Perspectives on reactor safety. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Perspectives on reactor safety

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

1994-03-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Perspectives on reactor safety

International Nuclear Information System (INIS)

Haskin, F.E.

1994-03-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

IAEA activities in nuclear safety: future perspectives. Spanish Nuclear Safety Council, Madrid, 28 May 1998

International Nuclear Information System (INIS)

ElBaradei, M.

1998-01-01

The document represents the conference given by the Director General of the IAEA at the Spanish Nuclear Safety Council in Madrid, on 28 May 1998, on Agency's activities in nuclear safety. The following aspects are emphasized: Agency's role in creating a legally binding nuclear safety regime, non-binding safety standards, services provided by the Agency to assist its Member States in the Application of safety standards, Agency's nuclear safety strategy, and future perspective concerning safety aspects related to radioactive wastes, residues of past nuclear activities, and security of radiological sources

Reactor safety instrumentation of Paks NPP (experience and perspective)

International Nuclear Information System (INIS)

Elo, S.; Hamar, K.

1993-01-01

The majority of the existing control and protection systems in nuclear power plants use old analog technology and design philosophy. Maintenance and the procurement of spare parts is becoming increasingly difficult. In general there is an age degradation concern. Aging degradation in nuclear power plants must be effectively managed to avoid a loss of vital safety function, shutdown of the station, a reduced power generation, or any failure leading to expensive repair. Even with the best efforts in developing reliable and long life instrumentation and control systems for nuclear power plants it is expected that these systems for most plants will require replacements during the life of the plants. The instrumentation and control system of the nuclear power plants designed during the 70's and constructed in the 80's went out-of-date since nuclear safety is not a static concept and the digital computer technology has undergone rapid improvements during the 70's and 80's. Simultaneously the operation and the maintenance of the I ampersand C system of those plants described above becomes more and more difficult and expensive. In this context the pure quality of the former Soviet designed process instrumentation system increases the needs of upgrading this system. The author reviews the main design characteristics of the reactor safety instrumentation of the Paks NPP. Further he attempts to convey the perspective on upgrading the reactor safety instrumentation as seen by the HAEC and its Nuclear Safety Inspectorate

A primer of drug safety surveillance: an industry perspective. Part II: Product labeling and product knowledge.

Science.gov (United States)

Allan, M C

1992-01-01

To place the fundamentals of clinical drug safety surveillance in a conceptual framework that will facilitate understanding and application of adverse drug event data to protect the health of the public and support a market for pharmaceutical manufacturers' products. Part II of this series discusses specific issues regarding product labeling, such as developing the labeling, changing the labeling, and the legal as well as commercial ramifications of the contents of the labeling. An adverse event report scenario is further analyzed and suggestions are offered for maintaining the product labeling as an accurate reflection of the drug safety surveillance data. This article also emphasizes the necessity of product knowledge in adverse event database management. Both scientific and proprietary knowledge are required. Acquiring product knowledge is a part of the day-to-day activities of drug safety surveillance. A knowledge of the history of the product may forestall adverse publicity, as shown in the illustration. This review uses primary sources from the federal laws (regulations), commentaries, and summaries. Very complex topics are briefly summarized in the text. Secondary sources, ranging from newspaper articles to judicial summaries, illustrate the interpretation of adverse drug events and opportunities for drug safety surveillance intervention. The reference materials used were articles theoretically or practically applicable in the day-to-day practice of drug safety surveillance. The role of clinical drug safety surveillance in product monitoring and drug development is described. The process of drug safety surveillance is defined by the Food and Drug Administration regulations, product labeling, product knowledge, and database management. Database management is subdivided into the functions of receipt, retention, retrieval, and review of adverse event reports. Emphasis is placed on the dynamic interaction of the components of the process. Suggestions are offered

The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

International Nuclear Information System (INIS)

Shimo, Michikuni

2002-03-01

This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

Occupational Safety And Health (Osh From Islamic Perspective: A Conceptual Study

Directory of Open Access Journals (Sweden)

Afifah Binti Ismail

2018-05-01

Full Text Available ABSTRACT This paper illustrates occupational safety and health (OSH based on Islamic perspective in human resource management. This paper has been written based on the following objectives; ato state the duty of employer to provide safety workplace and to concern on employee health; bto list out the management system of OSH based on Islamic perspective as preventive measure. A purely qualitative approach of literature review was done and Islamic OSH is derived from Islamic principles which are guide by Al-Quran and sunnah. The responsibility to preserve safety and health of employee does not only relies to the employer solely but involved all workers, the government and the authority bodies as the runner for the Occupational safety and Health Act  OSHA 1994, Islamic order’s and policy to be implemented in the organization. The Occupational Safety and Health Master Plan (OSHMP 2020 is a tremendous incentive by the Ministry of Human Resource to cope and minimize the number of accident and injuries in Malaysia.   Keywords: Islamic occupational safety and health, employee safety and health, Islamic management system of OSH

Safety assessment in plant layout design using indexing approach: Implementing inherent safety perspective

International Nuclear Information System (INIS)

Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

2008-01-01

Layout planning plays a key role in the inherent safety performance of process plants since this design feature controls the possibility of accidental chain-events and the magnitude of possible consequences. A lack of suitable methods to promote the effective implementation of inherent safety in layout design calls for the development of new techniques and methods. In the present paper, a safety assessment approach suitable for layout design in the critical early phase is proposed. The concept of inherent safety is implemented within this safety assessment; the approach is based on an integrated assessment of inherent safety guideword applicability within the constraints typically present in layout design. Application of these guidewords is evaluated along with unit hazards and control devices to quantitatively map the safety performance of different layout options. Moreover, the economic aspects related to safety and inherent safety are evaluated by the method. Specific sub-indices are developed within the integrated safety assessment system to analyze and quantify the hazard related to domino effects. The proposed approach is quick in application, auditable and shares a common framework applicable in other phases of the design lifecycle (e.g. process design). The present work is divided in two parts: Part 1 (current paper) presents the application of inherent safety guidelines in layout design and the index method for safety assessment; Part 2 (accompanying paper) describes the domino hazard sub-index and demonstrates the proposed approach with a case study, thus evidencing the introduction of inherent safety features in layout design

Safety culture in design. Final report

International Nuclear Information System (INIS)

Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M.; Kahlbom, U.; Rollenhagen, C.

2013-04-01

In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

Safety culture in design. Final report

Energy Technology Data Exchange (ETDEWEB)

Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Kahlbom, U. [Risk Pilot AB, Stockholm (Sweden); Rollenhagen, C. [Vattenfall, Stockholm, (Sweden)

2013-04-15

In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

Nurses' experiences and perspectives on medication safety practices: an explorative qualitative study

NARCIS (Netherlands)

Smeulers, Marian; Onderwater, Astrid T.; van Zwieten, Myra C. B.; Vermeulen, Hester

2014-01-01

To explore nurses' experiences with and perspectives on preventing medication administration errors. Insight into nurses' experiences with and perspectives on preventing medication administration errors is important and can be utilised to tailor and implement safety practices. A qualitative

Safeguards and nuclear safety: a personal perspective

International Nuclear Information System (INIS)

Manning Muntzing, L.

1982-01-01

The IAEA's twenty-fifth anniversary provides an occasion for taking stock, for reviewing what the Agency has accomplished, for appraising its present status and for setting out the imperatives that should guide the activities in the near future. In the spirit of this occasion, the author offers his personal perspective on two fundamental aspects of the Agency's work: safeguards and nuclear safety

Perspectives on managing nuclear safety at Cernavoda NPP past, present and future

International Nuclear Information System (INIS)

Serban, M.

1997-01-01

The presentation considers the following issues: background of Romanian nuclear programme; 1990 management issues involved in Cernavoda project, nuclear safety perspectives; Cernavoda U1 operating organization today (safety related issues); good practices at Cernavoda NPP

Perspectives on managing nuclear safety at Cernavoda NPP past, present and future

Energy Technology Data Exchange (ETDEWEB)

Serban, M [Technical Safety Directorate, Unit 1., Cernavoda Nuclear Power Plant (Romania)

1997-12-01

The presentation considers the following issues: background of Romanian nuclear programme; 1990 management issues involved in Cernavoda project, nuclear safety perspectives; Cernavoda U1 operating organization today (safety related issues); good practices at Cernavoda NPP.

Safety culture in an RBMK perspective; Sostoyanie i perspektivy razvitiya sistemy povysheniya kul`tury bezopasnosti AEhS Rossii

Energy Technology Data Exchange (ETDEWEB)

Porokhin, V G [Rosenergoatom, Moscow (Russian Federation)

1997-12-31

The presentation discusses the following issues: state and perspectives of the development of the system on Russia NPP safety culture enhancement; steps of Rosehnergoatom on development of system on Russia NPP Russia NPP safety culture enhancement, qualitative and quantitative evaluation of the safety culture, the nearest perspectives on safety culture enhancement in Russia.

Safety system upgrades to a research reactor: A regulatory perspective

International Nuclear Information System (INIS)

Lamarre, G.B.; Martin, W.G.

2003-01-01

The NRU (National Research Universal) reactor, located at the Chalk River Laboratories of Atomic Energy of Canada Limited (AECL), first achieved criticality November 3, 1957. AECL continues to operate NRU for research to support safety and reliability studies for CANDU reactors and as a major supplier of medical radioisotopes. Following a detailed systematic review and assessment of NRU's design and the condition of its primary systems, AECL formally notified the Canadian Nuclear Safety Commission's (CNSC) predecessor - the Atomic Energy Control Board - in 1992 of its intention to upgrade NRU's safety systems. AECL proposed seven major upgrades to provide improvements in shutdown capability, heat removal, confinement, and reactor monitoring, particularly during and after a seismic event. From a CNSC perspective, these upgrades were necessary to meet modern safety standards. From the start of the upgrades project, the CNSC provided regulatory oversight aimed at ensuring that AECL maintained a structured approach to the upgrades. The elements of the approach include, but are not limited to, the determination of project milestones and target dates; the formalization of the design process and project quality assurance requirements; the requirements for updated documentation, including safety reports, safety notes and commissioning reports; and the approval and authorization process. This paper details, from a regulatory perspective, the structured approach used in approving the design, construction, commissioning and subsequent operation of safety system upgrades for an existing and operating research reactor, including the many challenges faced when attempting to balance the requirements of the upgrades project with AECL's need to keep NRU operating to meet its important research and production objectives. (author)

Safety climate and culture: Integrating psychological and systems perspectives.

Science.gov (United States)

Casey, Tristan; Griffin, Mark A; Flatau Harrison, Huw; Neal, Andrew

2017-07-01

Safety climate research has reached a mature stage of development, with a number of meta-analyses demonstrating the link between safety climate and safety outcomes. More recently, there has been interest from systems theorists in integrating the concept of safety culture and to a lesser extent, safety climate into systems-based models of organizational safety. Such models represent a theoretical and practical development of the safety climate concept by positioning climate as part of a dynamic work system in which perceptions of safety act to constrain and shape employee behavior. We propose safety climate and safety culture constitute part of the enabling capitals through which organizations build safety capability. We discuss how organizations can deploy different configurations of enabling capital to exert control over work systems and maintain safe and productive performance. We outline 4 key strategies through which organizations to reconcile the system control problems of promotion versus prevention, and stability versus flexibility. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

A gender perspective on work-related accidents

DEFF Research Database (Denmark)

Jensen, Sune Qvotrup; Kyed, Morten; Christensen, Ann Dorte

2014-01-01

relevant to safety researchers are introduced: The first position outlined is the theory of hegemonic masculinity which highlights the privileged position of men who represent dominant and legitimate form of masculinity. The next two positions outlined represent a classic distinction in gender theory......The key argument in the article is that a perspective on gender and masculinity could be beneficial to safety research. The aim is to outline a theoretical framework for combining gender research and safety research. In the first part of the article four strands of gender and masculinity theory...... is outlined. The second part of the article re-interprets two examples of existing outstanding safety research which have all been published in Safety Science. The two contributions are re-interpreted through a gender lens illustrating how gender and masculinity perspectives can be crucial for understandings...

Advanced vehicle dynamics of heavy trucks with the perspective of road safety

Science.gov (United States)

Trigell, Annika Stensson; Rothhämel, Malte; Pauwelussen, Joop; Kural, Karel

2017-10-01

This paper presents state-of-the art within advanced vehicle dynamics of heavy trucks with the perspective of road safety. The most common accidents with heavy trucks involved are truck against passenger cars. Safety critical situations are for example loss of control (such as rollover and lateral stability) and a majority of these occur during speed when cornering. Other critical situations are avoidance manoeuvre and road edge recovery. The dynamic behaviour of heavy trucks have significant differences compared to passenger cars and as a consequence, successful application of vehicle dynamic functions for enhanced safety of trucks might differ from the functions in passenger cars. Here, the differences between vehicle dynamics of heavy trucks and passenger cars are clarified. Advanced vehicle dynamics solutions with the perspective of road safety of trucks are presented, beginning with the topic vehicle stability, followed by the steering system, the braking system and driver assistance systems that differ in some way from that of passenger cars as well.

Quantitative Safety and Security Analysis from a Communication Perspective

Directory of Open Access Journals (Sweden)

Boris Malinowsky

2015-12-01

Full Text Available This paper introduces and exemplifies a trade-off analysis of safety and security properties in distributed systems. The aim is to support analysis for real-time communication and authentication building blocks in a wireless communication scenario. By embedding an authentication scheme into a real-time communication protocol for safety-critical scenarios, we can rely on the protocol’s individual safety and security properties. The resulting communication protocol satisfies selected safety and security properties for deployment in safety-critical use-case scenarios with security requirements. We look at handover situations in a IEEE 802.11 wireless setup between mobile nodes and access points. The trade-offs involve application-layer data goodput, probability of completed handovers, and effect on usable protocol slots, to quantify the impact of security from a lower-layer communication perspective on the communication protocols. The results are obtained using the network simulator ns-3.

Improved Management of Part Safety Classification System for Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Park, Jin Young; Park, Youn Won; Park, Heung Gyu; Park, Hyo Chan [BEES Inc., Daejeon (Korea, Republic of)

2016-10-15

As, in recent years, many quality assurance (QA) related incidents, such as falsely-certified parts and forged documentation, etc., were reported in association with the supply of structures, systems, components and parts to nuclear power plants, a need for a better management of safety classification system was addressed so that it would be based more on the level of parts . Presently, the Korean nuclear power plants do not develop and apply relevant procedures for safety classifications, but rather the safety classes of parts are determined solely based on the experience of equipment designers. So proposed in this paper is a better management plan for safety equipment classification system with an aim to strengthen the quality management for parts. The plan was developed through the analysis of newly introduced technical criteria to be applied to parts of nuclear power plant.

Nurses' experiences and perspectives on medication safety practices: an explorative qualitative study.

Science.gov (United States)

Smeulers, Marian; Onderwater, Astrid T; van Zwieten, Myra C B; Vermeulen, Hester

2014-04-01

To explore nurses' experiences with and perspectives on preventing medication administration errors. Insight into nurses' experiences with and perspectives on preventing medication administration errors is important and can be utilised to tailor and implement safety practices. A qualitative interview study of 20 nurses in an academic medical centre was conducted between March and December of 2011. Three themes emerged from this study: (1) nurses' roles and responsibilities in medication safety: aside from safe preparation and administration, the clinical reasoning of nurses is essential for medication safety; (2) nurses' ability to work safely: knowledge of risks and nurses' work circumstances influence their ability to work safely; and (3) nurses' acceptance of safety practices: advantages, feasibility and appropriateness are important incentives for acceptance of a safety practice. Nurses' experiences coincide with the assumption that they are in a pre-eminent position to enable safe medication management; however, their ability to adequately perform this role depends on sufficient knowledge to assess the risks of medication administration and on the circumstances in which they work. Safe medication management requires a learning climate and professional practice environment that enables further development of professional nursing skills and knowledge. © 2014 John Wiley & Sons Ltd.

Probabilistic safety assessment - regulatory perspective

International Nuclear Information System (INIS)

Solanki, R.B.; Paul, U.K.; Hajra, P.; Agarwal, S.K.

2002-01-01

Full text: Nuclear power plants (NPPs) have been designed, constructed and operated mainly based on deterministic safety analysis philosophy. In this approach, a substantial amount of safety margin is incorporated in the design and operational requirements. Additional margin is incorporated by applying the highest quality engineering codes, standards and practices, and the concept of defence-in-depth in design and operating procedures, by including conservative assumptions and acceptance criteria in plant response analysis of postulated initiating events (PIEs). However, as the probabilistic approach has been improved and refined over the years, it is possible for the designer, operator and regulator to get a more detailed and realistic picture of the safety importance of plant design features, operating procedures and operational practices by using probabilistic safety assessment (PSA) along with the deterministic methodology. At present, many countries including USA, UK and France are using PSA insights in their decision making along with deterministic basis. India has also made substantial progress in the development of methods for carrying out PSA. However, consensus on the use of PSA in regulatory decision-making has not been achieved yet. This paper emphasises on the requirements (e.g.,level of details, key modelling assumptions, data, modelling aspects, success criteria, sensitivity and uncertainty analysis) for improving the quality and consistency in performance and use of PSA that can facilitate meaningful use of the PSA insights in the regulatory decision-making in India. This paper also provides relevant information on international scenario and various application areas of PSA along with progress made in India. The PSA perspective presented in this paper may help in achieving consensus on the use of PSA for regulatory / utility decision-making in design and operation of NPPs

Making safety an integral part of 5S in healthcare.

Science.gov (United States)

Ikuma, Laura H; Nahmens, Isabelina

2014-01-01

Healthcare faces major challenges with provider safety and rising costs, and many organizations are using Lean to instigate change. One Lean tool, 5S, is becoming popular for improving efficiency of physical work environments, and it can also improve safety. This paper demonstrates that safety is an integral part of 5S by examining five specific 5S events in acute care facilities. We provide two arguments for how safety is linked to 5S:1. Safety is affected by 5S events, regardless of whether safety is a specific goal and 2. Safety can and should permeate all five S's as part of a comprehensive plan for system improvement. Reports of 5S events from five departments in one health system were used to evaluate how changes made at each step of the 5S impacted safety. Safety was affected positively in each step of the 5S through initial safety goals and side effects of other changes. The case studies show that 5S can be a mechanism for improving safety. Practitioners may reap additional safety benefits by incorporating safety into 5S events through a safety analysis before the 5S, safety goals and considerations during the 5S, and follow-up safety analysis.

Safety in waste management plants: An Indian perspective

International Nuclear Information System (INIS)

Shekhar, P.; Ozarde, P.D.; Gandhi, P.M.

2000-01-01

Assurance of safety of public and plant workers and protection of the environment are prime objectives in the design and construction of Waste Management Plants. In India, waste management principles and strategies have been evolved in accordance with national and international regulations and standards for radiation protection. The regulations governing radiation protection have a far-reaching impact on the management of the radioactive waste. The wastes arise at each stages of the fuel cycle with varying chemical nature, generation rate and specific activity levels depending upon the type of the facility. Segregation of waste based on its chemical nature and specific activity levels is an essential feature, as its aids in selection of treatment and conditioning process. Selection of the process, equipment and materials in the plant, are governed by safety consideration alongside factors like efficiency and simplicity. The plant design considerations like physical separation, general arrangement, ventilation zoning, access control, remote handling, process piping routing, decontamination etc. have major role in realizing waste safety. Stringent quality control measures during all stages of construction have helped in achieving the design intended safety. These aspects together with operating experience gained form basis for the improved safety features in the design and construction of waste management plants. The comprehensive safety is derived from adoption of waste management strategies and appropriate plant design considerations. The paper briefly brings safety in waste management programme in India, in its current perspective. (author)

Safety culture issues and perspectives

International Nuclear Information System (INIS)

Dahlgren Persson, K.

1999-01-01

Strong economic performance in the nuclear business must be driven by excellence in nuclear operation and uncompromising safety. If this balance is not maintained then the ability of the utility to manage this technology safely will justifiably be challenged by the public and the nuclear safety regulator. Experience has shown that once nuclear installation performance has deteriorated to a level at which there are serious regulatory concerns about the adequacy of nuclear safety, then the magnitude and difficulty of the effort required to recover performance are such that continued viability of the organisation comes into question. Thus from both the perspective of individual utilities and the nuclear industry as a whole, it is extremely important to be able to detect shortcomings and deterioration in safety management performance before it becomes a serious concern, and to put effective corrective actions in place to restore and maintain performance at high levels. Following this theme and stimulated by the Canadian Government, senior representatives of utilities and regulators from Canada, United States, Sweden and Agency staff discussed common factors from recent cases involving safety management problems and subsequent recovery processes with a view to determining the need for further work to help prevent such difficulties in the future. From the working group discussion it was concluded that in most cases considered, the utility senior executives from, in some cases the Board of Directors and Chief Executive Officer, to senior nuclear site executives, did not have the nuclear business acumen or provide the leadership necessary for the management of a successful nuclear programme. Nuclear business acumen is the insight, knowledge and ability to manage the unique interaction between the technology, economics, human factors and safety in a changing nuclear generation environment. Senior utility management failed to recognize, within their suite of performance

Harmed patients gaining voice: challenging dominant perspectives in the construction of medical harm and patient safety reforms.

Science.gov (United States)

Ocloo, Josephine Enyonam

2010-08-01

Patient safety is a central issue in healthcare. In the United Kingdom, where there is more accurate information on National Health Service (NHS) hospitals than on primary care or the private sector, the evidence on adverse incidents shows that avoidable medical harm is a major concern. This paper looks at the occurrence of medical harm and argues that in the construction of patient safety reforms, it is important to be aware of alternative narratives about issues of power and accountability from harmed patients and self-help groups, that challenge dominant perspectives on the issues. The paper draws upon evidence from two sources. First, the paper draws on experiences of self-help groups set up as a result of medical harm and part of a campaigning network, where evidence was gathered from 14 groups over more than 2 years. In addition, data were obtained from 21 individuals affected by harm that attended a residential workshop called the Break Through Programme; 18 questionnaires were completed from participants and a written narrative account of their experiences and observational data were gathered from a range of workshop sessions. Looking at the issues from harmed patients' perspectives, the research illustrates that a model of medical harm focussing predominantly upon the clinical markers and individual agency associated with a medical model operates to obscure a range of social processes. These social processes, connected to the power and dominance of the medical profession and the activities of a wider state, are seen to be a major part of the construction of harm that impacts upon patients, which is further compounded by its concealment. Understanding the experiences of harmed patients is therefore seen as an important way of generating knowledge about the medical and social processes involved in harm, that can lead to a broader framework for addressing patient safety. Copyright 2010 Elsevier Ltd. All rights reserved.

Historical perspective of thermal reactor safety in light water reactors

International Nuclear Information System (INIS)

Levy, S.

1986-01-01

A brief history of thermal reactor safety in U.S. light water reactors is provided in this paper. Important shortcomings in safety philosophy evolution versus time are identified and potential corrective actions are suggested. It should be recognized, that this analysis represents only one person's opinion and that most historical accountings reflect the author's biases and specific areas of knowledge. In that sense, many of the examples used in this paper are related to heat transfer and fluid flow safety issues, which explains why it has been included in a Thermal Hydraulics session. One additional note of caution: the value of hindsight and the selective nature of human memory when looking at the past cannot be overemphasized in any historical perspective

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)

Prioritizing risks via several expert perspectives with application to runway safety

International Nuclear Information System (INIS)

Rogerson, Ellen C.; Lambert, James H.

