communication is not fully understood. As a result, it is either partially integrated into risk management practice or remains unconducive. The marginalisation of risk communication is observed in a variety of risk communication practices, or more evidently, in perception gaps between lays and experts about risks.

  20. Correlation between safety climate and contractor safety assessment programs in construction.

    Science.gov (United States)

    Sparer, Emily H; Murphy, Lauren A; Taylor, Kathryn M; Dennerlein, Jack T

    2013-12-01

    Contractor safety assessment programs (CSAPs) measure safety performance by integrating multiple data sources together; however, the relationship between these measures of safety performance and safety climate within the construction industry is unknown. Four hundred and one construction workers employed by 68 companies on 26 sites and 11 safety managers employed by 11 companies completed brief surveys containing a nine-item safety climate scale developed for the construction industry. CSAP scores from ConstructSecure, Inc., an online CSAP database, classified these 68 companies as high or low scorers, with the median score of the sample population as the threshold. Spearman rank correlations evaluated the association between the CSAP score and the safety climate score at the individual level, as well as with various grouping methodologies. In addition, Spearman correlations evaluated the comparison between manager-assessed safety climate and worker-assessed safety climate. There were no statistically significant differences between safety climate scores reported by workers in the high and low CSAP groups. There were, at best, weak correlations between workers' safety climate scores and the company CSAP scores, with marginal statistical significance with two groupings of the data. There were also no significant differences between the manager-assessed safety climate and the worker-assessed safety climate scores. A CSAP safety performance score does not appear to capture safety climate, as measured in this study. The nature of safety climate in construction is complex, which may be reflective of the challenges in measuring safety climate within this industry. Am. J. Ind. Med. 56:1463-1472, 2013. © 2013 Wiley Periodicals, Inc. © 2013 Wiley Periodicals, Inc.

  1. Probabilistic risk assessment for new and existing chemicals: Example calculations

    NARCIS (Netherlands)

    Jager T; Hollander HA den; Janssen GB; Poel P van der; Rikken MGJ; Vermeire TG; ECO; CSR; LAE; CSR

    2000-01-01

    In the risk assessment methods for new and existing chemicals in the EU, "risk" is characterised by means of the deterministic quotient of exposure and effects (PEC/PNEC or Margin of Safety). From a scientific viewpoint, the uncertainty in the risk quotient should be accounted for explicitly in the

  2. Interim main report of the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan [and others

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection in chapter 8

  3. Interim main report of the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Hedin, Allan

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10 -6 for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection in chapter 8. Hydrogeological

  4. Getting fire risk assessment right.

    Science.gov (United States)

    Charters, David

    2012-06-01

    The NHS has one of the world's largest and most varied estates, which at any time accommodates many of the most dependent people in society. With around 6,000 fires occurring in NHS premises each year, its duty of care--and that of other healthcare providers--demands very close attention to fire safety. Here Dr David Charters BSc, PhD, CEng, FIFireE, MIMechE, MSFPE, director of Fire Engineering at BRE Global, an independent third party approvals body offering certification of fire, security, and sustainability products and services, examines the critical role of fire risk assessment, and explains why the process should provide the 'foundation' for effective fire safety measures.

  5. Development and application of a living probabilistic safety assessment tool: Multi-objective multi-dimensional optimization of surveillance requirements in NPPs considering their ageing

    International Nuclear Information System (INIS)

    Kančev, Duško; Čepin, Marko; Gjorgiev, Blaže

    2014-01-01

    The benefits of utilizing the probabilistic safety assessment towards improvement of nuclear power plant safety are presented in this paper. Namely, a nuclear power plant risk reduction can be achieved by risk-informed optimization of the deterministically-determined surveillance requirements. A living probabilistic safety assessment tool for time-dependent risk analysis on component, system and plant level is developed. The study herein focuses on the application of this living probabilistic safety assessment tool as a computer platform for multi-objective multi-dimensional optimization of the surveillance requirements of selected safety equipment seen from the aspect of the risk-informed reasoning. The living probabilistic safety assessment tool is based on a newly developed model for calculating time-dependent unavailability of ageing safety equipment within nuclear power plants. By coupling the time-dependent unavailability model with a commercial software used for probabilistic safety assessment modelling on plant level, the frames of the new platform i.e. the living probabilistic safety assessment tool are established. In such way, the time-dependent core damage frequency is obtained and is further on utilized as first objective function within a multi-objective multi-dimensional optimization case study presented within this paper. The test and maintenance costs are designated as the second and the incurred dose due to performing the test and maintenance activities as the third objective function. The obtained results underline, in general, the usefulness and importance of a living probabilistic safety assessment, seen as a dynamic probabilistic safety assessment tool opposing the conventional, time-averaged unavailability-based, probabilistic safety assessment. The results of the optimization, in particular, indicate that test intervals derived as optimal differ from the deterministically-determined ones defined within the existing technical specifications

