Use of risk information to safety regulation. Fabrication facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

A procedure of ISA (Integrated Safety Analysis) for uranium fuel fabrication/enrichment facilities has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. There are two major activities in the year. First one is a study on ISA procedure for external events such as earthquakes. Second one is that for chemical consequences such as UF6 and HF. Other than the activities a fundamental study on a policy of utilizing risk information was conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

A direction to adopting risk-informed and performance-based regulation (RIPBR) in Korea

International Nuclear Information System (INIS)

Kim, W.S.; Sung, K.Y.; Lee, C.J.; Choi, Y.H.; Choi, Y.S.; Kim, H.J.

2004-01-01

The USNRC has pursued the incorporation of new regulatory approach of risk-informed and performance-based regulation (RIPBR) into nuclear safety regulation, as an alternative to improve existing nuclear safety regulation of nuclear power plants, which is deterministic and prescriptive. It focuses on the use of risk insight from probabilistic safety assessment (PSA). Recently, it becomes necessary to find a way to improve regulatory efficiency and effectiveness in order to cover the increasing regulatory needs in Korea. Also, the utility has optimized design and operation of the plant using PSA insight and equipment performance information. According to the increase of the necessity for regulatory improvement using risk and performance information, KINS (Korea Institute of Nuclear Safety) is developing, as a part of mid- and long-term project of Nuclear development program, how to adopt the RIPBR in Korean nuclear regulation. This paper presents the interim result of the study that comprises the assessment of feasibility to adopt the RIPBR, and basic directions and principles for implementing RIPBR model. It is concluded that adopting RIPBR is essential for risk management of the plant, public acceptance to nuclear safety, improvement of existing regulation, minimization of unnecessary regulatory burden, and effective use of regulatory resources, etc. Three basic directions and several principles that are necessary to implement RIPBR model are identified from the study. The application of the directions and principles to the assessment of RIPBR model to be established in the near future is expected to result in making the adoption of new regulatory system more objective and consistent. (authors)

FOOD SAFETY REGULATIONS BASED ON REAL SCIENCE

Directory of Open Access Journals (Sweden)

Huub LELIEVELD

2015-10-01

Full Text Available Differences in regulations result in needless destruction of safe food and hamper food trade. The differences are not just the result of the history of food safety regulations, often developed in times before global cooperation, but are also built in new regulations. It may be responses to media hypes or for other reasons, but in most cases the differences cannot be justified scientifically. A major difficulty is that, due to the developments in analytical techniques the number of chemicals that are found in food is increasing rapidly and chemicals are always suspected to be a safety risk. By far most chemicals are of natural origin but could not be detected in the past because the methods available in the past were not sensitive enough. Demanding the absence of chemicals because the risk they present is unknown, however, would eventually make all food unacceptable. The general public should be shown that everything they eat is chemical, and all food components will be toxic if the amount is too high. It should also be shown that many of these chemicals will also cause illness and death if there is not enough of it as is the case with vitamins and minerals.

Risk-based regulation: Challenges and opportunities

International Nuclear Information System (INIS)

Bari, R.A.

1995-01-01

Over the last twenty years, man has witnessed a gradual but steady movement toward increased usage of risk-based methods and results in the regulatory process. The ''risk perspective'' as a supportive view to existing (non-risk-based or deterministic) information used in decision making has a firm foothold now in most countries that regulate nuclear power. Furthermore, in the areas outside the nuclear power field, such as health risk assessment, risk-based information is used increasingly to make decisions on potential impacts of chemical, biological, and radiological exposures. Some of the principal concepts and issues that are pertinent to risk-based regulation are reviewed. There is a growing interest in most countries in the use of risk-based methods and results to facilitate decision-making associated with regulatory processes. A summary is presented of the challenges and opportunities related to expanded use of risk-based regulation

A Study on the Estimation Method of Risk Based Area for Jetty Safety Monitoring

Directory of Open Access Journals (Sweden)

Byeong-Wook Nam

2015-09-01

Full Text Available Recently, the importance of safety-monitoring systems was highlighted by the unprecedented collision between a ship and a jetty in Yeosu. Accordingly, in this study, we introduce the concept of risk based area and develop a methodology for a jetty safety-monitoring system. By calculating the risk based areas for a ship and a jetty, the risk of collision was evaluated. To calculate the risk based areas, we employed an automatic identification system for the ship, stopping-distance equations, and the regulation velocity near the jetty. In this paper, we suggest a risk calculation method for jetty safety monitoring that can determine the collision probability in real time and predict collisions using the amount of overlap between the two calculated risk based areas. A test was conducted at a jetty control center at GS Caltex, and the effectiveness of the proposed risk calculation method was verified. The method is currently applied to the jetty-monitoring system at GS Caltex in Yeosu for the prevention of collisions.

Risk based limits for Operational Safety Requirements

International Nuclear Information System (INIS)

Cappucci, A.J. Jr.

1993-01-01

OSR limits are designed to protect the assumptions made in the facility safety analysis in order to preserve the safety envelope during facility operation. Normally, limits are set based on ''worst case conditions'' without regard to the likelihood (frequency) of a credible event occurring. In special cases where the accident analyses are based on ''time at risk'' arguments, it may be desirable to control the time at which the facility is at risk. A methodology has been developed to use OSR limits to control the source terms and the times these source terms would be available, thus controlling the acceptable risk to a nuclear process facility. The methodology defines a new term ''gram-days''. This term represents the area under a source term (inventory) vs time curve which represents the risk to the facility. Using the concept of gram-days (normalized to one year) allows the use of an accounting scheme to control the risk under the inventory vs time curve. The methodology results in at least three OSR limits: (1) control of the maximum inventory or source term, (2) control of the maximum gram-days for the period based on a source term weighted average, and (3) control of the maximum gram-days at the individual source term levels. Basing OSR limits on risk based safety analysis is feasible, and a basis for development of risk based limits is defensible. However, monitoring inventories and the frequencies required to maintain facility operation within the safety envelope may be complex and time consuming

Use of risk information to safety regulation. Reprocessing facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

Safety risk management of underground engineering in China: Progress, challenges and strategies

Directory of Open Access Journals (Sweden)

Qihu Qian

2016-08-01

Full Text Available Underground construction in China is featured by large scale, high speed, long construction period, complex operation and frustrating situations regarding project safety. Various accidents have been reported from time to time, resulting in serious social impact and huge economic loss. This paper presents the main progress in the safety risk management of underground engineering in China over the last decade, i.e. (1 establishment of laws and regulations for safety risk management of underground engineering, (2 implementation of the safety risk management plan, (3 establishment of decision support system for risk management and early-warning based on information technology, and (4 strengthening the study on safety risk management, prediction and prevention. Based on the analysis of the typical accidents in China in the last decade, the new challenges in the safety risk management for underground engineering are identified as follows: (1 control of unsafe human behaviors; (2 technological innovation in safety risk management; and (3 design of safety risk management regulations. Finally, the strategies for safety risk management of underground engineering in China are proposed in six aspects, i.e. the safety risk management system and policy, law, administration, economy, education and technology.

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.

Risk based maintenance to increase safety and decrease costs

International Nuclear Information System (INIS)

Phillips, J.H.

2000-01-01

Risk-Based techniques have been developed for commercial nuclear power plants for the last eight years by a team working through the ASME Center for Research and Technology Development (CRTD). System boundaries and success criteria is defined using the Probabilistic Risk Analysis or Probabilistic Safety Analysis developed to meet the Individual Plant Evaluation. Final ranking of components is by a plant expert panel similar to the one developed for the Maintenance Rule. Components are identified as being high risk-significant or low risk-significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of plants. Results from the first risk-based inspection pilot plant indicates safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. Pilot studies on risk-based testing indicate that about 60% of pumps and 25 to 30% of valves in plants are high safety-significant The reduction in inspection and testing reduces the person-rem exposure and resulting in further increases in safety. These techniques have been documented in publications by the ASME CRTD which are referenced. (author)

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.

R and D perspectives on the advanced nuclear safety regulation system

International Nuclear Information System (INIS)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook; Han, Sang Hoon; Lee, Jung Won

2009-01-01

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea

R and D perspectives on the advanced nuclear safety regulation system

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Han, Sang Hoon; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-04-15

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea.

Improved nuclear power plant operations through performance-based safety regulation

International Nuclear Information System (INIS)

Golay, M.W.

1998-01-01

The US Nuclear Regulatory Commission (NRC) has recently instituted use of Risk-Informed, Performance-Based Regulation (RIPBR) for protecting public safety in the use of nuclear power. This was done most importantly during June 1997 in issuance of revised Regulatory Guides and Standard Review Plan (SRP) guidance to licensees and the NRC staff. The propose of RIPBR is to replace the previously-used system of prescriptive regulation, which focuses upon what licensees must do, to a system which focuses upon what they must achieve. RIPBR is goals-oriented and the previous system is means-oriented. This regulatory change is potentially revolutionary, and offers many opportunities for improving the efficiency of improving both nuclear power operations and safety. However, it must be nurtured carefully if is to be successful. The work reported in this paper is concerned with showing how RIPBR can be implemented successfully, with benefits in both areas being attained. It is also concerned with how several of the practical barriers to establishing a workable new regulatory system can be overcome. This work, sponsored by the US Dept. of Energy, is being performed in collaboration with Northeast Utilities Services Crop. and the Idaho National Engineering Laboratory. In our work we have examined a practical safety-related example at the Millstone 3 nuclear power station for implementation of RIPBR. In this examination we have formulated a set of modifications to the plant's technical specifications, and are in the process of investigating their bases and refining the modifications. (author)

The challenge of defining risk-based metrics to improve food safety: inputs from the BASELINE project.

Science.gov (United States)

Manfreda, Gerardo; De Cesare, Alessandra

2014-08-01

In 2002, the Regulation (EC) 178 of the European Parliament and of the Council states that, in order to achieve the general objective of a high level of protection of human health and life, food law shall be based on risk analysis. However, the Commission Regulation No 2073/2005 on microbiological criteria for foodstuffs requires that food business operators ensure that foodstuffs comply with the relevant microbiological criteria. Such criteria define the acceptability of a product, a batch of foodstuffs or a process, based on the absence, presence or number of micro-organisms, and/or on the quantity of their toxins/metabolites, per unit(s) of mass, volume, area or batch. The same Regulation describes a food safety criterion as a mean to define the acceptability of a product or a batch of foodstuff applicable to products placed on the market; moreover, it states a process hygiene criterion as a mean indicating the acceptable functioning of the production process. Both food safety criteria and process hygiene criteria are not based on risk analysis. On the contrary, the metrics formulated by the Codex Alimentarius Commission in 2004, named Food Safety Objective (FSO) and Performance Objective (PO), are risk-based and fit the indications of Regulation 178/2002. The main aims of this review are to illustrate the key differences between microbiological criteria and the risk-based metrics defined by the Codex Alimentarius Commission and to explore the opportunity and also the possibility to implement future European Regulations including PO and FSO as supporting parameters to microbiological criteria. This review clarifies also the implications of defining an appropriate level of human protection, how to establish FSO and PO and how to implement them in practice linked to each other through quantitative risk assessment models. The contents of this review should clarify the context for application of the results collected during the EU funded project named BASELINE (www

Framework for applying probabilistic safety analysis in nuclear regulation

International Nuclear Information System (INIS)

Dimitrijevic, V.B.

1997-01-01

The traditional regulatory framework has served well to assure the protection of public health and safety. It has been recognized, however, that in a few circumstances, this deterministic framework has lead to an extensive expenditure on matters hat have little to do with the safe and reliable operation of the plant. Developments of plant-specific PSA have offered a new and powerful analytical tool in the evaluation of the safety of the plant. Using PSA insights as an aid to decision making in the regulatory process is now known as 'risk-based' or 'risk-informed' regulation. Numerous activities in the U.S. nuclear industry are focusing on applying this new approach to modify regulatory requirements. In addition, other approaches to regulations are in the developmental phase and are being evaluated. One is based on the performance monitoring and results and it is known as performance-based regulation. The other, called the blended approach, combines traditional deterministic principles with PSA insights and performance results. (author)

Overview of Risk Mitigation for Safety-Critical Computer-Based Systems

Science.gov (United States)

Torres-Pomales, Wilfredo

2015-01-01

This report presents a high-level overview of a general strategy to mitigate the risks from threats to safety-critical computer-based systems. In this context, a safety threat is a process or phenomenon that can cause operational safety hazards in the form of computational system failures. This report is intended to provide insight into the safety-risk mitigation problem and the characteristics of potential solutions. The limitations of the general risk mitigation strategy are discussed and some options to overcome these limitations are provided. This work is part of an ongoing effort to enable well-founded assurance of safety-related properties of complex safety-critical computer-based aircraft systems by developing an effective capability to model and reason about the safety implications of system requirements and design.

Regulatory risks associated with nuclear safety legislation after Fukushima Daiichi Nuclear Accident in Japan. Focus on legal structure of the nuclear reactor regulation act

International Nuclear Information System (INIS)

Tanabe, Tomoyuki; Maruyama, Masahiro

2016-01-01

Nuclear safety regulations enforced after Fukushima Daiichi Nuclear Accident under the Nuclear Reactor Regulation Act face the following regulatory problems that involve potential risk factors for nuclear businesses; 1) 'entity based regulation' unable to cope with business cessation or bankruptcy of the entity subject of regulation, 2) potential risk of the Nuclear Regulation Authority's inappropriate involvement in nuclear industry policy beyond their duty, and 3) compliance of backfits under vague regulations. In order to alleviate them, this report, through analyzing these regulatory problems from the view point of sound development of the nuclear industry, proposes the following regulatory reforms; (1) To clarify the rule for industry policy in nuclear regulations and enable the authority, Ministry of Economy, Trade and Industry, to choose most appropriate industrial policy measure. (2) Through establishing safety goals as measures to promote continuous improvement of nuclear safety regulations, to stimulate timely adjustments of the regulations, and to introduce a legal mechanism into the nuclear regulation systems under which validity of administrative law and its application can be checked. (author)

Demonstration of risk-based approaches to nuclear plant regulation

International Nuclear Information System (INIS)

Rahn, F.J.; Sursock, J.P.; Darling, S.S.; Oddo, J.M.

1993-01-01

This paper describes generic technical support EPRI is providing to the nuclear power industry relative to its recent initiatives in the area of risk-based regulations (RBR). A risk-based regulatory approach uses probabilistic risk assessment (PRA), or similar techniques, to allocate safety resources commensurate with the risk posed by nuclear plant operations. This approach will reduce O ampersand M costs, and also improve nuclear plant safety. In order to enhance industry, Nuclear Regulatory Commission (NRC) and public confidence in RBR, three things need to be shown: (1) manpower/resource savings are significant for both NRC and industry; (2) the process is doable in a reasonable amount of time; and (3) the process, if uniformly applied, results in demonstrably cheaper power and safer plants. In 1992, EPRI performed a qualitative study of the key RBR issues contributing to high O ampersand M costs. The results are given on Table 1. This study is being followed up by an in-depth quantitative cost/benefit study to focus technical work on producing guidelines/procedures for licensing submittals to NRC. The guidelines/procedures necessarily will be developed from successful demonstration projects such as the Fitzpatrick pilot plant study proposed by the New York Power Authority and other generic applications. This paper presents three examples: two motor operated valve projects performed by QUADREX Energy Services Corporation working with utilities in responding to NRC Generic Letter 89-10, and a third project working with Yankee Atomic Electric Company on service water systems at a plant in its service system. These demonstration projects aim to show the following: (1) the relative ease of putting together a technical case based on RBR concepts; (2) clarity in differentiating the various risk trade-offs, and in communicating overall reductions in risk with NRC; and (3) improved prioritization of NRC directives

A study on the relevance and influence of the existing regulation and risk informed/performance based regulation

Energy Technology Data Exchange (ETDEWEB)

Cheong, B. J.; Kang, J. M.; Kim, H. S.; Koh, S. H.; Kang, D. H.; Park, C. H. [Cheju Univ., Jeju (Korea, Republic of)

2003-02-15

The goal of this study is to estimate the relevance and Influence of the Existing Regulation and the RI-PBR to the institutionalization of the regulatory system. This study reviews the current regulatory system and the status of the RI-PBR implementation of the US NRC and Korea based upon SECY Papers, Risk Informed Regulation Implementation Plan (RIRIP) of the US NRC and other domestic studies. In order to investigate the perceptions, knowledge level, ground for the regulatory change, a survey was performed to Korean nuclear utilities, researchers and regulators on the perception on the RIR. The questionnaire was composed of 50 questions regarding personal details on work experience, level of education and specific field of work ; level of knowledge on the risk informed performance based regulation (RI-PBR); the perception of the current regulation, the effectiveness, level of procedure, flexibility, dependency on the regulator and personal view, and the perception of the RI-PBR such as flexibility of regulation, introduction time and the effect of RI-PBR, safety improvement, public perception, parts of the existing regulatory system that should be changed, etc. 515 answered from all sectors of the nuclear field; utilities, engineering companies, research institutes, and regulatory bodies.

Presenting information on regulation values improves the public’s sense of safety: Perceived mercury risk in fish and shellfish and its effects on consumption intention

Science.gov (United States)

Suzuki, Mai; Yamaguchi, Tomiko

2017-01-01

Risk communication aims to promote health and understanding through information exchange; however, explanations regarding the basis of regulation values for the public are insufficient. Moreover, it is unclear how information presentation affects the public’s sense of safety and their consumption intentions. We first investigated the relationship between perception of mercury-risk in fish and shellfish and individual attributes and knowledge. We then examined how presenting information on regulation values and primary factors regarding perception affected sense of safety toward regulations and food-consumption intentions. An online survey was conducted with Japanese individuals (N = 1148). Respondents were randomly assigned to one of three groups based on the presentation level of regulation values. People who frequently consumed tuna had a high perception of dread risk of mercury. This suggests that the dread risk perception of mercury does not determine tuna-type consumption behavior; rather, individuals’ consumption behavior determines dread risk perception of mercury. Among those with high tuna-type consumption, those receiving information that a safety factor of 10 times had been considered showed a significantly greater sense of safety than did the group that was not presented with information on regulation values (odds ratio (95% confidence interval): 2.04 (1.18–3.53), p values showed a weak but significantly positive correlation with excessive intake of tuna-type fish (odds ratio: 2.95 (0.93–9.32), p values increases sense of safety; however, it may also lead to excessive intake. PMID:29267301

Regulator Loss Functions and Hierarchical Modeling for Safety Decision Making.

Science.gov (United States)

Hatfield, Laura A; Baugh, Christine M; Azzone, Vanessa; Normand, Sharon-Lise T

2017-07-01

Regulators must act to protect the public when evidence indicates safety problems with medical devices. This requires complex tradeoffs among risks and benefits, which conventional safety surveillance methods do not incorporate. To combine explicit regulator loss functions with statistical evidence on medical device safety signals to improve decision making. In the Hospital Cost and Utilization Project National Inpatient Sample, we select pediatric inpatient admissions and identify adverse medical device events (AMDEs). We fit hierarchical Bayesian models to the annual hospital-level AMDE rates, accounting for patient and hospital characteristics. These models produce expected AMDE rates (a safety target), against which we compare the observed rates in a test year to compute a safety signal. We specify a set of loss functions that quantify the costs and benefits of each action as a function of the safety signal. We integrate the loss functions over the posterior distribution of the safety signal to obtain the posterior (Bayes) risk; the preferred action has the smallest Bayes risk. Using simulation and an analysis of AMDE data, we compare our minimum-risk decisions to a conventional Z score approach for classifying safety signals. The 2 rules produced different actions for nearly half of hospitals (45%). In the simulation, decisions that minimize Bayes risk outperform Z score-based decisions, even when the loss functions or hierarchical models are misspecified. Our method is sensitive to the choice of loss functions; eliciting quantitative inputs to the loss functions from regulators is challenging. A decision-theoretic approach to acting on safety signals is potentially promising but requires careful specification of loss functions in consultation with subject matter experts.

European regulations on nutraceuticals, dietary supplements and functional foods: A framework based on safety

International Nuclear Information System (INIS)

Coppens, Patrick; Fernandes da Silva, Miguel; Pettman, Simon

2006-01-01

This article describes the legislation that is relevant in the marketing of functional foods in the European Union (EU), how this legislation was developed as well as some practical consequences for manufacturers, marketers and consumers. It also addresses some concrete examples of how the EU's safety requirements for food products have impacted a range of product categories. In the late nineties, research into functional ingredients was showing promising prospects for the use of such ingredients in foodstuffs. Due mainly to safety concerns, these new scientific developments were accompanied by an urgent call for legislation. The European Commission 2000 White Paper on Food Safety announced some 80 proposals for new and improved legislation in this field. Among others, it foresaw the establishment of a General Food Law Regulation, laying down the principles of food law and the creation of an independent Food Authority endowed with the task of giving scientific advice on issues based upon scientific risk assessment with clearly separated responsibilities for risk assessment, risk management and risk communication. Since then, more than 90% of the White Paper proposals have been implemented. However, there is not, as such, a regulatory framework for 'functional foods' or 'nutraceuticals' in EU Food Law. The rules to be applied are numerous and depend on the nature of the foodstuff. The rules of the general food law Regulation are applicable to all foods. In addition, legislation on dietetic foods, on food supplements or on novel foods may also be applicable to functional foods depending on the nature of the product and on their use. Finally, the two proposals on nutrition and health claims and on the addition of vitamins and minerals and other substances to foods, which are currently in the legislative process, will also be an important factor in the future marketing of 'nutraceuticals' in Europe. The cornerstone of EU legislation on food products, including

Progress toward risk informed regulation

International Nuclear Information System (INIS)

Rogers, K.C.

1997-01-01

For the last several years, the NRC, with encouragement from the industry, has been moving in the direction of risk informed regulation. This is consistent with the regulatory principle of efficiency, formally adopted by the Nuclear Regulatory Commission in 1991, which requires that regulatory activities be consistent with the degree of risk reduction they achieve. Probabilistic risk analysis has become the tool of choice for selecting the best of several alternatives. Closely related to risk informed regulation is the development of performance based rules. Such rules focus on the end result to be achieved. They do not specify the process, but instead establish the goals to be reached and how the achievement of those goals is to be judged. The inspection and enforcement activity is based on whether or not the goals have been met. The author goes on to offer comments on the history of the development of this process and its probable development in the future. He also addresses some issues which must be resolved or at least acknowledged. The success of risk informed regulation ultimately depends on having sufficiently reliable data to allow quantification of regulatory alternatives in terms of relative risk. Perhaps the area of human reliability and organizational performance has the greatest potential for improvement in reactor safety. The ability to model human performance is significantly less developed that the ability to model mechanical or electrical systems. The move toward risk informed, performance based regulation provides an unusual, perhaps unique, opportunity to establish a more rational, more effective basis for regulation

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

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.

Regulation of Aging Power Plants: Ensuring Safety in a Changing Environment

International Nuclear Information System (INIS)

Jackson, S.A.

1999-01-01

In her keynote address to the Plim and Plex 1997 Conference, Dr. Jackson, President of the US Nuclear Regulatory Commission, dealt with four problem areas: (i) the development and application of safety margins; (ii) aging mechanisms and the use of inspection and testing methods; (iii) the U. S. licence renewal process; and (iv) risk-informed, performance-based regulation. Aging effects can further complicate existing interactions between 'explicit' and 'implicit' safety margins. Attempting to satisfy these combined margins can have a significant technical and financial impact on the plant operator. Aging degradation affects a broad range of plant systems, structures and components. Inspection and testing methods are improved continually, but development of methods for direct measuring of material properties on a more microscopic level together with elaboration of more precise predictive models of aging is still needed. In the U. S., the decision on whether to seek licence renewal rests with the licensee. The NRC task is to establish a reasonable process and clear safety standards. License renewal (extension of a NPP 40-years operating licence for additional 20 years) is explicitly allowed in NRS regulations in 10 CFR Part 54. In the U. S. nuclear power industry, there is considerable interest in licence renewal. A 'risk informed' approach to regulation means that, in the decision-making, the risk information is considered along with other factors. Performance-based regulation is, by definition, results focused; its essential component is the feedback of operating experience into subsequent evaluation. When the results focus is linked to risk analysis and ranking, the result is risk-informed, performance-based regulation. The NRS applies this combined approach in all its activities and, also, in its collaborative programs with the nuclear power industry. At the threshold of the 21st century, the nuclear power industry faces an array of challenges and opportunities

Improving the rationality of nuclear safety regulations

International Nuclear Information System (INIS)

Choi, Byung Sun; Choi, Y. G.; Mun, G. H.

2005-03-01

This study focuses on human nature and institutions around the risk management in Korean Nuclear Installations. Nuclear safety regulatory system in Korea has had a tendency to overvalue the technical or engineering areas. But just like other risk management system, the knowledge of social science is also required to design more valid safety regulatory system. As a result of analysis, this study suggest that performance regulation need to be introduced to current nuclear safety regulation system. In this advanced regulatory system, each nuclear generation unit have to be evaluated by performance of its own regulatory implementation and would be treated differently by the performance. Additionally, self-regulation could be very effective was to guarantee nuclear safety. Because KHNP could be judged to have an considerable capabilities to manage its own regulatory procedures. To make self-regulatory system established successfully, it is also important to arrange the appropriate incentive and compensate structures

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.

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

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

Methods for formulation of design basis accidents within a risk-informed approach to safety regulation of new nuclear power plants

International Nuclear Information System (INIS)

Beer, B.C.; Apostolakis, G.E.; Golay, M.W.

2000-01-01

Within a project sponsored by the U.S. Department of Energy (DOE) an investigation is being conducted into creating a risk-informed safety regulatory framework and design process based upon the use of probabilistic risk assessment (PRA). In conjunction with efforts to formulate an overall regulatory framework (i.e., reported in PSAM 5 by F. Duran, A. Camp, G. Apostolakis and M. Golay, 'A Framework for Regulatory Requirements and Industry Standards for New Nuclear Power Plants'), this paper addresses the potential role(s) of Design Basis Accidents (DBAs) within this new framework. Currently that role, if any, is unclear. In previous nuclear safety regulatory treatments, DBAs have been of great practical value for both designers and regulators. However, they have suffered from being inconsistently formulated, and lacking fundamental justification. Any DBA set is likely to be formulated uniquely for a specific reactor concept. The staff of any nuclear power plant (NPP) in the U.S. routinely calculates the likelihood of core damage, the likelihood of radioactive release and the likelihood of adverse health effects due to radioactive release. As the accuracy of such estimates improves industry-wide, safety regulators consider weighing these calculated risks more heavily than strict adherence to the prescriptive conservatisms of existing regulations, hence risk-informed regulation. DBAs, despite their prescriptive nature, can remain useful tools for regulators and designers in a risk-informed regulatory framework, providing that they can be formulated in a fashion consistent with the risk profiles of a plant. DBAs also offer the opportunity to take into account factors of uncertainty not captured in a PRA, which are typically addressed via defense-in-depth features and subjective judgements. Designers seeking only to create a plant having a calculated risk below a certain value, while minimizing cost, may find themselves in an inefficient trial-and-error process as they

Synthetic risks, risk potency, and carcinogen regulation.