2012-01-01

Factor hierarchies have been widely used in the literature to represent the view of an expert of what factors most contribute to reliability or safety. The methods for rating and aggregating the influences across a set of expert-elicited factors to risk or reliability are well known as multiple criteria decision analysis. This paper describes a method for distinguishing levels of risk across a set of locations via the use of multiple factor hierarchies. The method avoids averaging across experts and is thus useful for situations where experts disagree and where an absence of expert consensus on the causative or contributing factors is important information for risk management. A case study demonstrates using seven expert perspectives on the airport-specific factors that can contribute to runway incursions. The results are described for eighty towered airports in the US. The expert perspectives include differing relative emphases across the following set of factors: airport geometry, operations, weather, geography, and days since last safety review. Future work is suggested to include human factors issues as pilot-and-controller communications styles at airports. - Highlights: ► We examine influential factors in seven expert perspectives on the problem domain. ► We assess eighty US airports with qualitative measurement scales for each risk factor. ► Results show robustness and sensitivity of the risk index to expert perspective. ► We examine factors of several types including runway geometry, operations, weather, and geography.

Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Louvat, D.; Lacoste, A.C.

2006-01-01

The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

Construction safety in DOE. Part 1, Students guide

Energy Technology Data Exchange (ETDEWEB)

Handwerk, E C

1993-08-01

This report is the first part of a compilation of safety standards for construction activities on DOE facilities. This report covers the following areas: general safety and health provisions; occupational health and environmental control/haz mat; personal protective equipment; fire protection and prevention; signs, signals, and barricades; materials handling, storage, use, and disposal; hand and power tools; welding and cutting; electrical; and scaffolding.

Pharmacy practice department chairs' perspectives on part-time faculty members.

Science.gov (United States)

Fjortoft, Nancy; Winkler, Susan R; Mai, Thy

2012-05-10

To identify the benefits and consequences of having part-time faculty members in departments of pharmacy practice from the department chair's perspective. A stratified purposive sample of 12 pharmacy practice department chairs was selected. Eleven telephone interviews were conducted. Two investigators independently read interview notes and categorized and enumerated responses to determine major themes using content analysis. The investigators jointly reviewed the data and came to consensus on major themes. Benefits of allowing full-time faculty members to reduce their position to part-time included faculty retention and improved individual faculty work/life balance. Consequences of allowing part-time faculty positions included the challenges of managing individual and departmental workloads, the risk of marginalizing part-time faculty members, and the challenges of promotion and tenure issues. All requests to switch to part-time status were faculty-driven and most were approved. There are a variety of benefits and consequences of having part-time faculty in pharmacy practice departments from the chair's perspective. Clear faculty and departmental expectations of part-time faculty members need to be established to ensure optimal success of this working arrangement.

Pharmacy Practice Department Chairs’ Perspectives on Part-Time Faculty Members

Science.gov (United States)

Winkler, Susan R.; Mai, Thy

2012-01-01

Objective. To identify the benefits and consequences of having part-time faculty members in departments of pharmacy practice from the department chair’s perspective. Methods. A stratified purposive sample of 12 pharmacy practice department chairs was selected. Eleven telephone interviews were conducted. Two investigators independently read interview notes and categorized and enumerated responses to determine major themes using content analysis. The investigators jointly reviewed the data and came to consensus on major themes. Results. Benefits of allowing full-time faculty members to reduce their position to part-time included faculty retention and improved individual faculty work/life balance. Consequences of allowing part-time faculty positions included the challenges of managing individual and departmental workloads, the risk of marginalizing part-time faculty members, and the challenges of promotion and tenure issues. All requests to switch to part-time status were faculty-driven and most were approved. Conclusions. There are a variety of benefits and consequences of having part-time faculty in pharmacy practice departments from the chair’s perspective. Clear faculty and departmental expectations of part-time faculty members need to be established to ensure optimal success of this working arrangement. PMID:22611268

Processes on Uncontrolled Aerodromes and Safety Indicators - Part II

Directory of Open Access Journals (Sweden)

Vladimír Plos

2014-01-01

Full Text Available This article follows on the Part I, where the basic processes on uncontrolled aerodromes were introduced. The uncontrolled aerodromes face with the growing traffic and from that result the higher workload on AFIS officer. This means a higher potential for dangerous situations.The article describes some models of sub-processes and creates several safety indicators related to the operation at uncontrolled aerodromes. Thanks to monitoring and evaluation of safety indicators can be adopted targeted safety measures and thus increase safety on small uncontrolled aerodromes.

A risk-informed perspective on deterministic safety analysis of nuclear power plants

International Nuclear Information System (INIS)

Wan, P.T.

2009-01-01

In this work, the deterministic safety analysis (DSA) approach to nuclear safety is examined from a risk-informed perspective. One objective of safety analysis of a nuclear power plant is to demonstrate via analysis that the risks to the public from events or accidents that are within the design basis of the power plant are within acceptable levels with a high degree of assurance. This nuclear safety analysis objective can be translated into two requirements on the risk estimates of design basis events or accidents: the nominal risk estimate to the public must be shown to be within acceptable levels, and the uncertainty in the risk estimates must be shown to be small on an absolute or relative basis. The DSA approach combined with the defense-in-depth (DID) principle is a simplified safety analysis approach that attempts to achieve the above safety analysis objective in the face of potentially large uncertainties in the risk estimates of a nuclear power plant by treating the various uncertainty contributors using a stylized conservative binary (yes-no) approach, and applying multiple overlapping physical barriers and defense levels to protect against the release of radioactivity from the reactor. It is shown that by focusing on the consequence aspect of risk, the previous two nuclear safety analysis requirements on risk can be satisfied with the DSA-DID approach to nuclear safety. It is also shown the use of multiple overlapping physical barriers and defense levels in the traditional DSA-DID approach to nuclear safety is risk-informed in the sense that it provides a consistently high level of confidence in the validity of the safety analysis results for various design basis events or accidents with a wide range of frequency of occurrence. It is hoped that by providing a linkage between the consequence analysis approach in DSA with a risk-informed perspective, greater understanding of the limitation and capability of the DSA approach is obtained. (author)

Patient Safety Culture in Intensive Care Units from the Perspective of Nurses: A Cross-Sectional Study.

Science.gov (United States)

Farzi, Sedigheh; Moladoost, Azam; Bahrami, Masoud; Farzi, Saba; Etminani, Reza

2017-01-01

One of the goals of nursing is providing safe care, prevention of injury, and health promotion of patients. Patient safety in intensive care units is threatened for various reasons. This study aimed to survey patient safety culture from the perspective of nurses in intensive care units. This cross-sectional study was conducted in 2016. Sampling was done using the convenience method. The sample consisted of 367 nurses working in intensive care units of teaching hospitals affiliated to Isfahan University of Medical Sciences. Data collection was performed using a two-part questionnaire that included demographic and hospital survey on Patient Safety Culture (HSOPSC) questionnaire. Data analysis was done using descriptive statistics (mean and standard deviation). Among the 12 dimensions of safety culture, the nurses assigned the highest score to "team work within units" (97.3%) and "Organizational learning-continuous improvement" (84%). They assigned the least score to "handoffs and transitions"(21.1%), "non-punitive response to errors" (24.7%), "Staffing" (35.6%), "Communication openness" (47.5%), and "Teamwork across units" (49.4%). The patient safety culture dimensions have low levels that require adequate attention and essential measures of health care centers including facilitating teamwork, providing adequate staff, and developing a checklist of handoffs and transitions. Furthermore, to increase reporting error and to promote a patient safety culture in intensive care units, some strategies should be adopted including a system-based approach to deal with the error.

A primer of drug safety surveillance: an industry perspective. Part I: Information flow, new drug development, and federal regulations.

Science.gov (United States)

Allan, M C

1992-01-01

To place the fundamentals of clinical drug safety surveillance in a conceptual framework that will facilitate understanding and application of adverse drug event data to protect the health of the public and support a market for pharmaceutical manufacturers' products. Part I of this series provides a background for the discussion of drug safety by defining the basic terms and showing the flow of safety information through a pharmaceutical company. The customers for adverse drug event data are identified to provide a basis for providing quality service. The development of a drug product is briefly reviewed to show the evolution of safety data. Drug development and safety are defined by federal regulations. These regulations are developed by the FDA with information from pharmaceutical manufacturers. The intent of the regulations and the accompanying guidelines is described. An illustration from the news media is cited to show an alternative, positive approach to handling an adverse event report. This review uses primary sources from the federal laws (regulations), commentaries, and summaries. Very complex topics are briefly summarized in the text and additional readings are presented in an appendix. Secondary sources, ranging from newspaper articles to judicial summaries, illustrate the interpretation of adverse drug events and opportunities for drug safety surveillance intervention. The reference materials used were articles theoretically or practically applicable in the day-to-day practice of drug safety surveillance. The role of clinical drug safety surveillance in product monitoring and drug development is described. The process of drug safety surveillance is defined by the Food and Drug Administration regulations, product labeling, product knowledge, and database management. Database management is subdivided into the functions of receipt, retention, retrieval, and review of adverse event reports. Emphasis is placed on the dynamic interaction ;of the components

A theoretical perspective on road safety communication campaigns.

Science.gov (United States)

Elvik, Rune

2016-12-01

This paper proposes a theoretical perspective on road safety communication campaigns, which may help in identifying the conditions under which such campaigns can be effective. The paper proposes that, from a theoretical point of view, it is reasonable to assume that road user behaviour is, by and large, subjectively rational. This means that road users are assumed to behave the way they think is best. If this assumption is accepted, the best theoretical prediction is that road safety campaigns consisting of persuasive messages only will have no effect on road user behaviour and accordingly no effect on accidents. This theoretical prediction is not supported by meta-analyses of studies that have evaluated the effects of road safety communication campaigns. These analyses conclude that, on the average, such campaigns are associated with an accident reduction. The paper discusses whether this finding can be explained theoretically. The discussion relies on the distinction made by many modern theorists between bounded and perfect rationality. Road user behaviour is characterised by bounded rationality. Hence, if road users can gain insight into the bounds of their rationality, so that they see advantages to themselves of changing behaviour, they are likely to do so. It is, however, largely unknown whether such a mechanism explains why some road safety communication campaigns have been found to be more effective than others. Copyright © 2015 Elsevier Ltd. All rights reserved.

A Glance on the Safety Culture in Industrial Gamma Radiography in the Philippines: Regulatory Body Perspective

International Nuclear Information System (INIS)

Borras, A.M.

2016-01-01

The current version of the Code of PNRI Regulations (CPR) Part 11 was published in the Official Gazette on 2010. It is just a year ahead of the publication of the IAEA Specific Safety Guide No. 11. In view of these, radiation safety culture in the practice of industrial gamma radiography was not yet fully introduced in the said national regulations in the country. However, it should not be a reflection that the radiation workers in the country specifically in the said field of practice do not exercise positive safety culture. The Nuclear Regulatory Division (NRD)—regulatory arm, although not yet separated from the Philippine Nuclear Research Institute (PNRI0) as mandated by law — the promotional organization, has a well established and systemic regulatory infrastructure. It is attested by several studies and reports, among others. This study aims to assess the status of the existing safety culture in the conduct of industrial gamma radiography in the country through personnel perception survey of the radiation workers, i.e., managers, radiation safety officers, radiographers and radiographer’s assistants, based on the IAEA five characteristics of safety culture stipulated in the IAEA Safety Guide No. GS-G-3.5, “The Management System for Nuclear Installations”. It is assessed by the NRD of the PNRI. Also, the study determines the existence of safety culture as to the perspective of NRD through observations on the conduct of radiographic operations and walk-through of the facility while using the three-level Schein Model, i.e., “artefacts”, “espoused values” and “basic assumptions” and document reviews, among others

Graphical symbols -- Safety colours and safety signs -- Part 1: Design principles for safety signs in workplaces and public areas

CERN Document Server

International Organization for Standardization. Geneva

2002-01-01

This International Standard establishes the safety identification colours and design principles for safety signs to be used in workplaces and in public areas for the purpose of accident prevention, fire protection, health hazard information and emergency evacuation. It also establishes the basic principles to be applied when developing standards containing safety signs. This part of ISO 3864 is applicable to workplaces and all locations and all sectors where safety-related questions may be posed. However, it is not applicable to the signalling used for guiding rail, road, river, maritime and air traffic and, generally speaking, to those sectors subject to a regulation which may differ.

Mapping a Research Agenda for Home Care Safety: Perspectives from Researchers, Providers, and Decision Makers

Science.gov (United States)

Macdonald, Marilyn; Lang, Ariella; MacDonald, Jo-Anne

2011-01-01

The purpose of this qualitative interpretive design was to explore the perspectives of researchers, health care providers, policy makers, and decision makers on key risks, concerns, and emerging issues related to home care safety that would inform a line of research inquiry. Defining safety specifically in this home care context has yet to be…

Patient safety culture in intensive care units from the perspective of nurses: A cross-sectional study

Directory of Open Access Journals (Sweden)

Sedigheh Farzi

2017-01-01

Full Text Available Background: One of the goals of nursing is providing safe care, prevention of injury, and health promotion of patients. Patient safety in intensive care units is threatened for various reasons. This study aimed to survey patient safety culture from the perspective of nurses in intensive care units. Materials and Methods: This cross-sectional study was conducted in 2016. Sampling was done using the convenience method. The sample consisted of 367 nurses working in intensive care units of teaching hospitals affiliated to Isfahan University of Medical Sciences. Data collection was performed using a two-part questionnaire that included demographic and hospital survey on Patient Safety Culture (HSOPSC questionnaire. Data analysis was done using descriptive statistics (mean and standard deviation. Results: Among the 12 dimensions of safety culture, the nurses assigned the highest score to “team work within units” (97.3% and “Organizational learning-continuous improvement” (84%. They assigned the least score to “handoffs and transitions”(21.1%, “non-punitive response to errors” (24.7%, “Staffing” (35.6%, “Communication openness” (47.5%, and “Teamwork across units” (49.4%. Conclusions: The patient safety culture dimensions have low levels that require adequate attention and essential measures of health care centers including facilitating teamwork, providing adequate staff, and developing a checklist of handoffs and transitions. Furthermore, to increase reporting error and to promote a patient safety culture in intensive care units, some strategies should be adopted including a system-based approach to deal with the error.

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.

Determining the causal relationships among balanced scorecard perspectives on school safety performance: case of Saudi Arabia.

Science.gov (United States)

Alolah, Turki; Stewart, Rodney A; Panuwatwanich, Kriengsak; Mohamed, Sherif

2014-07-01

In the public schools of many developing countries, numerous accidents and incidents occur because of poor safety regulations and management systems. To improve the educational environment in Saudi Arabia, the Ministry of Education seeks novel approaches to measure school safety performance in order to decrease incidents and accidents. The main objective of this research was to develop a systematic approach for measuring Saudi school safety performance using the balanced scorecard framework philosophy. The evolved third generation balanced scorecard framework is considered to be a suitable and robust framework that captures the system-wide leading and lagging indicators of business performance. The balanced scorecard architecture is ideal for adaptation to complex areas such as safety management where a holistic system evaluation is more effective than traditional compartmentalised approaches. In developing the safety performance balanced scorecard for Saudi schools, the conceptual framework was first developed and peer-reviewed by eighteen Saudi education experts. Next, 200 participants, including teachers, school executives, and Ministry of Education officers, were recruited to rate both the importance and the performance of 79 measurement items used in the framework. Exploratory factor analysis, followed by the confirmatory partial least squares method, was then conducted in order to operationalise the safety performance balanced scorecard, which encapsulates the following five salient perspectives: safety management and leadership; safety learning and training; safety policy, procedures and processes; workforce safety culture; and safety performance. Partial least squares based structural equation modelling was then conducted to reveal five significant relationships between perspectives, namely, safety management and leadership had a significant effect on safety learning and training and safety policy, procedures and processes, both safety learning and training

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

International Nuclear Information System (INIS)

Duncan, R. J.

2016-01-01

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

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.

Development and maturity of the safety case: an international perspective from the nea secretariat

International Nuclear Information System (INIS)

2008-01-01

This section describes the evolution and development of the concept of the safety case, provides some perspective on the maturity of the concept in practice, and highlights key outcomes and conclusions of the symposium. (author)

Safety Management in Non-Nuclear Contexts. Examples from Swedish Railway Regulatory and Company Perspectives

International Nuclear Information System (INIS)

Salo, Ilkka; Svensson, Ola

2005-06-01

studied organizations respectively. These three chapters give a detailed account of safety management from a system perspective and applications in the organizations studied, and could be read independently of each other. In the fourth chapter the report concludes with summarizing safety management in SRA and SJ by mapping the results on important concepts from the system theoretical framework, and general themes for safety management applicable across contexts are suggested. The qualitative descriptions of the organizations generated a detailed account on how safety is managed in Swedish railway operations. Examples of safety management in practice are given both from the regulatory point of view and from an organizational position close to the actual operations. The Swedish railway operations are strictly regulated and the safety goals are identifiable along the legislative documentation from the government's goals for safe operations expressed in the railway legislation, through SRA's regulations, to SJ's internal regulations. There is a high degree of coherence between SJ's and SRA's formulations of safety management and safe operations in general. Both organizations have their origin in the former national railway company, which may is partly reflected in the high degree of correspondence between the approaches towards safety. Both organizations make use of a system approach to their operations, which are clearly reflected in the highly structured organizations, with core objectives, operational responsibilities, procedures, and information feedback prerequisites sufficiently mapped on the organizational units. The report gives both detailed accounts and summaries of a number of central themes for safety management derived from the system theoretical framework, and also themes relevant for safety management in general. For example: the organizations definitions of safety management, descriptions of the organizational structures, recent processes of organizational

A summary of the Nordic-group conference on safety management

International Nuclear Information System (INIS)

Salo, I.; Svenson, O.

2005-04-01

The report summarizes the Nordic-group conference on safety management, which took place in Lund, Sweden on October 28-29, 2004. The theme-group was originally created by researchers who had a common interest in cooperation, sharing their results, and discuss topics focusing on safety management and safety culture in nuclear power production, but also in other technologies involving risks. The research has, so far, basically been related to the areas of MTO, partly from a psychological perspective, but also from other perspectives. Today, the group consists primarily of members from Sweden, Finland and Norway. During the last three years the group has gathered twice a year. (au)

Quantitative Safety and Security Analysis from a Communication Perspective

DEFF Research Database (Denmark)

Malinowsky, Boris; Schwefel, Hans-Peter; Jung, Oliver

2014-01-01

This paper introduces and exemplifies a trade-off analysis of safety and security properties in distributed systems. The aim is to support analysis for real-time communication and authentication building blocks in a wireless communication scenario. By embedding an authentication scheme into a real...... at handover situations in a IEEE 802.11 wireless setup between mobile nodes and access points. The trade-offs involve application-layer data goodput, probability of completed handovers, and effect on usable protocol slots, to quantify the impact of security from a lower-layer communication perspective...

Radiation safety - an IAEA perspective

International Nuclear Information System (INIS)

Persson, L.

1993-01-01

The activities of the IAEA relating to radiation safety cover: The preparation of International Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources - it is expected that the new Basic Safety Standards will be adopted by the sponsoring organizations in 1994. The radiological consequences of the Chernobyl accident: the thyroid cancer controversy - the hypothesis that must be tested is whether the reported increased incidence of thyroid cancer due to exposure to radioactive iodine released in the Chernobyl accident, and there are several questions that must be answered before a firm conclusion can be reached. Emergency Response Services (ERS): In March 1993, at the request of Viet Nam, which invoked the Energency Assistance Convention, a medical team organized by the IAEA went to Hanoi and assisted in arranging for an overexposed person to be transferred from Viet Nam to Paris for specialized medical treatment. In April 1993, the ERS was used to inform Member States of the consequences of an explosion at the Tomsk 7 fuel reprocessing plant in Siberia, Russia, which caused a radiation leak. Reassessing the long range transport of radioactive material through the environment: Data from the Chernobyl accident have been used for model validation in the Atmospheric Transport Model Evaluation Study (ATMES). A follow-up programme, the European Tracer Experiment (ETEX) with experimental studies of long range atmospheric movements over Europe has been established in order to increase knowledge and prediction capability. As part of the programme, a non-toxic atmospheric tracer will be released under suitable conditions in 1994. The Radiation Protection Advisory Teams Service (RAPAT): In many of the developing countries visited, the lack of an adequate infrastructure for radiation protection is the main obstacle to improved radiation protection. Strengthening radiation and nuclear safety infrastructures in successor states of the USSR: The

Perceived safety among off-piste & backcountry skiers

OpenAIRE

Berget, Håkon

2012-01-01

Survival in avalanche terrain is about being in the right place at the right time, i.e. taking the right decisions regarding avalanche danger. Psychological research has shown that emotions like fear and safety (absence of fear) influence our decisions. Perceived safety might therefore be an important part of the human factor in avalanche accidents. Few studies have examined perceived safety from a skier`s perspective. The aim of this study was to develop a scale for assessing perceived safet...

Road safety perspectives among employees of a multinational corporation in urban India: local context for global injury prevention.

Science.gov (United States)

Jacoby, Sara F; Winston, Flaura K; Richmond, Therese S

2017-12-01

In rapidly developing economies, like urban India, where road traffic injury rates are among the world's highest, the corporate workplace offers a non-traditional venue for road safety interventions. In partnership with a major multinational corporation (MNC) with a large Indian workforce, this study aimed to elicit local employee perspectives on road safety to inform a global corporate health platform. The safety attitudes and behaviours of 75 employees were collected through self-report survey and focus groups in the MNC offices in Bangalore and Pune. Analysis of these data uncovered incongruity between employee knowledge of safety strategies and their enacted safety behaviours and identified local preference for interventions and policy-level actions. The methods modelled by this study offer a straightforward approach for eliciting employee perspective for local road safety interventions that fit within a global strategy to improve employee health. Study findings suggest that MNCs can employ a range of strategies to improve the road traffic safety of their employees in settings like urban India including: implementing corporate traffic safety policy, making local infrastructure changes to improve road and traffic conditions, advocating for road safety with government partners and providing employees with education and access to safety equipment and safe transportation options.

Workshop on Indian Chemical Industry: perspectives on safety, cleaner production and environment production

NARCIS (Netherlands)

Ham, J.M.

1996-01-01

A Workshop on "Indian Chemical Industry: Perspectives on Safety, Cleaner Production and Environmental Protection" was held on 3, 4 and 5 January 1996, in Bombay, India. The main objective of the workshop, which was organised jointly by the Government of India, UNIDO/UNDP and the Indian Chemical

Procurement and control of spare and replacement parts - a regulatory perspective

International Nuclear Information System (INIS)

Baker, E.T.; Grimes, B.K.; Merschoff, E.W.