  6. Safety assessment of nuclear medicine practice using the Risk Matrix Method

    International Nuclear Information System (INIS)

    Cruz, Dumenigo; Cruz, Yoanis; Soler, Karen; Guerrero, Mayka

    2013-01-01

    This paper presents the main results from the application of the methodology of Risk Matrices in a hypothetical service / department of the Nuclear medicine that realize metabolic radiotherapy treatment and diagnostic studies with 131 I and 99 m Tc and 18 F. We could identify major equipment failures and human errors that could potentially lead to a accident in practice. For each analyzed initiating events evaluated the frequency of occurrence, identified key existing defenses to avoid the accident and assessed the potential consequences of an accident if this comes to fruition. With this methodology we could identify which accident sequences increased risk and to propose means to reduce the risk in such cases. As a result of this work was developed the 'RMA Nuclear Medicine' computer tools that will apply this methodology in nuclear medicine services that need to do similar risk assessments

  7. WE-B-BRC-00: Concepts in Risk-Based Assessment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-15

    Prospective quality management techniques, long used by engineering and industry, have become a growing aspect of efforts to improve quality management and safety in healthcare. These techniques are of particular interest to medical physics as scope and complexity of clinical practice continue to grow, thus making the prescriptive methods we have used harder to apply and potentially less effective for our interconnected and highly complex healthcare enterprise, especially in imaging and radiation oncology. An essential part of most prospective methods is the need to assess the various risks associated with problems, failures, errors, and design flaws in our systems. We therefore begin with an overview of risk assessment methodologies used in healthcare and industry and discuss their strengths and weaknesses. The rationale for use of process mapping, failure modes and effects analysis (FMEA) and fault tree analysis (FTA) by TG-100 will be described, as well as suggestions for the way forward. This is followed by discussion of radiation oncology specific risk assessment strategies and issues, including the TG-100 effort to evaluate IMRT and other ways to think about risk in the context of radiotherapy. Incident learning systems, local as well as the ASTRO/AAPM ROILS system, can also be useful in the risk assessment process. Finally, risk in the context of medical imaging will be discussed. Radiation (and other) safety considerations, as well as lack of quality and certainty all contribute to the potential risks associated with suboptimal imaging. The goal of this session is to summarize a wide variety of risk analysis methods and issues to give the medical physicist access to tools which can better define risks (and their importance) which we work to mitigate with both prescriptive and prospective risk-based quality management methods. Learning Objectives: Description of risk assessment methodologies used in healthcare and industry Discussion of radiation oncology

  8. WE-B-BRC-01: Current Methodologies in Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Rath, F. [University of Wisconsin Madison (United States)

    2016-06-15

    Prospective quality management techniques, long used by engineering and industry, have become a growing aspect of efforts to improve quality management and safety in healthcare. These techniques are of particular interest to medical physics as scope and complexity of clinical practice continue to grow, thus making the prescriptive methods we have used harder to apply and potentially less effective for our interconnected and highly complex healthcare enterprise, especially in imaging and radiation oncology. An essential part of most prospective methods is the need to assess the various risks associated with problems, failures, errors, and design flaws in our systems. We therefore begin with an overview of risk assessment methodologies used in healthcare and industry and discuss their strengths and weaknesses. The rationale for use of process mapping, failure modes and effects analysis (FMEA) and fault tree analysis (FTA) by TG-100 will be described, as well as suggestions for the way forward. This is followed by discussion of radiation oncology specific risk assessment strategies and issues, including the TG-100 effort to evaluate IMRT and other ways to think about risk in the context of radiotherapy. Incident learning systems, local as well as the ASTRO/AAPM ROILS system, can also be useful in the risk assessment process. Finally, risk in the context of medical imaging will be discussed. Radiation (and other) safety considerations, as well as lack of quality and certainty all contribute to the potential risks associated with suboptimal imaging. The goal of this session is to summarize a wide variety of risk analysis methods and issues to give the medical physicist access to tools which can better define risks (and their importance) which we work to mitigate with both prescriptive and prospective risk-based quality management methods. Learning Objectives: Description of risk assessment methodologies used in healthcare and industry Discussion of radiation oncology

  9. WE-B-BRC-01: Current Methodologies in Risk Assessment

    International Nuclear Information System (INIS)

    Rath, F.