Science.gov (United States)

Viscusi, W K; Hakes, J K

1998-01-01

This article analyzes a comprehensive sample of over 350 chemicals tested for carcinogenicity to assess the determinants of the probability of regulation. Controlling for differences in the risk potency and noncancer risks, synthetic chemicals have a significantly higher probability of regulation overall: this is due to the greater likelihood of U.S. Food and Drug Administration (FDA) regulation. Measures of risk potency increase the probability of regulation by the U.S. Environmental Protection Agency (EPA), have a somewhat weaker positive effect on regulation by the U.S. Occupational Safety and Health Administration (OSHA), and decrease the likelihood of regulation by the FDA. The overall regulatory pattern is one in which the FDA targets synthetic chemicals and chemicals that pose relatively minor cancer risk. The EPA particularly performed more sensibly than many critics have suggested.

Toward a Safety Risk-Based Classification of Unmanned Aircraft

Science.gov (United States)

Torres-Pomales, Wilfredo

2016-01-01

There is a trend of growing interest and demand for greater access of unmanned aircraft (UA) to the National Airspace System (NAS) as the ongoing development of UA technology has created the potential for significant economic benefits. However, the lack of a comprehensive and efficient UA regulatory framework has constrained the number and kinds of UA operations that can be performed. This report presents initial results of a study aimed at defining a safety-risk-based UA classification as a plausible basis for a regulatory framework for UA operating in the NAS. Much of the study up to this point has been at a conceptual high level. The report includes a survey of contextual topics, analysis of safety risk considerations, and initial recommendations for a risk-based approach to safe UA operations in the NAS. The next phase of the study will develop and leverage deeper clarity and insight into practical engineering and regulatory considerations for ensuring that UA operations have an acceptable level of safety.

Developing safety performance functions incorporating reliability-based risk measures.

Science.gov (United States)

Ibrahim, Shewkar El-Bassiouni; Sayed, Tarek

2011-11-01

Current geometric design guides provide deterministic standards where the safety margin of the design output is generally unknown and there is little knowledge of the safety implications of deviating from these standards. Several studies have advocated probabilistic geometric design where reliability analysis can be used to account for the uncertainty in the design parameters and to provide a risk measure of the implication of deviation from design standards. However, there is currently no link between measures of design reliability and the quantification of safety using collision frequency. The analysis presented in this paper attempts to bridge this gap by incorporating a reliability-based quantitative risk measure such as the probability of non-compliance (P(nc)) in safety performance functions (SPFs). Establishing this link will allow admitting reliability-based design into traditional benefit-cost analysis and should lead to a wider application of the reliability technique in road design. The present application is concerned with the design of horizontal curves, where the limit state function is defined in terms of the available (supply) and stopping (demand) sight distances. A comprehensive collision and geometric design database of two-lane rural highways is used to investigate the effect of the probability of non-compliance on safety. The reliability analysis was carried out using the First Order Reliability Method (FORM). Two Negative Binomial (NB) SPFs were developed to compare models with and without the reliability-based risk measures. It was found that models incorporating the P(nc) provided a better fit to the data set than the traditional (without risk) NB SPFs for total, injury and fatality (I+F) and property damage only (PDO) collisions. Copyright © 2011 Elsevier Ltd. All rights reserved.

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)

Study on institutionalization of risk-informed performance-based regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, M. G.; Hong, S. Y.; Seo, M. R. [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

2003-02-15

In this study, for the institutionalization of risk informed and performance based regulation in Korea, the latest technical movements of overseas countries are examined and reviewed. And the issues that was found when license change petition using risk information was submitted in Korean regulatory body are reviewed. Based on these review, the applicable areas to domestic situation will be found and proposed. This study can contribute to setting up the proper direction for the institutionalization of risk informed and performance based regulation.

Development of new risk based regulations

International Nuclear Information System (INIS)

Nielsen, L.

1999-01-01

A short presentation of the oil and gas industry in Norway, and a brief overview of the regulatory regime in the petroleum sector in Norway is given. Risk analysis has been performed in Norway since 1981 and the various applications will be described. These risk analyses are quite different from a nuclear PSA and some of these differences will be commented. Risk based optimisation techniques such as RCM (Reliability Centred Maintenance) and Risk Based Inspection is used in the industry, with very limited support from the risk analysis. Some of the limitation that exist when such techniques are imported from other industries will be commented on. NPD (Norwegian Petroleum Directorate) is revising our regulations and some of the future plants when it comes to risk informed regulatory requirements will be presented. (au)

The nuclear industry's transition to risk-informed regulation and operation in the United States

International Nuclear Information System (INIS)

Kadak, Andrew C.; Matsuo, Toshihiro

2007-01-01

This paper summarizes a study of the transition of the United States nuclear industry from a prescriptive regulatory structure to a more risk informed approach to operations and regulations. The transition occurred over a 20 yr period in which gradual changes were made in the fundamental regulations and to the approach to nuclear safety and operations. While the number of actual regulatory changes were few, they are continuing. The utilities that embraced risk informed operations made dramatic changes in the way they approached operations and outage management. Those utilities that used risk in operations showed dramatic improvement in safety based on Institute of Nuclear Power Operations (INPO) performance indicators. It was also shown that the use of risk did not negatively affect safety performance of the plants compared to standard prescriptive approaches. This was despite having greater flexibility in compliance to regulatory standards and the use of the newly instituted risk-informed reactor oversight process. Key factors affecting the successful transition to a more risk-informed approach to regulations and operations are: strong top management support and leadership both at the regulator and the utility; education and training in risk principles and probabilistic risk Assessment tools for engineers, operators and maintenance staff; a slow and steady introduction of risk initiatives in areas that can show value to both the regulator and the industry; a transparent regulatory foundation built around a safety goal policy and the development of a strong safety culture at the utility to allow for more independence in safety compliance and risk management. The experience of the United States shows positive results in both safety and economics. The INPO and NRC metrics presented show that the use of risk information in operations and regulation is marginally better with no degradation in safety when plants that have embraced risk-informed approaches are compared

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.)

Risk-based safety performance indicators for nuclear power plants

International Nuclear Information System (INIS)

Chakraborty, S.; Prohaska, G.; Flodin, Y.; Grint, G.; Habermacher, H.; Hallman, A.; Isasia, R.; Melendez, E.; Verduras, E.; Karsa, Z.; Khatib-Rahbar, M.; Koeberlein, K.; Schwaeger, C.; Matahri, N.; Moravcik, I.; Tkac, M.; Preston, J.

2003-01-01

In a Concerted Action (CA), sponsored by the European Commission within its 5th Framework Program, a consortium of eleven partners from eight countries has reviewed and evaluated the application of Safety Performance Indicators (SPIs), which - in combination with other tools - can be used to monitor and improve the safety of nuclear power plants. The project was aimed at identification of methods that can be used in a risk-informed regulatory system and environment, and to exploit PSA techniques for the development and use of meaningful additional/alternative SPIs. The CA included the review of existing indicator systems, and the collection of information on the experience from indicator systems by means of a specific questionnaire. One of the most important and challenging issues for nuclear plant owners and/or regulators is to recognize early signs of deterioration in safety performance, caused by influences from management, organization and safety culture (MOSC), before actual events and/or mishaps take place. Most of the existing SPIs as proposed by various organizations are considered as 'lagging' indicators, that is, they are expected to show an impact only when a downward trend has already started. Furthermore, most of the available indicators are at a relatively high level, such that they will not provide useful information on fundamental weaknesses causing the problem in the first place. Regulators' and utilities' views on the use of a Safety Performance Indicator System have also been a part of the development of the CA. (author)

Validation of risk-based performance indicators: Safety system function trends

International Nuclear Information System (INIS)

Boccio, J.L.; Vesely, W.E.; Azarm, M.A.; Carbonaro, J.F.; Usher, J.L.; Oden, N.

1989-10-01

This report describes and applies a process for validating a model for a risk-based performance indicator. The purpose of the risk-based indicator evaluated, Safety System Function Trend (SSFT), is to monitor the unavailability of selected safety systems. Interim validation of this indicator is based on three aspects: a theoretical basis, an empirical basis relying on statistical correlations, and case studies employing 25 plant years of historical data collected from five plants for a number of safety systems. Results using the SSFT model are encouraging. Application of the model through case studies dealing with the performance of important safety systems shows that statistically significant trends in, and levels of, system performance can be discerned which thereby can provide leading indications of degrading and/or improving performances. Methods for developing system performance tolerance bounds are discussed and applied to aid in the interpretation of the trends in this risk-based indicator. Some additional characteristics of the SSFT indicator, learned through the data-collection efforts and subsequent data analyses performed, are also discussed. The usefulness and practicality of other data sources for validation purposes are explored. Further validation of this indicator is noted. Also, additional research is underway in developing a more detailed estimator of system unavailability. 9 refs., 18 figs., 5 tabs

Risk regulation in environment, health and safety : Decision in the face of uncertainty

Energy Technology Data Exchange (ETDEWEB)

Ettlinger, L A [The Oxford Group, Baltimore, MD (United States)

1999-12-01

unlikely to be resolved solely by administrative reform, reliance on experts, or risk education because, generally, these reforms are focused strictly on narrowing the risk uncertainty. From economic principles, however, we recognize that the value of efforts to minimize this risk uncertainty (or to maximize the technical and scientific information about risks) is subject to 'diminishing marginal utility'. Thus, these efforts ultimately can be expected to become unpopular with both citizens and elected officials. We expect, therefore, that the outcome of the risk regulation debate, and ultimately environment, health and safety policy decisions, will primarily be determined by the values of the proponents and opponents as to the relative ranking of efficiency and equity. Most likely, the best means available for reforming risk regulation and making it more coherent and to avoid some of the costly mistakes of the past is to: 1. increase the resources available for identifying risks and effective responses to them, 2. build in mechanisms for informing the public that policy decisions using these regulations are value laden, and 3. publicize both the process and the outcomes of risk regulations and policy decisions.

Risk regulation in environment, health and safety : Decision in the face of uncertainty

Energy Technology Data Exchange (ETDEWEB)

Ettlinger, L.A. [The Oxford Group, Baltimore, MD (United States)

1999-12-01

relationship are unlikely to be resolved solely by administrative reform, reliance on experts, or risk education because, generally, these reforms are focused strictly on narrowing the risk uncertainty. From economic principles, however, we recognize that the value of efforts to minimize this risk uncertainty (or to maximize the technical and scientific information about risks) is subject to 'diminishing marginal utility'. Thus, these efforts ultimately can be expected to become unpopular with both citizens and elected officials. We expect, therefore, that the outcome of the risk regulation debate, and ultimately environment, health and safety policy decisions, will primarily be determined by the values of the proponents and opponents as to the relative ranking of efficiency and equity. Most likely, the best means available for reforming risk regulation and making it more coherent and to avoid some of the costly mistakes of the past is to: 1. increase the resources available for identifying risks and effective responses to them, 2. build in mechanisms for informing the public that policy decisions using these regulations are value laden, and 3. publicize both the process and the outcomes of risk regulations and policy decisions.

Risk regulation in environment, health and safety : Decision in the face of uncertainty

International Nuclear Information System (INIS)

Ettlinger, L.A.

1999-01-01

unlikely to be resolved solely by administrative reform, reliance on experts, or risk education because, generally, these reforms are focused strictly on narrowing the risk uncertainty. From economic principles, however, we recognize that the value of efforts to minimize this risk uncertainty (or to maximize the technical and scientific information about risks) is subject to 'diminishing marginal utility'. Thus, these efforts ultimately can be expected to become unpopular with both citizens and elected officials. We expect, therefore, that the outcome of the risk regulation debate, and ultimately environment, health and safety policy decisions, will primarily be determined by the values of the proponents and opponents as to the relative ranking of efficiency and equity. Most likely, the best means available for reforming risk regulation and making it more coherent and to avoid some of the costly mistakes of the past is to: 1. increase the resources available for identifying risks and effective responses to them, 2. build in mechanisms for informing the public that policy decisions using these regulations are value laden, and 3. publicize both the process and the outcomes of risk regulations and policy decisions

A strategy for the risk-based inspection of pressure safety valves

International Nuclear Information System (INIS)

Chien, C.-H.; Chen, C.-H.; Chao, Y.J.

2009-01-01

The purpose of a pressure safety valve (PSV) is to protect the life and safety of pressure vessels in a pressurized system. If a weakened PSV fails to function properly, a catastrophic event might occur if no other protective means are provided. By utilizing the as-received test data and statistical analysis of the aging conditions of PSVs in lubricant process units, a risk-based inspection (RBI) system was developed in this study. First of all, the characteristics of PSV were discussed from the practical viewpoint of engineering inspection and maintenance. The as-received test data, which shows obvious PSV damage, will be separated from the data used in the following statistical analysis. Then, the relationship between the aging conditions and the corresponding PSV parameters was analyzed by using the statistical technique-analysis of variance (ANOVA). Finally, a strategy for semi-quantitative RBI is proposed. Also, a definitive estimated inspection interval for every PSV is suggested. The outcome indicated most of the risks result from a few PSVs, for which the corresponding inspection intervals will be shorter than the 2 years in accordance with relative standards and local government regulations

Relationship between degree of risk, cost and level of compliance to occupational health and safety regulations in construction

Directory of Open Access Journals (Sweden)

Abimbola Olukemi Windapo

2013-06-01

Full Text Available This paper investigates the role of statutory health and safety (H&S regulations in managing construction project risks. The study examines whether the decision made by contractors to comply with the regulations, the cost of compliance and savings of H&S regulatory requirements is influenced by the degree or level of risk, which the regulations are trying to prevent. The rationale for the examination stems from previous studies which establish that building designers and contractors perceive the cost of complying with regulations as additional burdens, which they have to conform to, and which are in some cases unnecessary, and also the fact that construction related injuries and fatalities are on the increase. Qualitative and quantitative data obtained from a descriptive survey and H&S site audit by the Master Builder Association of the Western Cape (MBAWC were used as the measurements of risk, level of compliance to regulations, cost of compliance and savings. By correlating the quantitative and qualitative data, there is empirical evidence to support a negative relationship between the degree of risk, level and cost of compliance and cost savings. Based on the study’s findings, this paper concludes that the decision made by contractors to comply with H&S regulatory requirements is influenced by the perceived cost saving on account of compliance and that cost savings are influenced by the probability of accident occurrence which is an element of the degree of risk which the regulation is trying to prevent or control. 

Relationship between degree of risk, cost and level of compliance to occupational health and safety regulations in construction

Directory of Open Access Journals (Sweden)

Abimbola Olukemi Windapo

2013-06-01

Full Text Available This paper investigates the role of statutory health and safety (H&S regulations in managing construction project risks. The study examines whether the decision made by contractors to comply with the regulations, the cost of compliance and savings of H&S regulatory requirements is influenced by the degree or level of risk, which the regulations are trying to prevent. The rationale for the examination stems from previous studies which establish that building designers and contractors perceive the cost of complying with regulations as additional burdens, which they have to conform to, and which are in some cases unnecessary, and also the fact that construction related injuries and fatalities are on the increase. Qualitative and quantitative data obtained from a descriptive survey and H&S site audit by the Master Builder Association of the Western Cape (MBAWC were used as the measurements of risk, level of compliance to regulations, cost of compliance and savings. By correlating the quantitative and qualitative data, there is empirical evidence to support a negative relationship between the degree of risk, level and cost of compliance and cost savings. Based on the study’s findings, this paper concludes that the decision made by contractors to comply with H&S regulatory requirements is influenced by the perceived cost saving on account of compliance and that cost savings are influenced by the probability of accident occurrence which is an element of the degree of risk which the regulation is trying to prevent or control.

Classification of research reactors and discussion of thinking of safety regulation based on the classification

International Nuclear Information System (INIS)

Song Chenxiu; Zhu Lixin

2013-01-01

Research reactors have different characteristics in the fields of reactor type, use, power level, design principle, operation model and safety performance, etc, and also have significant discrepancy in the aspect of nuclear safety regulation. This paper introduces classification of research reactors and discusses thinking of safety regulation based on the classification of research reactors. (authors)

Challenges in developing competency-based training curriculum for food safety regulators in India

Directory of Open Access Journals (Sweden)

Anitha Thippaiah

2014-01-01

Full Text Available Context: The Food Safety and Standards Act have redefined the roles and responsibilities of food regulatory workforce and calls for highly skilled human resources as it involves complex management procedures. Aims: 1 Identify the competencies needed among the food regulatory workforce in India. 2 Develop a competency-based training curriculum for food safety regulators in the country. 3 Develop training materials for use to train the food regulatory workforce. Settings and Design: The Indian Institute of Public Health, Hyderabad, led the development of training curriculum on food safety with technical assistance from the Royal Society for Public Health, UK and the National Institute of Nutrition, India. The exercise was to facilitate the implementation of new Act by undertaking capacity building through a comprehensive training program. Materials and Methods: A competency-based training needs assessment was conducted before undertaking the development of the training materials. Results: The training program for Food Safety Officers was designed to comprise of five modules to include: Food science and technology, Food safety management systems, Food safety legislation, Enforcement of food safety regulations, and Administrative functions. Each module has a facilitator guide for the tutor and a handbook for the participant. Essentials of Food Hygiene-I (Basic level, II and III (Retail/ Catering/ Manufacturing were primarily designed for training of food handlers and are part of essential reading for food safety regulators. Conclusion: The Food Safety and Standards Act calls for highly skilled human resources as it involves complex management procedures. Despite having developed a comprehensive competency-based training curriculum by joint efforts by the local, national, and international agencies, implementation remains a challenge in resource-limited setting.

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

Outlook for risk assessment and risk-informed regulations

International Nuclear Information System (INIS)

Chakraborty, S.; Breutel, C.; Khatib-Rahbar, M.

2000-01-01

The Western nuclear regulatory process has evolved from the initial engineering judgment' framework of the 1960's, the prescriptive deterministic requirements of the 1970s, the transition years of the 1980s, to the present day movement toward risk-informed approaches. In this paper, a short overview of the historic development of safety regulation is provided. The critique of traditional regulatory practice will be summarized and the features of risk-informed regulation will be discussed. The implementation of risk-informed regulation is considered on the basis of general legal principles common to many member states of the NEA and IAEA. In a process to risk-inform regulation, principles such as equal treatment, proportionality of rules and predictability of administrative action are found to be important. (author)

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

Cost-benefit comparison of nuclear and nonnuclear health and safety protective measures and regulations

International Nuclear Information System (INIS)

O'Donnell, E.P.; Mauro, J.J.

1979-01-01

This article compares the costs and benefits of health and safety measures and regulations in the nuclear and nonnuclear fields. A cost-benefit methodology for nuclear safety concerns is presented and applied to existing nuclear plant engineered safety features. Comparisons in terms of investment costs to achieve reductions in mortality rates are then made between nuclear plant safety features and the protective measures and regulations associated with nonnuclear risks, particularly with coal-fired power plants. These comparisons reveal a marked inconsistency in the cost effectiveness of health and safety policy, in which nuclear regulatory policy requires much greater investments to reduce the risk of public mortality than is required in nonnuclear areas where reductions in mortality rates could be achieved at much lower cost. A specific example of regulatory disparity regarding gaseous effluent limits for nuclear and fossil-fuel power plants is presented. It is concluded that a consistent health and safety regulatory policy based on uniform risk and cost-benefit criteria should be adopted and that future proposed Nuclear Regulatory Commission regulatory requirements should be critically evaluated from a cost-benefit viewpoint

Nuclear safety and regulation

International Nuclear Information System (INIS)

Kim, Hho Jung

2000-03-01

This book contains 12 chapters, which are atom and radiation, nuclear reactor and kinds of nuclear power plant, safeguard actuation system and stability evaluation for rock foundation of nuclear power plant, nuclear safety and principle, safety analysis and classification of incident, probabilistic safety assessment and major incident, nuclear safety regulation, system of nuclear safety regulation, main function and subject of safety regulation in nuclear facilities, regulation of fuel cycle and a nuclear dump site, protection of radiation and, safety supervision and, safety supervision and measurement of environmental radioactivity.

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)

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)

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

Study on the risk-informed regulation of NPP

International Nuclear Information System (INIS)

Wang Chaogui

2007-01-01

The risk-informed regulation is a modern type of NPP safety management mode using both deterministic and probabilistic approaches. It is necessary to entirely and systematically study the associated regulations, standards and practices in order to promote the developments of risk-informed regulations in China. This paper introduces the risk-informed regulation, gives out the basic principles, method and acceptance risk criteria of risk-informed decision,making, discusses the PSA requirements for risk-informed decision-making and makes some suggestions about the application of risk-informed regulations in Chinese NPP. (authors)

FIRE SAFETY IN NUCLEAR POWER PLANTS: A RISK-INFORMED AND PERFORMANCE-BASED APPROACH

International Nuclear Information System (INIS)

AZARM, M.A.; TRAVIS, R.J.

1999-01-01

The consideration of risk in regulatory decision-making has long been a part of NRC's policy and practice. Initially, these considerations were qualitative and were based on risk insights. The early regulations relied on good practices, past insights, and accepted standards. As a result, most NRC regulations were prescriptive and were applied uniformly to all areas within the regulatory scope. Risk technology is changing regulations by prioritizing the areas within regulatory scope based on risk, thereby focusing on the risk-important areas. Performance technology, on the other hand, is changing the regulations by allowing requirements to be adjusted based on the specific performance expected and manifested, rather than a prior prescriptive requirement. Consistent with the objectives of risk-informed and performance-based regulatory requirements, BNL evaluated the feasibility of applying risk- and performance-technologies to modifying NRC's current regulations on fire protection for nuclear power plants. This feasibility study entailed several case studies (trial applications). This paper describes the results of two of them. Besides the case studies, the paper discusses an overall evaluation of methodologies for fire-risk analysis to support the risk-informed regulation. It identifies some current shortcomings and proposes some near-term solutions

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...

Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

Issues and future directions of 'introduction of Risk Informed Regulation'

International Nuclear Information System (INIS)

2008-01-01

In 2004, Nuclear Safety Commission of Japan (NSC) set up a taskforce for developing a scheme of Risk Informed Regulation (RIR) introduction, which had discussed various aspects of utilization of risk information in nuclear regulations. In the final report compiled in 2007, the taskforce identified the significance of RIR introduction from viewpoint of enhancement of rationality, consistency and transparency as well as appropriate allocation of regulatory resources in the nuclear safety regulation and major issues for the further promotion were as follows: NSC is to maintain the comprehensively promoting function of the RIR introduction with reviewing global trends and latest technological knowledge, regulatory bodies are to further enhance the RIR in inspection and operational area, utilities and industries are to utilize further risk information in their self-maintenance activities and to gather trouble information data, academic societies are to establish the standards for risk evaluation technology and RIR, and research institutes are to carry out safety research and risk training for risk-communicators. This article presented summary of the final report aiming at upgrading safety regulation with enhancement of RIR introduction. (T. Tanaka)

FIRE SAFETY IN NUCLEAR POWER PLANTS: A RISK-INFORMED AND PERFORMANCE-BASED APPROACH

Energy Technology Data Exchange (ETDEWEB)

AZARM,M.A.; TRAVIS,R.J.

1999-11-14

The consideration of risk in regulatory decision-making has long been a part of NRC's policy and practice. Initially, these considerations were qualitative and were based on risk insights. The early regulations relied on good practices, past insights, and accepted standards. As a result, most NRC regulations were prescriptive and were applied uniformly to all areas within the regulatory scope. Risk technology is changing regulations by prioritizing the areas within regulatory scope based on risk, thereby focusing on the risk-important areas. Performance technology, on the other hand, is changing the regulations by allowing requirements to be adjusted based on the specific performance expected and manifested, rather than a prior prescriptive requirement. Consistent with the objectives of risk-informed and performance-based regulatory requirements, BNL evaluated the feasibility of applying risk- and performance-technologies to modifying NRC's current regulations on fire protection for nuclear power plants. This feasibility study entailed several case studies (trial applications). This paper describes the results of two of them. Besides the case studies, the paper discusses an overall evaluation of methodologies for fire-risk analysis to support the risk-informed regulation. It identifies some current shortcomings and proposes some near-term solutions.

Legal bases of safety regulations in electrical engineering

Energy Technology Data Exchange (ETDEWEB)

Jeiter, W

1981-12-01

Apart from the governmental regulations the rule for the prevention of accidents 'Electric plants and equipment' must be observed in order to protect the insurants. Actually, all these regulations do not contain any independent instructions. They rather utilize the VDE regulations and refer to them. The laws of electrical safety engineering are strongly influenced by harmonization efforts particularly within the European Communitties.

Risk-based Regulatory Evaluation Program methodology

International Nuclear Information System (INIS)

DuCharme, A.R.; Sanders, G.A.; Carlson, D.D.; Asselin, S.V.

1987-01-01

The objectives of this DOE-supported Regulatory Evaluation Progrwam are to analyze and evaluate the safety importance and economic significance of existing regulatory guidance in order to assist in the improvement of the regulatory process for current generation and future design reactors. A risk-based cost-benefit methodology was developed to evaluate the safety benefit and cost of specific regulations or Standard Review Plan sections. Risk-based methods can be used in lieu of or in combination with deterministic methods in developing regulatory requirements and reaching regulatory decisions

The spread model of food safety risk under the supply-demand disturbance.

Science.gov (United States)

Wang, Jining; Chen, Tingqiang

2016-01-01

In this paper, based on the imbalance of the supply-demand relationship of food, we design a spreading model of food safety risk, which is about from food producers to consumers in the food supply chain. We use theoretical analysis and numerical simulation to describe the supply-demand relationship and government supervision behaviors' influence on the risk spread of food safety and the behaviors of the food producers and the food retailers. We also analyze the influence of the awareness of consumer rights protection and the level of legal protection of consumer rights on the risk spread of food safety. This model contributes to the explicit investigation of the influence relationship among supply-demand factors, the regulation behavioral choice of government, the behavioral choice of food supply chain members and food safety risk spread. And this paper provides a new viewpoint for considering food safety risk spread in the food supply chain, which has a great reference for food safety management.