1987-01-01

As the nuclear industry shifts from a construction to an operations orientation, a number of fundamental changes have occurred in the type of safety-related procurements and the manner in which the utilities accomplish these procurements. Specifically, procurements have shifted from the purchase of large systems and components by architect-engineers, and nuclear steam supply system (NSSS) suppliers to the procurement by utilities of subassemblies, individual pieces of equipment (e.g., breakers, relays), and small parts for repairing individual pieces of equipment. To ensure that equipment will continue to perform its intended function and to satisfy regulatory requirements utilities must consider several things: (1) does the equipment perform a safety function; (2) does the replacement part affect the safety function; and (3) does the replacement part affect the seismic or environmental qualification. If the answer to any of these questions is yes, the purchaser has two alternatives. He may procure the item as safety-related and require the supplier or manufacturer to comply with all the applicable technical and quality requirements or he may purchase the item commercial grade and perform the necessary inspections and tests to ensure the item meets the requirements, i.e., dedicate the item

FUNMIG Integrated Project results and conclusions from a safety case perspective

International Nuclear Information System (INIS)

Schwyn, B.; Wersin, P.; Rüedi, J.; Schneider, J.; Altmann, S.; Missana, T.; Noseck, U.

2012-01-01

The scope of the FUNMIG Integrated Project (IP) was to improve the knowledge base on biogeochemical processes in the geosphere which are relevant for the safety of radioactive waste repositories. An important part of this project involved the interaction between data producers (research) and data users (radioactive waste management organisations in Europe). The aim thereof was to foster the benefits of the research work for performance assessment (PA), and in a broader sense, for the safety case of radioactive waste repositories. For this purpose a specifically adapted procedure was elaborated. Thus, relevant features, events and processes (FEPs) for the three host rock types, clay, crystalline and salt, were taken from internationally accepted catalogues and mapped onto each of the 108 research tasks conducted during the FUNMIG project by a standardised procedure. The main outcome thereof was a host-rock specific tool (Task Evaluation Table) in which the relevance and benefits of the research results were evaluated both from the PA and research perspective. Virtually all generated data within FUNMIG are related to the safety-relevant FEP-groups “transport mechanisms” and “retardation”. Generally speaking, much of the work within FUNMIG helped to support and to increase confidence in the simplified PA transport and retardation models used for calculating radionuclide (RN) transport through the host rock. Some of the studies on retardation processes (e.g. coupled sorption-redox processes at the mineral–water interface) yielded valuable data for all three rock types dealt within the IP. However, most of the studies provided improved insight regarding host-rock specific features and processes, the majority of this work being dedicated to clay-rich and crystalline host rocks. For both of these host rock types, FUNMIG has significantly contributed to improving understanding on a conceptual level, both by providing new experimental data at different spatial

Safety issues in robotic handling of nuclear weapon parts

International Nuclear Information System (INIS)

Drotning, W.; Wapman, W.; Fahrenholtz, J.

1993-01-01

Robotic systems are being developed by the Intelligent Systems and Robotics Center at Sandia National Laboratories to perform automated handling tasks with radioactive weapon parts. These systems will reduce the occupational radiation exposure to workers by automating operations that are currently performed manually. The robotic systems at Sandia incorporate several levels of mechanical, electrical, and software safety for handling hazardous materials. For example, tooling used by the robot to handle radioactive parts has been designed with mechanical features that allow the robot to release its payload only at designated locations in the robotic workspace. In addition, software processes check for expected and unexpected situations throughout the operations. Incorporation of features such as these provides multiple levels of safety for handling hazardous or valuable payloads with automated intelligent systems

Days on safety of industrial radiographic controls

International Nuclear Information System (INIS)

2008-01-01

This program is divided in three parts: the context and the regulations, the preparation and the implementation, the tools of prevention and the initiatives and the perspectives.In the first part devoted to the context and regulation are: the context by the Authority of nuclear safety (A.S.N.), the regulation referential, the transport of gamma-graphs; in the second part are the distribution of liabilities, materials and associated requirements, the feedback of incidents and exploitation of it, training and base requirements, works of S.F.R.P./C.O.F.R.E.N.D. and the A.S.N. position; the third part includes help to evaluation of risks at working places of industry radiologists, dosimetry study of a working place, guide to evaluate oneself; the fourth part devoted to the initiatives and the perspectives are: regional experiences charters of good practices in industry radiography, integration of works and deployment by the members of the C.O.F.R.E.N.D., perspectives in matter of prevention of occupational risks in the area of industry radiography. (N.C.)

75 FR 68224 - Safety Management Systems for Part 121 Certificate Holders

Science.gov (United States)

2010-11-05

... safety audit (LOSA), and an advanced qualification program (AQP) as part of the SMS. The FAA must issue a... the SMS safety assurance process, periodic audits of flight crew performance, such as Line Operations... programs: ASAPs, flight operational quality assurance systems (FOQAs), LOSAs, and advanced qualification...

Modeling the factors affecting unsafe behavior in the construction industry from safety supervisors' perspective.

Science.gov (United States)

Khosravi, Yahya; Asilian-Mahabadi, Hassan; Hajizadeh, Ebrahim; Hassanzadeh-Rangi, Narmin; Bastani, Hamid; Khavanin, Ali; Mortazavi, Seyed Bagher

2014-01-01

There can be little doubt that the construction is the most hazardous industry in the worldwide. This study was designed to modeling the factors affecting unsafe behavior from the perspective of safety supervisors. The qualitative research was conducted to extract a conceptual model. A structural model was then developed based on a questionnaire survey (n=266) by two stage Structural Equation Model (SEM) approach. An excellent confirmed 12-factors structure explained about 62% of variances unsafe behavior in the construction industry. A good fit structural model indicated that safety climate factors were positively correlated with safety individual factors (Pconstruction workers' engagement in safe or unsafe behavior. In order to improve construction safety performance, more focus on the workplace condition is required.

Safety study of PCC 2140 and ALILOG 21 used as part of safety measurement systems

International Nuclear Information System (INIS)

Meriaux, Pierre; Adnot, Serge; Rayrolles, Catherine.

1978-03-01

The PCC 2140 and ALILOG 21 equipment may be used at C.E.A. or E.D.F., as part of safety measurement systems. In a study of a similar, but earlier equipment, it was noticed that certain types of failures caused the system to switch to the least sensitive measurement range, which was detrimental to safety. This report analyses failure modes leading to unsafe failures and evaluates the risks ran into taking in account tests during use [fr

The culture of patient safety from the perspective of the pediatric emergency nursing team

Directory of Open Access Journals (Sweden)

Taise Rocha Macedo

Full Text Available Abstract OBJECTIVE To identify the patient safety culture in pediatric emergencies from the perspective of the nursing team. METHOD A quantitative, cross-sectional survey research study with a sample composed of 75 professionals of the nursing team. Data was collected between September and November 2014 in three Pediatric Emergency units by applying the Hospital Survey on Patient Safety Culture instrument. Data were submitted to descriptive analysis. RESULTS Strong areas for patient safety were not found, with areas identified having potential being: Expectations and actions from supervisors/management to promote patient safety and teamwork. Areas identified as critical were: Non-punitive response to error and support from hospital management for patient safety. The study found a gap between the safety culture and pediatric emergencies, but it found possibilities of transformation that will contribute to the safety of pediatric patients. CONCLUSION Nursing professionals need to become protagonists in the process of replacing the current paradigm for a culture focused on safety. The replication of this study in other institutions is suggested in order to improve the current health care scenario.

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...

Child safety from the perspective of essential needs

Directory of Open Access Journals (Sweden)

Débora Falleiros de Mello

2014-08-01

Full Text Available OBJECTIVE: to characterize the maternal care for children under one year of age with a view to child health promotion at home.METHOD: exploratory study with qualitative data analysis, thematic mode, based on the conceptual framework of the essential needs of children, based on interviews recorded with 16 mothers.RESULTS: the analysis of the maternal narratives showed elements that facilitate the promotion of child safety: presence and involvement of the parents, constant surveillance for physical and emotional protection, experiences to stimulate child development, support networks for childcare at home; and inhibiting elements of child safety: limited perception of characteristics of child development and of children's singularities, overprotection and difficulties to set limits.CONCLUSION: the study enhances the understanding of home care in child health promotion, directing professional actions to guarantee ongoing nurturing relationships, protection, respect for individual differences, experiences appropriate to child development, limit setting and construction of stable and supportive social networks. In addition, the relevance of considering the maternal perspective in child health care is considered, as a strategy to apprehend aspects related to the attendance of the growth and development needs, particularly for child health promotion at home.

Scientific perspectives on greenhouse problem. Part 2

International Nuclear Information System (INIS)

Jastrow, R.; Nierenberg, W.; Seitz, F.

1992-01-01

The spectre of major climate change caused by the greenhouse effect has generated intensive research, heated scientific debate and a concerted international effort to draft agreements for the reduction of greenhouse gas emissions. This report of Scientific Perspectives on the greenhouse problem explains the technical issues in the debate in language readily understandable to the non-specialist. The inherent complexities of attempts to simulate the earth's climate are explained, particularly with regard to the effects of clouds and the circulation of the oceans, which together represent the largest factors of uncertainty in current global warming forecasts. Results of the search for the 'greenhouse signal' in existing climate records aredescribed in chapter 3 (part two). Chapter 5 (part two) develops a projection of 21st-century warming based on relatively firm evidence of the earth's actual response to known increases in greenhouse gas emissions during the last 100 years

Transport safety and traffic forecasting: An economist's perspective

Directory of Open Access Journals (Sweden)

Kenneth Button

2014-07-01

Full Text Available This paper is concerned with forecasting traffic accidents at a relatively aggregate level and over a long time period; the sort of information that is required as part of a comprehensive cost-benefit analysis of a major transportation investment or policy change. It is not so focused on appraising the social value of specific safety measures, although some of the points made seem germane. Whereas there has been much ex ante analysis at the meso- and macro-levels looking at the causes of accidents and ways of reducing both their number and severity, much less ex post has been done considering the accuracy of predictions of accident rates after an investment or policy initiative. Given the evidence that exists on the accuracy of traffic forecasts, especially involving oft over-optimistic predictions of public transit and rail use, there is at least a prima facie case for arguing that many investment and policy decisions are being based, in part, on over favorable assumptions with regard to their aggregate safety impacts.

Perspective on Secure Development Activities and Features of Safety I and C Systems

International Nuclear Information System (INIS)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui

2015-01-01

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle

Perspective on Secure Development Activities and Features of Safety I and C Systems

Energy Technology Data Exchange (ETDEWEB)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle.

Safety Management in Non-Nuclear Contexts. Examples from Swedish Railway Regulatory and Company Perspectives

Energy Technology Data Exchange (ETDEWEB)

Salo, Ilkka; Svensson, Ola (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

2005-06-15

studied organizations respectively. These three chapters give a detailed account of safety management from a system perspective and applications in the organizations studied, and could be read independently of each other. In the fourth chapter the report concludes with summarizing safety management in SRA and SJ by mapping the results on important concepts from the system theoretical framework, and general themes for safety management applicable across contexts are suggested. The qualitative descriptions of the organizations generated a detailed account on how safety is managed in Swedish railway operations. Examples of safety management in practice are given both from the regulatory point of view and from an organizational position close to the actual operations. The Swedish railway operations are strictly regulated and the safety goals are identifiable along the legislative documentation from the government's goals for safe operations expressed in the railway legislation, through SRA's regulations, to SJ's internal regulations. There is a high degree of coherence between SJ's and SRA's formulations of safety management and safe operations in general. Both organizations have their origin in the former national railway company, which may is partly reflected in the high degree of correspondence between the approaches towards safety. Both organizations make use of a system approach to their operations, which are clearly reflected in the highly structured organizations, with core objectives, operational responsibilities, procedures, and information feedback prerequisites sufficiently mapped on the organizational units. The report gives both detailed accounts and summaries of a number of central themes for safety management derived from the system theoretical framework, and also themes relevant for safety management in general. For example: the organizations definitions of safety management, descriptions of the organizational structures, recent

Drug safety: withdrawn medications are only part of the picture.

Science.gov (United States)

Rawson, Nigel S B

2016-02-13

In a research article published in BMC Medicine, Onakpoya and colleagues provide a historical review of withdrawals of medications for safety reasons. However, withdrawn medications are only one part of the picture about how regulatory agencies manage drug risks. Moreover, medications introduced before the increased pre-marketing regulations and post-marketing monitoring systems instituted after the thalidomide tragedy have little relevance when considering the present drug safety picture because the circumstances under which they were introduced were completely different. To more fully understand drug safety management and regulatory agency actions, withdrawals should be evaluated within the setting and timeframe in which the medications are approved, which requires information about approvals and safety warnings. Studies are needed that provide a more comprehensive current picture of the identification and evaluation of drug safety risks as well as how regulatory agencies deal with them. Please see related research article: http://bmcmedicine.biomedcentral.com/articles/10.1186/s12916-016-0553-2.

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

International Nuclear Information System (INIS)

Montewka, Jakub; Goerlandt, Floris; Kujala, Pentti

2014-01-01

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

Construction safety in DOE. Part 2, Students guide

Energy Technology Data Exchange (ETDEWEB)

Handwerk, E.C.

1993-08-01

This report is the second part of a compilation of safety standards for construction activities on DOE facilities. This report covers the following areas: floor and wall openings; cranes, derricks, hoists, elevators, and conveyors; motor vehicles, mechanized equipment, and marine operations; excavations; concrete and masonry construction; steel erection; underground construction, caisson, cofferdams, and compressed air; demolition; blasting and the use of explosives; power transmission and distribution; rollover protective structures, overhead protection; and ladders.

49 CFR Appendix B to Part 222 - Alternative Safety Measures

Science.gov (United States)

2010-10-01

.... 222, App. B Appendix B to Part 222—Alternative Safety Measures Introduction A public authority seeking... requirements associated with an SSM as listed in appendix A is revised or deleted, data or analysis supporting...); d. Photographic or video equipment deployed to capture images sufficient to document the violation...

Perspectives on understanding and verifying the safety terrain of modular high temperature gas-cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Carlson, Donald E., E-mail: donald@carlsonperin.net [11221 Empire Lane, Rockville, MD 20852 (United States); Ball, Sydney J., E-mail: beckysyd@comcast.net [100 Greywood Place, Oak Ridge, TN 37830 (United States)

2016-09-15

The passive safety characteristics of modular high temperature gas-cooled reactors (HTGRs) are conceptually well known and are largely supported by insights from past and ongoing research. This paper offers perspectives on selected issues in areas where further analysis and testing achievable within existing research and demonstration programs could help address residual uncertainties and better support the analysis of safety performance and the regulatory assessment of defense in depth. Areas considered include the evaluation of normal and anomalous core operating conditions and the analysis of accidents involving loss of forced cooling, coolant depressurization, air ingress, moisture ingress, and reactivity events. In addition to discussing associated uncertainties and potential measures to address them, this paper also proposes supplemental “safety terrain” studies that would use realistic assessments of postulated extreme event sequences to establish a more comprehensive understanding of the inherent behaviors and ultimate safety capabilities of modular HTGRs.

Perspectives on Understanding and Verifying the Safety Terrain of Modular High Temperature Gas-Cooled Reactors

International Nuclear Information System (INIS)

Carlson, Donald E.

2014-01-01

The inherent safety characteristics of modular high temperature gas-cooled reactors (HTGRs) are conceptually well known and are largely supported by insights from past and ongoing research. This paper offers perspectives on selected issues in areas where further analysis and testing achievable within existing research and demonstration programs could help address residual uncertainties and better support the analysis of safety performance and the regulatory assessment of defense in depth. Areas considered include the evaluation of normal and anomalous core operating conditions and the analysis of accidents involving coolant depressurization, air ingress, moisture ingress, and reactivity insertion. In addition to discussing associated uncertainties and potential measures to address them, the paper also proposes supplemental “safety terrain” studies that would use realistic assessments of postulated extreme event sequences to establish a more comprehensive understanding of the inherent behaviors and ultimate safety capabilities of modular HTGRs. (author)

Evaluating Safety Culture Under the Socio-Technical Complex Systems Perspective

International Nuclear Information System (INIS)

Lemos, F. L. de

2016-01-01

Since the term “safety culture” was coined, it has gained more and more attention as an effort to achieve higher levels of system safety. A good deal of effort has been done in order to better define, evaluate and implement safety culture programs in organizations throughout all industries, and especially in the Nuclear Industry. Unfortunately, despite all those efforts, we continue to witness accidents that are, in great part, attributed to flaws in the safety culture of the organization. Fukushima nuclear accident is one example of a serious accident in which flaws in the safety culture has been pointed to as one of the main contributors. In general, the definitions of safety culture emphasise the social aspect of the system. While the definitions also include the relations with the technical aspects, it does so in a general sense. For example, the International Nuclear Safety Advisory Group (INSAG) defines safety culture as: “The assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receives the attention warranted by their significance.” By the way safety culture is defined we can infer that it represents a property of a social system, or a property of the social aspect of the system. In this sense, the social system is a component of the whole system. Where, “system” is understood to be comprised of a social (humans) and technical (equipment) aspects, as a Nuclear Power Plant, for example. Therefore, treating safety culture as an identity on its own right, finding and fixing flaws in the safety culture may not be enough to improve safety of the system. We also needed to evaluate all the interactions between the components that comprise all the aspects of the system. In some cases a flaw in the safety culture can easily be detected, such as an employee not wearing appropriate individual protection equipment, e.g., dosimeter, or when basic safety

Safety Management. An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts

Energy Technology Data Exchange (ETDEWEB)

Svensson, Ola (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden)); Salo, Ilkka (Dept. of Psychology, Lund Univ., Lund (Sweden))

2004-11-15

A systems perspective on safety management is introduced followed by two briefly presented case studies of safety management in non-nuclear contexts. The first study concerns a car manufacturer and the second study a road traffic tunnel system. The risks of a car accident in the first case study are evident. The great exposure generates many incidents and accidents. In the second study, the rather low traffic intensity through the tunnel produces few incidents and accidents and only a few fatal accidents over the years. Yet, the risk of the individual traveler is much greater in the tunnel than on the average road. The case studies are presented in a systems perspective with emphasis on information feedback about the risks of the systems. The first case study illustrates high quality safety management, while the second case study shows many weaknesses of the safety management in the tunnel system. Some differences in safety management between the case studies are noted. The last part of the study presents an organizational perspective on safety management and offers alternative theoretical perspectives on the concept of safety management. The report shows that further studies are needed both (1) to develop a frame of reference for describing safety management across industries and activities and (2) to collect data illustrating of good and poor safety management. Then, the results can be used to strengthen and/or improving safety management in the nuclear power industry and its regulators

Safety Management. An Introduction to a Frame of Reference Exemplified with Case Studies from Non-Nuclear Contexts

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka

2004-11-01

A systems perspective on safety management is introduced followed by two briefly presented case studies of safety management in non-nuclear contexts. The first study concerns a car manufacturer and the second study a road traffic tunnel system. The risks of a car accident in the first case study are evident. The great exposure generates many incidents and accidents. In the second study, the rather low traffic intensity through the tunnel produces few incidents and accidents and only a few fatal accidents over the years. Yet, the risk of the individual traveler is much greater in the tunnel than on the average road. The case studies are presented in a systems perspective with emphasis on information feedback about the risks of the systems. The first case study illustrates high quality safety management, while the second case study shows many weaknesses of the safety management in the tunnel system. Some differences in safety management between the case studies are noted. The last part of the study presents an organizational perspective on safety management and offers alternative theoretical perspectives on the concept of safety management. The report shows that further studies are needed both (1) to develop a frame of reference for describing safety management across industries and activities and (2) to collect data illustrating of good and poor safety management. Then, the results can be used to strengthen and/or improving safety management in the nuclear power industry and its regulators

Survivorship Care Plan Information Needs: Perspectives of Safety-Net Breast Cancer Patients.

Science.gov (United States)

Burke, Nancy J; Napoles, Tessa M; Banks, Priscilla J; Orenstein, Fern S; Luce, Judith A; Joseph, Galen

2016-01-01

Despite the Institute of Medicine's (IOM) 2005 recommendation, few care organizations have instituted standard survivorship care plans (SCPs). Low health literacy and low English proficiency are important factors to consider in SCP development. Our study aimed to identify information needs and survivorship care plan preferences of low literacy, multi-lingual patients to support the transition from oncology to primary care and ongoing learning in survivorship. We conducted focus groups in five languages with African American, Latina, Russian, Filipina, White, and Chinese medically underserved breast cancer patients. Topics explored included the transition to primary care, access to information, knowledge of treatment history, and perspectives on SCPs. Analysis of focus group data identified three themes: 1) the need for information and education on the transition between "active treatment" and "survivorship"; 2) information needed (and often not obtained) from providers; and 3) perspectives on SCP content and delivery. Our data point to the need to develop a process as well as written information for medically underserved breast cancer patients. An SCP document will not replace direct communication with providers about treatment, symptom management and transition, a communication that is missing in participating safety-net patients' experiences of cancer care. Women turned to peer support and community-based organizations in the absence of information from providers. "Clear and effective" communication of survivorship care for safety-net patients requires dedicated staff trained to address wide-ranging information needs and uncertainties.

[Occupational health and safety management systems: scenarios and perspectives for occupational physicians].

Science.gov (United States)

Santantonio, P; Casciani, M; Bartolucci, G B

2008-01-01

This paper analyzes the role of the occupational physicians, taking into account the new Italian legislation within the frame of CSR, that puts in a new light the physicians inside the Organizations. In this context, Occupational Medicine and Workplace Health Promotion play a central role in most of the items of the Occupational Health and safety management systems, from H&S politics to training, from First Aid to audit and revision systems. From this innovative perspective, the authors try to identify the occupational physician's new challenges and opportunities.

Development Perspective of Regulatory Audit Code System for SFR Nuclear Safety Evaluation

Energy Technology Data Exchange (ETDEWEB)

Bae, Moo Hoon; Lee, Gil Soo; Shin, An Dong; Suh, Nam Duk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-05-15

A sodium-cooled fast reactor (SFR) in Korea is based on the KALIMER-600 concept developed by KAERI. Based on 'Long-term R and D Plan for Future Reactor Systems' which was approved by the Korea Atomic Energy Commission in 2008, the KAERI designer is scheduled to apply the design certification of the prototype SFR in 2017. In order to establish regulatory infrastructure for the licensing of a prototype SFR, KINS has develop the regulatory requirements for the demonstration SFR since 2010, and are scheduled to develop the regulatory audit code systems in regard to core, fuel, and system, etc. since 2012. In this study, the domestic code systems used for core design and safety evaluation of PWRs and the nuclear physics and code system for SFRs were briefly reviewed, and the development perspective of regulatory audit code system for SFR nuclear safety evaluation were derived

Hospital safety climate and safety behavior: A social exchange perspective.