    2016-01-01

    Prospective quality management techniques, long used by engineering and industry, have become a growing aspect of efforts to improve quality management and safety in healthcare. These techniques are of particular interest to medical physics as scope and complexity of clinical practice continue to grow, thus making the prescriptive methods we have used harder to apply and potentially less effective for our interconnected and highly complex healthcare enterprise, especially in imaging and radiation oncology. An essential part of most prospective methods is the need to assess the various risks associated with problems, failures, errors, and design flaws in our systems. We therefore begin with an overview of risk assessment methodologies used in healthcare and industry and discuss their strengths and weaknesses. The rationale for use of process mapping, failure modes and effects analysis (FMEA) and fault tree analysis (FTA) by TG-100 will be described, as well as suggestions for the way forward. This is followed by discussion of radiation oncology specific risk assessment strategies and issues, including the TG-100 effort to evaluate IMRT and other ways to think about risk in the context of radiotherapy. Incident learning systems, local as well as the ASTRO/AAPM ROILS system, can also be useful in the risk assessment process. Finally, risk in the context of medical imaging will be discussed. Radiation (and other) safety considerations, as well as lack of quality and certainty all contribute to the potential risks associated with suboptimal imaging. The goal of this session is to summarize a wide variety of risk analysis methods and issues to give the medical physicist access to tools which can better define risks (and their importance) which we work to mitigate with both prescriptive and prospective risk-based quality management methods. Learning Objectives: Description of risk assessment methodologies used in healthcare and industry Discussion of radiation oncology

  10. WE-B-BRC-00: Concepts in Risk-Based Assessment

    International Nuclear Information System (INIS)

    2016-01-01

    Prospective quality management techniques, long used by engineering and industry, have become a growing aspect of efforts to improve quality management and safety in healthcare. These techniques are of particular interest to medical physics as scope and complexity of clinical practice continue to grow, thus making the prescriptive methods we have used harder to apply and potentially less effective for our interconnected and highly complex healthcare enterprise, especially in imaging and radiation oncology. An essential part of most prospective methods is the need to assess the various risks associated with problems, failures, errors, and design flaws in our systems. We therefore begin with an overview of risk assessment methodologies used in healthcare and industry and discuss their strengths and weaknesses. The rationale for use of process mapping, failure modes and effects analysis (FMEA) and fault tree analysis (FTA) by TG-100 will be described, as well as suggestions for the way forward. This is followed by discussion of radiation oncology specific risk assessment strategies and issues, including the TG-100 effort to evaluate IMRT and other ways to think about risk in the context of radiotherapy. Incident learning systems, local as well as the ASTRO/AAPM ROILS system, can also be useful in the risk assessment process. Finally, risk in the context of medical imaging will be discussed. Radiation (and other) safety considerations, as well as lack of quality and certainty all contribute to the potential risks associated with suboptimal imaging. The goal of this session is to summarize a wide variety of risk analysis methods and issues to give the medical physicist access to tools which can better define risks (and their importance) which we work to mitigate with both prescriptive and prospective risk-based quality management methods. Learning Objectives: Description of risk assessment methodologies used in healthcare and industry Discussion of radiation oncology

  11. FLIGHT SAFETY CONTROL OF THE BASIS OF UNCERTAIN RISK EVALUATION WITH NON-ROUTINE FLIGHT CONDITIONS INVOLVED

    Directory of Open Access Journals (Sweden)

    2016-01-01

    Full Text Available The article deals with methods of forecasting the level of aviation safety operation of aircraft systems on the basis of methods of evaluation the risks of negative situations as a consequence of a functional loss of initial properties of the system with critical violations of standard modes of the aircraft. Mathematical Models of Risks as a Danger Measure of Discrete Random Events in Aviation Systems are presented. Technological Schemes and Structure of Risk Control Proce- dures without the Probability are illustrated as Methods of Risk Management System in Civil Aviation. The assessment of the level of safety and quality and management of aircraft, made not only from the standpoint of reliability (quality and consumer properties, but also from the position of ICAO on the basis of a risk-based approach. According to ICAO, the security assessment is performed by comparing the calculated risk with an acceptable level. The approach justifies the use of qualitative evaluation techniques safety in the forms of proactive forecasted and predictive risk management adverse impacts to aviation operations of various kinds, including the space sector and nuclear energy. However, for the events such as accidents and disasters, accidents with the aircraft, fighters in a training flight, during the preparation of the pilots on the training aircraft, etc. there is no required statistics. Density of probability distribution (p. d. f. of these events are only hypothetical, unknown with "hard tails" that completely eliminates the application of methods of confidence intervals in the traditional approaches to the assessment of safety in the form of the probability analysis.

  12. Dealing with uncertainty arising out of probabilistic risk assessment

    International Nuclear Information System (INIS)

    Solomon, K.A.; Kastenberg, W.E.; Nelson, P.F.