Risk Classification and Risk-based Safety and Mission Assurance

Science.gov (United States)

Leitner, Jesse A.

2014-01-01

Recent activities to revamp and emphasize the need to streamline processes and activities for Class D missions across the agency have led to various interpretations of Class D, including the lumping of a variety of low-cost projects into Class D. Sometimes terms such as Class D minus are used. In this presentation, mission risk classifications will be traced to official requirements and definitions as a measure to ensure that projects and programs align with the guidance and requirements that are commensurate for their defined risk posture. As part of this, the full suite of risk classifications, formal and informal will be defined, followed by an introduction to the new GPR 8705.4 that is currently under review.GPR 8705.4 lays out guidance for the mission success activities performed at the Classes A-D for NPR 7120.5 projects as well as for projects not under NPR 7120.5. Furthermore, the trends in stepping from Class A into higher risk posture classifications will be discussed. The talk will conclude with a discussion about risk-based safety and mission assuranceat GSFC.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

William E. Kastenberg; Edward Blandford; Lance Kim

2009-03-31

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

International Nuclear Information System (INIS)

Kastenberg, William E.; Blandford, Edward; Kim, Lance

2009-01-01

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public

Strengthening air traffic safety management by moving from outcome-based towards risk-based evaluation of runway incursions

International Nuclear Information System (INIS)

Stroeve, Sybert H.; Som, Pradip; Doorn, Bas A. van; Bakker, G.J.

2016-01-01

Current safety management of aerodrome operations uses judgements of severity categories to evaluate runway incursions. Incident data show a small minority of severe incursions and a large majority of less severe incursions. We show that these severity judgements are mainly based upon the outcomes of runway incursions, in particular on the closest distances attained. As such, the severity-based evaluation leads to coincidental safety management feedback, wherein causes and risk implications of runway incursions are not well considered. In this paper we present a new framework for the evaluation of runway incursions, which effectively uses all runway incursions, which judges same types of causes similarly, and which structures causes and risk implications. The framework is based on risks of scenarios associated with the initiation of runway incursions. As a basis an inventory of scenarios is provided, which can represent almost all runway incursions involving a conflict with an aircraft. A main step in the framework is the assessment of the conditional probability of a collision given a runway incursion scenario. This can be effectively achieved for large sets of scenarios by agent-based dynamic risk modelling. The results provide detailed feedback on risks of runway incursion scenarios, thus enabling effective safety management. - Highlights: • Current evaluation of runway incursions is primarily based on their outcomes. • A new framework assesses collision risk given initiation of runway incursions. • Agent-based dynamic risk modelling can evaluate the risks of many scenarios. • A developed scenario inventory can represent almost all runway incursions. • The framework provides detailed feedback to safety management.

Blended Risk Approach in Applying PSA Models to Risk-Based Regulations

International Nuclear Information System (INIS)

Dimitrijevic, V. B.; Chapman, J. R.

1996-01-01

In this paper, the authors will discuss a modern approach in applying PSA models in risk-based regulation. The Blended Risk Approach is a combination of traditional and probabilistic processes. It is receiving increased attention in different industries in the U. S. and abroad. The use of the deterministic regulations and standards provides a proven and well understood basis on which to assess and communicate the impact of change to plant design and operation. Incorporation of traditional values into risk evaluation is working very well in the blended approach. This approach is very application specific. It includes multiple risk attributes, qualitative risk analysis, and basic deterministic principles. In blending deterministic and probabilistic principles, this approach ensures that the objectives of the traditional defense-in-depth concept are not compromised and the design basis of the plant is explicitly considered. (author)

Safety evaluation and regulation of chemicals. 2. Impact of regulations - improvement of methods

Energy Technology Data Exchange (ETDEWEB)

Homburger, F [ed.

1985-01-01

This volume assesses the impact of new scientific knowledge on the testing and regulation of chemicals, including food additives, drugs, cosmetics, pesticides, and other commercial substances. Apart from describing the newest tests, regulations, and risk assessment strategies, chapters reflect changes forced by both the growing need for cost containment and the mounting pressure to find alternatives to animal testing. Based on an international congress, the book also brings the advantage of diversity in the background and nationality of the authors, thus allowing a view of central problems according to the different interests of academics, industry scientists, government scientists, and regulators. The book opens with coverage of national and international regulations designed to prevent and control damage to human health and the environment. Topics range from basic problems of policy design and enforcement to the specific requirements for chemical regulation in developing countries. The next chapters cover new tests, systems, and assays used in in vivo safety testing. Readers will find a critical assessment of tests used to determine teratogenicity, mutagenicity, carcinogenicity, neurotoxicity and chemical lethality. Other topics include factors operating in the public perception of chemical hazards, guidelines for decision making in the management and regulation of risks, and future trends in the methodology of safety evaluation. The volume concludes with an overview of in vitro methods for testing hepatotoxicity. Several short-term in vitro test models and limited in vivo bioassays are presented and evaluated in terms of their capacity to substitute for long-term animal studies. Expert and thorough in its coverage, the book offers a wealth of technical and practical information for toxicologists, pharmacologists, industrial policy makers, and government regulators. (orig.). With 67 figs., 34 tabs.

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...

New Nuclear Safety Regulations

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.; Cizmek, A.

2008-01-01

Beside new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06), based on Nuclear Safety Act (Official Gazette No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of announcing the intention to perform nuclear activity, submitting an application for the issue of a license to perform nuclear activity, and the procedure for adoption a decision on issuing a nuclear activity license. The Ordinance also regulates the contents of the application form for the announcement of the intention to perform nuclear activity, as well as of the application for the issue of a nuclear activity license and the method of keeping a nuclear activity register. The Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, SONS finalized the text of new Ordinance on nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance regulates nuclear safety and protection conditions for location, design, construction, operation and decommissioning of facility in which nuclear activity is performed. This Ordinance defines facilities in which nuclear activity is

Industry participation in the development of a risk-informed, performance-based regulation for fire protection at US nuclear power plants

International Nuclear Information System (INIS)

Emerson, F.A.

1998-01-01

The USNRC staff have recently been directed by the NRC Commissioners to evaluate quickly the development of a risk-informed, performance-based fire protection regulation to replace the current regulations. The US nuclear industry does not believe a new rule is necessary to increase fire safety, and believes that there are significant risks and potentially significant benefits depending on the construction of the rule. However, the industry will actively work with NRC staff if rulemaking proceeds such that the risks are minimized and the benefits maximized. A Nuclear Energy Institute (NEI) Issue Task Force (ITF) has been established to guide the participation of industry in any rulemaking activity. If rulemaking proceeds, a framework should be established for the evolution of a fire protection rule from the current prescriptive basis to a risk-informed, performance-based rule. (author)

Co-operative development of nuclear safety regulations, guides and standards based on NUSS

International Nuclear Information System (INIS)

Pachner, J.; Boyd, F.C.; Yaremy, E.M.

1985-01-01

A major need of developing Member States building nuclear power plants (NPPs) of foreign origin is to acquire a capability to regulate such nuclear plants independently. Among other things, this requires the development of national nuclear safety regulations, guides and standards to govern the development and use of nuclear technology. Recognizing the importance and complexity of this task, it seems appropriate that the NPP-exporting Member States share their experience and assist the NPP-importing Member States in the development of their national regulations and guides. In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Ltd. conducted a study of a possible joint programme involving Canada, an NPP-importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design regulations, safety guides and a guide for regulatory evaluation of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the programme. The study showed that such a joint programme could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation. (author)

Risk-based evaluation tool for safety-related maintenance involving scaffolding

International Nuclear Information System (INIS)

Stevens, C.; Azizi, M.; Massman, M.

1988-01-01

The US Nuclear Regulatory Commission (NRC) has expressed a general concern that transient materials in and around safety systems at nuclear power plants represent a seismic safety hazard to the plant, in particular, the uncontrolled use of scaffolding during maintenance activities. Currently, most plants perform a seismic safety analysis for all uses of scaffolding near safety-related equipment to determine appropriate tie-down locations, scaffolding reinforcements, etc. This is both time-consuming and, for the most part, unnecessary. A workable engineering solution based on risk analysis techniques has been developed and is being used at the Palo Verde nuclear generating station (PVNGS)

The Wicked Character of Psychosocial Risks: Implications for Regulation

Directory of Open Access Journals (Sweden)

Anne Helbo Jespersen

2016-10-01

Full Text Available Psychosocial risks constitute a significant problem in most workplaces, and they are generally considered more difficult to regulate than many other occupational health and safety risks. This article investigates the challenges of regulating psychosocial risks in the workplace. The difficulties lie in the particular nature of psychosocial risks: their complexity, uncertainty, value, and power divergences. Psychosocial risks therefore resemble ‘wicked problems’, typically characterized by unclear cause-effect relationships and uncertain solutions. We use the ‘wicked problems’ concept to show how workplace regulation, and particularly the enforcement in the form of inspection and audits of certified occupational health and safety management systems, face challenges in assessing psychosocial risks and the strategies used by regulators to overcome these challenges. While regulation has become more effective in several countries, a better understanding of the nature of the challenges is still needed. It is necessary to accept the uncertain nature of psychosocial risks in the search for more efficient regulation. Achieving more effective regulation should involve stakeholders in the workplace who deal with the prerogatives of management, and should help develop the competencies of the inspectors and auditors in the field.

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

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.

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.

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

NARCIS (Netherlands)

Barlow, S.M.; Boobis, A.R.; Bridges, J.; Cockburn, A.; Dekant, W.; Hepburn, P.; Houben, G.F.; König, J.; Nauta, M.J.; Schuermans, J.; Bánáti, D.

2015-01-01

Background: Food 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

The improvement of nuclear safety regulation : American, European, Japanese, and South Korean experiences

International Nuclear Information System (INIS)

Cho, Byung Sun

2005-01-01

Key concepts in South Korean nuclear safety regulation are safety and risk. Nuclear regulation in South Korea has required reactor designs and safeguards that reduce the risk of a major accident to less than one in a million reactor-years-a risk supposedly low enough to be acceptable. To data, in South Korean nuclear safety regulation has involved the establishment of many technical standards to enable administration enforcement. In scientific lawsuits in which the legal issue is the validity of specialized technical standards that are used for judge whether a particular nuclear power plant is to be licensed, the concept of uncertainty law is often raised with regard to what extent the examination and judgement by the judicial power affects a discretion made by the administrative office. In other words, the safety standards for nuclear power plants has been adapted as a form of the scientific technical standards widely under the idea of uncertainty law. Thus, the improvement of nuclear safety regulation in South Korea seems to depend on the rational lawmaking and a reasonable, judicial examination of the scientific standards on nuclear safety

Risk-informed, performance-based safety-security interface

International Nuclear Information System (INIS)

Mrowca, B.; Eltawila, F.

2012-01-01

Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

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.

Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

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.

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

Nuclear safety: economic analysis of American, French and Japanese regulations

International Nuclear Information System (INIS)

Leveque, Francois

2013-05-01

While discussing and comparing the American, Japanese and French approaches and practices, and identifying the strengths and weaknesses of each of them, the author discusses why self-regulation and civil responsibility cannot guarantee a sufficient nuclear safety level, why the safety regulation authority must be independent from industry and government, whether a figure must be put to the safety objective (for example with a risk threshold), whether it is better to define detailed standards to be applied by manufacturers and operators or to define general performance criteria to be reached

Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

International Nuclear Information System (INIS)

Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

1997-12-01

This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues

Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

Energy Technology Data Exchange (ETDEWEB)

Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

1997-12-01

This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

Risk-Based Predictive Maintenance for Safety-Critical Systems by Using Probabilistic Inference

Directory of Open Access Journals (Sweden)

Tianhua Xu

2013-01-01

Full Text Available Risk-based maintenance (RBM aims to improve maintenance planning and decision making by reducing the probability and consequences of failure of equipment. A new predictive maintenance strategy that integrates dynamic evolution model and risk assessment is proposed which can be used to calculate the optimal maintenance time with minimal cost and safety constraints. The dynamic evolution model provides qualified risks by using probabilistic inference with bucket elimination and gives the prospective degradation trend of a complex system. Based on the degradation trend, an optimal maintenance time can be determined by minimizing the expected maintenance cost per time unit. The effectiveness of the proposed method is validated and demonstrated by a collision accident of high-speed trains with obstacles in the presence of safety and cost constrains.

A performance-oriented and risk-based regulation for containment testing

International Nuclear Information System (INIS)

Dey, M.

1994-01-01

In August 1992, the NRC initiated a major initiative to develop requirements for containment testing that are less prescriptive, and more performance-oriented and risk-based. This action was a result of public comments and several studies that concluded that the economic burden of certain, present containment testing requirements are not commensurate with their safety benefits. The rulemaking will include consideration of relaxing the allowable containment leakage rate, increasing the interval for the integrated containment test, and establishing intervals for the local containment leak rate tests based on their performance. A study has been conducted to provide technical information for establishing the performance criteria for containment tests, the allowable leakage rate, commensurate with its significance to total public risk. The study used results of a recent comprehensive study conducted by the NRC, NUREG-1150, 'Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants,' to examine the sensitivity of containment leakage to public risk. Risk was found to be insensitive to containment leakage rate up to levels of about 100 percent-volume per day for certain types of containments. PRA methods have also been developed to establish risk-based intervals for containment tests based on their past experience. Preliminary evaluations show that increasing the interval for the integrated containment leakage test from three times to once every ten years would have an insignificant impact on public risk. Preliminary analyses of operational experience data for local leak rate tests show that performance-based testing, valves and penetrations that perform well are tested less frequently, is feasible with marginal impact on safety. The above technical studies are being used to develop efficient (cost-effective) requirements for containment tests. (author). 4 refs., 2 figs

A macromarketing perspective on food safety regulation

DEFF Research Database (Denmark)

Bech-Larsen, Tino; Aschemann-Witzel, Jessica

2012-01-01

of the major stakeholders in the Danish food marketing system. Adding to the literature on diffusion of regulatory initiatives, the analysis shows that the Danish ban on trans-fats had—and still has—an important impact on trans-fat regulation in other European and overseas countries. In the final section......This article discusses the implementation and diffusion of mandatory and voluntary food safety regulations from a marketing systems perspective, and specifically applies this framework to an analysis of the antecedents and implications of the Danish 2003 ban on trans-fatty acids (TFAs......). The analysis is based on reviews of published material and on interviews with food marketers, nutrition experts, and policy makers. It is established that the ban was implemented due to scientific proof of health risks associated with the intake of TFAs but also as a result of aligned interests and efforts...

Calculations of risk: regulation and responsibility for asbestos in social housing.

Science.gov (United States)

Waldman, Linda; Williams, Heather

2013-01-01

This paper examines questions of risk, regulation, and responsibility in relation to asbestos lodged in UK social housing. Despite extensive health and safety legislation protecting against industrial exposure, very little regulatory attention is given to asbestos present in domestic homes. The paper argues that this lack of regulatory oversight, combined with the informal, contractual, and small-scale work undertaken in domestic homes weakens the basic premise of occupational health and safety, namely that rational decision-making, technical measures, and individual safety behavior lead concerned parties (workers, employers, and others) to minimize risk and exposure. The paper focuses on UK council or social housing, examining how local housing authorities - as landlords - have a duty to provide housing, to protect and to care for residents, but points out that these obligations do not extend to health and safety legislation in relation to DIY undertaken by residents. At the same time, only conventional occupational health and safety, based on rationality, identification, containment, and protective measures, cover itinerant workmen entering these homes. Focusing on asbestos and the way things work in reality, this paper thus explores the degree to which official health and safety regulation can safeguard maintenance and other workers in council homes. It simultaneously examines how councils advise and protect tenants as they occupy and shape their homes. In so doing, this paper challenges the notion of risk as an objective, scientific, and effective measure. In contrast, it demonstrates the ways in which occupational risk - and the choice of appropriate response - is more likely situational and determined by wide-ranging and often contradictory factors.

Assessing risks and regulating safety standards in the oil and gas industry: the Peruvian experience.

OpenAIRE

Arturo Leonardo Vásquez Cordano; Julio Salvador Jácome; Raúl Lizardo García Carpio; Victor Fernández Guzman

2013-01-01

Environmental regulation has usually focused on controlling continuous sources of pollution such as CO2 emissions through carbon taxes. However, the 2010 oil spill in the Gulf of Mexico has shown that accidents associated to safety failures can also generate bursts of pollution with serious environmental consequences. Regulating safety conditions to prevent accidents in the oil and gas industry is challenging because public regulators cannot perfectly observe whether firms comply with safety ...

Application of risk-based methodologies to prioritize safety resources

International Nuclear Information System (INIS)

Rahn, F.J.; Sursock, J.P.; Hosler, J.

1993-01-01

The Electric Power Research Institute (EPRI) started a program entitled risk-based prioritization in 1992. The purpose of this program is to provide generic technical support to the nuclear power industry relative to its recent initiatives in the area of operations and maintenance (O ampersand M) cost control using state-of-the-art risk methods. The approach uses probabilistic risk assessment (PRA), or similar techniques, to allocate resources commensurate with the risk posed by nuclear plant operations. Specifically, those items or events that have high risk significance would receive the most attention, while those with little risk content would command fewer resources. As quantified in a companion paper,close-quote the potential O ampersand M cost reduction inherent in this approach is very large. Furthermore, risk-based methods should also lead to safety improvements. This paper outlines the way that the EPRI technical work complements the technical, policy, and regulatory initiatives taken by others in the industry and provides an example of the approach as used to prioritize motor-operated valve (MOV) testing in response to US Nuclear Regulatory Commission (NRC) Generic Letter 89-10

Nuclear safety regulations

International Nuclear Information System (INIS)

1998-01-01

The Departmental Rules and The Safety Guides were issued by the NNSA in 1998. The NNSA performed the activities of propagation and implementation of nuclear safety regulations at QTNPP in order to improve the nuclear safety culture of operating organization and construct and contract organizations

Accounting for failure: risk-based regulation and the problems of ensuring healthcare quality in the NHS.

Science.gov (United States)

Beaussier, Anne-Laure; Demeritt, David; Griffiths, Alex; Rothstein, Henry

2016-05-18

In this paper, we examine why risk-based policy instruments have failed to improve the proportionality, effectiveness, and legitimacy of healthcare quality regulation in the National Health Service (NHS) in England. Rather than trying to prevent all possible harms, risk-based approaches promise to rationalise and manage the inevitable limits of what regulation can hope to achieve by focusing regulatory standard-setting and enforcement activity on the highest priority risks, as determined through formal assessments of their probability and consequences. As such, risk-based approaches have been enthusiastically adopted by healthcare quality regulators over the last decade. However, by drawing on historical policy analysis and in-depth interviews with 15 high-level UK informants in 2013-2015, we identify a series of practical problems in using risk-based policy instruments for defining, assessing, and ensuring compliance with healthcare quality standards. Based on our analysis, we go on to consider why, despite a succession of failures, healthcare regulators remain committed to developing and using risk-based approaches. We conclude by identifying several preconditions for successful risk-based regulation: goals must be clear and trade-offs between them amenable to agreement; regulators must be able to reliably assess the probability and consequences of adverse outcomes; regulators must have a range of enforcement tools that can be deployed in proportion to risk; and there must be political tolerance for adverse outcomes.

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)

Safety supervision on high-pressure gas regulations

International Nuclear Information System (INIS)

Lee, Won Il

1991-01-01

The first part lists the regulation on safety supervision of high-pressure gas, enforcement ordinance on high-pressure gas safety supervision and enforcement regulations about high-pressure gas safety supervision. The second part indicates safety regulations on liquefied petroleum gas and business, enforcement ordinance of safety on liquefied petroleum gas and business, enforcement regulation of safety supervision over liquefied petroleum gas and business. The third part lists regulation on gas business, enforcement ordinance and enforcement regulations on gas business. Each part has theory and explanation for questions.

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)

Safety goals and safety culture opening plenary. 2. Safety Regulation Implemented by Gosatomnadzor of Russia

International Nuclear Information System (INIS)

Gutsalov, A.T.; Bukrinsky, A.M.

2001-01-01

more strict than those recommended in the INSAG-3 and INSAG-12 reports, but they correlate with the value of negligible individual risk of 10 -6 , established in 'Radiation Safety Standards' (NRB-99) and consider still a high level of uncertainty in calculation of these probabilities. OPB- 88/97 also defines safety culture and principles of its formation and provision. Gosatomnadzor of Russia is a federal executive authority implementing state safety regulation in nuclear energy use. One of the main activities of Gosatomnadzor of Russia is nuclear and radiation safety regulation in sitting, design, construction, operation, and decommissioning of nuclear facilities. The activities include the following: 1. development and enactment of regulatory documents; 2. licensing of activities at nuclear facilities; 3. state supervision on observing the requirements of federal rules and regulations and license conditions. Gosatomnadzor of Russia strives toward solving the problems of consistent safety improvement of facilities and technologies up to the internationally accepted level, acting within the framework of the existing set of special safety rules and regulations in production and use of nuclear energy. Simultaneously, Gosatomnadzor of Russia develops proposals aimed at the improvement of legislative and regulatory bases of the Russian Federation as well as licensing and inspection procedures and implementing them. The main principles that Gosatomnadzor of Russia follows in its practical activities are openness, publicity, and cooperation with juridical and natural persons, whose activities are regulated with the purpose of achieving safety. This cooperation is accomplished in compliance with the principle of separation of responsibilities. According to this principle, the parties that are involved in activities related to the use of nuclear materials and nuclear energy on one hand, and in the state regulation of nuclear and radiation safety on the other hand, bear

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1982-09-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operations of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation pratice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS -or a letter- can also give the result of the examination of the constructor and operator code (RCC) by safety authorities

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1983-01-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operating of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridicial sense; they are called Regles Fondamentales de Surete (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS - or a letter - can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

Governance implications of nanomaterials companies’ inconsistent risk perceptions and safety practices

International Nuclear Information System (INIS)

Engeman, Cassandra D.; Baumgartner, Lynn; Carr, Benjamin M.; Fish, Allison M.; Meyerhofer, John D.; Satterfield, Terre A.; Holden, Patricia A.; Harthorn, Barbara Herr

2012-01-01

Current research on the nanotechnology industry indicates its downstream expansion at a rapid pace, while toxicological research and best practices for environmental health and safety are still being developed. Companies that use and/or produce engineered nanomaterials (ENMs) have enormous potential to influence safe-handling practices for ENMs across the product life cycle. Knowledge of both industry practices and leaders’ perceptions of risk is vital for understanding how companies will act to control potential environmental and health risks. This article reports results from a new international survey of nanomaterials companies in 14 countries. In this survey, company participants reported relatively high levels of uncertainty and/or perceived risk with regard to ENMs. However, these perspectives were not accompanied by expected risk-avoidant practices or preferences for regulatory oversight. A majority of companies indicated “lack of information” as a significant impediment to implementing nano-specific safety practices, but they also reported practices that were inconsistent with widely available guidance. Additionally, in the absence of safe-handling regulations, companies reported nano-specific health and safety programs that were narrow in scope. Taken together, these findings indicate that health and safety guidance is not reaching industry. While industry leaders’ reluctance toward regulation might be expected, their own reported unsafe practices and recognition of possible risks suggest a more top-down approach from regulators is needed to protect workers and the environment.

Governance implications of nanomaterials companies' inconsistent risk perceptions and safety practices

Science.gov (United States)

Engeman, Cassandra D.; Baumgartner, Lynn; Carr, Benjamin M.; Fish, Allison M.; Meyerhofer, John D.; Satterfield, Terre A.; Holden, Patricia A.; Harthorn, Barbara Herr

2012-03-01

Current research on the nanotechnology industry indicates its downstream expansion at a rapid pace, while toxicological research and best practices for environmental health and safety are still being developed. Companies that use and/or produce engineered nanomaterials (ENMs) have enormous potential to influence safe-handling practices for ENMs across the product life cycle. Knowledge of both industry practices and leaders' perceptions of risk is vital for understanding how companies will act to control potential environmental and health risks. This article reports results from a new international survey of nanomaterials companies in 14 countries. In this survey, company participants reported relatively high levels of uncertainty and/or perceived risk with regard to ENMs. However, these perspectives were not accompanied by expected risk-avoidant practices or preferences for regulatory oversight. A majority of companies indicated "lack of information" as a significant impediment to implementing nano-specific safety practices, but they also reported practices that were inconsistent with widely available guidance. Additionally, in the absence of safe-handling regulations, companies reported nano-specific health and safety programs that were narrow in scope. Taken together, these findings indicate that health and safety guidance is not reaching industry. While industry leaders' reluctance toward regulation might be expected, their own reported unsafe practices and recognition of possible risks suggest a more top-down approach from regulators is needed to protect workers and the environment.

NEA activities in safety and regulation

International Nuclear Information System (INIS)

Stadie, K.B.

1983-01-01

The NEA programme on Safety and Regulations is briefly reviewed. It encompasses four main areas - nuclear safety technology; nuclear licensing; radiation protection; and waste management - with three principal objectives: to promote exchanges of technical information in order to enlarge the data base for national decision making; to improve co-ordination of national R and D activities with emphasis on international standard problem exercises, and to promote international projects; to develop common technical, administrative and legal approaches to improve compatibility of safety and regulatory practices

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

Safety regulation : The lessons of workplace safety rule management for managing the regulatory burden

NARCIS (Netherlands)

Hale, A.R.; Borys, D.; Adams, M.

2012-01-01

There is a strong political consensus in a number of countries that occupational safety and health regulation is stifling industrial innovation and development and is feeding a culture of damaging risk aversion and petty bureaucracy. In a number of countries this has led to proposals to repeal

Nuclear regulation and safety

International Nuclear Information System (INIS)

Hendrie, J.M.

1982-01-01

Nuclear regulation and safety are discussed from the standpoint of a hypothetical country that is in the process of introducing a nuclear power industry and setting up a regulatory system. The national policy is assumed to be in favor of nuclear power. The regulators will have responsibility for economic, reliable electric production as well as for safety. Reactor safety is divided into three parts: shut it down, keep it covered, take out the afterheat. Emergency plans also have to be provided. Ways of keeping the core covered with water are discussed

The management of uncertainties in the French regulation on deep disposal: the development of a non-risk based approach

International Nuclear Information System (INIS)

Raimbault, P.