Science.gov (United States)

Ancarani, Alessandro; Di Mauro, Carmela; Giammanco, Maria D

Safety climate is considered beneficial to the improvement of hospital safety outcomes. Nevertheless, the relations between two of its key constituents, namely those stemming from leader-subordinate relations and coworker support for safety, are still to be fully ascertained. This article uses the theoretical lens of Social Exchange Theory to study the joint impact of leader-member exchange in the safety sphere and coworker support for safety on safety-related behavior at the hospital ward level. Social exchange constructs are further related to the existence of a shame-/blame-free environment, seen as a potential antecedent of safety behavior. A cross-sectional study including 166 inpatients in hospital wards belonging to 10 public hospitals in Italy was undertaken to test the hypotheses developed. Hypothesized relations have been analyzed through a fully mediated multilevel structural equation model. This methodology allows studying behavior at the individual level, while keeping into account the heterogeneity among hospital specialties. Results suggest that the linkage between leader support for safety and individual safety behavior is mediated by coworker support on safety issues and by the creation of a shame-free environment. These findings call for the creation of a safety climate in which managerial efforts should be directed not only to the provision of new safety resources and the enforcement of safety rules but also to the encouragement of teamwork and freedom to report errors as ways to foster the capacity of the staff to communicate, share, and learn from each other.

Days on safety of industrial radiographic controls; Securite des controles radiographiques industriels

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This program is divided in three parts: the context and the regulations, the preparation and the implementation, the tools of prevention and the initiatives and the perspectives.In the first part devoted to the context and regulation are: the context by the Authority of nuclear safety (A.S.N.), the regulation referential, the transport of gamma-graphs; in the second part are the distribution of liabilities, materials and associated requirements, the feedback of incidents and exploitation of it, training and base requirements, works of S.F.R.P./C.O.F.R.E.N.D. and the A.S.N. position; the third part includes help to evaluation of risks at working places of industry radiologists, dosimetry study of a working place, guide to evaluate oneself; the fourth part devoted to the initiatives and the perspectives are: regional experiences charters of good practices in industry radiography, integration of works and deployment by the members of the C.O.F.R.E.N.D., perspectives in matter of prevention of occupational risks in the area of industry radiography. (N.C.)

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

2004-11-01

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

Middle East food safety perspectives.

Science.gov (United States)

Idriss, Atef W; El-Habbab, Mohammad S

2014-08-01

Food safety and quality assurance are increasingly a major issue with the globalisation of agricultural trade, on the one hand, and intensification of agriculture, on the other. Consumer protection has become a priority in policy-making amongst the large economies of the Middle East and North Africa (MENA) countries following a number of food safety incidents. To enhance food safety, it is necessary to establish markets underpinned by knowledge and resources, including analysis of international rejections of food products from MENA countries, international laboratory accreditation, improved reporting systems and traceability, continued development and validation of analytical methods, and more work on correlating sensory evaluation with analytical results. MENA countries should develop a national strategy for food safety based on a holistic approach that extends from farm-to-fork and involves all the relevant stakeholders. Accordingly, food safety should be a regional programme, raising awareness among policy- and decision-makers of the importance of food safety and quality for consumer protection, food trade and economic development. © 2014 Society of Chemical Industry.

A worker perspective on nuclear safety

International Nuclear Information System (INIS)

Pigeau, T.

2000-01-01

The majority of the 15,000 members of the Power Workers Union (PWU) are employed in electricity production at Ontario Power Generation's nuclear generating stations and in nuclear technology research at the Chalk River Laboratories of Atomic Energy of Canada Limited. Our members therefore have an obvious vested interest in any discussion related to their jobs. Workers in nuclear power plants have a clearly defined responsibility to ensure a safe working environment for themselves and their fellow workers. They have an overwhelming vested interest in ensuring that the plants are constructed, maintained, and operated safely. As will be detailed in the presentation to the CNS, all workers are required to learn and demonstrate knowledge of the hazards as an integral part of employment initiation and subsequent training. As their union, the PWU has a responsibility to ensure conditions of employment that not only permit workers to refuse work they perceive to be unsafe but require them to bring safety concerns forward for resolution to the satisfaction of both management and workers' representatives. The PWU has accomplished this through the development of workplace structures to ensure worker input is sought and acted on. The paper will describe the next steps required to improve workplace safety at Ontario Power Generation, which could be adapted to other facilities and workgroups. (author)

Nuclear energy and public safety (Part I): a bibliography of popular literature

International Nuclear Information System (INIS)

Gabriel, M.R.

1982-01-01

The focus of Part 1 is to aid the general research (especially undergraduate students and the general public) to locate information on the safety aspects of nuclear energy. A subject index after the bibliography breaks down the entries into 11 subtopics. An author index is also provided. This part of the bibliography consists of books, periodical articles, and government publications dating from 1959 to 1980

76 FR 40648 - Safety Enhancements Part 139, Certification of Airports; Reopening of Comment Period

Science.gov (United States)

2011-07-11

... that was published on February 1, 2011. In that document, the FAA proposed several safety enhancements...-0247; Notice No. 11-01] RIN 2120-AJ70 Safety Enhancements Part 139, Certification of Airports... comment period for the NPRM published on February 1, 2011 (76 FR 5510) and reopened (76 FR 20570) April 13...

Utilization management in radiology, part 2: perspectives and future directions.

Science.gov (United States)

Duszak, Richard; Berlin, Jonathan W

2012-10-01

Increased utilization of medical imaging in the early part of the last decade has resulted in numerous efforts to reduce associated spending. Recent initiatives have focused on managing utilization with radiology benefits managers and real-time order entry decision support systems. Although these approaches might seem mutually exclusive and their application to radiology appears unique, the historical convergence and broad acceptance of both programs within the pharmacy sector may offer parallels for their potential future in medical imaging. In this second installment of a two-part series, anticipated trends in radiology utilization management are reviewed. Perspectives on current and future potential roles of radiologists in such initiatives are discussed, particularly in light of emerging physician payment models. Copyright © 2012 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Long-term storage of radioactive waste: IAEA perspectives on safety and sustainability

International Nuclear Information System (INIS)

Rowat, J.H.; Louvat, D.; Metcalf, P.E.

2006-01-01

As the amounts of radioactive waste in surface storage have increased, concern has grown over the safety and sustainability of storage in the long term. In response to increasing concerns, the International Atomic Energy Agency (IAEA) has included an action to address the safety implications of the long-term storage (LTS) of radioactive waste in its action plan for waste safety; the action plan was endorsed by the IAEA's Member States in 2001. In 2003, the IAEA published a position paper on the safety and sustainability of LTS as part fulfilment of the action in question. A key theme of the position paper is the contrast of safety and sustainability implications of LTS with those of disposal. The present paper provides a summary of the position paper, describes current IAEA activities that deal with the subject of LTS, and discusses findings from the 2004 Cordoba symposium on disposal of low activity radioactive waste that pertain to LTS. (author)

Thematic Analysis of Women's Perspectives on the Meaning of Safety During Hospital-Based Birth.

Science.gov (United States)

Lyndon, Audrey; Malana, Jennifer; Hedli, Laura C; Sherman, Jules; Lee, Henry C

2018-05-01

To explore women's birth experiences to develop an understanding of their perspectives on patient safety during hospital-based birth. Qualitative description using thematic analysis of interview data. Seventeen women ages 29 to 47 years. Women participated in individual or small group interviews about their birth experiences, the physical environment, interactions with clinicians, and what safety meant to them in the context of birth. An interdisciplinary group of five investigators from nursing, medicine, product design, and journalism analyzed transcripts thematically to examine how women experienced feeling safe or unsafe and identify opportunities for improvements in care. Participants experienced feelings of safety on a continuum. These feelings were affected by confidence in providers, the environment and organizational factors, interpersonal interactions, and actions people took during risk moments of rapid or confusing change. Well-organized teams and sensitive interpersonal interactions that demonstrated human connection supported feelings of safety, whereas some routine aspects of care threatened feelings of safety. Physical and emotional safety are inextricably embedded in the patient experience, yet this connection may be overlooked in some inpatient birth settings. Clinicians should be mindful of how the birth environment and their behaviors in it can affect a woman's feelings of safety during birth. Human connection is especially important during risk moments, which represent a liminal space at the intersection of physical and emotional safety. At least one team member should focus on the provision of emotional support during rapidly changing situations to mitigate the potential for negative experiences that can result in emotional harm. Copyright © 2018 AWHONN, the Association of Women's Health, Obstetric and Neonatal Nurses. Published by Elsevier Inc. All rights reserved.

Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-01

This guidance has been developed for use in the IAEA Safety Culture Services, which provides support to Member States in their efforts to develop a sound safety culture of their organizations. It will be of particular use in seminars and training workshops that are part of these services. Much of the information in this publication reflects the approach the IAEA has adopted to assist nuclear organizations in Member States in improving their safety culture. This guidance covers topics such as: what is culture, and in particular what is safety culture; what are the stages of development of safety culture, and how you can assess its development using employee surveys; what practices can be used to develop safety culture, and what indicators will help monitor progress. The symptoms of a weakening safety culture are described, as well as the lessons learned from organizations who have experienced safety culture problems. This guide also contains information on how to undertake the process of transforming the existing safety culture, and develop a learning culture in an organization that is based on continuous improvement. The relationship between quality and safety is discussed. The safety culture services offered by the IAEA are also described. The IAEA perspective of safety culture has expanded with time as its understanding of the complexities of the concept developed. The concept of safety culture was first introduced by the International Nuclear Safety Advisory Group formed by the IAEA. In their report (INSAG-4, 1991) they maintained that the establishment of a safety culture within an organization is one of the fundamental management principles necessary for the safe operation of a nuclear facility. The definition recognized that safety culture is both structural and attitudinal in nature and relates to the organization and its style, as well as to attitudes, approaches and the commitment of individuals at all levels in the organization. In the framework of the

Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

International Nuclear Information System (INIS)

2002-12-01

This guidance has been developed for use in the IAEA Safety Culture Services, which provides support to Member States in their efforts to develop a sound safety culture of their organizations. It will be of particular use in seminars and training workshops that are part of these services. Much of the information in this publication reflects the approach the IAEA has adopted to assist nuclear organizations in Member States in improving their safety culture. This guidance covers topics such as: what is culture, and in particular what is safety culture; what are the stages of development of safety culture, and how you can assess its development using employee surveys; what practices can be used to develop safety culture, and what indicators will help monitor progress. The symptoms of a weakening safety culture are described, as well as the lessons learned from organizations who have experienced safety culture problems. This guide also contains information on how to undertake the process of transforming the existing safety culture, and develop a learning culture in an organization that is based on continuous improvement. The relationship between quality and safety is discussed. The safety culture services offered by the IAEA are also described. The IAEA perspective of safety culture has expanded with time as its understanding of the complexities of the concept developed. The concept of safety culture was first introduced by the International Nuclear Safety Advisory Group formed by the IAEA. In their report (INSAG-4, 1991) they maintained that the establishment of a safety culture within an organization is one of the fundamental management principles necessary for the safe operation of a nuclear facility. The definition recognized that safety culture is both structural and attitudinal in nature and relates to the organization and its style, as well as to attitudes, approaches and the commitment of individuals at all levels in the organization. In the framework of the

Reactor safety research - results and perspectives

International Nuclear Information System (INIS)

Banaschik, M.

1989-01-01

The work performed so far is an essential contribution to the determination of the safety margins of nuclear facilities and their systems and to the further development of safety engineering. The further development of safety engineering involves a shift of emphasis in reactor safety research towards event sequences beyond the design basis. The aim of this shift in emphasis is the further development of the preventive level. This is based on the fact that the conservative design of the operating and safety systems involves and essential safety potential. The R and D work is intended to help develop accident management measures and to take the plant back into the safe state even after severe accidents. In this context, it is necessary to make full use of the safety margins of the plant and to include the operating systems for coping with accidents. As a result of the aims, the research work approaches operating and plant-specific processes. (orig./DG) [de

Safety from the operator's perspective: We are all in this together

International Nuclear Information System (INIS)

Ellis, J.

2005-01-01

Following the Three Mile Island accident, the U.S. nuclear industry recognized that all nuclear utilities are affected by the performance of any one utility - that they are hostages of each other. This led to the formation of INPO, a unique model of self-regulation through peer review. As part of the industry's pursuit of excellence, INPO promotes a strong safety culture at each member utility. Nuclear stations need a strong safety culture because of the unique nature of the technology - the presence of radioactive byproducts and decay heat, and the concentration of energy in the reactor core. INPO's evaluation program is an intentionally intrusive process that provides comprehensive insight about a nuclear station's safety culture. The foundation for the program is the 'Performance Objectives and Criteria', which contains standards for plant and corporate performance. It is a behavior-based 'safety checklist' that INPO evaluators use in the field as they observe people at work in the plant, in the control room, during training, and in meetings. Open, candid discussions about safety culture are held with the plant staff, senior utility management, and within INPO. The 2002 discovery of degradation of the Davis-Besse Nuclear Power Station reactor vessel head highlighted problems that result when the safety environment at a plant receives insufficient attention. It also served as a stark reminder that safety culture is perishable and must constantly be rebuilt. As a result, INPO has improved its ability to detect declining plant performance, which will help the industry prevent safety significant events in the future. Promoting and evaluating safety culture has always been fundamental to INPO's work. While it has been called different things over the years (operational excellence, professionalism, conservative decision-making, or reactivity management), ensuring that nuclear safety has the overriding priority is woven into the fabric of all INPO activities. (author)

OECD/NEA WGFCS Workshop: Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives

International Nuclear Information System (INIS)

2013-01-01

Nuclear fuel is produced, processed, and stored mainly in industrial-scale facilities. Uranium ores are processed and refined to produce a pure uranium salt stream, Uranium is converted and enriched, nuclear fuel is fabricated (U fuel and U/Pu fuel for the closed cycle option); and spent fuel is stored and reprocessed in some countries (close cycle option). Facilities dedicated to the research and development of new fuel or new processes are also considered as Fuel Cycle Facilities. The safety assessment of nuclear facilities has often been led by the methodology and techniques initially developed for Nuclear Power Plants. As FCFs cover a wide diversity of installations the various approaches of national regulators, and their technical support organizations, for the Safety Assessment of Fuel Cycle Facilities are also diverse, as are the approaches by their industries in providing safety justifications for their facilities. The objective of the Working Group on Fuel Cycle Safety is to advance the understanding for both regulators and operators of relevant aspects of nuclear fuel cycle safety in member countries. A large amount of experience is available in safety assessment of FCFs, which should be shared to develop ideas in this field. To contribute to this task, the Workshop on 'Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives' was held in Toronto, on 27 - 29 September 2011. The workshop was hosted by Canadian Nuclear Safety Commission. The current proceedings provide summary of the results of the workshop with the text of the papers given and presentations made

Individual plant examination program: Perspectives on reactor safety and plant performance. Part 6, appendices A, B, and C

International Nuclear Information System (INIS)

1997-12-01

This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events (including internal flooding, but excluding internal fire). The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, reviewed the WE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. In particular, these results are assessed in relation to the design and operational characteristics of the various reactor and containment types, and by comparing the IPEs to probabilistic risk assessment characteristics. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants

Pacific Northwest Laboratory: Annual report for 1986 to the Assistant Secretary for Environment, Safety and Health: Part 5, Nuclear and operational safety

International Nuclear Information System (INIS)

Faust, L.G.; Kennedy, W.E.; Steelman, B.L.; Selby, J.M.

1987-02-01

Part 5 of the 1986 Annual Report to the Department of Energy's Assistant Secretary for Environment, Safety and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety, the Office of Operational Safety, and for the Office of Environmental Analysis. For each project, as identified by the Field Task Proposal/Agreement, articles describe progress made during fiscal year 1986. Authors of these articles represent a broad spectrum of capabilities derived from three of the seven research departments of the Laboratory, reflecting the interdisciplinary nature of the work

Strengthening the safety and security of radioactive sources worldwide: a perspective on Philippine contributions

International Nuclear Information System (INIS)

Murray, Allan

2009-01-01

Radioactive sources have been used for many decades in a wide variety of applications in all countries. The safety of radioactive sources and the associated radiation protection have been implemented by national and international programs during this time with cooperation through the IAEA intended to achieve application of minimum standards and harmonization of approach. The security of radioactive sources is however relatively new consideration. A perspective on the Philippine contributions to the safety and security of radioactive sources will be provided with reference to the following: What is radioactive source security and why it is important?; International cooperation, including the IAEA Code of Conduct; Regulation for radioactive source security; Implementation of radioactive source security measures for licenses, operators and others; Impact of regulatory and operational matters such as professional development and training, emergency preparedness and response, and radiation protection. (author)

Safety margins and retrofit. The technical calculation perspective; Sicherheitsmargen durch Nachruestung aus Sicht der technischen Berechnung

Energy Technology Data Exchange (ETDEWEB)

Daichendt, Matthias [Kraftanlagen Heidelberg GmbH, Heidelberg (Germany). Systemtechnik - Technische Berechnungen

2016-01-15

Safety margins are an essential factor of the safety philosophy for nuclear power plants. They support to cover future requirements even today. The basic safety concept is one key topic as also aspects of process engineering, the dimensioning and mechanical analysis of systems and ageing management. Calculations with today's capabilities are an integral part of the determination of safety margins. They can be used to analyse and to assess retrofit measures.

Alternative perspectives of safety in home delivered health care: a sequential exploratory mixed method study.

Science.gov (United States)

Jones, Sarahjane

2016-10-01

The aim of this study was to discover and describe how patients, carers and case management nurses define safety and compare it to the traditional risk reduction and harm avoidance definition of safety. Care services are increasingly being delivered in the home for patients with complex long-term conditions. However, the concept of safety remains largely unexplored. A sequential, exploratory mixed method design. A qualitative case study of the UK National Health Service case management programme in the English UK National Health Service was deployed during 2012. Thirteen interviews were conducted with patients (n = 9) and carers (n = 6) and three focus groups with nurses (n = 17) from three community care providers. The qualitative element explored the definition of safety. Data were subjected to framework analysis and themes were identified by participant group. Sequentially, a cross-sectional survey was conducted during 2013 in a fourth community care provider (patient n = 35, carer n = 19, nurse n = 26) as a form of triangulation. Patients and carers describe safety differently to case management nurses, choosing to focus on meeting needs. They use more positive language and recognize the role they have in safety in home-delivered health care. In comparison, case management nurses described safety similarly to the definitions found in the literature. However, when offered the patient and carer definition of safety, they preferentially selected this definition to their own or the literature definition. Patients and carers offer an alternative perspective on patient safety in home-delivered health care that identifies their role in ensuring safety and is more closely aligned with the empowerment philosophy of case management. © 2016 John Wiley & Sons Ltd.

Probabilistic methods applied to the safety of nuclear power plant: annual report - 1980. Part. 1: theoretical fundaments

International Nuclear Information System (INIS)

Oliveira, L.F.S. de; Hesles, J.B.S.; Milidiu, R.L.; Maciel, C.C.; Gibelli, S.M.O.; Oliveira, L.C.; Fleming, P.V.; Rivera, R.R.J.

1981-02-01

The probabilistic Safety Analysis Group from COPPE was founded in 1980. This first part of the report shows the theoretical fundaments used for reliability analysis of some safety systems for Angra-1 [pt

Thermal hydraulic codes for LWR safety analysis - present status and future perspective

Energy Technology Data Exchange (ETDEWEB)

Staedtke, H. [Commission of the European Union, Ispra (Italy)

1997-07-01

The aim of the present paper is to give a review on the current status and future perspective of present best-estimate Thermal Hydraulic codes. Reference is made to internationally well-established codes which have reached a certain state of maturity. The first part of the paper deals with the common basic code features with respect to the physical modelling and their numerical methods used to describe complex two-phase flow and heat transfer processes. The general predictive capabilities are summarized identifying some remaining code deficiencies and their underlying limitations. The second part discusses various areas including physical modelling, numerical techniques and informatic structure where the codes could be substantially improved.

Thermal hydraulic codes for LWR safety analysis - present status and future perspective

International Nuclear Information System (INIS)

Staedtke, H.

1997-01-01

The aim of the present paper is to give a review on the current status and future perspective of present best-estimate Thermal Hydraulic codes. Reference is made to internationally well-established codes which have reached a certain state of maturity. The first part of the paper deals with the common basic code features with respect to the physical modelling and their numerical methods used to describe complex two-phase flow and heat transfer processes. The general predictive capabilities are summarized identifying some remaining code deficiencies and their underlying limitations. The second part discusses various areas including physical modelling, numerical techniques and informatic structure where the codes could be substantially improved

Safety climate and firefighting: Focus group results.

Science.gov (United States)

DeJoy, David M; Smith, Todd D; Dyal, Mari-Amanda

2017-09-01

Firefighting is a hazardous occupation and there have been numerous calls for fundamental changes in how fire service organizations approach safety and balance safety with other operational priorities. These calls, however, have yielded little systematic research. As part of a larger project to develop and test a model of safety climate for the fire service, focus groups were used to identify potentially important dimensions of safety climate pertinent to firefighting. Analyses revealed nine overarching themes. Competency/professionalism, physical/psychological readiness, and that positive traits sometimes produce negative consequences were themes at the individual level; cohesion and supervisor leadership/support at the workgroup level; and politics/bureaucracy, resources, leadership, and hiring/promotion at the organizational level. A multi-level perspective seems appropriate for examining safety climate in firefighting. Safety climate in firefighting appears to be multi-dimensional and some dimensions prominent in the general safety climate literature also seem relevant to firefighting. These results also suggest that the fire service may be undergoing transitions encompassing mission, personnel, and its fundamental approach to safety and risk. These results help point the way to the development of safety climate measures specific to firefighting and to interventions for improving safety performance. Copyright © 2017 National Safety Council and Elsevier Ltd. All rights reserved.

Identification of stakeholder perspectives on future flood management in the Rhine basin using Q methodology

Science.gov (United States)

Raadgever, G. T.; Mostert, E.; van de Giesen, N. C.

2008-08-01

This article identifies different stakeholder perspectives on future flood management in the downstream parts of the Rhine basin in Germany and The Netherlands. The perspectives were identified using Q methodology, which proved to be a good, but time-intensive, method for eliciting and analyzing stakeholder perspectives in a structured and unbiased way. Three shared perspectives were found: A) "Anticipation and institutions", B) "Space for flooding" and C) "Knowledge and engineering". These three perspectives share a central concern for the provision of safety against flooding, but disagree on the expected autonomous developments and the preferred measures. In perspective A, the expected climate change and economic growth call for fast action. To deal with the increasing flood risk, mostly institutional measures are proposed, such as the development of a stronger basin commission. In perspective B, an increasing spatial pressure on the river area is expected, and the proposed measures are focused on mitigating damage, e.g., through controlled flooding and compartmentalization. In perspective C, the role of expert knowledge and technological improvements is emphasized. Preferred strategies include strengthening the dikes and differentiation of safety standards. An overview of stakeholder perspectives can be useful in natural resources management for 1) setting the research agenda, 2) identifying differences in values and interests that need to be discussed, 3) creating awareness among a broad range of stakeholders, and 4) developing scenarios.

Nuclear utility self-assessment as viewed by the corporate nuclear safety committee

International Nuclear Information System (INIS)

Corcoran, W.R.