    1984-03-01

    In addressing the area of safety goal implementation, the question of uncertainty arises. This report suggests that the Nuclear Regulatory Commission (NRC) should examine how other regulatory organizations have addressed the issue. Several examples are given from the chemical industry, and comparisons are made to nuclear power risks. Recommendations are made as to various considerations that the NRC should require in probabilistic risk assessments in order to properly treat uncertainties in the implementation of the safety goal policy. 40 references, 7 figures, 5 tables

  13. Risk assessment of carcinogens in food

    International Nuclear Information System (INIS)

    Barlow, Susan; Schlatter, Josef

    2010-01-01

    Approaches for the risk assessment of carcinogens in food have evolved as scientific knowledge has advanced. Early methods allowed little more than hazard identification and an indication of carcinogenic potency. Evaluation of the modes of action of carcinogens and their broad division into genotoxic and epigenetic (non-genotoxic, non-DNA reactive) carcinogens have played an increasing role in determining the approach followed and provide possibilities for more detailed risk characterisation, including provision of quantitative estimates of risk. Reliance on experimental animal data for the majority of risk assessments and the fact that human exposures to dietary carcinogens are often orders of magnitude below doses used in experimental studies has provided a fertile ground for discussion and diverging views on the most appropriate way to offer risk assessment advice. Approaches used by national and international bodies differ, with some offering numerical estimates of potential risks to human health, while others express considerable reservations about the validity of quantitative approaches requiring extrapolation of dose-response data below the observed range and instead offer qualitative advice. Recognising that qualitative advice alone does not provide risk managers with information on which to prioritise the need for risk management actions, a 'margin of exposure' approach for substances that are both genotoxic and carcinogenic has been developed, which is now being used by the World Health Organization and the European Food Safety Authority. This review describes the evolution of risk assessment advice on carcinogens and discusses examples of ways in which carcinogens in food have been assessed in Europe.

  14. Risk assessment of carcinogens in food.

    Science.gov (United States)

    Barlow, Susan; Schlatter, Josef

    2010-03-01

    Approaches for the risk assessment of carcinogens in food have evolved as scientific knowledge has advanced. Early methods allowed little more than hazard identification and an indication of carcinogenic potency. Evaluation of the modes of action of carcinogens and their broad division into genotoxic and epigenetic (non-genotoxic, non-DNA reactive) carcinogens have played an increasing role in determining the approach followed and provide possibilities for more detailed risk characterisation, including provision of quantitative estimates of risk. Reliance on experimental animal data for the majority of risk assessments and the fact that human exposures to dietary carcinogens are often orders of magnitude below doses used in experimental studies has provided a fertile ground for discussion and diverging views on the most appropriate way to offer risk assessment advice. Approaches used by national and international bodies differ, with some offering numerical estimates of potential risks to human health, while others express considerable reservations about the validity of quantitative approaches requiring extrapolation of dose-response data below the observed range and instead offer qualitative advice. Recognising that qualitative advice alone does not provide risk managers with information on which to prioritise the need for risk management actions, a "margin of exposure" approach for substances that are both genotoxic and carcinogenic has been developed, which is now being used by the World Health Organization and the European Food Safety Authority. This review describes the evolution of risk assessment advice on carcinogens and discusses examples of ways in which carcinogens in food have been assessed in Europe.

  15. Review on the assessment of safety and risks

    Energy Technology Data Exchange (ETDEWEB)

    Leiber, C.O. [Fraunhofer-Institut fuer Chemische Technologie (ICT), Pfinztal (Germany); Doherty, R.M. [Naval Surface Warfare Center, Indian Head, MD (United States)

    2001-12-01

    Historically explosion accidents are linked with energetic materials. There is the further belief, that the proneness to accidents-and their severity-is linked with the sensitivity of these explosives. Consequently there exist seemingly very insensitive materials for which it is believed that their accidental explosion can be ignored, so that safety distances can be reduced to those that apply to materials for which the hazard is assumed to be mass fire rather than mass detonation. Evidence is presented here that shows these assumptions to be invalid. Reports of explosion accidents are gathered here for substances that are not generally considered to be explosives (non UN-class 1 substances, like ammonium nitrate (AN), neat alkali metal chlorates, and even hypochlorites and nitromethane). In most of these cases the proneness of accidents had not been foreseen by testing. The basic explosion mechanisms are of a more general nature than simply those that apply to high explosives. Explosion is not solely a matter of energy, but of any physical power conversion. In order to prove this, a survey of explosion events is given: Natural events, like the impacts of celestial bodies and volcanic erptions. Fuel/liquid interactions in nature are industrial risks too, which occur at very different occasions and sites: Cellulose processing, the oil industry, foundries, power stations, explosions of hot cinders, chemical processing, fire extinguishing, and (most common) in the kitchen, and (most catastrophic) in nuclear reactors. Explosions of similar type are Hydraulic Transients, Bubble resonance explosions with the possibility of associated chemical room explosions (BLEVE), Rollovers. Second order effects are sorption/desorption resonance explosions, which most powerful also occur in nat