2004-01-01

The development of a safety case for disposal of high level and medium level long-lived waste in a geological formation has to handle two main difficulties: - uncertainties associated to natural systems; - uncertainties associated to the consideration of long time scales. Licensing of the different steps leading to geological disposal implies thus that a sufficient level of confidence in the safety case will be obtained, at each step, among the different stakeholders. The confidence in the safety case relies on the whole set of arguments of different natures which complement each other and build up the file. This means that, to be defensible, the safety case should be organised in such a way that it can be reviewed and scrutinized in a structured manner. This also means that individual elements of the safety case will have to be considered separately even if all elements should fit well in the integrated safety case. This segregation implies some inherent decoupling of parts of the system, of its evolution over time and of the events that may impact on it. This decoupling will thus introduce inherent uncertainties that risk or non-risk based approaches have to deal with since both approaches have to introduce transparency in the analysis. In the non-risk based or deterministic approach this segregation is pushed further in order to put into perspective the different elements of appreciation that allow to judge the safety case as a whole. The French regulation on deep disposal presented in the basic safety rule RFS III.3.f, issued in 1991, takes these points into consideration to set the basis for the safety case in the framework of a deterministic approach. This basic safety rule is currently being revised in order to clarify some concepts and to take account evolution of ideas at the national and international level. However the basic rationale behind the safety assessment methodology will remain the same. The approach presented in RFS III.2.f implies that at

Perceptions about safety and risks in gender-based violence research: implications for the ethics review process.

Science.gov (United States)

Sikweyiya, Yandisa; Jewkes, Rachel

2011-10-01

Does research on gender-based violence (GBV) pose greater than minimal risk to researchers and participants? This question needs to be understood particularly in light of hesitancy by Institutional Review Boards to approve research on GBV. The safety and risks of doing GBV studies and the implications for the ethical review process have not been a focus of much research. This qualitative study collected data through in-depth interviews with 12 experienced GBV researchers from various countries and a desk review. This paper explores researchers' interpretation of and meanings of the safety recommendations as provided in the WHO guidelines and whether there is empirical evidence on the presence of risks and safety concerns unique to GBV research. Informants raised a number of safety concerns about GBV research, yet in the interviews there were very few examples of problems having occurred, possibly because of the precautions applied. This paper argues that the notion that GBV studies carry greater than minimal risk when ethics precautions are followed is based on speculation, not evidence. It highlights the need for empirical evidence to support assertions of risk in research.

Safety regulation: The lessons of workplace safety rule management for managing the regulatory burden

OpenAIRE

Hale, A.R.; Borys, D.; Adams, M.

2012-01-01

There is a strong political consensus in a number of countries that occupational safety and health regulation is stifling industrial innovation and development and is feeding a culture of damaging risk aversion and petty bureaucracy. In a number of countries this has led to proposals to repeal regulations and reduce the regulatory burden. The authors were commissioned to prepare a discussion paper on this issue by the Mercatus Center of George Mason University in Arlington, Virginia, aimed pa...

RISK-INFORMED BALANCING OF SAFETY, NONPROLIFERATION, AND ECONOMICS FOR THE SFR

Energy Technology Data Exchange (ETDEWEB)

Apostolakis, George; Driscoll, Michael; Golay, Michael; Kadak, Andrew; Todreas, Neil; Aldmir, Tunc; Denning, Richard; Lineberry, Michael

2011-10-20

A substantial barrier to the implementation of Sodium-cooled Fast Reactor (SFR) technology in the short term is the perception that they would not be economically competitive with advanced light water reactors. With increased acceptance of risk-informed regulation, the opportunity exists to reduce the costs of a nuclear power plant at the design stage without applying excessive conservatism that is not needed in treating low risk events. In the report, NUREG-1860, the U.S. Nuclear Regulatory Commission describes developmental activities associated with a risk-informed, scenario-based technology neutral framework (TNF) for regulation. It provides quantitative yardsticks against which the adequacy of safety risks can be judged. We extend these concepts to treatment of proliferation risks. The objective of our project is to develop a risk-informed design process for minimizing the cost of electricity generation within constraints of adequate safety and proliferation risks. This report describes the design and use of this design optimization process within the context of reducing the capital cost and levelized cost of electricity production for a small (possibly modular) SFR. Our project provides not only an evaluation of the feasibility of a risk-informed design process but also a practical test of the applicability of the TNF to an actual advanced, non-LWR design. The report provides results of five safety related and one proliferation related case studies of innovative design alternatives. Applied to previously proposed SFR nuclear energy system concepts We find that the TNF provides a feasible initial basis for licensing new reactors. However, it is incomplete. We recommend improvements in terms of requiring acceptance standards for total safety risks, and we propose a framework for regulation of proliferation risks. We also demonstrate methods for evaluation of proliferation risks. We also suggest revisions to scenario-specific safety risk acceptance standards

Risk-Informed Balancing Of Safety, Nonproliferation, And Economics For The SFR

International Nuclear Information System (INIS)

Apostolakis, George; Driscoll, Michael; Golay, Michael; Kadak, Andrew; Todreas, Neil; Aldmir, Tunc; Denning, Richard; Lineberry, Michael

2011-01-01

A substantial barrier to the implementation of Sodium-cooled Fast Reactor (SFR) technology in the short term is the perception that they would not be economically competitive with advanced light water reactors. With increased acceptance of risk-informed regulation, the opportunity exists to reduce the costs of a nuclear power plant at the design stage without applying excessive conservatism that is not needed in treating low risk events. In the report, NUREG-1860, the U.S. Nuclear Regulatory Commission describes developmental activities associated with a risk-informed, scenario-based technology neutral framework (TNF) for regulation. It provides quantitative yardsticks against which the adequacy of safety risks can be judged. We extend these concepts to treatment of proliferation risks. The objective of our project is to develop a risk-informed design process for minimizing the cost of electricity generation within constraints of adequate safety and proliferation risks. This report describes the design and use of this design optimization process within the context of reducing the capital cost and levelized cost of electricity production for a small (possibly modular) SFR. Our project provides not only an evaluation of the feasibility of a risk-informed design process but also a practical test of the applicability of the TNF to an actual advanced, non-LWR design. The report provides results of five safety related and one proliferation related case studies of innovative design alternatives. Applied to previously proposed SFR nuclear energy system concepts We find that the TNF provides a feasible initial basis for licensing new reactors. However, it is incomplete. We recommend improvements in terms of requiring acceptance standards for total safety risks, and we propose a framework for regulation of proliferation risks. We also demonstrate methods for evaluation of proliferation risks. We also suggest revisions to scenario-specific safety risk acceptance standards

Offshore regulators focus on incentives for safety

Energy Technology Data Exchange (ETDEWEB)

Reid, W.

2000-11-27

Strict safety regulations in effect at offshore drilling sites are discussed. The guiding principle in all existing regulation is that while economic or industrial considerations are important, the value and the concern for human life is paramount. Should some tragic event occur at an offshore drilling site that is shown to have been caused by negligence of an operator, there is no question at all that the regulatory authority, in this case the Canada-Newfoundland Offshore Petroleum Board (CNOPB), would take the negligent operator to court. Nevertheless, Canadian authorities remain confident that encouragement of maintaining a safe working environment is likely to be more successful in ensuring workplace safety than threats of punishment. Indeed, Canadian regulators have, in recent times, shown a tendency to move towards performance-based systems, as opposed to the more usual prescriptive or rule-bound regulatory regime. This new approach involves setting targets and giving companies the responsibility to implement measures to reach the targets rather than relying on government instructions. Still, performance-based regulation in Canada is relatively new and some regulations remain prescriptive. Examples are the requirement for two immersion suits and two lifeboat seats for every worker on a drilling unit.

75 FR 16370 - Regulated Navigation Areas, Safety Zones, Security Zones; Deepwater Ports in Boston Captain of...

Science.gov (United States)

2010-04-01

... rule under Executive Order 13045, Protection of Children from Environmental Health Risks and Safety Risks. This rule is not an economically significant rule and would not create an environmental risk to...] RIN 1625-AA00, RIN 1625-AA11 Regulated Navigation Areas, Safety Zones, Security Zones; Deepwater Ports...

Cooperative development of nuclear safety regulations, guides and standards based on NUSS

International Nuclear Information System (INIS)

Pachner, J.; Boyd, F.C.; Yaremy, E.M.

1984-10-01

In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Limited conducted a study of a possible joint program involving Canada, a nuclear power plant importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the program. The study showed that such a joint program could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation

Westinghouse Owners Group Risk-Informed Regulation Efforts: Options 2 and 3

International Nuclear Information System (INIS)

Brown, Jason A.; Osterrieder, Robert A.; Lutz, Robert J.; Dingler, Maurice; Ward, Lewis A.

2002-01-01

The U.S. Nuclear Regulatory Commission (NRC) has initiated efforts to incorporate risk-informed methods to redefine the scope of the existing 10 CFR 50 regulations (Option 2) and to change the technical requirements of the regulations (Option 3). The overall objectives of these efforts are to enhance plant safety, provide a framework for risk-informed regulations, add flexibility to plant operations, and reduce regulatory burden. The Westinghouse Owners Group (WOG) has a variety of active programs in the risk-informed area, including a program in the Option 2 and Option 3 areas. These two programs will be summarized including the benefits and the technical approach. The purpose of Option 2 is to make changes to the overall scope of structures, systems and components (SSCs) covered by 10 CFR 50 requiring special treatment by formulating new risk-informed safety classification categories that are linked to current definitions of safety-related and important-to-safety. This initiative would permit possible changes to the current special treatment requirements based on risk insights. The Nuclear Energy Institute (NEI) has developed an Option 2 implementation guideline (NEI 00-04 Draft Revision B). The WOG has initiated a program to validate the NEI guideline and to provide an initial cost-benefit assessment of the revised categorization and treatment under Option 2 via trial application to two systems at both Surry Unit 1 and Wolf Creek. The WOG Option 2 program includes consideration of all of the components in the selected systems, regardless of whether or not they are modeled in the respective plant probabilistic risk assessment (PRA) studies. As a result, quantitative risk measures are not available for many of the components being considered. In this case, the WOG program will provide valuable input to the NEI guideline. Additionally, the WOG program extends the use of both of the dominant methodologies for risk-informed ISI (RI-ISI) to address repair and

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)

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)

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....

Which risk understandings can be derived from the current disharmonized regulation of complementary and alternative medicine in Europe?

Science.gov (United States)

Wiesener, Solveig; Salamonsen, Anita; Fønnebø, Vinjar

2018-01-10

Many European citizens are seeking complementary and alternative medicine (CAM). These treatments are regulated very differently in the EU/EFTA countries. This may demonstrate differences in how risk associated with the use of CAM is perceived. Since most CAM treatments are practiced fairly similarly across Europe, differing risk understandings may influence patient safety for European CAM users. The overall aim of this article is thus to contribute to an overview and awareness of possible differing risk understandings in the field of CAM at a policymaking/structural level in Europe. The study is a re-analysis of data collected in the CAMbrella EU FP7 document and interview study on the regulation of CAM in 39 European countries. The 12 CAM modalities included in the CAMbrella study were ranked with regard to assumed risk potential depending on the number of countries limiting its practice to regulated professions. The 39 countries were ranked according to how many of the included CAM modalities they limit to be practiced by regulated professions. Twelve of 39 countries generally understand the included CAM treatments to represent "high risk", 20 countries "low risk", while the remaining 7 countries understand CAM treatments as carrying "very little or no risk". The CAM modalities seen as carrying a risk high enough to warrant professional regulation in the highest number of countries are chiropractic, acupuncture, massage, homeopathy and osteopathy. The countries understanding most of the CAM modalities in the study as potentially high-risk treatments are with two exceptions (Portugal and Belgium) all concentrated in the southeastern region of Europe. The variation in regulation of CAM may represent a substantial lack of common risk understandings between health policymakers in Europe. We think the discrepancies in regulation are to a considerable degree also based on factors unrelated to patient risk. We argue that it is important for patient safety that policy

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

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.

Development of Comprehensive Nuclear Safety Regulation Plan for 2007-2011

International Nuclear Information System (INIS)

Choi, Young Sung; Kim, Woong Sik; Park, Dong Keuk; Kim, Ho Ki

2006-01-01

The Article 8-2 of Atomic Energy Act requires the government to establish Atomic Energy Promotion Plan every five years. It sets out national nuclear energy policies in a systematic and consistent way. The plan presents the goals and basic directions of national nuclear energy policies on the basis of current status and prospects. Both areas of utilization and safety management of nuclear energy are included and various projects and schedules are delineated based on the national policy directions. The safety management area in this plan deals with the overall safety and regulation policy. Its detail projects and schedule should be developed in separate plans by responsible ministries under the mediation of the MOST. As a regulatory authority, MOST is responsible for safety management area and its technical support organization, KINS has developed Comprehensive Nuclear Safety Regulation Plan as an implementation plan of safety area. This paper presents the development process and specific projects contained in the Comprehensive Nuclear Safety Regulation Plan which is under development now

Governance implications of nanomaterials companies' inconsistent risk perceptions and safety practices

Energy Technology Data Exchange (ETDEWEB)

Engeman, Cassandra D. [University of California, Santa Barbara, Department of Sociology (United States); Baumgartner, Lynn; Carr, Benjamin M.; Fish, Allison M.; Meyerhofer, John D. [UC Center for the Environmental Implications of Nanotechnology (UC CEIN), University of California, Santa Barbara (United States); Satterfield, Terre A. [University of California, Santa Barbara, NSF Center for Nanotechnology and Society (United States); Holden, Patricia A. [UC Center for the Environmental Implications of Nanotechnology (UC CEIN), University of California, Santa Barbara (United States); Harthorn, Barbara Herr, E-mail: harthorn@cns.ucsb.edu [University of California, Santa Barbara, NSF Center for Nanotechnology and Society (United States)

2012-03-15

Current research on the nanotechnology industry indicates its downstream expansion at a rapid pace, while toxicological research and best practices for environmental health and safety are still being developed. Companies that use and/or produce engineered nanomaterials (ENMs) have enormous potential to influence safe-handling practices for ENMs across the product life cycle. Knowledge of both industry practices and leaders' perceptions of risk is vital for understanding how companies will act to control potential environmental and health risks. This article reports results from a new international survey of nanomaterials companies in 14 countries. In this survey, company participants reported relatively high levels of uncertainty and/or perceived risk with regard to ENMs. However, these perspectives were not accompanied by expected risk-avoidant practices or preferences for regulatory oversight. A majority of companies indicated 'lack of information' as a significant impediment to implementing nano-specific safety practices, but they also reported practices that were inconsistent with widely available guidance. Additionally, in the absence of safe-handling regulations, companies reported nano-specific health and safety programs that were narrow in scope. Taken together, these findings indicate that health and safety guidance is not reaching industry. While industry leaders' reluctance toward regulation might be expected, their own reported unsafe practices and recognition of possible risks suggest a more top-down approach from regulators is needed to protect workers and the environment.

Realism in nuclear criticality safety

International Nuclear Information System (INIS)

McLaughlin, T. P.

2009-01-01

Commercial nuclear power plant operation and regulation have made remarkable progress since the Three Mile Island Accident. This is attributed largely to a heavy dose of introspection and self-regulation by the industry and to a significant infusion of risk-informed and performance-based regulation by the Nuclear Regulatory Commission. This truly represents reality in action both by the plant operators and the regulators. On the other hand, the implementation of nuclear criticality safety in ex-reactor operations involving significant quantities of fissile material has not progressed, but, tragically, it has regressed. Not only is the practice of the discipline in excess of a factor of ten more expensive than decades ago; the trend continues. This unfortunate reality is attributed to a lack of coordination within the industry (as contrasted to what occurred in the reactor operations sector), and to a lack of implementation of risk-informed and performance-based regulation by the NRC While the criticality safety discipline is orders of magnitude smaller than the reactor safety discipline, both operators and regulators must learn from the progress made in reactor safety and apply it to the former to reduce the waste, inefficiency and potentially increased accident risks associated with current practices. Only when these changes are made will there be progress made toward putting realism back into nuclear criticality safety. (authors)

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)

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)

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

Health economics and outcomes methods in risk-based decision-making for blood safety

NARCIS (Netherlands)

Custer, Brian; Janssen, Mart P.

2015-01-01

Analytical methods appropriate for health economic assessments of transfusion safety interventions have not previously been described in ways that facilitate their use. Within the context of risk-based decision-making (RBDM), health economics can be important for optimizing decisions among competing

Application of REVEAL-W to risk-based configuration control

International Nuclear Information System (INIS)

Dezfuli, H.; Meyer, J.; Modarres, M.

1994-01-01

Over the past two years, the concept of risk-based configuration control has been introduced to the US Nuclear Regulatory Commission and the nuclear industry. Converting much of the current, deterministically based regulation of nuclear power plants to risk-based regulation can result in lower levels of risk while relieving unnecessary burdens on power plant operators and regulatory staff. To achieve the potential benefits of risk-based configuration control, the risk models developed for nuclear power plants should be (1) flexible enough to effectively support necessary risk calculations, and (2) transparent enough to encourage their use by all parties. To address these needs, SCIENTECH, Inc., has developed the PC-based REVEAL W (formerly known as SMART). This graphic-oriented and user-friendly application software allows the user to develop transparent complex logic models based on the concept of the master plant logic diagram. The logic model is success-oriented and compact. The analytical capability built into REVEAL W is generic, so the software can support different types of risk-based evaluations, such as probabilistic safety assessment, accident sequence precursor analysis, design evaluation and configuration management. In this paper, we focus on the application of REVEAL W to support risk-based configuration control of nuclear power plants. (author)

Assessment of policy issues in nuclear safety regulation according to circumstantial changes

Energy Technology Data Exchange (ETDEWEB)

Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Lee, Kwang Gu; Huh, Gyun Young; Hahn, Young Tae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

2000-03-15

The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. The approach to improve regulatory effectiveness is also reviewed and a transition to 'knowledge-based regulation' is suggested.

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...

Current products and future plan of regulatory research for risk-informed regulation in Korea

International Nuclear Information System (INIS)

Sung, Key Yong; Lee, Chang Ju; Kim, Woong Sik; Kim, Hho Jung

2003-01-01

The first phase of a regulatory research project for risk-informed regulation (RIR) and applications (RIA) was finished in March of 2002. Various results that could be useful for preparing Korean RIR system have been developed. One of the remarkable outputs is development of reactor safety goals and acceptance criteria for RIR and RIA in Korea. The Safety Goal has a 4-tier hierarchical structure and each tier has specified goals classified for their usage. Regulatory review guides for probabilistic safety assessment (PSA) including level-1, level-2 and low power and shutdown PSA have been updated by reflecting new information obtained from not only the overseas documents but also experience and insights from regulatory review in Korea. In addition, draft regulatory guides for risk-informed in-service inspection, in-service testing, importance ranking of motor-operated valves, and AOT/STI change of Technical Specifications have been developed for preparing ongoing and future licensing work. Risk-based inspection guides with inspection items selected from a viewpoint of risk importance have been suggested for Korean standard NPPs as well. In the second phase of a research project (April of 2002 to March of 2005), two regulatory research projects on RIR were initiated. One is a study on institutionalization of risk-informed and performance-based regulation. Main topics of this project are evaluation of benefit and characteristics of RIR, development of optimized Korean RIR model, impact analysis for the change of current regulation framework, and suggestion of RIR-related laws and rules. The other is focusing on the development in the areas of a regulatory audit PSA model and regulatory guides for risk monitoring, and application techniques of risk information to the significance determination of plant performance indicators and inspection findings. It is expected that a concrete scheme and detailed regulatory techniques for embodiment of RIR system in Korea will be

Safety- and Risk Analysis Activities in Chemical Industry in Europe

International Nuclear Information System (INIS)

Kozine, Igor; Duijm, Nijs Jan; Lauridsen Kurt

2001-01-01

The current paper gives an overview of the legislation and the methods used in safety and risk management in the chemical industry within Europe and in particular within the European Union. The paper is based on a report that has been written for the SOS-1 project under the Nordic nuclear safety research (NKS). Safety- and risk-related matters in the process industry, in particular, in chemical, within the EU are subject to consideration at three levels: (1) EU legislation, (2) European/intemational standardisation, and (3) socio-economic analysis. EC Directives define the 'essential requirements', e.g., protection of health and safety, that must be fulfilled when goods are placed on the market or some industry is put into operation. The European standards bodies (CEN, CENELEC and ETSI) have the task of establishing the corresponding technical specifications, meeting the essential requirements of the Directives, compliance with which will provide a presumption of conformity with the essential requirements. Such specifications are referred to as 'harmonised standards'. Compliance with harmonised standards remains voluntary, and manufacturers are free to choose any other technical solution that provides compliance with the essential requirements. This view is stated in the 'New Approach' to technical harmonisation and standardisation (details can be found on the web page: http://europe.eu.int/comm/enterprise/newapproach/standardization/index .html). Standardisation as well as the regulation of technical risks is increasingly being undertaken at European or international level. The European legislator limits its role to the affirmation of overall objectives, and leaves it to the economic players to draw up the technical procedures and standards to specify in detail the ways and means of attaining them. Many countries have introduced requirements that new legislation and/or administrative regulations be subject to socio-economic analysis. In this respect there is a

Safety- and Risk Analysis Activities in Chemical Industry in Europe

Energy Technology Data Exchange (ETDEWEB)

Kozine, Igor; Duijm, Nijs Jan; Lauridsen Kurt [Risoe National Laboratory, Roskilde (Denmark). Systems Analysis Department

2001-07-01

The current paper gives an overview of the legislation and the methods used in safety and risk management in the chemical industry within Europe and in particular within the European Union. The paper is based on a report that has been written for the SOS-1 project under the Nordic nuclear safety research (NKS). Safety- and risk-related matters in the process industry, in particular, in chemical, within the EU are subject to consideration at three levels: (1) EU legislation, (2) European/intemational standardisation, and (3) socio-economic analysis. EC Directives define the 'essential requirements', e.g., protection of health and safety, that must be fulfilled when goods are placed on the market or some industry is put into operation. The European standards bodies (CEN, CENELEC and ETSI) have the task of establishing the corresponding technical specifications, meeting the essential requirements of the Directives, compliance with which will provide a presumption of conformity with the essential requirements. Such specifications are referred to as 'harmonised standards'. Compliance with harmonised standards remains voluntary, and manufacturers are free to choose any other technical solution that provides compliance with the essential requirements. This view is stated in the 'New Approach' to technical harmonisation and standardisation (details can be found on the web page: http://europe.eu.int/comm/enterprise/newapproach/standardization/index .html). Standardisation as well as the regulation of technical risks is increasingly being undertaken at European or international level. The European legislator limits its role to the affirmation of overall objectives, and leaves it to the economic players to draw up the technical procedures and standards to specify in detail the ways and means of attaining them. Many countries have introduced requirements that new legislation and/or administrative regulations be subject to socio-economic analysis

Strategy for public understanding and participation in nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, H. J.; Chung, Yun Hyung

2004-02-15

The objective of this study is to help the general public and local residents to better understand and trust nuclear safety regulation. In order to obtain public confidence in nuclear safety regulation, the emotion and demand of public should be first understood and the change in an attitude to meet the present circumstances actively is requisite. Hence it is intended that a genuine communication shall be newly arranged and accomplished on the basis of mutual understanding. To achieve this, a series of public opinion poll have performed periodically and symposium for the public acceptance is held in order to frame a policy based on the understanding of nuclear safety and regulation of the general public and local residents. Besides nuclear safety indicators including safety sentiment indicators are being developed as a means to understand the safety of operating nuclear power plants from the viewpoint of the general public, a plan for the harmonious communication of nuclear safety information is established, and handbooks of nuclear terminologies and report-writing are under development in part. Finally plans for convergence of the public opinions and a wide public involvement in nuclear safety regulation are formulated and their applicability as organization and administration program is now under consideration.

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

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)

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.

Risk, regulation and biotechnology: the case of GM crops.

Science.gov (United States)

Smyth, Stuart J; Phillips, Peter W B

2014-07-03

The global regulation of products of biotechnology is increasingly divided. Regulatory decisions for genetically modified (GM) crops in North America are predictable and efficient, with numerous countries in Latin and South America, Australia and Asia following this lead. While it might have been possible to argue that Europe's regulations were at one time based on real concerns about minimizing risks and ensuring health and safety, it is increasingly apparent that the entire European Union (EU) regulatory system for GM crops and foods is now driven by political agendas. Countries within the EU are at odds with each other as some have commercial production of GM crops, while others refuse to even develop regulations that could provide for the commercial release of GM crops. This divide in regulatory decision-making is affecting international grain trade, creating challenges for feeding an increasing global population.

Bases of updating of nuclear safety regulations for NPP in Romania

International Nuclear Information System (INIS)

Biro, Lucian; Serbanescu, Dan

1999-01-01

The paper presents the basic principles of reviewing and updating process of the regulatory environment pyramid. The main part of this review process refers to Cernavoda NPP Unit 2. However, there is an important impact on Cernavoda NPP Unit 1. The basic principles were defined in 1993/1994 when the licensing process for Unit 1 was resumed in order to be in accordance with the latest developments of Candu 600 worldwide and with the IAEA and NEA latest recommended documents and practices. After the licensing process for the Unit 1 was completed up to operation stage, CNCAN developed new updated regulations on nuclear safety and the regulatory pyramid in the framework of the RAMG PHARE project. CNCAN issued in 1996 the regulatory Policy for Unit 2, self-sustained and independent of future possible revisions of the regulations. The use of the concept of hierarchical systems, systematic review of safety criteria and objectives and margins along with the feedback from international and national experience on this topic ensured issuance of a reference document for future approach of nuclear safety in Romania. (authors)

Risk-based regulation - an NRC perspective and status

International Nuclear Information System (INIS)

King, T.L.; Murphy, J.A.

1993-01-01

The consideration of risk in regulatory decision making has traditionally been part of the US Nuclear Regulatory Commission's (NRC's) policy and practice. In the early days of regulation, this consideration was more qualitative in nature and was reflected in prescriptive/deterministic regulatory requirements. However, with the development of quantitative risk assessment methods, more detailed and comprehensive (although not complete) risk information on nuclear power plants is available to the designer, operator, and regulator. The availability of such information provides an opportunity to assess the need for change in the current regulatory structure and to develop future regulatory requirements in a less prescriptive, more performance-oriented fashion

Safety and security in transportation of radioactive material- the perception of risk

Energy Technology Data Exchange (ETDEWEB)

Ericsson, A.M.; Jaernry, C. [AMC Konsult AB, Bromma (Sweden)

2004-07-01

Since the event of September 11, 2001, the way most people look at transportation risk has changed. There is now a lot more focusing on the security concerns related to the transportation of radioactive material. Most people are now more concerned about the risk of terrorist actions or sabotage than of accidents. This is probably due to the fact that the safety record for transportation of radioactive material has so far been very good and that most people experience terrorism and sabotage more scaring and less controllable than general accidents. This paper will compare the safety and the security regulations and discuss synergies and contradictions between the sets of regulations.