1992-01-01

This paper discusses how corporate nuclear safety committees use the principles of self-assessment to enhance nuclear power plant safety performance. Corporate nuclear safety committees function to advise the senior nuclear power executive on matters affecting nuclear safety. These committees are required by the administrative controls section of the plant technical specifications which are part of the final safety analysis report and the operating license. Committee membership includes senior utility executives, executives from sister utilities, utility senior technical experts, and outside consultants. Current corporate nuclear safety committees often have a finely tuned intuitive feel for self-assessment that they use to probe the underlying opportunities for quality and safety enhancements. The questions prompted by the self-assessment orientation enable the utility line organization members to gain better perspectives on the characteristics of the organizational systems that they manage and work in

Taking up national safety alerts to improve patient safety in hospitals: The perspective of healthcare quality and risk managers.

Science.gov (United States)

Pfeiffer, Yvonne; Schwappach, David

2016-01-01

National safety alert systems publish relevant information to improve patient safety in hospitals. However, the information has to be transformed into local action to have an effect on patient safety. We studied three research questions: How do Swiss healthcare quality and risk managers (qm/rm(1)) see their own role in learning from safety alerts issued by the Swiss national voluntary reporting and analysis system? What are their attitudes towards and evaluations of the alerts, and which types of improvement actions were fostered by the safety alerts? A survey was developed and applied to Swiss healthcare risk and quality managers, with a response rate of 39 % (n=116). Descriptive statistics are presented. The qm/rm disseminate and communicate with a broad variety of professional groups about the alerts. While most respondents felt that they should know the alerts and their contents, only a part of them felt responsible for driving organizational change based on the recommendations. However, most respondents used safety alerts to back up their own patient safety goals. The alerts were evaluated positively on various dimensions such as usefulness and were considered as standards of good practice by the majority of the respondents. A range of organizational responses was applied, with disseminating information being the most common. An active role is related to using safety alerts for backing up own patient safety goals. To support an active role of qm/rm in their hospital's learning from safety alerts, appropriate organizational structures should be developed. Furthermore, they could be given special information or training to act as an information hub on the issues discussed in the alerts. Copyright © 2016. Published by Elsevier GmbH.

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...

China's approach to nuclear safety — From the perspective of policy and institutional system

International Nuclear Information System (INIS)

Mu, Ruimin; Zuo, Jian; Yuan, Xueliang

2015-01-01

Nuclear energy plays an important role in the energy sector in the world. It has achieved a rapid development during the past six decades and contributes to over 11% of the world's electricity supply. On the other side, nuclear accidents have triggered substantial debates with a growing public concern on nuclear facilities. Followed by the Fukushima nuclear accident, some developed countries decided to shut down the existing nuclear power plants or to abandon plans to build new ones. Given this background, accelerating the development of nuclear power on the basis of safety in China will make it a bellwether for other countries. China assigns the top priority to the nuclear safety in nuclear energy development and has maintained a good record in this field. The policy and institutional system provide the necessary guarantee for the nuclear energy development and safety management. Furthermore, China's approach to nuclear safety provides a benchmark for the safe development and utilization of nuclear power. This research draws an overall picture of the nuclear energy development and nuclear safety in China from the policy and institutional perspective. - Highlights: • China's Approach to Nuclear Safety. • Policy and Institutional System for Nuclear Energy Development. • A Benchmark for the Peaceful and Safe Utilization of Nuclear Power. • Further Efforts for Specific Laws and Administrative System

Network management in motion. Part 1. Network management in perspective. Transition or paradox?

International Nuclear Information System (INIS)

Van Beuge, M.

2010-01-01

In a series of articles various legal aspects of network management are discussed from a European and a Dutch perspective. In this first part a general introduction is given on network management and related topics, such as developing local networks to international networks, the integration to unbundling the energy market in Europe, the development of centralized to decentralized, and from conventional to sustainable. [nl

Safety case: An international perspective

International Nuclear Information System (INIS)

Pescatore, C.; Voinis, S.

2002-01-01

In recent years, it has become more and more evident that repository development will involve a number of stages punctuated by interdependent decisions on whether and how to move to the next stage. These decisions require a clear and traceable presentation of technical arguments that will help in giving confidence in the feasibility and safety of the proposed concept. The depth of understanding and technical information available to support decisions will vary from step to step. A safety case is a key item to support the decision to move to the next stage in repository development. Progress is noted, in the past decade, in the performance and safety assessment areas, particularly in the methodologies for repository system analysis. Progress is also observed regarding the understanding of the natural system and its characterisation, treatment of uncertainties, and modelling. Some areas are under active development, e.g. the area of scenario development and analysis. Finally, to increase confidence, rigorous quality assurance procedures need to be implemented, as well as the factoring of the contribution of R and D in underground research laboratories. The paper summarises the lessons learnt within relevant NEA initiatives as they evolved over the course of a decade and now allow a comprehensive view of what constitutes a safety case. (author)

Most common road safety engineering deficiencies in South Eastern Europe as a part of safe system approach

Science.gov (United States)

Jovanov, D.; Vollpracht, H. J.; Beles, H.; Popa, V.; Tolea, B. A.

2017-10-01

Most common road safety engineering deficiencies identified by the authors in South Eastern Europe, including Romania, have been collected together and presented in this paper as a part of road safety unbreakably connected to the safe system approach (driver-vehicle-road). In different South Eastern Europe countries Road Safety Audit (RSA), Road Safety Inspection (RSI), as well as Black Spot Management (BSM) was introduced and practical implementation experience enabled the authors to analyze the road safety problems. Typical road safety engineering deficiencies have been presented in 8 different subsections, based on PIARC (World Road Association) RSA approach. This paper presents collected common road safety problems with relevant illustrations (real pictures) with associated accident risks.

Current and future perspectives on the development, evaluation and application of in silico approaches for predicting toxicity

Science.gov (United States)

Safety-related problems continue to be one of the major reasons of attrition in drug development. Non-testing approaches to predict toxicity could form part of the solution. This review provides a perspective of current status of non-testing approaches available for the predictio...

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.

Integrated prevention: new perspectives for public safety policies in Brazil

Directory of Open Access Journals (Sweden)

Rodrigo Ghiringhelli de Azevedo

2006-04-01

Full Text Available This article seeks to identify the elements that are establishing a new perspective in the handling contemporary social conflicts. It is based on the recognition of the limits of the reactive paradigm, characteristic of modernity in relation to criminal issues, which is based on the formal and dogmatic logic of government normativity. On one hand the crisis in this paradigm has led to the reappearance of a punitive approach, and proposals to increase punishments that are no longer seen as a retribution for a crime or a way to reinsert the individual into society. Punishments have often become mechanisms of pure and simple contention and suppression of rights in name of efficiency and combating crime. On the other hand, many experiences are appearing in public safety administration based on citizen participation, and on the engagement of civil society in policies for social inclusion and public control of police activity and of the penal system.

Internet safety education for youth: stakeholder perspectives.

Science.gov (United States)

Moreno, Megan A; Egan, Katie G; Bare, Kaitlyn; Young, Henry N; Cox, Elizabeth D

2013-06-05

Internet use is nearly ubiquitous among US youth; risks to internet use include cyberbullying, privacy violations and unwanted solicitation. Internet safety education may prevent these negative consequences; however, it is unclear at what age this education should begin and what group is responsible for teaching this topic. Surveys were distributed to key stakeholders in youth safety education including public school teachers, clinicians, parents and adolescents. Surveys assessed age at which internet safety education should begin, as well as experiences teaching and learning internet safety. Surveys of adults assessed willingness to teach internet safety. Finally, participants were asked to identify a group whose primary responsibility it should be to teach internet safety. A total of 356 participants completed the survey (93.4% response rate), including 77 teachers, 111 clinicians, 72 parents and 96 adolescents. Stakeholders felt the optimal mean age to begin teaching internet safety was 7.2 years (SD = 2.5), range 2-15. Internet safety was regularly taught by some teachers (20.8%), few clinicians (2.6%) and many parents (40.3%). The majority of teachers, clinicians and parents were willing to teach internet safety, but all groups surveyed identified parents as having primary responsibility for teaching this topic. Findings suggest agreement among key stakeholders for teaching internet safety at a young age, and for identifying parents as primary teachers of this topic. Clinicians have a unique opportunity to support parents by providing resources, guidance and support.

Software Safety Risk in Legacy Safety-Critical Computer Systems

Science.gov (United States)

Hill, Janice L.; Baggs, Rhoda

2007-01-01

Safety Standards contain technical and process-oriented safety requirements. Technical requirements are those such as "must work" and "must not work" functions in the system. Process-Oriented requirements are software engineering and safety management process requirements. Address the system perspective and some cover just software in the system > NASA-STD-8719.13B Software Safety Standard is the current standard of interest. NASA programs/projects will have their own set of safety requirements derived from the standard. Safety Cases: a) Documented demonstration that a system complies with the specified safety requirements. b) Evidence is gathered on the integrity of the system and put forward as an argued case. [Gardener (ed.)] c) Problems occur when trying to meet safety standards, and thus make retrospective safety cases, in legacy safety-critical computer systems.

Converting the GSR part3 into a national regulations for the protection and safety of radiation sources

International Nuclear Information System (INIS)

Hatim, Abdulrahman

2016-04-01

The achievement and maintenance of a high level of Radiation Protection and Safety of Radiation Sources depends on a sound legal and governmental infrastructure, including a regulatory body with well-defined responsibilities and functions. The project aimed at converting the IAEA GRS Part 3 into National regulations in Sudan for the protection against the harmful effects of ionizing radiation and safety of radiation sources. The regulations developed covered general requirements for radiation protection, verification of safety, planned exposure situations, emergency exposure situations and existing exposure situation. The Government of Sudan is expected to empower the Sudanese Nuclear Radiological Regulatory Authority (SNRAA) and other relevant authorities to undertake the conversion of IAEA GSR Part 3 into national regulations to be used to regulate all facilities and activities in Sudan. (au)

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

2004-11-15

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

Nuclear energy and public safety (Part II): a bibliography of technical resources

International Nuclear Information System (INIS)

Gabriel, M.R.

1982-01-01

Part 2 of the bibliography focuses on technical information of interest to those concerned with the operation of nuclear power plants and the subjects of safety and accidents. A subject index included after the bibliography provides a breakdown of the references into seven categories. There is also an author index. The material cited is available through the National Technical Information Service (NTIS) in Springfield, Virginia

Fast breeder reactor safety : a perspective

International Nuclear Information System (INIS)

Kale, R.D.

1992-01-01

Taking into consideration India's limited reserves of natural and vast reserves of thorium, the fast reactor route holds a great promise for India's energy supply in future. The fast reactor fueled with 239 Pu/ 238 U (unused or depleted) produces (breeds) more fissionable fuel material 239 Pu than it consumes. Calculations show that a fast breeder reactor (FBR) increases energy potential of natural uranium by about 60 times. As the fast reactor can also convert 232 Th into 233 U which is a fissionable material, it can make India's thorium reserves a source of almost inexhaustible energy supply for a long time to come. Significant advantage of FBR plants cooled by sodium and their world-wide operating experience are reviewed. There are two main safety issues of FBR, one nuclear and the other non-nuclear. The nuclear issue concerns core disruptive accident and the non-nuclear one concerns the high chemical energy potential of sodium. These two issues are analysed and it is pointed that they are manageable by current design, construction and operational practices. Main findings of safety research during the last six to eight years in West European Countries and United States of America (US) are summarised. Three stage engineered safety provision incorporated into the design of the sodium cooled Fast Breeder Test Reactor (FBTR) commissioned at Kalpakkam are explained. The important design safety features of FBTR such as primary system containment, emergency core cooling, plant protection system, inherent safety features achieved through reactivity coefficients, and natural convection cooling are discussed. Theoretical analysis and experimental research in fast reactor safety carried out at the Indira Gandhi Centre for Atomic Research during the past some years are reviewed. (M.G.B.)

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

A survey on management perspectives of the state of workplace health and safety practices in Kenya.

Science.gov (United States)

Mbakaya, C F; Onyoyo, H A; Lwaki, S A; Omondi, O J

1999-07-01

A baseline survey was conducted in 1995 on management perspectives of occupational health and safety (OHS) structures and practices in Kenya. This was achieved by interviewing management and supervisory staff attending 1 week multi-disciplinary courses that were organized by the Federation of Kenya Employers (FKE) and the International Labour Office (ILO) at hotel venues in Kenya. The purpose of the survey was to gain some insight into work safety conditions in Kenya and to assess the potential for a new OHS manual to meet existing knowledge gaps. The manual was locally developed in 1993/4 by Kenyan OHS experts in collaboration with colleagues from the Swedish National Institute for Working Life. Results of the survey from 65 participants indicated that most workplace managers were not familiar with the Kenyan work safety legislation. Work injuries were largely attributable to working with dangerous machinery. Occupational diseases and HIV/AIDS were cited as other causes of workplace morbidity and mortality. Although most respondents (70%) were satisfied with their work safety conditions, only 37% said their workplaces were annually audited by labour inspectors while 45% said injured workers were not treated well by management. Many workplaces (65%) violated the mandatory legal requirement on the establishment of health and safety committees. The OHS resource person and course content were rated highly by most respondents (96%). The foregoing results provided the basis of a needs analysis for future OHS programs in Kenya.

Educational status and organizational safety climate: does educational attainment influence workers' perceptions of workplace safety?

OpenAIRE

Gyekye, Seth; Salminen, Simo

2009-01-01

From a practical perspective, understanding the impact of education on perceptions of workplace safety would benefit management’s decisions regarding workers’ adaptability, general work effectiveness, accident frequency, implementation of safety management policies, and handling of education-related accident characteristics. The current study thus examined the relationship between educational attainment and (i) safety perception, (ii) job satisfaction, (iii) compliance with safety management ...

2015 annual report of the managing director of the CEA general and nuclear inspection for nuclear safety and radiation protection

International Nuclear Information System (INIS)

2016-08-01

After an introduction by the managing director of the CEA general and nuclear inspection about activities and events of 2015, this report proposes some key figures and indicators to illustrate these activities and events. The next parts discuss, present and comment how a culture of safety is at the heart of the continuous progress approach by the CEA. The next chapters propose overviews and comments of lessons learned from nuclear inspections within the frame of audit programme or within the frame of centres' safety audits, and from reactive inspections. The last parts address the follow-up of recommendations, and progress orientations and perspectives

Anthropology in Agricultural Health and Safety Research and Intervention.

Science.gov (United States)

Arcury, Thomas

2017-01-01

Agriculture remains a dangerous industry, even as agricultural science and technology continue to advance. Research that goes beyond technological changes to address safety culture and policy are needed to improve health and safety in agriculture. In this commentary, I consider the potential for anthropology to contribute to agricultural health and safety research by addressing three aims: (1) I briefly consider what the articles in this issue of the Journal of Agromedicine say about anthropologists in agricultural health and safety; (2) I discuss what anthropologists can add to agricultural health and safety research; and (3) I examine ways in which anthropologists can participate in agricultural health and safety research. In using their traditions of rigorous field research to understand how those working in agriculture perceive and interpret factors affecting occupational health and safety (their "emic" perspective), and translating this perspective to improve the understanding of occupational health professionals and policy makers (an "etic" perspective), anthropologists can expose myths that limit improvements in agricultural health and safety. Addressing significant questions, working with the most vulnerable agricultural communities, and being outside establishment agriculture provide anthropologists with the opportunity to improve health and safety policy and regulation in agriculture.

Prescribing Safety in Ambulatory Care: Physician Perspectives

National Research Council Canada - National Science Library

Rundall, Thomas G; Hsu, John; Lafata, Jennifer E; Fung, Vicki; Paez, Kathryn A; Simpkins, Jan; Simon, Steven R; Robinson, Scott B; Uratsu, Connie; Gunter, Margaret J; Soumerai, Stephen B; Selby, Joseph V

2005-01-01

.... We asked about current safety practices, perceptions of ambulatory prescribing safety. Using a content analysis approach, three investigators independently coded responses into thematic categories...

Safety of research reactors - A regulator's perspective

International Nuclear Information System (INIS)

Rahman, M.S.

2001-01-01

Due to historical reasons research reactors have received less regulatory attention in the world than nuclear power plants. This has given rise to several safety issues which, if not addressed immediately, may result in an undesirable situation. However, in Pakistan, research reactors and power reactors have received due attention from the regulatory authority. The Pakistan Research Reactor-1 has been under regulatory surveillance since 1965, the year of its commissioning. The second reactor has also undergone all the safety reviews and checks mandated by the licensing procedures. A brief description of the regulatory framework, the several safety reviews carried out have been briefly described in this paper. Significant activities of the regulatory authority have also been described in verifying the safety of research reactors in Pakistan along with the future activities. The views of the Pakistani regulatory authority on the specific issues identified by the IAEA have been presented along with specific recommendations to the IAEA. We are of the opinion that there are more Member States operating nuclear research reactors than nuclear power plants. Therefore, there should be more emphasis on the research reactor safety, which somehow has not been the case. In several recommendations made to the IAEA on the specific safety issues the emphasis has been, in general, to have a similar documentation and approach for maintaining and verifying operational safety at research reactors as is currently available for nuclear power reactors and may be planned for nuclear fuel cycle facilities. (author)

Should Nuclear Safety Care About Resilience Engineering?

International Nuclear Information System (INIS)

Paries, J.

2016-01-01

The current nuclear industry safety paradigm is based on the deterministic and/or probabilistic anticipation of all potential situations, and the predetermination of all the (safe) responses. Even the defense in depth concept, which is the core of the nuclear safety strategy and is intended to handle situations in which part of the control is lost, heavily relies on detailed anticipations. In other words, nuclear safety is mainly expected from the real world’s conformity to a designed-to-be-safe world, i.e., a well controlled world, where organizations, processes, hardware, teams, and individuals comply with their rationally predetermined behaviors. In this “command and control” perspective, risk is seen as mainly generated by deviations and variations from rules, procedures, norms, and expectations. However, real operations are complex, even in normal situations, which means that they include some unpredictable events and adaptation behaviors. The traditional “command and control” perspective fail to properly acknowledge the limits to predictability inherent to a complex adaptive system. It actually strives to reduce complexity through tighter compliance to specifications and to improve predictions capabilities through a tighter monitoring of “weak signals” and “precursors”. But in a complex world, precursors are usually obvious after the event, while not identifiable before. And the efforts made to reduce complexity may also simultaneously tighten couplings between system’s components— hence increase complexity — and reduce the diversity and flexibility needed to respond to it.

Acute nursing care of the older adult with fragility hip fracture: An international perspective (Part 2)

LENUS (Irish Health Repository)

Maher, Ann Butler

2012-10-23

The second part of this paper provides those who care for orthopaedic patients with evidence-supported international perspectives about acute nursing care of the older adult with fragility hip fracture. Developed by an international group of nurse experts and guided by a range of information from research and clinical practice, it focuses on nurse sensitive quality indicators during the acute hospitalisation for fragility hip fracture. Optimal care for the patient who has experienced such a fracture is the focus. This includes (in the first, earlier, part):\\r\

Pharmaceutical company perspectives on current safety risk communications in Japan.

Science.gov (United States)

Urushihara, Hisashi; Kobashi, Gen; Masuda, Hideaki; Taneichi, Setsuko; Yamamoto, Michiko; Nakayama, Takeo; Kawakami, Koji; Matsuda, Tsutomu; Ohta, Kaori; Sugimori, Hiroki

2014-01-01

In 1987, a group infection of hepatitis in patients receiving a contaminated fibrinogen product was first reported to the Japanese regulatory agency. Eventually, this serious drug incident involved more than 10,000 cases of infection. In response, the Government of Japan established a responding inspection committee in 2008 to make recommendations for the restructuring of drug regulatory administration. The final report was issued in 2010. One agenda item of this restructuring was the improvement of drug-related safety risk communications. Our research group on drug safety risk communications, which is funded by the Government of Japan, surveyed pharmaceutical companies regarding their perspective on current risk communications. The survey was conducted using an anonymous questionnaire developed for this study which included the three operational domains of targets, contents, and measures of drug risk communication. Fifty-two of the 74 member companies of the Post-marketing Surveillance Subcommittee of the Japan Pharmaceutical Manufacturer's Association participated, and this response rate of more than 70% was considered sufficient to ensure the external validity of the survey results. Results showed that the most highly prioritized aspect of risk messaging was the strength of evidence, and that outcome evaluation of risk communication gained recognition. Further, while physicians and pharmacists were the most prioritized communication targets, pharmacovigilance departments devoted the most resources to regulators, at more than 30%. The Internet was recognized as a useful public source of risk information, whereas Drug Guides for Patients delivered on the web were considered under-recognized. Further discussion of these results with the aim of enhancing the restructuring of the Japanese drug regulatory administration system are warranted.

Information report on nuclear safety and radiation protection of MELOX - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2012 and perspectives for 2013. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2012 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2013. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of MELOX - Issue 2013

International Nuclear Information System (INIS)

2014-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2013 and perspectives for 2014. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2013 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2014. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of MELOX - Issue 2014

International Nuclear Information System (INIS)

2015-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the MELOX plant which produces MOX fuel: location and environment, history of basic nuclear installation or INB 151, presentation of the nuclear operator and of the industrial operator, assets of MOX fuel, MOX customers, regulatory framework of the MELOX plant, policy for sustainable development and continuous progress. It addresses the various measures regarding nuclear safety and radiation protection: general overview of nuclear safety in France, presentation of the Areva's nuclear safety Charter, measures adopted in MELOX, review for 2014 and perspectives for 2015. The next part addresses nuclear events: presentation of the INES scale and of the event declaration procedure, review of events declared in 2014 and regarding MELOX. The report gives an overview of activities and measures regarding protection and control of the environment: environmental management, consumption of natural resources, control of effluent releases, measurement of the impact on the environment, waste management, and perspectives for 2015. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)

International Nuclear Information System (INIS)

VINCENT, Andrew

2005-01-01

In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the

Nuclear power plant safety, their a social acceptance and the part played by the Administration in Spain

International Nuclear Information System (INIS)

Alonso Santos, A.

1980-01-01

The safety of nuclear power plants is introduced as the complement of risk, which is futhermore explained as the proximity of damage, therefore as frequency of accidents times damage. The reduced risk and, as a consequence, the high standards of safety of nuclear power plants are explained with reference to the American Reactor Safety Study and the German Risikostudie; the situation in less industrial countries is also analyzed. The social rejection of nuclear energy is studied with reference to the concept of risk and explanations are given of the present situation. Within this context, and making reference to Spain, the part played by the Administration is safeguarding the health and safety of the public is discussed. Specific reference is made to the newly published law regulating Nuclear Safety. (author)

Support for learning in the perspective of patient safety in primary health care

Directory of Open Access Journals (Sweden)

Thatianny Tanferri de Brito Paranaguá

Full Text Available ABSTRACT Objective: to analyze the support for learning, in the perspective of patient safety, offered in the work environment, according to health professionals working in primary care. Method: a transversal study, held with 86 health professionals working in primary care. A validated instrument was used, applied via the Internet. Descriptive statistical analysis was undertaken with a presentation of median, mean, standard deviation and coefficient of variation. Results: points which are favorable to supporting learning were evidenced, such as mutual respect, autonomy for organizing the work and valorization of new ideas, which obtained means above 7.0. The variables which hinder the process of learning in the work environment, perceived by the professionals, were: resistance to changes, and excess of work impeding reflection on how to improve the work, with means above 6.0. Conclusion: the study found evidence of indicators related to the process of staff development in the area of health and indicates the influence of support for learning for the improvement of the work processes and of patient safety. It is necessary that a culture involving the systematic assessment of educational interventions in health should be established, the aim being to diagnose actions which are more incisive for changing health professionals' attitude and, therefore, clinical practice.