Safety and security in transportation of radioactive material- the perception of risk

International Nuclear Information System (INIS)

Ericsson, A.M.; Jaernry, C.

2004-01-01

Since the event of September 11, 2001, the way most people look at transportation risk has changed. There is now a lot more focusing on the security concerns related to the transportation of radioactive material. Most people are now more concerned about the risk of terrorist actions or sabotage than of accidents. This is probably due to the fact that the safety record for transportation of radioactive material has so far been very good and that most people experience terrorism and sabotage more scaring and less controllable than general accidents. This paper will compare the safety and the security regulations and discuss synergies and contradictions between the sets of regulations

Identification of Patient Safety Risks Associated with Electronic Health Records: A Software Quality Perspective.

Science.gov (United States)

Virginio, Luiz A; Ricarte, Ivan Luiz Marques

2015-01-01

Although Electronic Health Records (EHR) can offer benefits to the health care process, there is a growing body of evidence that these systems can also incur risks to patient safety when developed or used improperly. This work is a literature review to identify these risks from a software quality perspective. Therefore, the risks were classified based on the ISO/IEC 25010 software quality model. The risks identified were related mainly to the characteristics of "functional suitability" (i.e., software bugs) and "usability" (i.e., interface prone to user error). This work elucidates the fact that EHR quality problems can adversely affect patient safety, resulting in errors such as incorrect patient identification, incorrect calculation of medication dosages, and lack of access to patient data. Therefore, the risks presented here provide the basis for developers and EHR regulating bodies to pay attention to the quality aspects of these systems that can result in patient harm.

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)

Alternative risk-based criteria for transportation of radioactive materials on the United States Department of Energy Hanford Site

International Nuclear Information System (INIS)

Mercado, J.E.; Field, J.G.; Smith, R.J.; Wang, O.S.

1993-01-01

This paper presents the development of an alternative method to evaluate packaging safety for radioactive material transported solely within the boundaries of a restricted site; the method uses risk-based criteria to assess and document packaging safety. These criteria offer a standard against which the results of a risk assessment are compared to evaluate the safety of a transportation operation. Numerous payloads are transported entirely within the U.S. Department of Energy's Hanford Site boundaries. The U.S. Department of Energy requires that the safety of onsite transportation be equivalent to the safety provided for transporting radioactive materials in commerce as regulated by the U.S. Department of Transportation and the U.S. Nuclear Regulatory Commission. Some onsite packaging configurations do not meet the performance criteria that form the basis of these regulations, necessitating the establishment of alternative criteria to evaluate safety. Quantitatively defined criteria have been derived from the U.S. Department of Transportation limits for package radiation levels, curie content, activity release, and external contamination levels. Recommendations of the International Committee on Radiation Protection may further restrict the criteria. The proposed method documents packaging safety in a transportation risk assessment. The assessment estimates accident frequencies, conservatively evaluates the dose consequences of these accidents, and compares the results to the established risk acceptance criteria. Specific Hanford Site onsite packaging and transportation issues illustrate the alternative method. The paper compares the solutions resulting from the application of risk-based criteria to those resulting from strict compliance with commercial transportation regulations. (author)

Comparison of Country Risk, Sustainability and Economic Safety Indices

Directory of Open Access Journals (Sweden)

Jelena Stankeviciene

2014-03-01

Full Text Available Country risk, sustainability an economic safety are becoming more important in the contemporary economic world. The aim of this paper is to present the importance of comparison formalisation of country risk, sustainability, and economic safety indices for strategic alignment. The work provides an analysis on the relationship between country risk, sustainability an economic safety in EU countries, based on statistical data. Investigations and calculations of rankings provided by Euromoney Country Risk Index, European Economic Sustainability Index as well as for Economic Security Index were made and the results of EU country ranking based on three criteria were provided. Furthermore, the data for the Baltic States was summarised and the corresponding index of consistency for random judgments was evaluated.

Policy for introduction of risk-informed regulation for nuclear facilities in Japan

International Nuclear Information System (INIS)

Akihide Hidaka; Shoichiro Sakaguchi; Toshihiro Bannai; Kunihiro Matsui

2005-01-01

The nuclear safety regulations in Japan place a basis on the deterministic approach with the defence-in-depth philosophy and engineering judgments. However, as the development of PSA (Probabilistic Safety Assessment) technologies in recent years, the Nuclear Safety Commission (NSC) began to consider that the utilization of risk information in addition to the traditional deterministic approach could be very effective for the safety regulations to improve rationality, consistency, transparency and efficiency by appropriate allocation of limited resources for the regulatory activities. In order to show the basic strategy, the NSC published the policy for introduction of Risk-Informed Regulation (RIR) in November 2003. The safety goals that play an important role in RIR were tentatively established in December 2003 while the performance goals are under development as of May, 2005. It is expected that RIR be gradually introduced from the applicable area. The NSC is now examining what the RIR system in Japan should be by making each role and incentive of the competent organizations clear. In the future, when the experiences on application of the safety goals are accumulated, RIR will be consistently applied from design to operational area. This paper describes the recent activities of the NSC for introduction of RIR in Japan and development of the safety goals including the performance goals. (authors)

Prescribing safety, negotiating expertise

International Nuclear Information System (INIS)

Rolina, Gregory

2010-01-01

Owing to their presumed impact on the safety of high-risk installations, the interactions between regulators and the regulated are a major but seldom explored subject of research in risk management. A study by experts on human and organizational factors in nuclear safety sheds light on the various phases (and their effects) of the process whereby experts produce assessments. Light is shed on a 'negotiated expertise' typical of the French style of safety regulations in nuclear installations. It is based on an ongoing technical dialog between experts and operators ('French cooking' for Anglo-Saxons). This analysis of 'expertise' and thus of the 'logics of action' implemented by experts proposes a typology of actions that can be transposed to other sorts of risk or other fields of activity. It hands us the keys for understanding a very contemporary activity. (author)

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...

Risk-informed decision making during Bohunice NPP safety upgrading

International Nuclear Information System (INIS)

Lipar, M.; Muzikova, E.; Kubanyi, J.

2001-01-01

The paper summarizes some facts of risk-informed regulation developments within UJD regulatory environment. Based on national as well as international operating experience and indications resulted from PSA, Nuclear Regulatory Authority of the Slovak Republic (UJD) since its constituting in 1993 has devoted an effort to use PSA technology to support the regulatory policy in Slovakia. The PSA is considered a complement, not a substitute, to the deterministic approach. Suchlike integrated approach is used in decision making processes and the final decision on scope and priorities is based on it. The paper outlines risk insights used in the decision making process concerning Bohunice NPP safety upgrading and focuses on the role of PSA results in Gradual Reconstruction of Bohunice VI NPP. Besides, two other examples of the PSA results application to the decision making process are provided: the assessment of proposal of modifications to the main power supply diagram (incorporation of generator switches) and the assessment of licensee request for motor generator AOT (Allowable Outage Time) extension. As an example of improving support of Bohunice V-2 risk-informed operations, concept of AOT calculations and Bohunice V-2 Risk Monitor Project are briefly described. (author)

Proposal of a risk-factor-based analytical approach for integrating occupational health and safety into project risk evaluation.

Science.gov (United States)

Badri, Adel; Nadeau, Sylvie; Gbodossou, André

2012-09-01

Excluding occupational health and safety (OHS) from project management is no longer acceptable. Numerous industrial accidents have exposed the ineffectiveness of conventional risk evaluation methods as well as negligence of risk factors having major impact on the health and safety of workers and nearby residents. Lack of reliable and complete evaluations from the beginning of a project generates bad decisions that could end up threatening the very existence of an organization. This article supports a systematic approach to the evaluation of OHS risks and proposes a new procedure based on the number of risk factors identified and their relative significance. A new concept called risk factor concentration along with weighting of risk factor categories as contributors to undesirable events are used in the analytical hierarchy process multi-criteria comparison model with Expert Choice(©) software. A case study is used to illustrate the various steps of the risk evaluation approach and the quick and simple integration of OHS at an early stage of a project. The approach allows continual reassessment of criteria over the course of the project or when new data are acquired. It was thus possible to differentiate the OHS risks from the risk of drop in quality in the case of the factory expansion project. Copyright © 2011 Elsevier Ltd. All rights reserved.

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

Improvement of infrastructure for risk-informed regulation

International Nuclear Information System (INIS)

Muta, Hitoshi; Tanji, Junichi; Kondo, Keisuke; Uchida, Tsuyoshi; Ito, Tomomichi

2011-01-01

Improvement of the infrastructure of probabilistic safety assessment (PSA) is essential to the risk-informed regulation for nuclear power plants. JNES conducted update of initiating event frequency and improvement of method for uncertainty analysis to enhance the technology bases of PSA in 2010. Furthermore, JNES improved human reliability assessment method and reliability assessment method for digital reactor protection systems. JNES estimated initiating event frequencies both for power and shutdown operation based on the recent operating experiences in NPPs of Japan using hierarchical Bayesian method. As for improvement of uncertainty analysis method, JNES conducted trial analysis using SOKC (State-Of-Knowledge Correlation) for representative PWR and BWR of Japan. The study on the advanced HRA method with operator cognitive action model was conducted. The study on reliability analysis method for digital reactor protection systems using Bayesian Network Method was conducted. In order to ensure the quality of PSA, JNES studied requirements and methods for PSA peer review via the preparation of peer review for PSA of a representative Japanese BWR plant conducted by JNES. As an effort to develop the procedures of internal fire PSA and internal flooding PSA, trial analyses were conducted to grasp the risk level cause by fire and flooding in nuclear power plants. JNES participated in OECD/NEA PRISME and FIRE project to obtain the latest information and data to validate and improve the fire propagation analysis codes and the parameters for fire PSA. Furthermore, JNES studies schemes for endorsement and application in risk-informed regulation of PSA standards established by Atomic Energy Society of Japan. (author)

After the Fukushima Daiichi Accident, Extending the Human and Organizational Factors (HOF) Framework to Safety Regulation

International Nuclear Information System (INIS)

Chanton, O.; Mangeon, M.; Jeffroy, F.

2016-01-01

The accident of Fukushima-Daichi is regarded as a product of multiple failures of the nuclear risks regulation system in Japan and more particularly as a failure of the regulatory system (authorities, regulator and operator) to take into account seismic risks and flood risks caused by tsunamis. This statement conducted the French institute for radiological protection and nuclear safety (IRSN) to develop a research program dedicated to the study of the way the French nuclear regulatory system developed and addresses flood risks. A regulatory system rests upon a number of institutional and organizational devices and upon normative tools, such as technical standards or guidelines. The aim of these normative tools is to guide NPP operators during both stages of risks identification and characterisation and of the design of protections against risks. These instruments have profound and multiple effects on the stakeholders involved. They affect the design of nuclear facilities, significantly influence the safety demonstration of a plant, but also the manner in which the actions implemented by the operator are evaluated and their reality controlled by the regulator.

Software for occupational health and safety risk analysis based on a fuzzy model.

Science.gov (United States)

Stefanovic, Miladin; Tadic, Danijela; Djapan, Marko; Macuzic, Ivan

2012-01-01

Risk and safety management are very important issues in healthcare systems. Those are complex systems with many entities, hazards and uncertainties. In such an environment, it is very hard to introduce a system for evaluating and simulating significant hazards. In this paper, we analyzed different types of hazards in healthcare systems and we introduced a new fuzzy model for evaluating and ranking hazards. Finally, we presented a developed software solution, based on the suggested fuzzy model for evaluating and monitoring risk.

Guidance on the implementation of a risk based safety performance monitoring system for nuclear power plants

International Nuclear Information System (INIS)

Sewell, R.T.; Kuritzky, A.S.; Khatib-Rahbar, M.

1997-05-01

The principal objective of the present study is to review and evaluate existing Performance Indicator (PI) monitoring programs, and to develop and demonstrate an overall PSA-based methodology and framework for the monitoring and use of risk-based PIs and SIs (Safety Indicator), that would enable: Identification of trends and patterns in safety performance at a specific plant and a population of plants; Assessment of the significance of the trends and patterns; Identification of precursors of accident sequences and safety reductions; Identification of the most critical functional areas of concern, especially as they relate to a defense-in-depth safety philosophy; Comparison of safety performance trends at a plant with those at comparable plants; Incorporation of the PIs and SIs into a risk- and performance-based decision process. To support the overall project objective, it is important that information needs and data collection procedures are clearly outlined. Of key significance in this regard is the premise that a performance monitoring system should not be burdened by an excessive number of low-level PIs that may have only a peripheral relationship to safety. Other supporting objectives of the study include: To identify and discuss other issues pertaining to the practical implementation of a safety performance monitoring system (outlining the databases and algorithms needed); and to demonstrate implementation of the preliminary guidance for monitoring and use of the selected set of PIs and SIs, within the proposed framework, via application to the operating history of a NPP having a PSA and readily available event data

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

Safety Culture for Regulator Competence Management in Embarking States

International Nuclear Information System (INIS)

Kandil, M.

2016-01-01

Full text: Safety is based on preventive actions where the ability of a regulatory body to fulfill its responsibilities depends largely on the competence of its staff. Building employees’ skills and knowledge is an investment for each employee and in the future of the organization. This building must be the competence of its staff integration with their safety culture, the essential to ensure competent human resources as required in the IAEA safety standards and other documents, in which the need and importance of ensuring regulatory competence is emphasized. As it involves both operational and management issues, safety culture is a sensitive topic for regulators whose role is to ensure compliance with safety requirements and not to intervene in management decisions. A number of embarking States are aspiring to develop nuclear power generation and this means that, among other things, regulatory bodies have to be established and rapidly expanded. This paper reports major considerations on the integration of safety culture with an adequate competence management system for regulators in embarking states. (author

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.

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.)

Knowledge-Based Energy Damage Model for Evaluating Industrialised Building Systems (IBS Occupational Health and Safety (OHS Risk

Directory of Open Access Journals (Sweden)

Abas Nor Haslinda

2016-01-01

Full Text Available Malaysia’s construction industry has been long considered hazardous, owing to its poor health and safety record. It is proposed that one of the ways to improve safety and health in the construction industry is through the implementation of ‘off-site’ systems, commonly termed ‘industrialised building systems (IBS’ in Malaysia. This is deemed safer based on the risk concept of reduced exposure, brought about by the reduction in onsite workers; however, no method yet exists for determining the relative safety of various construction methods, including IBS. This study presents a comparative evaluation of the occupational health and safety (OHS risk presented by different construction approaches, namely IBS and traditional methods. The evaluation involved developing a model based on the concept of ‘argumentation theory’, which helps construction designers integrate the management of OHS risk into the design process. In addition, an ‘energy damage model’ was used as an underpinning framework. Development of the model was achieved through three phases, namely Phase I – knowledge acquisitaion, Phase II – argument trees mapping, and Phase III – validation of the model. The research revealed that different approaches/methods of construction projects carried a different level of energy damage, depending on how the activities were carried out. A study of the way in which the risks change from one construction process to another shows that there is a difference in the profile of OHS risk between IBS construction and traditional methods.Therefore, whether the option is an IBS or traditional approach, the fundamental idea of the model is to motivate construction designers or decision-makers to address safety in the design process and encourage them to examine carefully the probable OHS risk variables surrounding an action, thus preventing accidents in construction.

The Competence Promoting by NNSA for Keeping High Level Nuclear Safety: The Corner Stone of the Nuclear Safety Regulation Edifice

International Nuclear Information System (INIS)

Hu, L.

2016-01-01

Facing the fast development of the nuclear power industry and the application of radioactive sources, The MEP(NNSA) is endeavoured to promoting its competency, including: complementing the law system, training and recruiting staff to keep a capable team, constructing the R&D base to keep the basic capability, promoting safety culture both for the industry and the regulator. After the Fukushima nuclear accident, the MEP(NNSA) planned to construct R&D base, in which the Platform Nuclear Safety Monitoring and Emergency Responding, the Platform of Safety Technology of PWR Testing, the Laboratory of Safety Management Technology of Nuclear Waste Verification, the Laboratory of Environmental Radiation Monitoring and the Center of International Cooperation are included. On the other hand, the MEP(NNSA) issued Chinese nuclear safety culture policy declaration in 2014, and carried out a large scale Specialized Action for Nuclear Safety Promotion to promote the nuclear safety culture both for the industry and herself. For the nuclear regulator, It is essential to conduct the competence promoting by both “hardware” and “software”, the former is the material foundation of regulation authority, which will be effectively functioning under the facilitating of the latter. (author)

Research needs for risk-informed, performance-based regulation

International Nuclear Information System (INIS)

Bailey, J.A.

1997-01-01

Palo Verde Nuclear Generating Station has used PRA-derived risk insights for about 10 years now. The plant originally started applying PRA modeling to an auxiliary feedwater system during the initial licensing phases of the plant, and as a result of that, they were able to work with the NRC and apply some graded quality requirements to that particular system. There was a third redundant auxiliary feedwater pump, and they now can treat that system as partially safety related and partially non-safety related. So it was an advance for Palo Verde at that time to be able to make decisions with a PRA and they began learning how to use those techniques. After completing the IPE it became natural for the plant to make a transition into other areas at the plant to look for areas where the insights gained from PRA could be applied into their decision-making processes. Those that the plant embarked upon initially were areas where they could gain operational risk assessment insights. The author goes on to discuss experiences gained in using these techniques to better assess the safety of operations within the plant. In addition he offers comments on areas which need further development and research to make them more applicable to a plant by plant basis

Fog lamp regulation as a safety measure to reduce risk in fog conditions.

NARCIS (Netherlands)

Oppe, S.

1992-01-01

This short note summarizes the relevant aspects for a decision concerning the fog lamp use regulation. Most motorway accidents in the Netherlands took place in fog conditions in the early morning hours. The safety problem in fog conditions is a serious problem caused by bad driving behaviour. The

Protection of environment, health and safety using risk management

Energy Technology Data Exchange (ETDEWEB)

Abraham, G [Ghafari Associates, Inc. 17101 Michegan Avenue Dearborn, MI 48126-2736 (United States); Kummler, R H [Department of Chemical engineering Wayne Stae University Detroit, MI 48202 (United States); louvar, J [Research Services Basf Corporation Wyandotte, MI 48192 (United States)

1997-12-31

Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA`s PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility`s need for compliance and review the regulations for risk management.

Protection of environment, health and safety using risk management

International Nuclear Information System (INIS)

Abraham, G.; Kummler, R.H.; louvar, J.

1996-01-01

Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA's PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility's need for compliance and review the regulations for risk management

Assessment of safety regulation using an artificial society

International Nuclear Information System (INIS)

Furuta, Kazuo; Nagase, Masaya

2005-01-01

This study proposes using an artificial society to assess impacts of safety regulation on the society. The artificial society used in this study is a multi-agent system, which consists of many agents representing companies. The agents cannot survive unless they get profits by producing some products. Safety regulation functions as the business environment, which the agents will evolve to fit to. We modeled this process of survival and adaptation by the genetic algorithm. Using the proposed model, case simulations were performed to compare various regulation styles, and some interesting insights were obtained how regulation style influences behavior of the agents and then productivity and safety level of the industry. In conclusion, an effective method for assessment of safety regulation has been developed, and then several insights were shown in this study

Towards a Fuzzy Bayesian Network Based Approach for Safety Risk Analysis of Tunnel-Induced Pipeline Damage.

Science.gov (United States)

Zhang, Limao; Wu, Xianguo; Qin, Yawei; Skibniewski, Miroslaw J; Liu, Wenli

2016-02-01

Tunneling excavation is bound to produce significant disturbances to surrounding environments, and the tunnel-induced damage to adjacent underground buried pipelines is of considerable importance for geotechnical practice. A fuzzy Bayesian networks (FBNs) based approach for safety risk analysis is developed in this article with detailed step-by-step procedures, consisting of risk mechanism analysis, the FBN model establishment, fuzzification, FBN-based inference, defuzzification, and decision making. In accordance with the failure mechanism analysis, a tunnel-induced pipeline damage model is proposed to reveal the cause-effect relationships between the pipeline damage and its influential variables. In terms of the fuzzification process, an expert confidence indicator is proposed to reveal the reliability of the data when determining the fuzzy probability of occurrence of basic events, with both the judgment ability level and the subjectivity reliability level taken into account. By means of the fuzzy Bayesian inference, the approach proposed in this article is capable of calculating the probability distribution of potential safety risks and identifying the most likely potential causes of accidents under both prior knowledge and given evidence circumstances. A case concerning the safety analysis of underground buried pipelines adjacent to the construction of the Wuhan Yangtze River Tunnel is presented. The results demonstrate the feasibility of the proposed FBN approach and its application potential. The proposed approach can be used as a decision tool to provide support for safety assurance and management in tunnel construction, and thus increase the likelihood of a successful project in a complex project environment. © 2015 Society for Risk Analysis.

49 CFR 176.4 - Port security and safety regulations.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Port security and safety regulations. 176.4... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS CARRIAGE BY VESSEL General § 176.4 Port security and safety regulations. (a) Each carrier, master, agent, and charterer of a...

Safety regulation on high-pressure gas and gas business

International Nuclear Information System (INIS)

Kim, Du Yeoung; An, Dae Jun

1978-09-01

This book is divided into two parts. The first part introduces safety regulation on high-pressure gas, enforcement ordinance on safety regulation about high-pressure gas and enforcement regulation on safety regulation about high-pressure gas. The second part indicates regulations on gas business such as general rules, gas business gas supplies, using land, supervision, supple mentary rules and penalty. It has two appendixes on expected questions and questions during last years.

Risk informed regulation of nuclear facilities: Overview of the current status

International Nuclear Information System (INIS)

2005-02-01

This report provides guidance on the use of risk information by regulatory bodies as part of an integrated decision making process. This addresses the way in which risk information is being used in decisions about safety issues at nuclear plants, sometimes referred to as risk informed decision making, and how risk information is being used by regulatory bodies as an input into the activities that they carry out, sometimes referred to as risk informed regulation

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)

Managing for safety and safety culture within the UK nuclear industry. A regulator's perspective

International Nuclear Information System (INIS)

Tyrer, M.J.

2002-01-01

This paper outlines the basis of the legal system for the regulation of health and safety at work within the United Kingdom (UK), and in particular, the regulation of the nuclear industry. The framework, formulated by the regulator, which has been published as a practical guide for directors, managers, health and safety professionals and employee representatives for the successful management of health and safety is explained. This guidance, however, concentrates, to a large extent, on management systems and only addresses in part the types of issues, such as behaviours, values, attitudes and beliefs which contribute to the safety culture of an organization. The regulator of the UK nuclear industry has considered research, and other work, carried out by several organizations in this area, notably the Advisory Committee on the Safety of Nuclear Installations (ACSNI) and the International Atomic Energy Agency (IAEA), and produced its own framework for managing for safety at nuclear installations. As a regulator, the Health and Safety Executive (HSE), and its inspectorate responsible for regulation of the nuclear industry, HM Nuclear Installations Inspectorate (HMNII), are not the appropriate organization to assess the safety culture of an organization, but positively encourage organizations to both carry out this assessment themselves and to monitor their performance. To this end, HSE has developed, and made available, the Health and Safety Climate Tool which is aimed at providing organizations with information which can be used as part of a continuous improvement process. (author)

An evaluation of a risk-based environmental regulation in Brazil: Limitations to risk management of hazardous installations

International Nuclear Information System (INIS)

Naime, Andre

2017-01-01

The environmental regulation of hazardous projects with risk-based decision-making processes can lead to a deficient management of human exposure to technological hazards. Such an approach for regulation is criticized for simplifying the complexity of decisions involving the economic, social, and environmental aspects of the installation and operation of hazardous facilities in urban areas. Results of a Brazilian case study indicate that oil and gas transmission pipelines may represent a threat to diverse communities if the relationship between such linear projects and human populations is overlooked by regulatory bodies. Results also corroborate known challenges to the implementation of EIA processes and outline limitations to an effective environmental and risk management. Two preliminary topics are discussed to strengthen similar regulatory practices. Firstly, an effective integration between social impact assessment and risk assessment in EIA processes to have a more comprehensive understanding of the social fabric. Secondly, the advancement of traditional management practices for hazardous installations to pursue a strong transition from assessment and evaluation to management and control and to promote an effective interaction between land-use planning and environmental regulation.

An evaluation of a risk-based environmental regulation in Brazil: Limitations to risk management of hazardous installations

Energy Technology Data Exchange (ETDEWEB)

Naime, Andre, E-mail: andre.naime.ibama@gmail.com

2017-03-15

The environmental regulation of hazardous projects with risk-based decision-making processes can lead to a deficient management of human exposure to technological hazards. Such an approach for regulation is criticized for simplifying the complexity of decisions involving the economic, social, and environmental aspects of the installation and operation of hazardous facilities in urban areas. Results of a Brazilian case study indicate that oil and gas transmission pipelines may represent a threat to diverse communities if the relationship between such linear projects and human populations is overlooked by regulatory bodies. Results also corroborate known challenges to the implementation of EIA processes and outline limitations to an effective environmental and risk management. Two preliminary topics are discussed to strengthen similar regulatory practices. Firstly, an effective integration between social impact assessment and risk assessment in EIA processes to have a more comprehensive understanding of the social fabric. Secondly, the advancement of traditional management practices for hazardous installations to pursue a strong transition from assessment and evaluation to management and control and to promote an effective interaction between land-use planning and environmental regulation.

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.

Knowledge and perceived implementation of food safety risk analysis framework in Latin America and the Caribbean region.

Science.gov (United States)

Cherry, C; Mohr, A Hofelich; Lindsay, T; Diez-Gonzalez, F; Hueston, W; Sampedro, F

2014-12-01

Risk analysis is increasingly promoted as a tool to support science-based decisions regarding food safety. An online survey comprising 45 questions was used to gather information on the implementation of food safety risk analysis within the Latin American and Caribbean regions. Professionals working in food safety in academia, government, and private sectors in Latin American and Caribbean countries were contacted by email and surveyed to assess their individual knowledge of risk analysis and perceptions of its implementation in the region. From a total of 279 participants, 97% reported a familiarity with risk analysis concepts; however, fewer than 25% were able to correctly identify its key principles. The reported implementation of risk analysis among the different professional sectors was relatively low (46%). Participants from industries in countries with a long history of trade with the United States and the European Union, such as Mexico, Brazil, and Chile, reported perceptions of a higher degree of risk analysis implementation (56, 50, and 20%, respectively) than those from the rest of the countries, suggesting that commerce may be a driver for achieving higher food safety standards. Disagreement among respondents on the extent of the use of risk analysis in national food safety regulations was common, illustrating a systematic lack of understanding of the current regulatory status of the country. The results of this survey can be used to target further risk analysis training on selected sectors and countries.