Using historical crash data as part of traffic work zone safety planning and project management strategies.

Science.gov (United States)

2014-07-01

This funding enabled the project entitled, USING HISTORICAL CRASH DATA AS PART OF TRAFFIC WORK ZONE SAFETY : PLANNING AND PROJECT MANAGEMENT STRATEGIES to address the following: : Evaluate current organizational strategies with respect to w...

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-09-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

Food Safety: an Integral Part of Food Security

International Nuclear Information System (INIS)

Kilian, Lizette

2012-01-01

In recent years, many countries have developed integrated and harmonized food safety and quality control guidelines in accordance with national legislation and international standards to protect the health of consumers. But food safety standards alone are not enough. Radiation technology can complement and supplement existing technologies to ensure food security, safety and quality.

The culture of patient safety from the perspective of the pediatric emergency nursing team.

Science.gov (United States)

Macedo, Taise Rocha; Rocha, Patricia Kuerten; Tomazoni, Andreia; Souza, Sabrina de; Anders, Jane Cristina; Davis, Karri

2016-01-01

To identify the patient safety culture in pediatric emergencies from the perspective of the nursing team. A quantitative, cross-sectional survey research study with a sample composed of 75 professionals of the nursing team. Data was collected between September and November 2014 in three Pediatric Emergency units by applying the Hospital Survey on Patient Safety Culture instrument. Data were submitted to descriptive analysis. Strong areas for patient safety were not found, with areas identified having potential being: Expectations and actions from supervisors/management to promote patient safety and teamwork. Areas identified as critical were: Non-punitive response to error and support from hospital management for patient safety. The study found a gap between the safety culture and pediatric emergencies, but it found possibilities of transformation that will contribute to the safety of pediatric patients. Nursing professionals need to become protagonists in the process of replacing the current paradigm for a culture focused on safety. The replication of this study in other institutions is suggested in order to improve the current health care scenario. Identificar a cultura de segurança do paciente em emergências pediátricas, na perspectiva da equipe de enfermagem. Pesquisa quantitativa, tipo survey transversal. Amostra composta por 75 profissionais da equipe de enfermagem. Dados coletados entre setembro e novembro de 2014, em três Emergências Pediátricas, aplicando o instrumento Hospital Survey on Patient Safety Culture. Dados submetidos à análise descritiva. Não foram encontradas áreas de força para a segurança do paciente, sendo identificadas áreas com potencial de assim se tornarem: Expectativas e ações do supervisor/chefia para promoção da segurança do paciente e Trabalho em equipe. Como área crítica identificaram-se: Resposta não punitiva ao erro e Apoio da gestão hospitalar para segurança do paciente. O estudo apontou distanciamento

Patients' and families' perspectives of patient safety at the end of life: a video-reflexive ethnography study.

Science.gov (United States)

Collier, Aileen; Sorensen, Ros; Iedema, Rick

2016-02-01

The aim of this study was to investigate patients' and families' perspectives of safety and quality in the setting of a life-limiting illness. Data reported here were generated from a qualitative study using video-reflexive ethnographic methodology. Data were collected over 18 months and generated through participant observation, shadowing of clinicians, field-interviews and semi-structured interviews with patients and families. The study was conducted at two hospital sites in Sydney, Australia and in patients' homes. Patients with an advanced life-limiting illness (n = 29) ranging in age between 27 and 89 years and family members (n = 5) participated in the study. Patient safety remains important to dying patients and families. For dying people, iatrogenic harm is not regarded as 'one off' incidents. Rather, harm is experienced as a result of an unfolding series of negative events. Critically, iatrogenic harm is emotional, social and spiritual and not solely technical-clinical misadventure and is inextricably linked with feeling unsafe. Thus, patient safety extends beyond narrowly defined technical-clinical parameters to include interpersonal safety. Current approaches to patient safety do not address fully the needs of dying patients and their families. Patients and their families regard poor communication with and by health professionals to be harmful in and of itself. © The Author 2015. Published by Oxford University Press in association with the International Society for Quality in Health Care; all rights reserved.

Nurses' perceptions of patient safety culture in Jordanian hospitals.

Science.gov (United States)

Khater, W A; Akhu-Zaheya, L M; Al-Mahasneh, S I; Khater, R

2015-03-01

Patients' safety culture is a key aspect in determining healthcare organizations' ability to address and reduce risks of patients. Nurses play a major role in patients' safety because they are accountable for direct and continuous patient care. There is little known information about patients' safety culture in Jordanian hospitals, particularly from the perspective of healthcare providers. The study aimed to assess patient safety culture in Jordanian hospitals from nurses' perspective. A cross-sectional, descriptive design was utilized. A total number of 658 nurses participated in the current study. Data were collected using an Arabic version of the hospital survey of patients' safety culture. Teamwork within unit dimensions had a high positive response, and was perceived by nurses to be the only strong suit in Jordanian hospitals. Areas that required improvement, as perceived by nurses, are as follows: communication openness, staffing, handoff and transition, non-punitive responses to errors, and teamwork across units. Regression analysis revealed factors, from nurses' perspectives, that influenced patients' safety culture in Jordanian hospital. Factors included age, total years of experience, working in university hospitals, utilizing evidence-based practice and working in hospitals that consider patient safety to be a priority. Participants in this study were limited to nurses. Therefore, there is a need to assess patient safety culture from other healthcare providers' perspectives. Moreover, the use of a self-reported questionnaire introduced the social desirability biases. The current study provides insight into how nurses perceive patient safety culture. Results of this study have revealed that there is a need to replace the traditional culture of shame/blame with a non-punitive culture. Study results implied that improving patient safety culture requires a fundamental transformation of nurses' work environment. New policies to improve collaboration between

Pacific Northwest Laboratory annual report for 1989 to the Assistant Secretary for Environment, Safety, and Health - Part 5: Environment, Safety, Health, and Quality Assurance

Energy Technology Data Exchange (ETDEWEB)

Faust, L.G.; Doctor, P.G.; Selby, J.M.

1990-04-01

Part 5 of the 1989 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1989. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work. 35 refs., 1 fig.

NB Power's public safety perspective

Energy Technology Data Exchange (ETDEWEB)

Sisk, P [New Brunswick Power, Fredericton, NB (Canada)

2009-07-01

New Brunswick Power Generation (NB Power) - Genco operates and maintains one of North America's most diverse generating systems. It consists of 15 hydro, coal, oil and diesel-powered generating stations and supplies approximately 75 per cent of the in-province load. It also exports energy to neighbouring New England, Quebec, Prince Edward Island, and Nova Scotia. This presentation provided some history regarding public safety issues at NB Power. The Mactaquac generating system was discussed with particular reference to its activities, challenges and control measures such as signage, audible alarms, visuals, security fencing, and coast guard navigation buoys. Several recommendations were presented, such as developing a tool to conduct risk assessment at all hydro stations; developing a public safety campaign; installing booms where required; standardizing signs; evaluating security risks; and conducting pre-spill inspections to remove the public from dangerous areas. figs.

Soft systems methodology as a systemic approach to nuclear safety management

International Nuclear Information System (INIS)

Vieira Neto, Antonio S.; Guilhen, Sabine N.; Rubin, Gerson A.; Caldeira Filho, Jose S.; Camargo, Iara M.C.

2017-01-01

Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, does not properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring socio technical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors. (author)

Soft systems methodology as a systemic approach to nuclear safety management

Energy Technology Data Exchange (ETDEWEB)

Vieira Neto, Antonio S.; Guilhen, Sabine N.; Rubin, Gerson A.; Caldeira Filho, Jose S.; Camargo, Iara M.C., E-mail: asvneto@ipen.br, E-mail: snguilhen@ipen.br, E-mail: garubin@ipen.br, E-mail: jscaldeira@ipen.br, E-mail: icamargo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNE-SP), Sao Paulo, SP (Brazil)

2017-07-01

Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, does not properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring socio technical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors. (author)

Perspective channel-type reactor with enhanced safety

International Nuclear Information System (INIS)

Adamov, E.O.; Grozdov, I.I.; Kuznetsov, S.P.; Petrov, A.A.; Rozhdestvensky, M.I.; Cherkashov, Yu.M.

1994-01-01

Following the search for new design solutions to develop within the framework of channel trends the reactor with enhanced safety the Research and Development Institute of Power Engineering has developed the design of the multiloop boiling water reactor (MKER). The MKER enhanced safety is attained when involving the inherent safety features, passive safety systems as well as the accident consequences confinement devices. The design realizes several advantages which are typical of the channel-type reactors, namely: The design desintegration simplifying the manufacture, control, equipment delivery and decreasing, versus the pressure vessel reactors, the accident effect if it proceeds in an explosive manner; small operating reactivity margin and fuel burnup increased due to continuous refuelling; fuel cycle flexibility allowing comparatively easily to adopt the reactor to the conjuncture of the country fuel balance; multiloop circuit of the main coolant which reduces the degree and effect of the accidents connected with the equipment and pipings rupture; monitoring of the channels and fuel assemblies leak-tightness. (orig.)

An Innovative Hybrid Loop-Pool SFR Design and Safety Analysis Methods: Today and Tomorrow

International Nuclear Information System (INIS)

Hongbin Zhang; Haihua Zhao; Vincent Mousseau

2008-01-01

Investment in commercial sodium cooled fast reactor (SFR) power plants will become possible only if SFRs achieve economic competitiveness as compared to light water reactors and other Generation IV reactors. Toward that end, we have launched efforts to improve the economics and safety of SFRs from the thermal design and safety analyses perspectives at Idaho National Laboratory. From the thermal design perspective, an innovative hybrid loop-pool SFR design has been proposed. This design takes advantage of the inherent safety of a pool design and the compactness of a loop design to further improve economics and safety. From the safety analyses perspective, we have initiated an effort to develop a high fidelity reactor system safety code

Some international perspectives on legislation for the management of human-induced safety risks

Directory of Open Access Journals (Sweden)

Alfonso Niemand

2016-01-01

Full Text Available Legislation that governs the health and safety of communities near major-hazard installations in South Africa is largely based on existing legislation that had been developed in the United Kingdom and other European Union countries. The latter was developed as a consequence of several major human-induced technological disasters in Europe. The history of the evolution of health-and-safety legislation for the protection of vulnerable communities in European Union (EU countries, France, Malaysia and the USA is explored through a literature survey. A concise comparison is drawn between EU countries, the USA and South Africa to obtain an exploratory view of whether current South-African legislation represents an optimum model for the protection of the health-and-safety of workers and communities near major-hazard installations. The authors come to the conclusion that South-African legislation needs revision as was done in the UK in 2011. Specific areas in the legislation that need revision are an overlap between occupational health and safety and environmental legislation, appropriate land-use planning for the protection of communities near major-hazard installations, the inclusion of vulnerability studies and the refinement of appropriate decision-making instruments such as risk assessment. This article is the first in a series that forms part of a broader study aimed at the development of an optimised model for the regulatory management of human-induced health and safety risks associated with hazardous installations in South Africa.

The Aube Storage Centre. Information report on nuclear safety and radiation protection for 2014 - Annual report 2014

International Nuclear Information System (INIS)

2014-06-01

After a presentation of the installations of CSA (Aube Storage Centre), its equipment, its exploitation (deliveries, storage, compacting unit, injection unit, storage works), works performed and highlights in 2014, and perspectives of evolution for 2015 and 2016, this report presents the measures regarding nuclear safety: safety principles, technical measures to meet objectives, inspections performed by the Nuclear Safety Authority (ASN), and quality management. The next part presents measures regarding measures for radiation protection and safety: staff dosimetry (measurements results and evolutions), safety exercise. It outlines that no important incident occurred, and described three minor events which have been declared to the ASN. The next part addresses actions related to the control of the environment and of releases: water management, presentation and discussion of the main results of radiological measurements (rainfalls, air, brook waters, sediments, underground waters, radiation at the edge of the centre, ground vegetal, food chain, aquatic ecosystems), physical-chemical control of waters, actions for the protection of the environment. The report then gives an overview of the management of radioactive and conventional wastes produced by the Centre. The last part indicates and comments actions related to transparency and information (they may concern the public, local authorities, institutions, or media): visits, conferences, exhibitions, animations, partnerships, publications

Inherent safety characteristics of innovative reactors

International Nuclear Information System (INIS)

Heil, J.A.

1995-11-01

The added safety value of innovative or third generation reactor designs has been evaluated in order to determine the most suitable candidate for Dutch government funded research and development support. To this end, four innovative reactor concepts, viz. PIUS (Process Inherent Ultimate Safety), PRISM (Power Reactor Innovative Small), HTR-M (High Temperature Reactor Module) and MHTGR (Modular High Temperature Gas-cooled Reactor), have been studied and their passive and inherent safety characteristics have been outlined. Also the outlook for further technological and industrial development has been considered. The results of the study confirm the perspective of the innovative reactors for reduced dependence on active safety provisions and for a further reduced vulnerability to technical failures and human errors. The accident responses to generic accident initiators, viz. reactivity and cooling accidents, and also to reactor specific accidents show that neither active safety systems nor short term operator actions are required for maintaining the reactor core in a controlled and coolable condition. Whether this gives rise to a higher total safety of the innovative reactor designs, compared to evolutionary or advanced reactors, cannot be concluded. Supplementary experimental and analytical analyses of reactor specific accidents are required to be able to assess the safety of these innovative designs in a more quantitative manner. It is believed that the safety case of innovative reactors, which are less dependent on active safety systems, can be communicated with the general public in a more transparent way. Considering the perspective for further technological and industrial development it is not expected that any of the considered innovative reactor concepts will become commercially available within the next one to two decades. However, they could be made available earlier if they would receive sufficient financial backing. Considering the added safety perspectives

Pacific Northwest Laboratory annual report for 1987 to the Assistant Secretary for Environment, Safety, and Health: Part 5: Environment, safety, health, and quality assurance

International Nuclear Information System (INIS)

Faust, L.G.; Steelman, B.L.; Selby, J.M.

1988-02-01

Part 5 of the 1987 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety, the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, and the Office of National Environmental Policy Act Project Assistance. For each project, as identified by the Field Work Proposal, articles describe progress made during fiscal year 1987. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work

Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

Energy Technology Data Exchange (ETDEWEB)

Salo, Ilkka (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

2005-12-15

The present study investigated safety management characteristics reflected in interviews with participants from two Swedish nuclear power plants. A document analysis regarding the plants' organization, safety policies, and safety culture work was carried out as well. The participants (n=9) were all nuclear power professionals, and the majority managers at different levels with at least 10 years of nuclear power experience. The interview comprised themes relevant for organizational safety and safety management, such as: organizational structures and organizational change, threats to safety, information feedback and knowledge transfer, safety analysis, safety policy, and accident and incident analysis and reporting. The results were in part modeled to important themes derived from a general system theoretical framework suggested by Svenson and developed by Svenson and Salo in relation to studies of 'non-nuclear' safety organizations. A primer to important features of the system theoretical framework is presented in the introductory chapter. The results from the interviews generated interesting descriptions about nuclear safety management in relation to the above themes. Regarding organizational restructuring, mainly centralizations of resources, several examples of reasons for the restructuring and related benefits for this centralization of resources were identified. A number of important reminders that ought to be considered in relation to reorganization were also identified. Regarding threats to the own organization a number of such was interpreted from the interviews. Among them are risks related to generation and competence change-over and risks related to outsourcing of activities. A thorough picture of information management and practical implications related to this was revealed in the interviews. Related to information feedback is the issue of organizational safety indicators and safety indicators in general. The interview answers indicated

Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

International Nuclear Information System (INIS)

Salo, Ilkka

2005-12-01

The present study investigated safety management characteristics reflected in interviews with participants from two Swedish nuclear power plants. A document analysis regarding the plants' organization, safety policies, and safety culture work was carried out as well. The participants (n=9) were all nuclear power professionals, and the majority managers at different levels with at least 10 years of nuclear power experience. The interview comprised themes relevant for organizational safety and safety management, such as: organizational structures and organizational change, threats to safety, information feedback and knowledge transfer, safety analysis, safety policy, and accident and incident analysis and reporting. The results were in part modeled to important themes derived from a general system theoretical framework suggested by Svenson and developed by Svenson and Salo in relation to studies of 'non-nuclear' safety organizations. A primer to important features of the system theoretical framework is presented in the introductory chapter. The results from the interviews generated interesting descriptions about nuclear safety management in relation to the above themes. Regarding organizational restructuring, mainly centralizations of resources, several examples of reasons for the restructuring and related benefits for this centralization of resources were identified. A number of important reminders that ought to be considered in relation to reorganization were also identified. Regarding threats to the own organization a number of such was interpreted from the interviews. Among them are risks related to generation and competence change-over and risks related to outsourcing of activities. A thorough picture of information management and practical implications related to this was revealed in the interviews. Related to information feedback is the issue of organizational safety indicators and safety indicators in general. The interview answers indicated that the area

Medicine use and safety while breastfeeding: investigating the perspectives of community pharmacists in Australia.

Science.gov (United States)

de Ponti, Martine; Stewart, Kay; Amir, Lisa H; Hussainy, Safeera Y

2015-01-01

Consumers and health professionals rely on community pharmacists for accurate information about the safety of medicines. Many breastfeeding women require medications, yet we know little about the advice provided to them by pharmacists in Australia. The aim of this study therefore was to investigate the perspectives of community pharmacists in Australia on medication use and safety in breastfeeding using a postal survey of a national random sample of 1166 community pharmacies in 2011. One hundred and seventy-six pharmacists responded (51% female). Of the 52% of participants with children, many (70%) had a total breastfeeding duration (self or partner) of 27 weeks or more. The majority (92%) were confident about supplying or counselling on medication during breastfeeding. The most commonly used resources were drug company information, Australian Medicines Handbook and the Royal Women's Pregnancy and Breastfeeding Medicine Guide. Most (80%) believed the available information to be adequate and 86% thought it accessible. Over one-third were unaware that ibuprofen and metronidazole are compatible with breastfeeding. Most (80%) were able to name at least one medicine that may decrease milk supply. We found that community pharmacists discuss medicine use in lactation and are confident of their ability to do so; however, their knowledge may be variable.

Changed nursing scheduling for improved safety culture and working conditions - patients' and nurses' perspectives.

Science.gov (United States)

Kullberg, Anna; Bergenmar, Mia; Sharp, Lena

2016-05-01

To evaluate fixed scheduling compared with self-scheduling for nursing staff in oncological inpatient care with regard to patient and staff outcomes. Various scheduling models have been tested to attract and retain nursing staff. Little is known about how these schedules affect staff and patients. Fixed scheduling and self-scheduling have been studied to a small extent, solely from a staff perspective. We implemented fixed scheduling on two of four oncological inpatient wards. Two wards kept self-scheduling. Through a quasi-experimental design, baseline and follow-up measurements were collected among staff and patients. The Safety Attitudes Questionnaire was used among staff, as well as study-specific questions for patients and staff. Fixed scheduling was associated with less overtime and fewer possibilities to change shifts. Self-scheduling was associated with more requests from management for short notice shift changes. The type of scheduling did not affect patient-reported outcomes. Fixed scheduling should be considered in order to lower overtime. Further research is necessary and should explore patient outcomes to a greater extent. Scheduling is a core task for nurse managers. Our study suggests fixed scheduling as a strategy for managers to improve the effective use of resources and safety. © 2016 John Wiley & Sons Ltd.

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

International Nuclear Information System (INIS)

Neall, Fiona; Pastina, Barbara; Snellman, Margit; Smith, Paul; Gribi, P.; Johnson, Lawrence

2008-12-01

The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments that lie outside the

Safety standards and safety record of nuclear power plants

International Nuclear Information System (INIS)

Davis, A.B.

1984-01-01

This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

Brazilian consensus on Duchenne muscular dystrophy. Part 1: diagnosis, steroid therapy and perspectives

Directory of Open Access Journals (Sweden)

Alexandra P. Q. C. Araujo

Full Text Available ABSTRACT Significant advances in the understanding and management of Duchenne muscular dystrophy (DMD took place since international guidelines were published in 2010. Our objective was to provide an evidence-based national consensus statement for multidisciplinary care of DMD in Brazil. A combination of the Delphi technique with a systematic review of studies from 2010 to 2016 was employed to classify evidence levels and grade of recommendations. Our recommendations were divided in two parts. We present Part 1 here, where we describe the guideline methodology and overall disease concepts, and also provide recommendations on diagnosis, steroid therapy and new drug treatment perspectives for DMD. The main recommendations: 1 genetic testing in diagnostic suspicious cases should be the first line for diagnostic confirmation; 2 patients diagnosed with DMD should have steroids prescribed; 3 lack of published results for phase 3 clinical trials hinders, for now, the recommendation to use exon skipping or read-through agents.

Making Residents Part of the Safety Culture: Improving Error Reporting and Reducing Harms.

Science.gov (United States)

Fox, Michael D; Bump, Gregory M; Butler, Gabriella A; Chen, Ling-Wan; Buchert, Andrew R

2017-01-30

Reporting medical errors is a focus of the patient safety movement. As frontline physicians, residents are optimally positioned to recognize errors and flaws in systems of care. Previous work highlights the difficulty of engaging residents in identification and/or reduction of medical errors and in integrating these trainees into their institutions' cultures of safety. The authors describe the implementation of a longitudinal, discipline-based, multifaceted curriculum to enhance the reporting of errors by pediatric residents at Children's Hospital of Pittsburgh of University of Pittsburgh Medical Center. The key elements of this curriculum included providing the necessary education to identify medical errors with an emphasis on systems-based causes, modeling of error reporting by faculty, and integrating error reporting and discussion into the residents' daily activities. The authors tracked monthly error reporting rates by residents and other health care professionals, in addition to serious harm event rates at the institution. The interventions resulted in significant increases in error reports filed by residents, from 3.6 to 37.8 per month over 4 years (P error reporting correlated with a decline in serious harm events, from 15.0 to 8.1 per month over 4 years (P = 0.01). Integrating patient safety into the everyday resident responsibilities encourages frequent reporting and discussion of medical errors and leads to improvements in patient care. Multiple simultaneous interventions are essential to making residents part of the safety culture of their training hospitals.

GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

Energy Technology Data Exchange (ETDEWEB)

Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

2015-07-01

International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

Personalized translational epilepsy research - Novel approaches and future perspectives: Part II: Experimental and translational approaches.

Science.gov (United States)

Bauer, Sebastian; van Alphen, Natascha; Becker, Albert; Chiocchetti, Andreas; Deichmann, Ralf; Deller, Thomas; Freiman, Thomas; Freitag, Christine M; Gehrig, Johannes; Hermsen, Anke M; Jedlicka, Peter; Kell, Christian; Klein, Karl Martin; Knake, Susanne; Kullmann, Dimitri M; Liebner, Stefan; Norwood, Braxton A; Omigie, Diana; Plate, Karlheinz; Reif, Andreas; Reif, Philipp S; Reiss, Yvonne; Roeper, Jochen; Ronellenfitsch, Michael W; Schorge, Stephanie; Schratt, Gerhard; Schwarzacher, Stephan W; Steinbach, Joachim P; Strzelczyk, Adam; Triesch, Jochen; Wagner, Marlies; Walker, Matthew C; von Wegner, Frederic; Rosenow, Felix

2017-11-01

Despite the availability of more than 15 new "antiepileptic drugs", the proportion of patients with pharmacoresistant epilepsy has remained constant at about 20-30%. Furthermore, no disease-modifying treatments shown to prevent the development of epilepsy following an initial precipitating brain injury or to reverse established epilepsy have been identified to date. This is likely in part due to the polyetiologic nature of epilepsy, which in turn requires personalized medicine approaches. Recent advances in imaging, pathology, genetics, and epigenetics have led to new pathophysiological concepts and the identification of monogenic causes of epilepsy. In the context of these advances, the First International Symposium on Personalized Translational Epilepsy Research (1st ISymPTER) was held in Frankfurt on September 8, 2016, to discuss novel approaches and future perspectives for personalized translational research. These included new developments and ideas in a range of experimental and clinical areas such as deep phenotyping, quantitative brain imaging, EEG/MEG-based analysis of network dysfunction, tissue-based translational studies, innate immunity mechanisms, microRNA as treatment targets, functional characterization of genetic variants in human cell models and rodent organotypic slice cultures, personalized treatment approaches for monogenic epilepsies, blood-brain barrier dysfunction, therapeutic focal tissue modification, computational modeling for target and biomarker identification, and cost analysis in (monogenic) disease and its treatment. This report on the meeting proceedings is aimed at stimulating much needed investments of time and resources in personalized translational epilepsy research. This Part II includes the experimental and translational approaches and a discussion of the future perspectives, while the diagnostic methods, EEG network analysis, biomarkers, and personalized treatment approaches were addressed in Part I [1]. Copyright © 2017

Safety Training Parks – Cooperative Contribution to Safety and Health Trainings

DEFF Research Database (Denmark)

Reiman, Arto; Pedersen, Louise Møller; Väyrynen, Seppo

2017-01-01

. The concept of Safety Training Park (STP) has been developed to meet these challenges. Eighty stakeholders from the Finnish construction industry have been involved in the construction and financing of the STP in northern Finland (STPNF). This unique cooperation has contributed to the immediate success......, and evidence from the literature are presented with a focus on the pros and cons of the STPNF. The STP is a new and innovative method for safety training that stimulates different learning styles and inspires changes in individuals’ behavior and in the organizations’ safety climate. The stakeholders’ high...... commitment, a long-term perspective, and a strong safety climate are identified as preconditions for the STP concept to work....

Issues of construction health and safety in developing countries: a case of Jordan

Directory of Open Access Journals (Sweden)

Suhair Zaid Alkilani

2013-09-01

Full Text Available The construction industry is widely regarded as one of the most significant interms of its impact on health and safety (H&S. Recent findings suggestthat in developing countries H&S awareness and performance is low. In this paper,the current state of H&S on construction sites in Jordan was explored usinga two-part investigation. The first part introduces the area of research in aliterature based study of on-site safety. The second part is a case study onthe Jordanian construction industry and its current H&S practices. Primary datawas collected from field visits, expert interviews and semi-structuredquestionnaires. Supporting secondary data was collected from archival studiesand related research literature. The research findings highlight a lack of governmentcommitment exemplified by regulations, policies and legal constraints thatlimit the operational efficiency of those government departments responsiblefor H&S management, and hindering the development of good H&S practice.Research results also highlight the key constraints of good H&S practice fromthe perspective of construction contractors.The study concludes with discussion ofpotential solutions toimprove H&S performance on construction sites in Jordan.

Formulation of nuclear safety under various induced events. Part 1. Current status and challenges for risk-informed activities in nuclear safety

International Nuclear Information System (INIS)

Itoi, Tatsuya; Hayashi, Kentaro; Yamato, Masaaki

2016-01-01

The Nuclear Safety Subcommittee published in March 2013 a report on 'Seminar on the Fukushima Daiichi Nuclear Power Station accident' (hereinafter referred to as Seminar Report), and has thereafter continued discussions on the challenges that were pointed out in Seminar Report as the target of discussions. This commentary series summarizes the current situation and challenges for the ideal way of nuclear safety against a variety of causal events as one of the above challenges. This paper, as Part 1 of the above theme, firstly summarizes the current state of the challenges of regulatory bodies and business operators who are engaging risk information utilization. It secondly discusses the future risk information utilization of regulations and business operators, realization of integrated decision-making process, timeliness and promptness required in decision-making, and future efforts including incentives. (A.O.)

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

Implementation of safety management systems in Hong Kong construction industry - A safety practitioner's perspective.

Science.gov (United States)

Yiu, Nicole S N; Sze, N N; Chan, Daniel W M

2018-02-01

In the 1980s, the safety management system (SMS) was introduced in the construction industry to mitigate against workplaces hazards, reduce the risk of injuries, and minimize property damage. Also, the Factories and Industrial Undertakings (Safety Management) Regulation was introduced on 24 November 1999 in Hong Kong to empower the mandatory implementation of a SMS in certain industries including building construction. Therefore, it is essential to evaluate the effectiveness of the SMS in improving construction safety and identify the factors that influence its implementation in Hong Kong. A review of the current state-of-the-practice helped to establish the critical success factors (CSFs), benefits, and difficulties of implementing the SMS in the construction industry, while structured interviews were used to establish the key factors of the SMS implementation. Results of the state-of-the-practice review and structured interviews indicated that visible senior commitment, in terms of manpower and cost allocation, and competency of safety manager as key drivers for the SMS implementation. More so, reduced accident rates and accident costs, improved organization framework, and increased safety audit ratings were identified as core benefits of implementing the SMS. Meanwhile, factors such as insufficient resources, tight working schedule, and high labor turnover rate were the key challenges to the effective SMS implementation in Hong Kong. The findings of the study were consistent and indicative of the future development of safety management practice and the sustainable safety improvement of Hong Kong construction industry in the long run. Copyright © 2018 National Safety Council and Elsevier Ltd. All rights reserved.

Patron Banning in the Nightlife Entertainment Districts: A Key Informant Perspective.

Science.gov (United States)

Miller, Peter; Curtis, Ashlee; Palmer, Darren; Warren, Ian; McFarlane, Emma

2016-07-01

Alcohol-related harm in and around licensed venues is associated with substantial costs. Many interventions have been introduced in an effort to combat these harms, and one such intervention is known as patron banning. Patron banning involves prohibiting patrons who have been violent or disorderly in a licensed venue in an attempt to reduce alcohol-related harm. It can be implemented by the venue, by members of police, or by liquor accords. This study aimed to obtain key informant perspectives on the benefits of patron banning as well as on the effectiveness of patron banning in reducing alcohol-related harm. Thirty-six key informants provided perspectives on patron banning through in-depth interviews that were part of a larger study. Key informants were supportive of patron banning for reducing alcohol-related harm, noting that it had many benefits including increased venue safety, general risk management, and deterrence of antisocial behavior. Although processes for banning were not always consistent, identification scanners were generally recognized as a way to ensure that patron banning was enforced. Key informants viewed patron banning as an effective measure for increasing patron safety and reducing alcohol-related harms.

Selection of indicators for continuous monitoring of patient safety: recommendations of the project 'safety improvement for patients in Europe'

DEFF Research Database (Denmark)

Kristensen, Solvejg; Mainz, Jan; Bartels, Paul

2009-01-01

such as culture, infections, surgical complications, medication errors, obstetrics, falls and specific diagnostic areas. CONCLUSION: The patient safety indicators recommended present a set of possible measures of patient safety. One of the future perspectives of implementing patient safety indicators...... for systematic monitoring is that it will be possible to continuously estimate the prevalence and incidence of patient safety quality problems. The lesson learnt from quality improvement is that it will pay off in terms of improving patient safety....

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...

Strategies of training as a part of radiation protection and nuclear safety in the 21st century

International Nuclear Information System (INIS)

Tafuni, O.

2009-01-01

Elaboration of national strategies and national training system is one of the main direction in the field of radio protection and nuclear safety in the Republic of Moldova. Necessary seminars and advanced training courses are held in the country and abroad, as well as the educational and informational materials are published to obtain these objectives. Scientific personnel of high educational institutions and specialists in the field of nuclear safety take part in accomplishment of the strategy. The demands of International and European organizations in this field are taken into consideration

Food safety objective: an integral part of food chain management

NARCIS (Netherlands)

Gorris, L.G.M.

2005-01-01

The concept of food safety objective has been proposed to provide a target for operational food safety management, leaving flexibility in the way equivalent food safety levels are achieved by different food chains. The concept helps to better relate operational food safety management to public

Safety features of subcritical fluid fueled systems

International Nuclear Information System (INIS)

Bell, C.R.

1995-01-01

Accelerator-driven transmutation technology has been under study at Los Alamos for several years for application to nuclear waste treatment, tritium production, energy generation, and recently, to the disposition of excess weapons plutonium. Studies and evaluations performed to date at Los Alamos have led to a current focus on a fluid-fuel, fission system operating in a neutron source-supported subcritical mode, using molten salt reactor technology and accelerator-driven proton-neutron spallation. In this paper, the safety features and characteristics of such systems are explored from the perspective of the fundamental nuclear safety objectives that any reactor-type system should address. This exploration is qualitative in nature and uses current vintage solid-fueled reactors as a baseline for comparison. Based on the safety perspectives presented, such systems should be capable of meeting the fundamental nuclear safety objectives. In addition, they should be able to provide the safety robustness desired for advanced reactors. However, the manner in which safety objectives and robustness are achieved is very different from that associated with conventional reactors. Also, there are a number of safety design and operational challenges that will have to be addressed for the safety potential of such systems to be credible

Safety features of subcritical fluid fueled systems

International Nuclear Information System (INIS)

Bell, C.R.

1994-01-01

Accelerator-driven transmutation technology has been under study at Los Alamos for several years for application to nuclear waste treatment, tritium production, energy generation, and recently, to the disposition of excess weapons plutonium. Studies and evaluations performed to date at Los Alamos have led to a current focus on a fluid-fuel, fission system operating in a neutron source-supported subcritical mode, using molten salt reactor technology and accelerator-driven proton-neutron spallation. In this paper, the safety features and characteristics of such systems are explored from the perspective of the fundamental nuclear safety objectives that any reactor-type system should address. This exploration is qualitative in nature and uses current vintage solid-fueled reactors as a baseline for comparison. Based on the safety perspectives presented, such systems should be capable of meeting the fundamental nuclear safety objectives. In addition, they should be able to provide the safety robustness desired for advanced reactors. However, the manner in which safety objectives and robustness are achieved in very different from that associated with conventional reactors. Also, there are a number of safety design and operational challenges that will have to be addressed for the safety potential of such systems to be credible

Safety features of subcritical fluid fueled systems

Energy Technology Data Exchange (ETDEWEB)

Bell, C.R. [Los Alamos National Laboratory, NM (United States)

1995-10-01

Accelerator-driven transmutation technology has been under study at Los Alamos for several years for application to nuclear waste treatment, tritium production, energy generation, and recently, to the disposition of excess weapons plutonium. Studies and evaluations performed to date at Los Alamos have led to a current focus on a fluid-fuel, fission system operating in a neutron source-supported subcritical mode, using molten salt reactor technology and accelerator-driven proton-neutron spallation. In this paper, the safety features and characteristics of such systems are explored from the perspective of the fundamental nuclear safety objectives that any reactor-type system should address. This exploration is qualitative in nature and uses current vintage solid-fueled reactors as a baseline for comparison. Based on the safety perspectives presented, such systems should be capable of meeting the fundamental nuclear safety objectives. In addition, they should be able to provide the safety robustness desired for advanced reactors. However, the manner in which safety objectives and robustness are achieved is very different from that associated with conventional reactors. Also, there are a number of safety design and operational challenges that will have to be addressed for the safety potential of such systems to be credible.

White paper on nuclear safety in 2005

International Nuclear Information System (INIS)

2006-04-01

The white paper consists of four parts. The first part described the outline of international discussions on safety culture and activities promoted by utilities and regulatory bodies in Japan. The second part explained the main activities of the Nuclear Safety Commission of Japan and nuclear regulatory authorities on nuclear safety regulation. The third part introduced various activities for ensuring overall nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster measures at nuclear facilities, progress in nuclear research, nuclear safety regulation by risk-informed utilization, environmental radiation surveys, international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission of Japan. (J.P.N.)

Occupational safety of different industrial sectors in Khartoum State, Sudan. Part 1: Safety performance evaluation.

Science.gov (United States)

Zaki, Gehan R; El-Marakby, Fadia A; H Deign El-Nor, Yasser; Nofal, Faten H; Zakaria, Adel M

2012-12-01

Safety performance evaluation enables decision makers improve safety acts. In Sudan, accident records, statistics, and safety performance were not evaluated before maintenance of accident records became mandatory in 2005. This study aimed at evaluating and comparing safety performance by accident records among different cities and industrial sectors in Khartoum state, Sudan, during the period from 2005 to 2007. This was a retrospective study, the sample in which represented all industrial enterprises in Khartoum state employing 50 workers or more. All industrial accident records of the Ministry of Manpower and Health and those of different enterprises during the period from 2005 to 2007 were reviewed. The safety performance indicators used within this study were the frequency-severity index (FSI) and fatal and disabling accident frequency rates (DAFR). In Khartoum city, the FSI [0.10 (0.17)] was lower than that in Bahari [0.11 (0.21)] and Omdurman [0.84 (0.34)]. It was the maximum in the chemical sector [0.33 (0.64)] and minimum in the metallurgic sector [0.09 (0.19)]. The highest DAFR was observed in Omdurman [5.6 (3.5)] and in the chemical sector [2.5 (4.0)]. The fatal accident frequency rate in the mechanical and electrical engineering industry was the highest [0.0 (0.69)]. Male workers who were older, divorced, and had lower levels of education had the lowest safety performance indicators. The safety performance of the industrial enterprises in Khartoum city was the best. The safety performance in the chemical sector was the worst with regard to FSI and DAFR. The age, sex, and educational level of injured workers greatly affect safety performance.

76 FR 53086 - Pipeline Safety: Safety of Gas Transmission Pipelines

Science.gov (United States)

2011-08-25

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket No. PHMSA-2011-0023] RIN 2137-AE72 Pipeline Safety: Safety of Gas Transmission Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), Department of Transportation (DOT...

Enhancing vaccine safety capacity globally: A lifecycle perspective

NARCIS (Netherlands)

R.T. Chen (Robert T.); T.T. Shimabukuro (Tom T.); D.B. Martin (David); P. Zuber (Patrick); D.M. Weibel (Daniel); M.C.J.M. Sturkenboom (Miriam)

2015-01-01

textabstractMajor vaccine safety controversies have arisen in several countries beginning in the last decades of 20th century. Such periodic vaccine safety controversies are unlikely to go away in the near future as more national immunization programs mature with near elimination of target

Post-mining safety implementations and environmental aspects of abandoned mine sites in Limousin. 2006 status (and perspectives 2007)

International Nuclear Information System (INIS)

2007-01-01

This document summarizes the actions carried out in 2006 at some French abandoned mine sites: 1 - safety implementations and risks abatement in the framework of post-mining actions: coal mines of Ahun (23) and Argentat (19), antimony mines of Biard (87); 2 - remedial actions at the tin/tungsten mine of Puy-les-Vignes (87) and at the gold mine of Chatelet (23); 3 - 2007 post-mining perspectives; 4 - environmental aspects of abandoned mine sites: gold mines of Chatelet (23), Cheni and Bourneix (87), uranium mines of Haute-Vienne (expertise, control of effluents, financial warranties about tailings storage sites maintenance). (J.S.)

Patient safety in undergraduate radiography curricula: A European perspective

International Nuclear Information System (INIS)

England, A.; Azevedo, K.B.; Bezzina, P.; Henner, A.; McNulty, J.P.

2016-01-01

Purpose: To establish an understanding of patient safety within radiography education across Europe by surveying higher education institutions registered as affiliate members of the European Federation of Radiographer Societies (EFRS). Method: An online survey was developed to ascertain data on: programme type, patient safety definitions, relevant safety topics, specific areas taught, teaching and assessment methods, levels of teaching and curriculum drivers. Responses were identifiable in terms of educational institution and country. All 54 affiliated educational institutions were invited to participate. Descriptive and thematic analyses are reported. Results: A response rate of 61.1% (n = 33) was achieved from educational institutions representing 19 countries. Patient safety topics appear to be extremely well covered across curricula, however, topics including radiation protection and optimisation were not reported as being taught at an ‘advanced level’ by five and twelve respondents, respectively. Respondents identified the clinical department as the location of most patient safety-related teaching. Conclusions: Patient safety topics are deeply embedded within radiography curricula across Europe. Variations exist in terms of individual safety topics including, teaching and assessment methods, and the depth in which subjects are taught. Results from this study provide a baseline for assessing developments in curricula and can also serve as a benchmark for comparisons. - Highlights: • First European report on patient safety (PS). • PS deeply embedded within training curricula. • Terms and definitions largely consistent. • Some variety in the delivery and assessment methods. • Report provides baseline and opportunities for comparisons.

Fukushima 2015: situational analysis and perspectives

International Nuclear Information System (INIS)

Jouette, Isabelle; Le Ngoc, Boris

2015-01-01

This publication proposes an overview of the situation of the Fukushima-Daiichi nuclear power station, four years after the accident. It addresses how the situation is managed in terms of evacuation of nuclear fuels, of storage of contaminated water, and of temporary storage of radioactive wastes produced by decontamination activities. It addresses the decontamination of the environment and the return of populations: progress of decontamination, return of populations, and absence of contamination of food products. The next part addresses the perspectives for the Japanese nuclear sector: a strengthened nuclear safety authority, reactors ready to start up again (some reactors seem to be able to be authorized to soon start up again). It describes how French technology is involved at the service of Fukushima-Daiichi through the Onet Technologies project by the CEA (a remote controlled laser cutting process). It evokes the evolutions of safety requirements in France after the Fukushima accident, notably with the introduction of the hard core notion, and of the FARN or Fast Nuclear Task Force

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

International Nuclear Information System (INIS)

2008-12-01

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the

Safety assessment for a KBS-3H spent nuclear fuel repository at Olkiluoto. Complementary evaluations of safety

Energy Technology Data Exchange (ETDEWEB)

Neall, Fiona; Pastina, Barbara; Snellman, Margit; Smith, Paul; Gribi, P.; Johnson, Lawrence

2008-12-15

The KBS-3H design is a variant of the more general KBS-3 method for the geological disposal of spent nuclear fuel in Finland and Sweden. In the KBS-3H design, multiple assemblies containing spent fuel are emplaced horizontally in parallel, approximately 300 m long, slightly inclined deposition drifts. The copper canisters, each with a surrounding layer of bentonite clay, are placed in perforated steel shells prior to deposition in the drifts; the assembly is called the 'supercontainer'. The other KBS-3 variant is the KBS-3V design, in which the copper canisters are emplaced vertically in individual deposition holes surrounded by bentonite clay but without steel supercontainer shells. SKB and Posiva have conducted a Research, Development and Demonstration programme over the period 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to KBS-3V. As part of this programme, the long-term safety of a KBS-3H repository has been assessed in the KBS-3H safety studies. In order to focus the safety studies, the Olkiluoto site in the municipality of Eurajoki, which is the proposed site for a spent fuel repository in Finland, was used as a hypothetical site for a KBS-3H repository. The present report is part of a portfolio of reports discussing the long-term safety of the KBS-3H repository. The overall outcome of the KBS-3H safety studies is documented in the summary report, 'Safety assessment for a KBS-3H repository for spent nuclear fuel at Olkiluoto'. The purpose and scope of the KBS-3H complementary evaluations of safety report is provided in Posiva's Safety Case Plan, which is based on Regulatory Guide YVL 8.4 and on international guidelines on complementary lines of argument to long-term safety that are considered an important element of a post-closure safety case for geological repositories. Complementary evaluations of safety require the use of evaluations, evidence and qualitative supporting arguments

76 FR 70953 - Pipeline Safety: Safety of Gas Transmission Pipelines

Science.gov (United States)

2011-11-16

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket ID PHMSA-2011-0023] RIN 2137-AE72 Pipeline Safety: Safety of Gas Transmission Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION: Advance notice of...

The safety performance management system: A tool for diagnosis, intervention and measurement

International Nuclear Information System (INIS)

Haber, S.B.; Shurberg, D.A.

2002-01-01

Many organizations depend on human performance to avoid incidents involving significant adverse consequences. Such organizations are typically termed high reliability organizations (HROs). While heavy emphasis has been placed on designing system hardware and software to intercept and mitigate events that could cause adverse consequences, dealing with the design of the human component has proven to be more complicated. Examination of various safety-related incidents makes it clear that human performance, and in particular organizational processes, plays a dominant role. The human errors are of various origins and are typically part of larger organizational processes that encourage unsafe acts that ultimately produce system failures. It is generally postulated that without an effective organizational safety culture, a safe working environment is impossible. While many different perspectives exist from which safety issues might be addressed, a method that allows the quantitative measurement of organizational processes deemed to impact overall safety performance is considered useful to understand the potential for future inadequate safety performance. This paper describes the Safety Performance Management System, a method useful for diagnosis, subsequent intervention and follow-on measurement. Implications for use of this method are presented and the concluding discussion includes insights regarding the general application of the method to improved facility safety performance. (author)

A verified and efficient approach towards fatigue validation of safety parts

Energy Technology Data Exchange (ETDEWEB)

Weihe, Stefan; Weigel, Nicolas [Daimler AG, Stuttgart (Germany); Dressler, Klaus; Speckert, Michael; Feth, Sascha

2011-07-01

In the automotive industry, safety parts must be designed according to the state of the art of science and technology such that they do not fail as long as the vehicle is used according to its purpose and misuse of the vehicle does not exceed a reasonably expectable degree. Due to scatter in customer loads and component properties, fatigue validation needs to be based on statistical methods. Mathematically sound methods are devised in order to make the validation process as efficient as possible. They allow considering all test results, including censored test data (e.g. tests suspended due to premature failure of components which are not under consideration). Furthermore, these methods permit adapting the success run criterion successively to the testing process. (orig.)

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (French Edition)

International Nuclear Information System (INIS)

2010-01-01

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Chinese Edition)

International Nuclear Information System (INIS)

2010-01-01

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-09-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

The future of road safety: A worldwide perspective

Directory of Open Access Journals (Sweden)

Fred Wegman

2017-03-01

The future of road safety is uncertain and definitely not the same for all regions of the world. Countries with a mature road safety approach and an ambition to make further progress are expected to move in the direction of a pro-active approach: a Safe System approach. It is reported that many LMIC, meanwhile, are on the brink of designing road safety strategies and implementing action plans. The international community is willing to support LMIC, but LMIC cannot simply copy successful HIC strategies because local circumstances differ. The principles of successful HIC strategies are applicable, but the priorities and action plans should take root in and align with local conditions.