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

A study on the relevance and influence of the existing regulation and risk informed/performance based regulation

Energy Technology Data Exchange (ETDEWEB)

Cheong, B. J.; Koh, Y. J.; Kim, H. S.; Koh, S. H.; Kang, D. H.; Kang, T. W. [Cheju National Univ., Jeju (Korea, Republic of)

2004-02-15

The goal of this study is to estimate the Relevance and Influence of the Existing Regulation and the RI-PBR to the institutionalization of the regulatory system. This study reviews the current regulatory system and the status of the RI-PBR implementation of the US NRC and Korea based upon SECY Papers, Risk Informed Regulation Implementation Plan (RIRIP) of the US NRC and other domestic studies. Also the recent trends of the individual technologies regarding the RI-PBR and RIA are summarized.

Intelligent monitoring-based safety system of massage robot

Institute of Scientific and Technical Information of China (English)

胡宁; 李长胜; 王利峰; 胡磊; 徐晓军; 邹雲鹏; 胡玥; 沈晨

2016-01-01

As an important attribute of robots, safety is involved in each link of the full life cycle of robots, including the design, manufacturing, operation and maintenance. The present study on robot safety is a systematic project. Traditionally, robot safety is defined as follows: robots should not collide with humans, or robots should not harm humans when they collide. Based on this definition of robot safety, researchers have proposed ex ante and ex post safety standards and safety strategies and used the risk index and risk level as the evaluation indexes for safety methods. A massage robot realizes its massage therapy function through applying a rhythmic force on the massage object. Therefore, the traditional definition of safety, safety strategies, and safety realization methods cannot satisfy the function and safety requirements of massage robots. Based on the descriptions of the environment of massage robots and the tasks of massage robots, the present study analyzes the safety requirements of massage robots; analyzes the potential safety dangers of massage robots using the fault tree tool; proposes an error monitoring-based intelligent safety system for massage robots through monitoring and evaluating potential safety danger states, as well as decision making based on potential safety danger states; and verifies the feasibility of the intelligent safety system through an experiment.

Analysis of concept and application or Risk-Informed Performed-Based Regulation (RI-PBR)

International Nuclear Information System (INIS)

Kim, W. S.; Sung, K. Y.; Lee, C. J.; Kim, H. J.

2002-01-01

For improving regulation of nuclear power plants, the USNRC is adopting the Risk-Informed Performance-Based Regulation (RI-PBR) as an alternative, in parallel with implementing current deterministic regulation. This paper introduces a research plan for 'Institutionalization of RI-PBR' that is being conducted by KINS as a national project for evaluating feasibility for application of the alternative to Korean regulation system. Analysis of regulation characteristics, case study and experience on RI-PBR were presented as interim research results. In addition, the future plan of development of RI-PBR concept as understandable to the public and evaluation of level of techniques needed for implementation of RI-PBR was introduced

NRC safety research in support of regulation, 1988

International Nuclear Information System (INIS)

1989-05-01

This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

Bowtie Risk Management methodology and Modern Nuclear Safety Reports

International Nuclear Information System (INIS)

Ilizastigui Pérez, F.

2016-01-01

The Safety Report (SR) plays a crucial role within the nuclear licensing regime as the principal means for demonstrating the adequacy of safety analysis for a nuclear facility to ensure that it can be constructed, operated, maintained, shut down, and decommissioned safely and in compliance with applicable laws and regulations. It serves as the basis for granting authorizations for the commencement of the main stages of the facility’s life cycle as well as decision-making processes related to safety. Historically, the majority of nuclear safety reports have operated under rather prescriptive regimes, with emphasis placed on demonstrations of the robustness of the facility’s design (design safety) against prescriptive technical requirements set by the regulatory body, and less attention paid to demonstrating the adequacy and effectiveness of Operator’s management system for managing risks to daily operation.

Handbook of methods for risk-based analysis of technical specifications

International Nuclear Information System (INIS)

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

1996-01-01

Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operations (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements are based on deterministic analyses and engineering judgments. Improvements in these requirements are facilitated by the availability of plant-specific Probabilistic Risk Assessments (PRAs). The US Nuclear Regulatory Commission (USNRC) Office of Research sponsored research to develop systematic, risk-based methods to improve various aspects of TS requirements. A handbook of methods summarizing such risk-based approaches has been completed in 1994. It is expected that this handbook will provide valuable input to NRC's present work in developing guidance for using PRA in risk-informed regulation. The handbook addresses reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), managing plant configurations, and scheduling maintenance

From mutual recognition to mutual scientific opinion? Constitutional framework for risk analysis in EU food safety law

NARCIS (Netherlands)

Szajkowska, A.

2009-01-01

Regulation 178/2002 (the so-called General Food Law – GFL) codifies risk analysis as the core principle of the modern food safety policy. This article places the GFL in EU multi-level food safety governance and analyses the impact of risk analysis, the precautionary principle and mechanisms of

Risk and safety in the nuclear industry and conventional norms of society

International Nuclear Information System (INIS)

Tadmor, J.

1977-01-01

The societal acceptance of various risks is analyzed and rules of risk acceptance as a function of different parameters (e. g., expected benefit, intensity of effect) are spelled out. The monetary value of a human life is estimated, based on investments in safety of different human activities. The acceptable risks and safety investments in different human activities are then compared with risks and safety investments of the nuclear industry. Safety investments required to reduce radioactivity releases and risks from nuclear power stations to ALAP (as low as practiable) levels are taken as a study case. It is found that risks in the nuclear industry are several orders of magnitude lower and safety investments per human life saved are several orders of magnitude higher, as compared with risks and safety investments in other human activities

Risk-informed approach for safety, safeguards, and security (3S) by design

International Nuclear Information System (INIS)

Suzuki, Mitsutoshi; Burr, Tom; Howell, John

2011-01-01

Over several decades the nuclear energy society worldwide has developed safety assessment methodology based on probabilistic risk analysis for incorporating its benefit into design and accident prevention for nuclear reactors. Although safeguards and security communities have different histories and technical aspects compared to safety, risk assessment as a supplement to their current requirements could be developed to promote synergism between Safety, Safeguards, and Security (3S) and to install effective countermeasures in the design of complex nuclear fuel cycle facilities. Since the 3S initiative was raised by G8 countries at Hokkaido Toyako-Summit in 2008, one approach to developing synergism in a 3S By Design (3SBD) process has been the application of risk-oriented assessment methodology. In the existing regulations of safeguards and security, a risk notion has already been considered for inherent threat and hazard recognition. To integrate existing metrics into a risk-oriented approach, several mathematical methods have already been surveyed, with attention to the scarcity of intentional acts in the case of safeguards and the sparseness of actual event data. A two-dimensional probability distribution composed of measurement error and incidence probabilities has been proposed to formalize inherent difficulties in the International Atomic Energy Agency (IAEA) safeguards criteria. In particular, the incidence probability that is difficult to estimate has been explained using a Markov model and game theory. In this work, a feasibility study of 3SBD is performed for an aqueous reprocessing process, and synergetic countermeasures are presented for preliminary demonstration of 3SBD. Although differences and conflicts between individual 'S' communities exist, the integrated approach would be valuable for optimization and balance between the 3S design features as well as for effective and efficient implementation under existing regulation frameworks. In addition

Application of the risk based inspection in chemical and nuclear installations: a critical evaluation

International Nuclear Information System (INIS)

Sousa, Anna Leticia Barbosa de

2004-01-01

Risk-based Inspection (RBI) has arisen as an opportunity for the industry to give a specific treatment to items as equipment integrity, failures consequences and the level of risk of each piece of equipment in the inspection programs definitions. Risk-based inspection programs are replacing the traditional ones based on prescriptive requirements, for both the oil and nuclear industries. The aim of this thesis is to demonstrate how the nuclear industry has gotten over several difficulties in implementing risk-based programs considering that its safety design and regulations have traditionally been based on deterministic and prescriptive criteria and requirements. During the development of the work, the study has shown how the absence of a rigid regulation favored the dissemination of RBI diffusion in the oil industry, mainly in the USA, where such industries do not face those difficulties found by the European plants, as long as it is well known that in Europe there are complex interrelations among documents from different countries with diversity of regulation procedures. (author)

Safety Politics and Risk Perceptions in Malaysian Industry

DEFF Research Database (Denmark)

Wangel, Arne

Abstract The book deals with the analysis of work hazards and safety in industrial enterprises in Peninsular Malaysia, Southeast Asia. It traces the development of this theme of conflict within the context constituted by state, labour market and labour-management relations in Malaysia. The book...... and safety, when compared with the influence of local conditions? What kind of process develops, as local theory about work hazards are formed among workers. And, which are the opportunities for changing working environment institutions in Malaysia? The first part of the book discusses traditions...... by the state from Burawoy, Beronius, and Adesina about production politics and social relations in the labour process provides an integrated perspective on individual risk perceptions, safety practices in enterprises, and government regulation. The empirical data were collected during the period 1989...

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.)

Discussion on the safety production risk managmeent of uranium mines

International Nuclear Information System (INIS)

Liu Bin; Luo Yun; Hu Penghua; Zhu Disi

2009-01-01

Based on the modern safety risk management theories and according to the actual situation, risk management for work safety in uranium mines is discussed from three aspects: risk identification,risk analysis and evaluation, and risk control. Referring to the '4M(Men,Machine,Medium,Management) factors' and 'Three types of hazards' theory, the classification of uranium mine accidents and risk factors are analyzed. In addition, the types and evaluation indexes of major risks of uranium mines as well as the 'spot, line, area' model of risk identification and analysis and the 'hierarchical' risk control mechanism are also studied. (authors)

Risk communication activities toward nuclear safety in Tokai: your safety is our safety

International Nuclear Information System (INIS)

Tsuchiya, T.

2007-01-01

As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C 3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C 3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

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

Development and application of nuclear safety goals in Japan. Lessons learnt from the case of 2003 draft safety goals

International Nuclear Information System (INIS)

Sugawara, Shin-etsu; Inamura, Tomoaki

2016-01-01

The Nuclear Safety Commission in Japan offered a detailed draft of nuclear safety goals to the public in 2003, though its position was ambiguous in nuclear safety regulation. This report shows the circumstances behind the development and application of 2003 draft safety goals based on our interviews with the experts who had been involved in making the draft. According to our interviews, they had intention to utilize safety goals for improving risk management of regulatory authority and nuclear energy industry, such as ameliorating deterministic regulations, accumulating experience of risk assessment and management, promoting related research, and communicating risks with general public. In practice, however, safety goals had functioned as a tool for emphasizing an assertion that 'nuclear power plants had already been safe enough'. We identified the following four major impediments to utilizing safety goals; 1) lack of sharing overall recognition of the importance of establishing safety goals among nuclear community, 2) excessive emphasis of internal event risks which leads to an inferior priority to tackle with the issue of external events risks, 3) adverse effect of 'tunnel-visioned incrementalism', that is, nuclear energy industrial entities are attracted their foci too much on what they have been told to do by regulators or local governments, and, 4) negative attitude to disclose the outcomes of risk assessment for fear of societal reactions. To encourage upcoming safety goals and risk management, this report provides the following points for overcoming these problems; 1) sharing insights on the reasons why nuclear community set up safety goals, 2) introducing the concept of adaptive risk management for maintaining questioning attitude, 3) conducting a periodic review of goal attainment level and also safety goals themselves from the eyes of a detached observer, and, 4) rebuilding relationship with society beginning with arguments with local stakeholders over

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.

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

Fire safety regulations and licensing

International Nuclear Information System (INIS)

Berg, H.P.

1998-01-01

Experience of the past tow decades of nuclear power plant operation and results obtained from modern analytical techniques confirm that fires may be a real threat to nuclear safety and should receive adequate attention from the design phase throughout the life of the plant. Fire events, in particular influence significantly plant safety due to the fact that fires have the potential to simultaneously damage components of redundant safety-related equipment. Hence, the importance of fire protection for the overall safety of a nuclear power plant has to be reflected by the fire safety regulations and to be checked during the licensing process of a plant as well as during the continuous supervision of the operating plant

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

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.

Behavior based safety

International Nuclear Information System (INIS)

Sudhikumaran, T.V.; Mehta, S.C.; Goyal, D.K.

2009-01-01

Behaviour Based Safety (popularly known as BBS) is a new methodology for achieving injury free work place and total Safety Culture. BBS is successfully being implemented and is being practiced as a work methodology for achieving a loss and injury free work environment and work practice. Through BBS, it was brought out that the root causes of all Industrial accidents some how originate from the 'at risk' behaviour of some individual or group of individuals at some level. The policy of NPCIL is to excel in the field of Industrial and Fire Safety in comparison to international standards. This article indents to bring out the various parameters helping in installing BBS programme at any plant. (author)

A nuclear safety in 21 century

International Nuclear Information System (INIS)

Osmachkin, V.S.

2003-01-01

In the paper some topics of nuclear safety are discussed, namely current situation in the world energetics and a potential of nuclear energy for sustainable development of the world, Nuclear Safety Standards and modern trends in Safety Regulation, Radiation Protection Standards are rather conservative, are based on disputable approaches and have to be more pragmatic, necessity to overcome the syndromes of awful consequences of nuclear accidents at nuclear plants, residual risks of nuclear accidents have to be covered by clear compulsory insurance actions. It is shown, that now it is worthwhile to consider efficiency of existing methods of nuclear safety regulation. It is possible, that an idea of guaranteed safety [1] could become a new approach to nuclear safety. It is based on practically total elimination of severe accidents and insurance of residual risks of nuclear accidents. The realization of such idea necessitates the consideration of all spectrum of initiating events, human errors and man-made actions, more realistically predicting consequences of accidents and the probable economical detriments. It will be a benefit for gaining public support to nuclear power. (author)

Fuzzy-based Prioritization of Health, Safety, and Environmental Risks: The Case of a Large Gas Refinery

Directory of Open Access Journals (Sweden)

Auob Mirsaeidi

2017-01-01

Full Text Available The main objective of this study was to develop a fuzzy–based framework for the prioritization of health, safety and environment related risks posed against employees, working conditions, and process equipment in large gas refineries. The First Refinery at Pars Special Economic Energy Zone in South of Iran was taken as a case study. For this purpose, health, safety and environment related risks were determined based on the three criteria of impact severity, occurrence probability, and detect-ability using a questionnaire of 33 identified failures. The values obtained were processed by a so-called ‘contribution coefficient’. The results were then subjected to fuzzification and fuzzy rules were defined to calculate the risk level indices as the model outputs, which was then employed to facilitate the management decision-making process by prioritizing the management options. The prioritization values were then classified in six categories in the order of risk severity. Results revealed that failure in a combustion furnace had the highest rank while failure in the slug catcher ranked the lowest among the risk sources. It was also found that about 0.4% of the identified risks prioritized as “intolerable”, 79% as “major”, 20% as “tolerable”, and 0.7% as “minor”. Thus, most of the risks (more than 79% associated with the refinery has the potential of significant risks. The results indicated that the risk of the pollutant emissions from the combustion furnaces is the highest. Exposures to harmful physical, chemical, psychological, and ergonomic substances are the other risks, respectively.

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.

Study on default setting for risk-informed regulation

International Nuclear Information System (INIS)

Jang, S.C.; Ha, J.J.; Jung, W.D.; Jeong, K.S.; Han, S.H.

1998-12-01

Both performing and validating a detailed risk analysis of a complex system are costly and time-consuming undertakings. With the increased use of probabilistic safety analysis (PSA) in regulatory decision making, both regulated parties and regulators have generally favored the use of defaults, because they can greatly facilitate the process of performing a PSA in the first place as well as the process of reviewing and verifying the PSA. The use of defaults may also ensure more uniform standards of PSA quality. However, regulatory agencies differ in their approaches to the use of default values, and the implications of these differences are not yet well understood. Moreover, large heterogeneity among licensees makes it difficult to set suitable defaults. This study focus on the development of model for setting defaults in order to achieve more applicability of risk-informed regulation. In particular, explored are the effects of different levels of conservatism in setting defaults, and their implications for the crafting of regularity incentives. (author). 17 refs., 1 tab

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.

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.

Economic consideration of nuclear safety and cost benefit analysis in nuclear safety regulation

International Nuclear Information System (INIS)

Choi, Y. S.; Choi, K. S.; Choi, K. W.; Song, I. J.; Park, D. K.

2001-01-01

For the optimization of nuclear safety regulation, understanding of economic aspects of it becomes increasingly important together with the technical approach used so far to secure nuclear safety. Relevant economic theories on private and public goods were reviewed to re-illuminate nuclear safety from the economic perspective. The characteristics of nuclear safety as a public good was reviewed and discussed in comparison with the car safety as a private safety good. It was shown that the change of social welfare resulted from the policy change induced can be calculated by the summation of compensating variation(CV) of individuals. It was shown that the value of nuclear safety could be determined in monetary term by this approach. The theoretical background and history of cost benefit analysis of nuclear safety regulation were presented and topics for future study were suggested

Current products and future plan of regulatory technology R and D for risk-informed regulation and applications

International Nuclear Information System (INIS)

Song, K. Y.; Lee, C. J.; Kim, W. S.; Jeong, D. W.; Kim, H. J.

2002-01-01

The first phase of a R and D project for risk-informed regulation (RIR) and applications (RIA) has been finished. Various results which would be useful for preparing domestic RIR system were accomplished, in areas of safety goals and general principles of RIR, which provide fundamental bases for establishment of RIR system as well as regulatory review guides, which ensure the quality for PSA. RIA guidelines for ISI, IST, MOV, Tech.-Sepc. also have been developed, implementing some pilot plant applications. As essential documents for actual RIR inspection, risk-informed inspection guides and implementation guide for maintenance effectiveness were prepared. In the second phase of R and D, two projects on RIR area will be performed. One is to study on institutionalization of RIR and performance-based regulation, another is to develop a PSA model for regulatory audit as well as regulatory technology for risk monitoring

The Hidden Risk Decisions in Waste Repository Regulation

International Nuclear Information System (INIS)

Frishman, Steve

2001-01-01

The move toward risk-informed, performance-based regulation of activities involving radioactive materials is becoming wide spread and broadly applied. While this approach may have some merit in specific applications in which there is a considerable body of experience, its strict application in regulation of geologic repositories for highly radioactive wastes may not be appropriate for this unproven and socially controversial technology. The U.S. Nuclear Regulatory Commission describes risk-informed, performance-based regulation as 'an approach in which risk insights, engineering analysis and judgement (eg. defense in depth), and performance history are used to (1) focus attention on the most important activities, (2) establish objective criteria based upon risk insights for evaluating performance, (3) develop measurable or calculable parameters for monitoring system and licensee performance, and (4) focus on the results as the primary basis for regulatory decision-making.' Both the risk-informed and performance-based elements of the approach are problematic when considering regulation of geologic repositories for highly radioactive wastes - an activity yet to be accomplished by any nation. In investigating potential sites for geologic repositories there will always be residual uncertainty in understanding the natural system and the events and processes that affect it. The more complex the natural system, the greater will be the uncertainty in both the data and the models used to describe the characteristics of the site's natural barriers, and the events and processes that could affect repository waste isolation. The engineered barriers also are subject to uncertainties that are important to the repository system. These uncertainties translate themselves into a range of probabilities that certain events or processes, detrimental to waste isolation, will occur. The uncertainties also translate to a range of consequences and magnitudes of consequences, should the

Radiation Safety (Qualifications) Regulations 1980

International Nuclear Information System (INIS)

1980-01-01

These Regulations, promulgated pursuant to the provisions of the Radiation Safety Act, 1975-1979, require persons engaged in activities involving radiation to pass a radiation safety examination or to possess an approved qualification in radiation. The National Health and Medical Research Council is authorised to exempt persons from compliance with these requirements or, conversely, to impose such requirements on persons other than those designated. (NEA) [fr

Risk-based performance indicators

International Nuclear Information System (INIS)

Azarm, M.A.; Boccio, J.L.; Vesely, W.E.; Lofgren, E.

1987-01-01

The purpose of risk-based indicators is to monitor plant safety. Safety is measured by monitoring the potential for core melt (core-melt frequency) and the public risk. Targets for these measures can be set consistent with NRC safety goals. In this process, the performance of safety systems, support systems, major components, and initiating events can be monitored using measures such as unavailability, failure or occurrence frequency. The changes in performance measures and their trends are determined from the time behavior of monitored measures by differentiation between stochastical and actual variations. Therefore, degradation, as well as improvement in the plant safety performance, can be determined. The development of risk-based performance indicators will also provide the means to trace a change in the safety measures to specific problem areas which are amenable to root cause analysis and inspection audits. In addition, systematic methods will be developed to identify specific improvement policies using the plant information system for the identified problem areas. The final product of the performance indicator project will be a methodology, and an integrated and validated set of software packages which, if properly interfaced with the logic model software of a plant, can monitor the plant performance as plant information is provided as input

Environmental Regulation and Food Safety: Studies of Protection ...

International Development Research Centre (IDRC) Digital Library (Canada)

Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Book cover Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Directeur(s) : Veena Jha. Maison(s) d'édition : Edward Elgar, IDRC. 1 janvier 2006. ISBN : 184542512X. 250 pages. e-ISBN : 155250185X.

Pesticide regulations and farm worker safety: the need to improve pesticide regulations in Viet Nam.

Science.gov (United States)

Phung, Dung Tri; Connell, Des; Miller, Greg; Rutherford, Shannon; Chu, Cordia

2012-06-01

Agricultural pesticide use in Viet Nam has more than tripled since 1990. However, pesticide legislation and regulations have not been developed in response to this large increase in usage, as a result of which pesticides pose a serious threat to human health and the environment. This paper identifies the need to improve pesticide regulations in Viet Nam through a comparative analysis of pesticide regulations in Viet Nam and the United States of America, where the rate of acute poisoning among agricultural workers is much lower than in Viet Nam and where information pertaining to pesticide regulations is made accessible to the public. The analysis identified several measures that would help to improve Viet Nam's pesticide regulations. These include enhancing pesticide legislation, clarifying the specific roles and active involvement of both the environmental and health sectors; performing a comprehensive risk-benefit evaluation of pesticide registration and management practices; improving regulations on pesticide suspension and cancellation, transport, storage and disposal; developing import and export policies and enhancing pesticide-related occupational safety programmes.

48 CFR 245.7311-2 - Safety, security, and fire regulations.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Safety, security, and fire regulations. 245.7311-2 Section 245.7311-2 Federal Acquisition Regulations System DEFENSE ACQUISITION... Inventory 245.7311-2 Safety, security, and fire regulations. ...

Study of a risk-based piping inspection guideline system.

Science.gov (United States)

Tien, Shiaw-Wen; Hwang, Wen-Tsung; Tsai, Chih-Hung

2007-02-01

A risk-based inspection system and a piping inspection guideline model were developed in this study. The research procedure consists of two parts--the building of a risk-based inspection model for piping and the construction of a risk-based piping inspection guideline model. Field visits at the plant were conducted to develop the risk-based inspection and strategic analysis system. A knowledge-based model had been built in accordance with international standards and local government regulations, and the rational unified process was applied for reducing the discrepancy in the development of the models. The models had been designed to analyze damage factors, damage models, and potential damage positions of piping in the petrochemical plants. The purpose of this study was to provide inspection-related personnel with the optimal planning tools for piping inspections, hence, to enable effective predictions of potential piping risks and to enhance the better degree of safety in plant operations that the petrochemical industries can be expected to achieve. A risk analysis was conducted on the piping system of a petrochemical plant. The outcome indicated that most of the risks resulted from a small number of pipelines.

Bayesian Network Assessment Method for Civil Aviation Safety Based on Flight Delays

OpenAIRE

Huawei Wang; Jun Gao

2013-01-01

Flight delays and safety are the principal contradictions in the sound development of civil aviation. Flight delays often come up and induce civil aviation safety risk simultaneously. Based on flight delays, the random characteristics of civil aviation safety risk are analyzed. Flight delays have been deemed to a potential safety hazard. The change rules and characteristics of civil aviation safety risk based on flight delays have been analyzed. Bayesian networks (BN) have been used to build ...

Product-based Safety Certification for Medical Devices Embedded Software.

Science.gov (United States)

Neto, José Augusto; Figueiredo Damásio, Jemerson; Monthaler, Paul; Morais, Misael

2015-01-01

Worldwide medical device embedded software certification practices are currently focused on manufacturing best practices. In Brazil, the national regulatory agency does not hold a local certification process for software-intensive medical devices and admits international certification (e.g. FDA and CE) from local and international industry to operate in the Brazilian health care market. We present here a product-based certification process as a candidate process to support the Brazilian regulatory agency ANVISA in medical device software regulation. Center of Strategic Technology for Healthcare (NUTES) medical device embedded software certification is based on a solid safety quality model and has been tested with reasonable success against the Class I risk device Generic Infusion Pump (GIP).

NRC safety research in support of regulation--FY 1989

International Nuclear Information System (INIS)

1990-04-01

This report, the fifth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1989. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation, FY 1991

International Nuclear Information System (INIS)

1992-04-01

This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation, FY 1990

International Nuclear Information System (INIS)

1991-04-01

This report, the sixth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1990. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

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.

Identification of Behavior Based Safety by Using Traffic Light Analysis to Reduce Accidents

Science.gov (United States)

Mansur, A.; Nasution, M. I.

2016-01-01

This work present the safety assessment of a case study and describes an important area within the field production in oil and gas industry, namely behavior based safety (BBS). The company set a rigorous BBS and its intervention program that implemented and deployed continually. In this case, observers requested to have discussion and spread a number of determined questions related with work behavior to the workers during observation. Appraisal of Traffic Light Analysis (TLA) as one tools of risk assessment used to determine the estimated score of BBS questionnaire. Standardization of TLA appraisal in this study are based on Regulation of Minister of Labor and Occupational Safety and Health No:PER.05/MEN/1996. The result shown that there are some points under 84%, which categorized in yellow category and should corrected immediately by company to prevent existing bad behavior of workers. The application of BBS expected to increase the safety performance at work time-by-time and effective in reducing accidents.

The new risk paradigm for chemical process security and safety.

Science.gov (United States)

Moore, David A

2004-11-11

The world of safety and security in the chemical process industries has certainly changed since 11 September, but the biggest challenges may be yet to come. This paper will explain that there is a new risk management paradigm for chemical security, discuss the differences in interpreting this risk versus accidental risk, and identify the challenges we can anticipate will occur in the future on this issue. Companies need to be ready to manage the new chemical security responsibilities and to exceed the expectations of the public and regulators. This paper will outline the challenge and a suggested course of action.

Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to develop the safety evaluation methods and analysis codes needed in the design and construction stage of fast breeder reactor (FBR). In JFY 2012, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination conducted for the reactor establishment permission, development of the analysis codes, such as core damage analysis code, were carried out following the planned schedule. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Nuclear safety regulations in the Republic of Croatia

International Nuclear Information System (INIS)

Cizmek, A.; Horvatic, M.; Ilijas, B.; Medakovic, S.

2009-01-01

Based on Nuclear Safety Act (Official Gazette No. 173/03) in 2006 State Office for Nuclear Safety (SONS) adopted beside Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06) the new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08) and Ordinance on conditions for nuclear safety and protection with regard to the sitting, design, construction, use and decommissioning of a facility in which a nuclear activity is to be performed (Official Gazette No. 71/08). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a license to perform nuclear activity. The Ordinance also regulates the content of the form for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear conditions, whereas compliance is established by the decision passed by SONS. Ordinance on special conditions (requirements) for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned activities Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a licence to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance

The simple analytics of systemic liquidity risk regulation

NARCIS (Netherlands)

Perotti, E.; Suarez, J.

2011-01-01

How to regulate systemic risk? This column presents a new CEPR discussion paper assessing the performance of Pigouvian taxes and quantity-based regulations in containing the social costs of high-risk banking. It finds that, depending on how banks differ, the socially efficient solution may be

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.

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.

Encouraging Maternal Sacrifice: How Regulations Governing the Consumption of Pharmaceuticals During Pregnancy Prioritize Fetal Safety over Maternal Health and Autonomy.

Science.gov (United States)

Donley, Greer

Pregnant women are routinely faced with the stressful decision of whether to consume needed medications during their pregnancies. Because the risks associated with pharmaceutical drug consumption during pregnancy are largely unknown, pregnant women both inadvertently consume dangerous medications and avoid needed drugs. Both outcomes are harmful to pregnant women and their fetuses. This unparalleled lack of drug safety information is a result of ill-conceived, paternalistic regulations in two areas of the law: regulations governing ethical research in human subjects and regulations that dictate the required labels on drugs. The former categorizes pregnant women as "vulnerable" and thus precludes them from most medical research. The result is that ninety-one percent of drugs lack any reliable safety information for pregnant consumers. The latter currently requires all drug labels to encourage drug avoidance during pregnancy, despite ample evidence that avoiding needed medications can harm pregnant women. On June 30, 2015, new pregnancy labeling regulations took effect. Though these regulations make important improvements, they continue to treat pregnant women unlike any population, including other unique subpopulations, such as children. As a result, the new regulations do not fix the problem of over-warning pregnant women about the risks of drug consumption. This article questions the legitimacy of both regulations and suggests three reforms for how to improve access to vital safety information: (1) amend the regulations governing ethical research in human subjects to reclassify pregnant women as non-vulnerable adults; (2) create incentives to generate safety data in pregnant women by granting a period of market exclusivity for drug companies that invest in this research; and (3) make the FDA pregnancy labeling regulations consistent with the routine FDA practice of requiring the display of balanced, human data on risk.

Collaborative, cross-national studies on health and safety in seafaring for evidence-based Maritime policy and regulations.

Science.gov (United States)

Jensen, Olaf C

2009-01-01

Until recently, maritime health and safety policies and regulations were sparsely based on health and safety research, and only a small number of countries contributed to new research. To strengthen maritime health and safety research activities by presenting a study example and discussing the possibilities and needs for more national and cross-national research. In a cross-national epidemiological study example, the seafarers from eleven countries completed small, anonymous questionnaires concerning the working conditions on their latest tours at sea while waiting for their health examinations. Significant disparities were pointed out among the nationalities, e.g., the length of the tours at sea, the proportional distribution of officers and non-officers, the mean age structure, the injury incidence rates, and the differences of occupational safety standards. The analysis of all data together increased the statistical strength of the multivariate analyses and allowed for valid comparisons among the nationalities. The questionnaire data was used successfully in the collaborative study example, but other data sources and methods are useful for health and safety research in seafaring as well. More national and cross-national research on maritime health and safety is warranted.

The politics of nuclear safety regulation

International Nuclear Information System (INIS)

Adam, G.

2002-01-01

The paper discusses political aspects of decision making about the safety of nuclear power plants especially in Eastern Europe and in connection with the enlargement of the European Union. The problem of the Kozloduy NPP safety is also discussed. Recommendations on the policy and tasks for nuclear regulators are given

Should the model for risk-informed regulation be game theory rather than decision theory?

Science.gov (United States)

Bier, Vicki M; Lin, Shi-Woei

2013-02-01

Risk analysts frequently view the regulation of risks as being largely a matter of decision theory. According to this view, risk analysis methods provide information on the likelihood and severity of various possible outcomes; this information should then be assessed using a decision-theoretic approach (such as cost/benefit analysis) to determine whether the risks are acceptable, and whether additional regulation is warranted. However, this view ignores the fact that in many industries (particularly industries that are technologically sophisticated and employ specialized risk and safety experts), risk analyses may be done by regulated firms, not by the regulator. Moreover, those firms may have more knowledge about the levels of safety at their own facilities than the regulator does. This creates a situation in which the regulated firm has both the opportunity-and often also the motive-to provide inaccurate (in particular, favorably biased) risk information to the regulator, and hence the regulator has reason to doubt the accuracy of the risk information provided by regulated parties. Researchers have argued that decision theory is capable of dealing with many such strategic interactions as well as game theory can. This is especially true in two-player, two-stage games in which the follower has a unique best strategy in response to the leader's strategy, as appears to be the case in the situation analyzed in this article. However, even in such cases, we agree with Cox that game-theoretic methods and concepts can still be useful. In particular, the tools of mechanism design, and especially the revelation principle, can simplify the analysis of such games because the revelation principle provides rigorous assurance that it is sufficient to analyze only games in which licensees truthfully report their risk levels, making the problem more manageable. Without that, it would generally be necessary to consider much more complicated forms of strategic behavior (including

Improvement of infrastructure for risk-informed regulation

International Nuclear Information System (INIS)

2012-01-01

Improvement of the infrastructure of probabilistic safety assessment (PSA) is essential to the risk-informed regulation for nuclear power plants. JNES conducted update of initiating event frequencies and improvement of the method for uncertainty analysis to enhance the technology bases of PSA in 2011. Furthermore, JNES improved the human reliability analysis method and the reliability analysis method for digital reactor protection systems. JNES estimated initiating event frequencies both for power and shutdown operation based on the recent operating experiences in Nuclear Power Plants (NPPs) of Japan using the hierarchical Bayesian method. As for improvement of the uncertainty analysis method, JNES conducted trial analyses using SOKC (State-Of-Knowledge Correlation) for the representative PWR plant and BWR plant of Japan. The study on the advanced HRA method with operator cognitive action model was conducted to improve a quality of HRA. The study on analyses of 'defense in depth' and 'diversity' for introducing digital instrumentation and control (I and C) systems was conducted. In order to ensure the quality of PSA, JNES conducted a peer review of a representative Japanese BWR plant PSA by the professional PSA engineers from the U.S. in order to extract to improve quality of PSA, and made an effort to develop the procedures of internal fire PSA. JNES participated in OECD/NEA PRISME and FIRE project to obtain the latest information and data to validate and improve the fire propagation analysis codes and the parameters for fire PSA as well. Furthermore, JNES studied schemes for the endorsement and application in the risk-informed regulation of PSA standards established by Atomic Energy Society of Japan. (author)

Risk and safety in the nuclear industry and conventional norms of society

International Nuclear Information System (INIS)

Tadmor, J.

In the present study the societal acceptance of various risks is analyzed and rules of risk acceptance as a function of different parameters are spelled out. The monetary value of a human life is estimated, based on investments in safety of different human activities. The acceptable risks and safety investments in different human activities are then compared with risks and safety investments of the nuclear industry. Safety investments required to reduce the radioactivity releases and risks from nuclear power stations to ALAP levels are taken as a study case. It is found that risks in the nuclear industry are several orders of magnitude lower and safety investments per human life saved are several orders of magnitude higher, as compared with risks and safety investments in other human activities. It is also shown that the incremental safety investments needed to further reduce the radiation doses in the environment during normal and continuous operation of nuclear plants are extravagantly high as compared to safety investments in other human activities and in other facets of human life. Considering that there is a limit to the economic means available, societal expenditures for reducing risks should by spread, as much as possible, over all human activities to get the maximum return from investments. (B.G.)

Safety prediction for basic components of safety-critical software based on static testing

International Nuclear Information System (INIS)

Son, H.S.; Seong, P.H.

2000-01-01

The purpose of this work is to develop a safety prediction method, with which we can predict the risk of software components based on static testing results at the early development stage. The predictive model combines the major factor with the quality factor for the components, which are calculated based on the measures proposed in this work. The application to a safety-critical software system demonstrates the feasibility of the safety prediction method. (authors)

Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

Energy Technology Data Exchange (ETDEWEB)

Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z., E-mail: raissaomarques@gmail.com, E-mail: vasconv@cdtn.br, E-mail: soaresw@cdtn.br, E-mail: silvasf@cdtn.br, E-mail: amandaraso@hotmail.com, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

International Nuclear Information System (INIS)

Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z.

2017-01-01

Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

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

International Nuclear Information System (INIS)

Bernard, Benoit

2014-01-01

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

JICST Factual DatabaseJICST Chemical Substance Safety Regulation Database

Science.gov (United States)

Abe, Atsushi; Sohma, Tohru

JICST Chemical Substance Safety Regulation Database is based on the Database of Safety Laws for Chemical Compounds constructed by Japan Chemical Industry Ecology-Toxicology & Information Center (JETOC) sponsored by the Sience and Technology Agency in 1987. JICST has modified JETOC database system, added data and started the online service through JOlS-F (JICST Online Information Service-Factual database) in January 1990. JICST database comprises eighty-three laws and fourteen hundred compounds. The authors outline the database, data items, files and search commands. An example of online session is presented.

Stakeholder confidence in effective safety regulation. A regulator's view on the role of independent research capability

International Nuclear Information System (INIS)

Kotra, Janet; Mohanty, Sitakanto

2006-01-01

The authors provided a regulator's view on the role of independent research capability and its relationship to stakeholder confidence. They underscored the NRC's commitment to regulatory openness in its Strategic Plan. A number of actions have been adopted to achieve openness: public access to information about risks, safety and licensee performance that is accurate and timely; enhanced awareness of NRC as an independent regulator; fair and timely process for public involvement in NRC's decision-making; and early public involvement and two-way communication to enhance public confidence in NRC's regulatory process. The presentation reviewed the ways through which the NRC seeks to inspire confidence in its process as independent regulator and in future decisions concerning whether to authorize the U.S. DOE to construct the proposed repository at Yucca Mountain. Key to this will be reviewing all information objectively, making open decisions based on sound, scientific judgements about the facts; and maintaining an open and fair public process, and accessing independent R and D. It was noted that among the requirements for the safety review for the Yucca Mountain repository will be extensive technical and scientific analyses, evaluation of expert judgement, and long-range modelling assessments of expected repository performance. NRC requires independent scientific and engineering analyses to develop technical bases for regulations and guidance; evaluate adequacy of DOE's safety case for a potential repository; assist preparation of NRC Safety Evaluation Report; provide technical support for NRC testimony during licensing hearing; and develop effective outreach and communication tools. Confidence in NRC's use of science and engineering will depend upon: competence; independence; open and fair process; regulatory outcomes that are subject to verification and monitoring. To assist, the NRC established the Centre for Nuclear Waste Regulatory

Five Years of a Computer Based New Training Program in Safety and Radiation Protection

International Nuclear Information System (INIS)

Ben-Shachar, B.; Tshuva, M.; Fitussi, I.; Ankri, D.

2004-01-01

One of the main goals of the Department of Human Resources Development is to give employees fundamental knowledge, refreshing know-how and increasing safety awareness. In this regard safety deals with risks in operating nuclear facilities, including radiation, industrial risks and fire. Israeli Work Supervision (informing and training employees, 1992) (1) and work safety regulations (industrial safety and health for ionization radiation employees) state the need for training by the employer at least once a year. The employer also must take means to verify that the employees actually understand what they were trained for

Regulatory Body Safety Culture in Non-nuclear HROs: Lessons for Nuclear Regulators

International Nuclear Information System (INIS)

Fleming, M.; Bowers, K.

2016-01-01

Regulator safety culture is a relatively new area of investigation, even though deficiencies in regulatory oversight have been identified in a number of public inquiries (e.g., Piper Alpha, Deep Water Horizon). More recently the IAEA report into the Fukushima disaster specifically identified the need for regulatory bodies to have a positive safety culture. While there are clear parallels between duty holder safety culture and regulator safety culture there are also likely to be differences. To date they have been no published studies investigating regulator safety culture. In order to develop a framework to understand regulator safety culture we conducted a literature review and interviewed safety culture subject matter experts from a range of HRO domains (e.g., offshore oil and gas). There was general consensus among participants that regulatory safety culture was an important topic that was worthy of further investigation. That there was general agreement that regulatory safety culture was multi-dimensional and that some of the elements of existing safety culture models applied to regulator culture (e.g., learning and leadership). The participants also identified unique dimensions of regulator safety culture including commitment to high standards and ethics, transparency and perceived role of the regulator. In this paper we will present the results of the interviews and present a model of regulator safety culture. This model will be contrasted with models being used in the nuclear industry. Implications for assessing regulatory safety culture will be discussed. (author)

Development of NPP safety regulation in Russia

International Nuclear Information System (INIS)

Vishnevsky, Y.G.; Gutsalov, A.T.; Bukrinsky, A.M.; Gordon, B.G.

1999-01-01

The presentation describes the organisation scheme of Russian safety regulatory bodies, their tasks and responsibilities. Legislative and regulatory basis of NPP safety regulations rely on the federal laws: Law on the Use of Nuclear Energy and Law on Radiation Safety of the Population. Role of international cooperation and Improvement of regulatory activities in Russia are emphasised

Safety prediction for basic components of safety critical software based on static testing

International Nuclear Information System (INIS)

Son, H.S.; Seong, P.H.

2001-01-01

The purpose of this work is to develop a safety prediction method, with which we can predict the risk of software components based on static testing results at the early development stage. The predictive model combines the major factor with the quality factor for the components, both of which are calculated based on the measures proposed in this work. The application to a safety-critical software system demonstrates the feasibility of the safety prediction method. (authors)

[Communication on health and safety risk control in contemporary society: an interdisciplinary approach].

Science.gov (United States)

Rangel-S, Maria Ligia

2007-01-01

This paper discusses communication as a technology for risk control with health and safety protection and promotion, within the context of a "risk society". As a component of Risk Analysis, risk communication is a technology that appears in risk literature, with well defined objectives, principles and models. These aspects are described and the difficulties are stressed, taking into consideration the multiple rationales related to risks in the culture and the many different aspects of risk regulation and control in the so-called "late modernity". Consideration is also given to the complexity of the communications process, guided by theoretical and methodological discussions in the field. In order to understand the true value of the communications field for risk control with health and safety protection and promotion, this paper also offers an overview of communication theories that support discussions of this matter, proposing a critical approach to models that include the dimensions of power and culture in the context of a capitalist society.

Improving construction site safety through leader-based verbal safety communication.

Science.gov (United States)

Kines, Pete; Andersen, Lars P S; Spangenberg, Soren; Mikkelsen, Kim L; Dyreborg, Johnny; Zohar, Dov

2010-10-01

The construction industry is one of the most injury-prone industries, in which production is usually prioritized over safety in daily on-site communication. Workers have an informal and oral culture of risk, in which safety is rarely openly expressed. This paper tests the effect of increasing leader-based on-site verbal safety communication on the level of safety and safety climate at construction sites. A pre-post intervention-control design with five construction work gangs is carried out. Foremen in two intervention groups are coached and given bi-weekly feedback about their daily verbal safety communications with their workers. Foremen-worker verbal safety exchanges (experience sampling method, n=1,693 interviews), construction site safety level (correct vs. incorrect, n=22,077 single observations), and safety climate (seven dimensions, n=105 questionnaires) are measured over a period of up to 42 weeks. Baseline measurements in the two intervention and three control groups reveal that foremen speak with their workers several times a day. Workers perceive safety as part of their verbal communication with their foremen in only 6-16% of exchanges, and the levels of safety at the sites range from 70-87% (correct observations). Measurements from baseline to follow-up in the two intervention groups reveal that safety communication between foremen and workers increases significantly in one of the groups (factor 7.1 increase), and a significant yet smaller increase is found when the two intervention groups are combined (factor 4.6). Significant increases in the level of safety are seen in both intervention groups (7% and 12% increases, respectively), particularly in regards to 'access ways' and 'railings and coverings' (39% and 84% increases, respectively). Increases in safety climate are seen in only one of the intervention groups with respect to their 'attention to safety.' No significant trend changes are seen in the three control groups on any of the three measures

Safety regulations for radioisotopes, etc. (interim report)

International Nuclear Information System (INIS)

1980-01-01

An (interim) report by an ad hoc expert committee to the Nuclear Safety Commission, on the safety regulations for radioisotopes, etc., was presented. For the utilization of radioisotopes, etc., there is the Law Concerning Prevention of Radiation Injury Due to Radioisotopes, etc. with the advances in this field and the improvement in international standards, the regulations by the law have been examined. After explaining the basic ideas of the regulations, the problems and countermeasures in the current regulations are described: legal system, rationalization in permission procedures and others, inspection on RI management, the system of the persons in charge of radiation handling, RI transport, low-level radioactive wastes, consumer goods, definitions of RIs, radiation and sealed sources, regulations by group partitioning, RI facilities, system of personnel exposure registration, entrusting of inspection, etc. to private firms, and reduction in the works for permission among governmental offices. (author)

The risk-based approach to ATMP development - generally accepted by regulators but infrequently used by companies.

Science.gov (United States)

Kooijman, M; van Meer, P J K; Gispen-de Wied, C C; Moors, E H M; Hekkert, M P; Schellekens, H

2013-11-01

Advanced therapy medicinal products (ATMPs) are the cutting edge of drug innovation. ATMPs have different challenges than other drug classes. To accommodate these challenges and facilitate science-driven development, flexibility in the requirements to demonstrate the safety and efficacy of this rapidly evolving drug class is necessary. To create flexibility, the European Union introduced the risk-based approach. This approach provides the possibility of omitting guideline-based studies based on risk analyses. To gain insight into the effect of the risk-based approach on the non-clinical development of ATMPs, two questions are addressed in this paper. Firstly, "Do companies use a risk-based approach for the non-clinical development of ATMPs?" and, secondly, "Does the Committee for Medicinal Products for Human Use (CHMP) of the European Medicines Agency (EMA) accept non-clinical development programs based on the risk-based approach?" Scientific advice letters formulated by the CHMP were analyzed. The risk-based approach was used to justify deviations from the guidelines in the majority (75%) of the cases. The CHMP accepted 40% of the proposals to omit studies and stated that additional data was necessary to make an informed decision for 35% of the proposals. This indicates that the risk-based approach facilitates the science-driven development of ATMPs. Copyright © 2013 Elsevier Inc. All rights reserved.

Coal Mine Health and Safety Regulation 2006 under the Coal Mine Health and Safety Act 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-12-22

The aim of the Act is to secure the health, safety and welfare of people in connection with coal operations (which include all places of work where coal is mined and certain other places). The Regulation contains provisions about the following matters: (a) places of work to which the Act does not apply, (b) duties relating to health, welfare and safety at coal operations, including the following: (i) the nomination of the operator of a coal operation and the provision of health and safety information for incoming operators, (ii) the contents of health and safety management systems for coal operations, (iii) major hazards and the contents of major hazard management plans for coal operations, (iv) duties relating to contractors, (v) the contents of management structures and emergency management systems for coal operations, escape and rescue plans and fire fighting plans and high risk activities, (c) notifications, including (i) notification of incidents, (ii) inquiries, (iii) notification of other matters to the Chief Inspector), (d) aspects of safety at coal operations, including the following: (i) controlled materials, plants and practices, (ii) coal dust explosion prevention and suppression, (iii) ventilation at coal operations, (iv) escape from coal operations, (v) the operation of transport at coal operations, (vi) surveys and certified plans, (vii) employment at coal operations, (e) the licensing of certain activities, (f) competence standards, (g) the Coal Competence Board, (h) check inspectors, (i) exemptions from provisions of this Regulation, (j) the following miscellaneous matters concerning coal mine health and safety: (i) the keeping of records and reporting, (ii) penalties, the review of decisions by the Administrative Decisions Tribunal, fees and charges, consultation, information and other miscellaneous matters, (k) savings and transitional provisions.

The safety monitor and RCM workstation as complementary tools in risk based maintenance optimization

International Nuclear Information System (INIS)

Rawson, P.D.

2000-01-01

Reliability Centred Maintenance (RCM) represents a proven technique for rendering maintenance activities safer, more effective, and less expensive, in terms of systems unavailability and resource management. However, it is believed that RCM can be enhanced by the additional consideration of operational plant risk. This paper discusses how two computer-based tools, i.e., the RCM Workstation and the Safety Monitor, can complement each other in helping to create a living preventive maintenance strategy. (author)

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

Nanomaterials: Regulation and Risk Assessment

DEFF Research Database (Denmark)

Hansen, Steffen Foss; Grieger, Khara Deanne; Baun, Anders

2013-01-01

, the Water Framework Directive, pharmaceuticals regulation, and the Novel Foods Regulation. Current regulation of nanomaterials entail three overall challenges: 1) limitations in regard to terminology and definitions of key terms such as a “substance,” “novel food,” etc.; 2) safety assessment requirements...

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

Risk-based SMA for Cubesats

Science.gov (United States)

Leitner, Jesse

2016-01-01

This presentation conveys an approach for risk-based safety and mission assurance applied to cubesats. This presentation accompanies a NASA Goddard standard in development that provides guidance for building a mission success plan for cubesats based on the risk tolerance and resources available.

Legislation for the countermeasures on special issues of nuclear safety regulations

International Nuclear Information System (INIS)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul

2003-02-01

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea

Legislation for the countermeasures on special issues of nuclear safety regulations

Energy Technology Data Exchange (ETDEWEB)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

2003-02-15

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

Development and application of the Safe Performance Index as a risk-based methodology for identifying major hazard-related safety issues in underground coal mines

Science.gov (United States)

Kinilakodi, Harisha

The underground coal mining industry has been under constant watch due to the high risk involved in its activities, and scrutiny increased because of the disasters that occurred in 2006-07. In the aftermath of the incidents, the U.S. Congress passed the Mine Improvement and New Emergency Response Act of 2006 (MINER Act), which strengthened the existing regulations and mandated new laws to address the various issues related to a safe working environment in the mines. Risk analysis in any form should be done on a regular basis to tackle the possibility of unwanted major hazard-related events such as explosions, outbursts, airbursts, inundations, spontaneous combustion, and roof fall instabilities. One of the responses by the Mine Safety and Health Administration (MSHA) in 2007 involved a new pattern of violations (POV) process to target mines with a poor safety performance, specifically to improve their safety. However, the 2010 disaster (worst in 40 years) gave an impression that the collective effort of the industry, federal/state agencies, and researchers to achieve the goal of zero fatalities and serious injuries has gone awry. The Safe Performance Index (SPI) methodology developed in this research is a straight-forward, effective, transparent, and reproducible approach that can help in identifying and addressing some of the existing issues while targeting (poor safety performance) mines which need help. It combines three injury and three citation measures that are scaled to have an equal mean (5.0) in a balanced way with proportionate weighting factors (0.05, 0.15, 0.30) and overall normalizing factor (15) into a mine safety performance evaluation tool. It can be used to assess the relative safety-related risk of mines, including by mine-size category. Using 2008 and 2009 data, comparisons were made of SPI-associated, normalized safety performance measures across mine-size categories, with emphasis on small-mine safety performance as compared to large- and

Towards an occupational safety and health culture

NARCIS (Netherlands)

Zwetsloot, G.I.J.M.; Steijger, N.

2014-01-01

Occupational safety and health (OSH) is a highly regulated area that appears to be based on rational planning and logical management approaches, e.g. OSM Management Systems: employers and employees of organisations should be aware of OSH risks, assess these risks systematically, provide the

Safety Cultures in Water-Based Outdoor Activities in Denmark

DEFF Research Database (Denmark)

Andkjær, Søren; Arvidsen, Jan

2015-01-01

In this paper, we report on the study Safe in Nature (Tryg i naturen) in which the aim was to analyze and discuss risk and safety related to outdoor recreation in the coastal regions of Denmark. A cultural perspective is applied to risk management and the safety cultures related to three selected...... water-based outdoor activities: small boat fishing, sea kayaking, and kite surfing. The theoretical framework used was cultural analysis and the methodological approach was mixed methods using case studies with survey and qualitative interviews. The study indicates that safety is a complex matter...... and that safety culture can be understood as the sum and interaction among six categories. The safety culture is closely related to the activity and differs widely among activities. We suggest a broad perspective be taken on risk management wherein risk and safety can be managed at different levels. Small boat...

Regulation of chemical safety at fuel cycle facilities by the United States Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Ramsey, Kevin M.

2013-01-01

When the U.S. Nuclear Regulatory Commission (NRC) was established in 1975, its regulations were based on radiation dose limits. Chemical hazards rarely influenced NRC regulations. After the Three Mile Island reactor accident in 1979, the NRC staff was directed to address emergency planning at non-reactor facilities. Several fuel cycle facilities were ordered to submit emergency plans consistent with reactor emergency plans because no other guidance was available. NRC published a notice that it was writing regulations to codify the requirements in the Orders and upgrade the emergency plans to address all hazards, including chemical hazards. The legal authority of NRC to regulate chemical safety was questioned. In 1986, an overfilled uranium hexafluoride cylinder ruptured and killed a worker. The NRC staff was directed to address emergency planning for hazardous chemicals in its regulations. The final rule included a requirement for fuel cycle facilities to certify compliance with legislation requiring local authorities to establish emergency plans for hazardous chemicals. As with emergency planning, NRC's authority to regulate chemical safety during routine operations was limited. NRC established memoranda of understanding (MOUs) with other regulatory agencies to encourage exchange of information between the agencies regarding occupational hazards. In 2000, NRC published new, performance-based, regulations for fuel cycle facilities. The new regulations required an integrated safety analysis (ISA) which used quantitative standards to assess chemical exposures. Some unique chemical exposure cases were addressed while implementing the new regulations. In addition, some gaps remain in the regulation of hazardous chemicals at fuel cycle facilities. The status of ongoing efforts to improve regulation of chemical safety at fuel cycle facilities is discussed. (authors)

On the role of safety culture in risk-informed regulation

International Nuclear Information System (INIS)

Sorensen, J.N.; Apostolakis, G.E.; Powers, D.A.

2000-01-01

There is a widespread belief that safety culture is an important contributor to safety of operations. The commonly accepted attributes of safety culture include good organizational communications, good organizational learning, and senior management commitment to safety. Safety culture may be particularly important in reducing latent errors in complex, well-defended systems. The role of regulatory bodies in fostering strong safety cultures remains unclear, and additional work is required to define the essential attributes of safety culture and to identify reliable performance indicators. (author)

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

Performance based regulation - The maintenance rule

Energy Technology Data Exchange (ETDEWEB)

Correia, Richard P. [NRR/DOTS/TQMP, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, M/S OWFN 10A19, Washington, D.C. 20555 (United States)

1997-07-01

The U.S. Nuclear Regulatory Commission has begun a transition from 'process-oriented' to 'results-oriented' regulations. The maintenance rule is a results-oriented rule that mandates consideration of risk and plant performance. The Maintenance Rule allows licensees to devise the most effective and efficient means of achieving the results described in the rule including the use of Probabilistic Risk (or Safety) Assessments. The NRC staff conducted a series of site visits to evaluate implementation of the Rule. Conclusions from the site visits indicated that the results-oriented Maintenance Rule can be successfully implemented and enforced. (author)

Performance based regulation - The maintenance rule

International Nuclear Information System (INIS)

Correia, Richard P.

1997-01-01

The U.S. Nuclear Regulatory Commission has begun a transition from 'process-oriented' to 'results-oriented' regulations. The maintenance rule is a results-oriented rule that mandates consideration of risk and plant performance. The Maintenance Rule allows licensees to devise the most effective and efficient means of achieving the results described in the rule including the use of Probabilistic Risk (or Safety) Assessments. The NRC staff conducted a series of site visits to evaluate implementation of the Rule. Conclusions from the site visits indicated that the results-oriented Maintenance Rule can be successfully implemented and enforced. (author)

RiskSOAP: Introducing and applying a methodology of risk self-awareness in road tunnel safety.

Science.gov (United States)

Chatzimichailidou, Maria Mikela; Dokas, Ioannis M

2016-05-01

Complex socio-technical systems, such as road tunnels, can be designed and developed with more or less elements that can either positively or negatively affect the capability of their agents to recognise imminent threats or vulnerabilities that possibly lead to accidents. This capability is called risk Situation Awareness (SA) provision. Having as a motive the introduction of better tools for designing and developing systems that are self-aware of their vulnerabilities and react to prevent accidents and losses, this paper introduces the Risk Situation Awareness Provision (RiskSOAP) methodology to the field of road tunnel safety, as a means to measure this capability in this kind of systems. The main objective is to test the soundness and the applicability of RiskSOAP to infrastructure, which is advanced in terms of technology, human integration, and minimum number of safety requirements imposed by international bodies. RiskSOAP is applied to a specific road tunnel in Greece and the accompanying indicator is calculated twice, once for the tunnel design as defined by updated European safety standards and once for the 'as-is' tunnel composition, which complies with the necessary safety requirements, but calls for enhancing safety according to what EU and PIARC further suggest. The derived values indicate the extent to which each tunnel version is capable of comprehending its threats and vulnerabilities based on its elements. The former tunnel version seems to be more enhanced both in terms of it risk awareness capability and safety as well. Another interesting finding is that despite the advanced tunnel safety specifications, there is still room for enriching the safe design and maintenance of the road tunnel. Copyright © 2016 Elsevier Ltd. All rights reserved.

Research needs for risk-informed, performance-based regulations

International Nuclear Information System (INIS)

Thadani, A.C.

1997-01-01

This article summarizes the activities of the Office of Research of the NRC, both from a historical aspect as well as it applies to the application of risk-based decision making. The office has been actively involved in problems related to understanding risks related to core accidents, to understanding the problem of aging of reactor components and materials from years of service, and toward the understanding and analysis of severe accidents. In addition new policy statements regarding the role of risk assessment in regulatory applications has given focus for the need of further work. The NRC has used risk assessment in regulatory questions in the past but in a fairly ad hoc sort of manner. The new policies will clearly require a better defined application of risk assessment, and help for people evaluating applications in judging the applicability of such applications when a component of them is based on risk-based decision making. To address this, standard review plans are being prepared to serve as guides for such questions. In addition, with regulatory decisions being allowed to be based upon risk-based decisions, it is necessary to have an adequate data base prepared, and made publically available, to support such a position

Guidelines on the safety of light-based home-use hair removal devices from the European Society for Laser Dermatology

DEFF Research Database (Denmark)

Town, Graham; Ash, C; Dierickx, C

2012-01-01

. These guidelines provide a definition of light-based home-use technology, to inform healthcare professionals about home-use light-based technology and encourage manufacturers wishing to sell in Europe to adopt 'best practice'. The review presents the current status on standards and regulation issues and considers...... home-use safety issues, encompassing human, device and electrical safety, given risks to the eyes and skin from optical radiation both to the consumer and persons in the vicinity. Proposed technical measurement methodology is considered with focus on recognized critical parameters for the safe use...... of light-based hair removal technology including recording the technical performance and safety claims of a range of home-use hair removal devices. The literature review emphasizes potential adverse incidents and safety aspects of treating cosmetic conditions, such as unwanted hair growth. Although some...

Risk evaluation method for faults by engineering approach. (1) Nuclear safety for accident scenario and measures for fault movement

International Nuclear Information System (INIS)

Narabayashi, Tadashi; Chiba, Go; Okamoto, Koji; Kameda, Hiroyuki; Ebisawa, Katsumi; Yamazaki, Haruo; Konagai, Kazuo; Kamiya, Masanobu; Nagasawa, Kazuyuki

2016-01-01

Japan, as a frequent earthquake country, has a responsibility to resolve efficient measures to enhance nuclear safety, to continue utilizing the nuclear power, based on the risks and importance levels in the scientific and rational manner. In his paper describes how to evaluate the risk of faults movement by engineering approach. An open fruitful discussion by experts in the various area of earthquake, geology, geotechnical, civil, and a seismic design as well as other stakeholders such as academia professors, nuclear reactor engineers, regulators, and licensees. The Atomic Energy Society established an Investigation Committee on Development of Activity and Risk Evaluation Method for Faults by Engineering Approach (IC-DAREFEA) on October 1st, a 2014. The Investigation Committee utilizes the most advanced scientific and rational judgement, and continuous discussions and efforts in the global field, in order to collect and organize these knowledge and reflect the global standards and nuclear regulations, such as risk evaluation method for the faults movements and prevention of severe accidents, based on the accumulated database in the world, including Chuetsuoki Earthquake, North Nagano Earthquake and Kumamoto Earthquake. (author)

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)

A risk informed safety classification for a Nordic NPP

International Nuclear Information System (INIS)

Jaenkaelae, K.

2002-01-01

The report describes a study to develop a safety classification proposal or classi- fication recommendations based on risks for selected equipment of a nuclear power plant. The application plant in this work is Loviisa NPP unit 1. The safety classification proposals are to be considered as an exercise in this pilot study and do not necessarily represent final proposals in a real situation. Comparisons to original safety classifications and technical specifications were made. The study concludes that it is possible to change safety classes or safety signifi- cances as considered in technical specifications and in in-service-inspections into both directions without endangering the safety or even by improving the safety. (au)

Risk based modelling

International Nuclear Information System (INIS)

Chapman, O.J.V.; Baker, A.E.

1993-01-01

Risk based analysis is a tool becoming available to both engineers and managers to aid decision making concerning plant matters such as In-Service Inspection (ISI). In order to develop a risk based method, some form of Structural Reliability Risk Assessment (SRRA) needs to be performed to provide a probability of failure ranking for all sites around the plant. A Probabilistic Risk Assessment (PRA) can then be carried out to combine these possible events with the capability of plant safety systems and procedures, to establish the consequences of failure for the sites. In this way the probability of failures are converted into a risk based ranking which can be used to assist the process of deciding which sites should be included in an ISI programme. This paper reviews the technique and typical results of a risk based ranking assessment carried out for nuclear power plant pipework. (author)

Risk management for existing energy facilities. A global approach to numerical safety goals

International Nuclear Information System (INIS)

Pate-Cornell, M.E.

1993-01-01

This paper presents a structured set of numerical safety goals for risk management of existing energy facilities. The rationale behind these safety goals is based on principles of equity and economic efficiency. Some of the issues involved when using probabilistic risk analyses results for safety decisions are discussed. A brief review of existing safety targets and open-quotes floating numbersclose quotes is presented, and a set of safety goals for industrial risk management is proposed. Relaxation of these standards for existing facilities, the relevance of the lifetime of the plant, the treatment of uncertainties, and problems of failure dependencies are discussed briefly. 17 refs., 1 fig

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.)

Alternative development and action plan for the atomic safety regulation instruments

International Nuclear Information System (INIS)

Kim, J. Y.; Ahn, S. K.; Ham, Y. S.

2004-01-01

The goal of this study to provide highly practical model to regulation agency. Since nuclear power safety regulation has different characteristics, compared to general regulation, it is important to have new point of view and approach. But application possibility for regulation that guarantees the 'perfect safety' is very low. Therefore, it is important establish nuclear power safety regulation that is realistic as well as safety securing. In order to establish high quality regulation, evaluation of existing regulation must be done first. Thus in this study, 6 standards to evaluate existing regulation are suggested. They are clearness, efficiency, flexibility, reliability, responsibility and political consideration. Also, strategies to complement the weak points of regulatory governance, regulatory sunset, regulatory map, regulatory negotiation, regulatory benefit cost analysis, etc. These strategies can be applied all in one regulation, and can strategically be selected for application. After analyzing the result if case analysis on nuclear furnace regulation for research study, agreement was made that it is most efficient to consider in the order if clearness reliability, flexibility, confidence, political consideration, administrative efficiency and economic efficiency

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)

Are Management-Based Regulations Effective? Evidence from State Pollution Prevention Programs

Science.gov (United States)

Bennear, Lori Snyder

2007-01-01

This paper evaluates a recent innovation in regulating risk called management-based regulation. Traditionally, risk regulation has either specified a particular means of achieving a risk-reduction goal or specified the goal and left the means of achieving that goal up to the regulated entity. In contrast, management-based regulation neither…

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.

78 FR 11092 - Safety and Health Regulations for Construction

Science.gov (United States)

2013-02-15

... LABOR DEPARTMENT Occupational Safety and Health Administration 29 CFR Part 1926 Safety and Health Regulations for Construction CFR Correction In Title 29 of the Code of Federal Regulations, Part 1926, revised as of July 1, 2012, on page 225, in Sec. 1926.152, paragraph (c)(16) is added to read as follows: Sec...

The Concepts of Risk, Safety, and Security: Applications in Everyday Language.

Science.gov (United States)

Boholm, Max; Möller, Niklas; Hansson, Sven Ove

2016-02-01

The concepts of risk, safety, and security have received substantial academic interest. Several assumptions exist about their nature and relation. Besides academic use, the words risk, safety, and security are frequent in ordinary language, for example, in media reporting. In this article, we analyze the concepts of risk, safety, and security, and their relation, based on empirical observation of their actual everyday use. The "behavioral profiles" of the nouns risk, safety, and security and the adjectives risky, safe, and secure are coded and compared regarding lexical and grammatical contexts. The main findings are: (1) the three nouns risk, safety, and security, and the two adjectives safe and secure, have widespread use in different senses, which will make any attempt to define them in a single unified manner extremely difficult; (2) the relationship between the central risk terms is complex and only partially confirms the distinctions commonly made between the terms in specialized terminology; (3) whereas most attempts to define risk in specialized terminology have taken the term to have a quantitative meaning, nonquantitative meanings dominate in everyday language, and numerical meanings are rare; and (4) the three adjectives safe, secure, and risky are frequently used in comparative form. This speaks against interpretations that would take them as absolute, all-or-nothing concepts. © 2015 Society for Risk Analysis.

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

Review of Policy Documents for Nuclear Safety and Regulation

International Nuclear Information System (INIS)

Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki

2006-01-01

The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies

Review of Policy Documents for Nuclear Safety and Regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

2006-07-01

The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies.

Implementation of the new regulation on radiological safety in Peru

International Nuclear Information System (INIS)

Medina Gironzini, E.

1997-01-01

Since its creation in 1975, the Peruvian Institute of Nuclear Energy (IPEN) has enacted three regulations of national importance on the norms of protection against ionizing radiation. The first regulation, which is called regulation of radiological protection (1980) approved by a resolution of IPEN, is the result of the work of a committee constituted by IPEN and the Ministry of Health. Its implementation caused some problems as result of which, in 1989, a new regulation on radiological protection was enacted through a supreme decree. Taking into account the new recommendation of the International Commission on Radiological Protection and the International Basic Safety Standard for Protection against Ionizing Radiation and for the Safety of Radiation Sources, approved in May 1997, the regulation of radiological safety also considers evolving aspects in the Project ARCAL XVII/IAEA. This regulation includes various topics such as exclusions, requirements of protection (medical exposure, occupational exposure, public exposure, chronic exposure), requirements of source safety, interventions and emergencies, control of sources and practices (exemptions, authorizations, inspections) etc. The implementation of this regulation at the national level falls to IPEN, the unique authority commissioned to control nuclear installations, radioactivity and x ray facilities in medicine, industry and research

Education and Training of Safety Regulation for Nuclear Safety Infrastructure: Its Necessity and Unique Features

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Young Joon; Lee, Jae Cheon

2009-01-01

Faced with global warming and electricity demands, countries over the world recognize the comparative advantages of nuclear energy. It is estimated that about 300 nuclear power plants (NPPs) expect to be constructed until 2030 worldwide. In addition, according to the IAEA, approximately 20 new countries might have their first NPP in operation by 2030 in the high projection compared with bout 5 new countries in the low projection. When introducing nuclear power, the implementation of an appropriate infrastructure to address all of the relevant issues is a central concern of international community. In particular, nuclear power program requires, at an earlier stage than when construction starts, the development of a legal and regulatory framework and training of regulators and safety experts whose combined knowledge adequately covers all areas of nuclear safety and regulation applied at a NPP construction and operation. As an essential component of such human resource development, special attention was paid to the provision of education and training to regulators of which countries plan to introduce NPPs. In term of education theory, safety regulation has some unique features in learning and teaching, which are different from those of nuclear engineering or development. This paper overviews nuclear safety infrastructure, explores the roles of exporting countries, and presents features and components in education of nuclear safety regulation

Scientists versus Regulators: Precaution, Novelty & Regulatory Oversight as Predictors of Perceived Risks of Engineered Nanomaterials

Science.gov (United States)

Beaudrie, Christian E. H.; Satterfield, Terre; Kandlikar, Milind; Harthorn, Barbara H.

2014-01-01

Engineered nanoscale materials (ENMs) present a difficult challenge for risk assessors and regulators. Continuing uncertainty about the potential risks of ENMs means that expert opinion will play an important role in the design of policies to minimize harmful implications while supporting innovation. This research aims to shed light on the views of ‘nano experts’ to understand which nanomaterials or applications are regarded as more risky than others, to characterize the differences in risk perceptions between expert groups, and to evaluate the factors that drive these perceptions. Our analysis draws from a web-survey (N = 404) of three groups of US and Canadian experts: nano-scientists and engineers, nano-environmental health and safety scientists, and regulatory scientists and decision-makers. Significant differences in risk perceptions were found across expert groups; differences found to be driven by underlying attitudes and perceptions characteristic of each group. Nano-scientists and engineers at the upstream end of the nanomaterial life cycle perceived the lowest levels of risk, while those who are responsible for assessing and regulating risks at the downstream end perceived the greatest risk. Perceived novelty of nanomaterial risks, differing preferences for regulation (i.e. the use of precaution versus voluntary or market-based approaches), and perceptions of the risk of technologies in general predicted variation in experts' judgments of nanotechnology risks. Our findings underscore the importance of involving a diverse selection of experts, particularly those with expertise at different stages along the nanomaterial lifecycle, during policy development. PMID:25222742

Scientists versus regulators: precaution, novelty & regulatory oversight as predictors of perceived risks of engineered nanomaterials.

Directory of Open Access Journals (Sweden)

Christian E H Beaudrie

Full Text Available Engineered nanoscale materials (ENMs present a difficult challenge for risk assessors and regulators. Continuing uncertainty about the potential risks of ENMs means that expert opinion will play an important role in the design of policies to minimize harmful implications while supporting innovation. This research aims to shed light on the views of 'nano experts' to understand which nanomaterials or applications are regarded as more risky than others, to characterize the differences in risk perceptions between expert groups, and to evaluate the factors that drive these perceptions. Our analysis draws from a web-survey (N = 404 of three groups of US and Canadian experts: nano-scientists and engineers, nano-environmental health and safety scientists, and regulatory scientists and decision-makers. Significant differences in risk perceptions were found across expert groups; differences found to be driven by underlying attitudes and perceptions characteristic of each group. Nano-scientists and engineers at the upstream end of the nanomaterial life cycle perceived the lowest levels of risk, while those who are responsible for assessing and regulating risks at the downstream end perceived the greatest risk. Perceived novelty of nanomaterial risks, differing preferences for regulation (i.e. the use of precaution versus voluntary or market-based approaches, and perceptions of the risk of technologies in general predicted variation in experts' judgments of nanotechnology risks. Our findings underscore the importance of involving a diverse selection of experts, particularly those with expertise at different stages along the nanomaterial lifecycle, during policy development.

Legislation for the countermeasures on special issues of nuclear safety regulations

International Nuclear Information System (INIS)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul

2004-02-01

Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation

Legislation for the countermeasures on special issues of nuclear safety regulations

Energy Technology Data Exchange (ETDEWEB)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

2004-02-15

Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

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.

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.

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.

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)

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

Management by process based systems and safety focus

International Nuclear Information System (INIS)

Rydnert, Bo; Groenlund, Bjoern

2005-12-01

An initiative from The Swedish Nuclear Power Inspectorate led to this study carried out in the late autumn of 2005. The objective was to understand in more detail how an increasing use of process management affects organisations, on the one hand regarding risks and security, on the other hand regarding management by objectives and other management and operative effects. The main method was interviewing representatives of companies and independent experts. More than 20 interviews were carried out. In addition a literature study was made. All participating companies are using Management Systems based on processes. However, the methods chosen, and the results achieved, vary extensively. Thus, there are surprisingly few examples of complete and effective management by processes. Yet there is no doubt that management by processes is effective and efficient. Overall goals are reached, business results are achieved in more reliable ways and customers are more satisfied. The weaknesses found can be translated into a few comprehensive recommendations. A clear, structured and acknowledged model should be used and the processes should be described unambiguously. The changed management roles should be described and obeyed extremely legibly. New types of process objectives need to be formulated. In addition one fact needs to be observed and effectively fended off. Changes are often met by mental opposition on management level, as well as among co-workers. This fact needs attention and leadership. Safety development is closely related to the design and operation of a business management system and its continual improvement. A deep understanding of what constitutes an efficient and effective management system affects the understanding of safety. safety culture and abilities to achieve safety goals. Concerning risk, the opinions were unambiguous. Management by processes as such does not result in any further risks. On the contrary. Processes give a clear view of production and

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)

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)

Safety of light water reactors. Risks of nuclear technology

International Nuclear Information System (INIS)

Veser, Anke; Schlueter, Franz-Hermann; Raskob, Wolfgang; Landman, Claudia; Paesler-Sauer, Juergen; Kessler, Guenter

2012-01-01

The book on the safety of light-water reactors includes the following chapters: Part I: Physical and technical safety concept of actual German and future European light-water reactors: (1) Worldwide operated nuclear power plants in 2011, (2) Some reactor physical fundamentals. (3) Nuclear power plants in Germany. (4) Radioactive exposure due to nuclear power plants. (5) Safety concept of light-water reactors. (6) Probabilistic analyses and risk studies. (7) Design of light-water reactors against external incidents. (8) Risk comparison of nuclear power plants and other energy systems. (9) Evaluation of risk studies using the improved (new) safety concept for LWR. (19) The severe reactor accidents of Three Mile Island, Chernobyl and Fukushima. Part II: Safety of German LWR in case of a postulated aircraft impact. (11) Literature. (12) Review of requirements and actual design. (13) Incident scenarios. (14) Load approach for aircraft impact. (15) Demonstration of the structural behavior in case of aircraft impact. (16) Special considerations. (17) Evaluation of the safety state of German and foreign nuclear power plants. Part III: ROSOS as example for a computer-based decision making support system for the severe accident management. (19) Literature. (20) Radiological fundamentals, accident management, modeling of the radiological situation. (21) The decision making support system RODOS. (22) RODOS and the Fukushima accident. (23) Recent developments in the radiological emergency management in the European frame.

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.

The Regulation of Major Risks in Relation to Large Nuclear Installations in France

International Nuclear Information System (INIS)

Phan Van, L.

1991-01-01

Recently, major risk prevention has generated legislative and regulatory texts in French law, particularly regarding nuclear installations. This article reviews the context and analyses the scope of the new regulations. They require the nuclear operator to take preventive measures, namely more stringent obligations from the safety viewpoint to inform the public. These include risk assessments and preparing emergency plans in case if accidents. (NEA)

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.

Utilization of a risk matrix based on Probabilistic Safety Analysis to improve nuclear safety in NPP

International Nuclear Information System (INIS)

Stubbe, Gerald

2010-01-01

The Probabilistic Safety Analysis (PSA) is a systematic and comprehensive methodology to evaluate risks associated with a complex engineered technological entity. Risk in a PSA is defined as a feasible detrimental outcome of an initiator. Those initiators can be 'classical' transient as the loss of main feedwater, loss of the secondary heat sink, etc.. or accident (LOCA - Loss Of Coolant Accident, SGTR - Steam Generator Tube Rupture, LOOP - Loss Of Offsite Power, etc..) In a PSA, risk is characterized by two quantities: the magnitude (severity) of the possible adverse consequence, the likelihood (probability) of occurrence of each consequence. Consequences are expressed numerically (for this purpose: the core damage) and their likelihoods of occurrence are expressed as probabilities or frequencies (i.e., the number of occurrences or the probability of occurrence per unit time). The total risk is the expected loss: the sum of the products of the consequences multiplied by their probabilities. This lead to the parameter CDF: The Core Damage Frequency, which is expressed by unit of time. The main advantage of this risk calculation is to have a global, integrated, overview of the plants and their systems. This allows to have an objective and quantitative point of view on the importance of the equipments, human action, or common cause failures that can challenge the plant's safety. A total PSA model is divided in three levels: Level one, which consider the core damage; Level two, which consider the robustness of the containment; Level three, which consider the impact of the radiological release on the public. For the purpose of the risk matrix, a level one PSA is needed. The scope of a PSA model is important to have a good characterization of the plant's risk. The matrix makes more sense if you have a full scope level one model, containing, furthermore the internal events, the fire and flooding, but also seismic event (if relevant). Asymmetries are also classical in the

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

Leadership for Safety in Practice: Perspectives from a Nuclear Regulator

International Nuclear Information System (INIS)

Tyobeka, B. M.

2016-01-01

The principal responsibility for a nuclear regulator is to assure compliance with regulations and safety standards by operators. One of these requirements is demonstration of, and adherence to, nuclear safety culture by the operators. At the same time, the regulators themselves are expected to live the talk and practice what they preach, i.e., demonstrate highest levels of nuclear safety culture within their organizations. Consequently, it is recognised that leadership is important in the creation of a culture that supports and promotes a strong nuclear safety performance of an organization. The leaders of a regulatory body are vital in inspiring employees to a higher level of safety and productivity, which means that they must apply good leadership attributes on a daily basis. This paper will attempt to bring forth and share attributes for strong leadership role in promoting a safety culture within a nuclear regulatory body by surveying world-wide practices and examples in developing and advanced nuclear countries. (author)

The use of a basic safety investment model in a practical risk management context

International Nuclear Information System (INIS)

Aven, Terje; Hiriart, Yolande

2011-01-01

We consider a basic model in economic safety analysis: a firm is willing to invest an amount x in safety measures to avoid an accident A, which in the case of occurrence, leads to a loss of size L. The probability of an accident is a function of x. The optimal value of x is determined by minimizing the expected costs. In the paper, we re-examine this model by adopting a practical risk/safety management perspective. We question how this model can be used for guiding the firm and regulators in determining the proper level of investment in safety. Attention is given to issues like how to determine the probability of an accident and how to take into account uncertainties that extend beyond the expected value. It is concluded that the model, with suitable extensions and if properly implemented, provides a valuable decision support tool. By focusing on investment levels and stimulating thereby the generation of alternative risk-reducing measures, the model is considered particularly useful in risk reduction (ALARP) processes. - Highlights: → It is shown how to use a basic investment model in a practical risk management setting. → The model may be a valuable decision support tool if properly implemented. → It guides decision makers on risk reduction and how to determine what is ALARP. → The model stimulates the generation of alternative risk-reducing measures.

Improving the regulation of safety at DOE nuclear facilities. Final report

International Nuclear Information System (INIS)

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE's nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation

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

Domestic Regulation for Periodic Safety Review of Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Daesik; Ahn, Seunghoon; Auh, Geunsun; Lee, Jonghyeok

2015-01-01

The so-called Periodic Safety Review (PSR) has been carried out such safety assessment throughout its life, on a periodic basis. In January 2001, the Atomic Energy Act and related regulations were amended to adopt the PSR institutional scheme from IAEA Nuclear Safety Guide 50-SG-O12. At that time the safety assessment was made to review the plant safety on 10 safety factors, such as aging management and emergency planning, where the safety factor indicates the important aspects of safety of an operating NPP to be addressed in the PSR. According to this legislation, the domestic utility, the KHNP has conducted the PSR for the operating NPP of 10 years coming up from operating license date, starting since May 2000. Some revisions in the PSR rule were made to include the additional safety factors last year. This paper introduces the current status of the PSR review and regulation, in particular new safety factors and updated technical regulation. Comprehensive safety assessment for Korea Nuclear Power Plants have performed a reflecting design and procedure changes and considering the latest technology every 10 years. This paper also examined the PSR system changes in Korea. As of July 2015, reviews for PSR of 18 units have been completed, with 229 nuclear safety improvement items. And implementation have been completed for 165 of them. PSR system has been confirmed that it has contributed to improvement of plant safety. In addition, this paper examined the PSR system change in Korea

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

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.