Influences on the adoption of patient safety innovation in primary care: a qualitative exploration of staff perspectives.

Science.gov (United States)

Litchfield, Ian; Gill, Paramjit; Avery, Tony; Campbell, Stephen; Perryman, Katherine; Marsden, Kate; Greenfield, Sheila

2018-05-22

Primary care is changing rapidly to meet the needs of an ageing and chronically ill population. New ways of working are called for yet the introduction of innovative service interventions is complicated by organisational challenges arising from its scale and diversity and the growing complexity of patients and their care. One such intervention is the multi-strand, single platform, Patient Safety Toolkit developed to help practices provide safer care in this dynamic and pressured environment where the likelihood of adverse incidents is increasing. Here we describe the attitudes of staff toward these tools and how their implementation was shaped by a number of contextual factors specific to each practice. The Patient Safety Toolkit comprised six tools; a system of rapid note review, an online staff survey, a patient safety questionnaire, prescribing safety indicators, a medicines reconciliation tool, and a safe systems checklist. We implemented these tools at practices across the Midlands, the North West, and the South Coast of England and conducted semi-structured interviews to determine staff perspectives on their effectiveness and applicability. The Toolkit was used in 46 practices and a total of 39 follow-up interviews were conducted. Three key influences emerged on the implementation of the Toolkit these related to their ease of use and the novelty of the information they provide; whether their implementation required additional staff training or practice resource; and finally factors specific to the practice's local environment such as overlapping initiatives orchestrated by their CCG. The concept of a balanced toolkit to address a range of safety issues proved popular. A number of barriers and facilitators emerged in particular those tools that provided relevant information with a minimum impact on practice resource were favoured. Individual practice circumstances also played a role. Practices with IT aware staff were at an advantage and those previously

Maintenance of ageing CANDU reactors. A regulatory perspective

International Nuclear Information System (INIS)

Dunstan, T.

1996-01-01

The subject of this paper is, 'requirements for maintenance of ageing reactors from the perspective of a regulator', with a focus on the particular theme of; 'continuing safety assurance'. A major role of maintenance is to ensure the continuing reliability and effectiveness of safety related systems and equipment. Continuing safety assurance is an issue the Atomic Energy Control Board has been wrestling with for some time. From my perspective, much remains to be done before the AECB can be confident that Canadian nuclear plants have the necessary programs in place to achieve continuing safety assurance. To introduce the topic, it would be appropriate to say a few words about the AECB's position with respect to the situation at the Pickering NGS. Why did we blow the whistle last August and, what are we doing about it? (author)

Characteristics of safety critical organizations . work psychological perspective

International Nuclear Information System (INIS)

Oedewald, P.; Reiman, T.

2006-02-01

This book deals with organizations that operate in high hazard industries, such as the nuclear power, aviation, oil and chemical industry organisations. The society puts a great strain on these organisations to rigorously manage the risks inherent in the technology they use and the products they produce. In this book, an organisational psychology view is taken to analyse what are the typical challenges of daily work in these environments. The analysis is based on a literature review about human and organisational factors in safety critical industries, and on the interviews of Finnish safety experts and safety managers from four different companies. In addition to this, personnel interviews conducted in the Finnish nuclear power plants are utilised. The authors come up with eight themes that seem to be common organizational challenges cross the industries. These include e.g. how does the personnel understand the risks and what is the right level for rules and procedures to guide the work activities. The primary aim of this book is to contribute to the Finnish nuclear safety research and safety management discussion. However, the book is equally suitable for risk management, organizational development and human resources management specialists in different industries. The purpose is to encourage readers to consider how the human and organizational factors are seen in the field they work in. (orig.)

Special characteristics of safety organizations. Work psychological perspective

Energy Technology Data Exchange (ETDEWEB)

Oedewald, P.; Reiman, T.

2007-03-15

This book deals with organizations that operate in high hazard industries, such as the nuclear power, aviation, oil and chemical industry organizations. The society puts a great strain on these organizations to rigorously manage the risks inherent in the technology they use and the products they produce. In this book, an organizational psychology view is taken to analyse what are the typical challenges of daily work in these environments. The analysis is based on a literature review about human and organizational factors in safety critical industries, and on the interviews of Finnish safety experts and safety managers from four different companies. In addition to this, personnel interviews conducted in the Finnish nuclear power plants are utilised. The authors come up with eight themes that seem to be common organizational challenges cross the industries. These include e.g. how does the personnel understand the risks and what is the right level for rules and procedures to guide the work activities. The primary aim of this book is to contribute to the nuclear safety research and safety management discussion. However, the book is equally suitable for risk management, organizational development and human resources management specialists in different industries. The purpose is to encourage readers to consider how the human and organizational factors are seen in the field they work in. (orig.)

Special characteristics of safety organizations. Work psychological perspective

International Nuclear Information System (INIS)

Oedewald, P.; Reiman, T.

2007-03-01

This book deals with organizations that operate in high hazard industries, such as the nuclear power, aviation, oil and chemical industry organizations. The society puts a great strain on these organizations to rigorously manage the risks inherent in the technology they use and the products they produce. In this book, an organizational psychology view is taken to analyse what are the typical challenges of daily work in these environments. The analysis is based on a literature review about human and organizational factors in safety critical industries, and on the interviews of Finnish safety experts and safety managers from four different companies. In addition to this, personnel interviews conducted in the Finnish nuclear power plants are utilised. The authors come up with eight themes that seem to be common organizational challenges cross the industries. These include e.g. how does the personnel understand the risks and what is the right level for rules and procedures to guide the work activities. The primary aim of this book is to contribute to the nuclear safety research and safety management discussion. However, the book is equally suitable for risk management, organizational development and human resources management specialists in different industries. The purpose is to encourage readers to consider how the human and organizational factors are seen in the field they work in. (orig.)

Evaluation of replacement tritium facility (RTF) compliance with DOE safety goals using probabilistic consequence assessment methodology

International Nuclear Information System (INIS)

O'Kula, K.R.; East, J.M.; Moore, M.L.

1993-01-01

The Savannah River Site (SRS), operated by the Westinghouse Savannah River Company (WSRC) for the US Department of Energy (DOE), is a major center for the processing of nuclear materials for national defense, deep-space exploration, and medical treatment applications in the United States. As an integral part of the DOE's effort to modernize facilities, implement improved handling and processing technology, and reduce operational risk to the general public and onsite workers, transition of tritium processing at SRS from the Consolidated Tritium Facility to the Replacement Tritium Facility (RTF) began in 1993. To ensure that operation of new DOE facilities such as RTF present minimum involuntary and voluntary risks to the neighboring public and workers, indices of risk have been established to serve as target levels or safety goals of performance for assessing nuclear safety. These goals are discussed from a historical perspective in the initial part of this paper. Secondly, methodologies to quantify risk indices are briefly described. Lastly, accident, abnormal event, and normal operation source terms from RTF are evaluated for consequence assessment purposes relative to the safety targets

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.

Perspectives on radioactive waste repository monitoring. Confirmation, compliance, confidence building, and societal vigilance

Energy Technology Data Exchange (ETDEWEB)

Bergmans, Anne [Antwerp Univ. (Belgium). Research Group Society and Environment; Elam, Mark [Gothenburg Univ. (Sweden); Simmons, Peter [East Anglia Univ., Norwich (United Kingdom); Sundqvist, Goeran [Oslo Univ. (Norway)

2012-12-15

Monitoring is now widely seen as a necessary part of programmes for the geological disposal of radioactive waste. However, we find different perspectives on the nature and role of monitoring. Among technical experts it is viewed firstly as a matter of performance confirmation, a tool for validating the safety case underlying repository construction. Among concerned citizens we find a view of monitoring as enabling the critical scrutiny of safety, an instrument for acknowledging uncertainties and detecting emergent problems in a repository. After outlining differing views on questions of whether, why, what, where and for how long to monitor we discuss monitoring in light of constant vigilance as a technical and moral principle of nuclear safety. We suggest that ''how much monitoring'' and ''how should it be organised'' are societal questions and as such need to be broadly discussed.

Perspectives on nuclear material safety management methods at DOE sites

International Nuclear Information System (INIS)

Hyder, M.L.

1997-01-01

The management of nuclear materials, and fissile materials in particular, at the USDOE facilities is undergoing significant changes. These result in large part from decreasing requirements for these materials in the US weapons program. Not only is new production no longer required, but returns must be handled and safely stored. Eventually surplus fissile material will be used for power production, or else put into a form suitable for long term disposition. In the meanwhile concentrates must be stored with protection against releases of radioactive material to the environment, and also against theft or deliberate dispersion. In addition, cleaning up large volumes of materials contaminated with fissile isotopes will be a major activity, and there will also be some quantity of spent fuel containing enriched uranium that cannot readily be processed. All these activities pose safety problems, some of which are addressed here

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume I

International Nuclear Information System (INIS)

2000-12-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing error) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This publication is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canadian deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including the Soviet designed 'water moderated and water cooled energy reactors' (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts and managers from NPPs and from regulatory, plant design, manufacturing

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume II

International Nuclear Information System (INIS)

2000-12-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing error) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This publication is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canadian deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including the Soviet designed 'water moderated and water cooled energy reactors' (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts and managers from NPPs and from regulatory, plant design, manufacturing

How good is BNFL's health and safety?

International Nuclear Information System (INIS)

Berry, R.J.; Coulston, D.J.

1989-01-01

A historical perspective of the development of health and safety philosophy and practice within the nuclear industry is followed by a description of the Company's safety management system. This involves three elements, policy, implementation and audit. Data given on discharges to the environment and occupational dose. (U.K.)

Safety and Security at School: A Pedagogical Perspective

Science.gov (United States)

de Waal, Elda; Grosser, M. M.

2009-01-01

Education law and policy currently focus on broader physical aspects of safety and security at schools, as well as, for example, on pedagogical insecurity such as is caused by discriminatory teaching, but law and policy have yet to pay attention to the overall and far-reaching pedagogical safety and security of learners. By means of a descriptive…

Prospects for probabilistic safety assessment

International Nuclear Information System (INIS)

Hirschberg, S.

1992-01-01

This article provides some reflections on future developments of Probabilistic Safety Assessment (PSA) in view of the present state of the art and evaluates current trends in the use of PSA for safety management. The main emphasis is on Level 1 PSA, although Level 2 aspects are also highlighted to some extent. As a starting point, the role of PSA is outlined from a historical perspective, demonstrating the rapid expansion of the uses of PSA. In this context the wide spectrum of PSA applications and the associated benefits to the users are in focus. It should be kept in mind, however, that PSA, in spite of its merits, is not a self-standing safety tool. It complements deterministic analysis and thus improves understanding and facilitating prioritization of safety issues. Significant progress in handling PSA limitations - such as reliability data, common-cause failures, human interactions, external events, accident progression, containment performance, and source-term issues - is described. This forms a background for expected future developments of PSA. Among the most important issues on the agenda for the future are PSA scope extensions, methodological improvements and computer code advancements, and full exploitation of the potential benefits of applications to operational safety management. Many PSA uses, if properly exercised, lead to safety improvements as well as major burden reductions. The article provides, in addition, International Atomic Energy Agency (IAEA) perspective on the topics covered, as reflected in the current PSA programs of the agency. 74 refs., 6 figs., 1 tab

SOS-1 seminar about safety culture

International Nuclear Information System (INIS)

Wahlstroem, B.; Hammar, L.

2000-01-01

The aim of the seminar was to discuss safety culture in nuclear power utilities, and to exchange experiences about how the term safety culture is accepted by the personnel. The titles of the presentations are: 1) Organisational culture. General ideas as basis for organising; 2) Safety culture - ability and will; 3) View on safety culture at Swedish and Finnish nuclear power plants; 4) Safety culture at Barsebaeck Power Company; 5) Safety culture at Olkiluoto Nuclear Power Plant; 6) How do we improve the safety culture at OKG AB?; 7) Safety culture activities at Ringhals; 8) Aspects in relation to safety culture; 9) Development of regulatory activities/effectiveness of STUK - development as an aspect of culture; 10) Organisational culture research at STUK's Department of Nuclear Reactor Regulation; 11) The IAEA safety culture services; 12) Industrial safety - different perspectives and cultures. (EHS)

Relationship between organizational justice and organizational safety climate: do fairness perceptions influence employee safety behaviour?

Science.gov (United States)

Gyekye, Seth Ayim; Haybatollahi, Mohammad

2014-01-01

This study investigated the relationships between organizational justice, organizational safety climate, job satisfaction, safety compliance and accident frequency. Ghanaian industrial workers participated in the study (N = 320). Safety climate and justice perceptions were assessed with Hayes, Parender, Smecko, et al.'s (1998) and Blader and Tyler's (2003) scales respectively. A median split was performed to dichotomize participants into 2 categories: workers with positive and workers with negative justice perceptions. Confirmatory factors analysis confirmed the 5-factor structure of the safety scale. Regression analyses and t tests indicated that workers with positive fairness perceptions had constructive perspectives regarding workplace safety, expressed greater job satisfaction, were more compliant with safety policies and registered lower accident rates. These findings provide evidence that the perceived level of fairness in an organization is closely associated with workplace safety perception and other organizational factors which are important for safety. The implications for safety research are discussed.

Safety inspections to TRIGA reactors

International Nuclear Information System (INIS)

Byszewski, W.

1988-01-01

The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

Producing health, producing safety. Developing a collective safety culture in radiotherapy

International Nuclear Information System (INIS)

Nascimento, Adelaide

2009-01-01

This research thesis aims at a better understanding of safety management in radiotherapy and at proposing improvements for patient safety through the development of a collective safety culture. A first part presents the current context in France and abroad, addresses the transposition of other safety methods to the medical domain, and discusses the peculiarities of radiotherapy in terms of risks and the existing quality-assurance approaches. The second part presents the theoretical framework by commenting the intellectual evolution with respect to system safety and the emergence of the concept of safety culture, and by presenting the labour collective aspects and their relationship with system safety. The author then comments the variety of safety cultures among the different professions present in radiotherapy, highlights the importance of the collective dimension in correcting discrepancies at the end of the treatment process, and highlights how physicians take their colleagues work into account. Recommendations are made to improve patient safety in radiotherapy

Barriers to occupational health and safety management in small Brazilian enterprises

OpenAIRE

Garnica, Guilherme Besse; Barriga, Gladys Dorotea Cacsire

2018-01-01

Abstract Paper aims To determine main barriers to the implementation of occupational health and safety management systems OHSMS in the context of small Brazilian enterprises from the perspectives of owners/managers, labor auditors, and OHS consultants. Originality: Survey with three different perspectives on small Brazilian enterprises. Research method: Survey conducted with stakeholders who influence the safety culture in small enterprises to identify the main barriers to the implementati...

Reactor safety; Description and evaluation of safety activities in Nordic countries

International Nuclear Information System (INIS)

Wahlstroem, B.; Gunsell, L.

1998-03-01

The report gives a description of safety activities in the nuclear power industry. The study has been carried out as a part of the four year programme in Nordic Safety Research (NKS) which was completed in 1997. The objective of the NKS/RAK-1.1 project 'A survey and an evaluation of safety activities in nuclear power' was to make a broad description of various activities important for safety and to make an assessment of their efficiency. A special consideration was placed on a comparison of practices in Finland and Sweden, and between their nuclear utilities. The study has been divided into two parts, one theoretical part in which a model of the relationships between various activities important for safety has been constructed and one practical part where a total of 62 persons have been interviewed at the authorities, the nuclear utilities and one reactor vendor. To restrict the amount of work two activities, safety analysis and experience feedback, were selected. A few cases connected to incidents at nuclear power plants were discussed in more detail. The report has been structured around a simple model of nuclear safety consisting of the concepts of goals, means and outcomes. This model illustrates the importance of goal formulation, systematic planning and feedback of operational experience as major components in nuclear safety. In assessing organisation and management at authorities and the power utilities there is a clear trend of decentralisation and delegation of authority. The general impression from the study is that the safety activities in Finland and Sweden are efficient and well targeted. The experience from the methodology is favourable and the comparison of practices gives a good ground for a discussion of contents and targeting of safety activities. (EG) activities. (EG)

[Human orgasm from the physiological perspective--part I].

Science.gov (United States)

Gałecki, Piotr; Depko, Andrzej; Jedrzejewska, Sylwia; Talarowska, Monika

2012-07-01

Physiological phenomenon of sexuality occurring in both sexes that brings physical and mental satisfaction, and often affects the quality of life is an orgasm. The ability to experience regular orgasms affects relationship with partner. The definition of orgasm is not an easy task. The way of experiencing it is subjective, and the possibility of observing significantly reduced. Contemporary works on the phenomenon of orgasm are concentrated on several aspects: biological perspective (neurophysiological and biochemical determinants of orgasm), psychological perspective and on the differences in its course in both sexes. In sexology are two models of sexual response: a linear model of sexual response (by W. Masters and V. Johnson, and H. S. Kaplan) and the circular model of sexual response (created by R. Basson). The ability to experiencing an orgasm is inherent in men. In women, that phenomenon is acquired, is the consequence of further experience.

White paper on nuclear safety in 2000

International Nuclear Information System (INIS)

2001-04-01

This report is composed of three parts and a subjective part Part 1 includes special articles on the measures for the security of nuclear safety and the future problems described from the beginning of the security. Taking consideration that there exists potential risk in the utilization of nuclear energy in addition to the previous accidents in the area of nuclear energy, future measures to take for safety security were discussed as well as the reorganization of government facilities. In addition, the measures for nuclear safety according to the special nuclear disaster countermeasure law and the future problems were described. In Part 2, the trend of nuclear safety in 2000 and the actual effects of 'the basic principle for the countermeasures of the hour' proposed by the nuclear safety commission were outlined. Moreover, the activities of the commission in 2000 were briefly described. In Part 3, various activities for security of nuclear safety, the safety regulation system and the disaster protection system in nuclear facilities, nuclear safety researches in Japan were described in addition to international cooperation as to nuclear safety. Finally, various materials related to the nuclear safety commission, and the materials on the practical activities for nuclear safety were listed in the subjective part. (M.N.)

Radiation safety in nuclear industry in retrospect and perspective

International Nuclear Information System (INIS)

Pan Ziqiang

1993-01-01

More than 30 years have passed since the starting up of nuclear industry in China from the early 1950's. Over the past 30-odd years, nuclear industry has always kept a good record in China thanks to the policy of 'quality first, safety first' clearly put forward for nuclear industry from the outset and a lot of suitable effective measures taken over that period. Internationally, there is rapid progress in radiation protection and nuclear safety (hereafter refereed to as radiation safety) and a number of new concepts in the field of radiation protection have been advanced. Nuclear industry is developing based on the international standardization. To ensure the further development of nuclear utility, radiation safety needs to be further strengthened

Integrated Safety Culture Model and Application

Institute of Scientific and Technical Information of China (English)

汪磊; 孙瑞山; 刘汉辉

2009-01-01

A new safety culture model is constructed and is applied to analyze the correlations between safety culture and SMS. On the basis of previous typical definitions, models and theories of safety culture, an in-depth analysis on safety culture's structure, composing elements and their correlations was conducted. A new definition of safety culture was proposed from the perspective of sub-cuhure. 7 types of safety sub-culture, which are safety priority culture, standardizing culture, flexible culture, learning culture, teamwork culture, reporting culture and justice culture were defined later. Then integrated safety culture model (ISCM) was put forward based on the definition. The model divided safety culture into intrinsic latency level and extrinsic indication level and explained the potential relationship between safety sub-culture and all safety culture dimensions. Finally in the analyzing of safety culture and SMS, it concluded that positive safety culture is the basis of im-plementing SMS effectively and an advanced SMS will improve safety culture from all around.

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

Science.gov (United States)

Zelkin, Natalie; Henriksen, Stephen

2011-01-01

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

White paper on nuclear safety in 2004

International Nuclear Information System (INIS)

2005-05-01

The white paper consists of four parts. The first part described the regulation of nuclear facility decommissioning and the clearance level at which the decommissioned waste materials are not necessarily treated as radioactive materials. The second part explained the main operations of the nuclear safety regulation of the Nuclear Safety Commission and the regulatory bodies in 2004 and Mihama unit 3 accident. The third part introduced various activities for the general preservation of nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster preparedness of nuclear facilities, progress in nuclear research, environmental radiation surveys and international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission. (J.P.N.)

Evaluation of a Patient Perspective Module in a Required Medication Safety and Quality Course at a College of Pharmacy

Directory of Open Access Journals (Sweden)

Jessica N Battaglia

2013-01-01

Full Text Available Objectives: To develop and evaluate the impact of a module discussing the patient's perspective on medication errors in a required medication safety course at a college of pharmacy. Methods: Students were required to read Josie's Story, a true story written by a mother after her daughter died from a medical error, and attend an in-class discussion regarding the book. A questionnaire, which employed a pre-post retrospective method and extracted items from the Caring Ability Inventory, was then administered to measure the change in students' perceptions of patient care. Additional questions gathered students' perceptions of the assignment, their personal experiences with the topic, and the importance of medication safety. Results: 120 out of 138 students (response rate = 87% completed the questionnaire. 56% of students indicated they would be more likely to speak with a patient directly about a medication error after reading the book, whereas only 3% were less likely, and 42% indicated they were just as likely. Most students (59% reported that they felt more motivated to learn about medication safety after reading Josie's Story. Implications: This course previously addressed strategies to prevent medication errors. Successfully adding a component that introduces how a medication error impacted a patient and her family may help motivate students to recognize the importance and need for a culture of safety, personalize how medication errors impact patients, and provide a venue for students to gain patient centeredness and caring skills.   Type: Original Research

Evaluation of a Patient Perspective Module in a Required Medication Safety and Quality Course at a College of Pharmacy

Directory of Open Access Journals (Sweden)

Jessica N. Battaglia

2013-01-01

Full Text Available Objectives: To develop and evaluate the impact of a module discussing the patient’s perspective on medication errors in a required medication safety course at a college of pharmacy. Methods: Students were required to read Josie’s Story, a true story written by a mother after her daughter died from a medical error, and attend an in-class discussion regarding the book. A questionnaire, which employed a pre-post retrospective method and extracted items from the Caring Ability Inventory, was then administered to measure the change in students’ perceptions of patient care. Additional questions gathered students’ perceptions of the assignment, their personal experiences with the topic, and the importance of medication safety. Results: 120 out of 138 students (response rate = 87% completed the questionnaire. 56% of students indicated they would be more likely to speak with a patient directly about a medication error after reading the book, whereas only 3% were less likely, and 42% indicated they were just as likely. Most students (59% reported that they felt more motivated to learn about medication safety after reading Josie’s Story. Implications: This course previously addressed strategies to prevent medication errors. Successfully adding a component that introduces how a medication error impacted a patient and her family may help motivate students to recognize the importance and need for a culture of safety, personalize how medication errors impact patients, and provide a venue for students to gain patient centeredness and caring skills.

Study on safety analysis of VVER-1200/V491 in scenario of Loss of Coolant Accidents along with partly failure of ECCS using RELAP5 code

International Nuclear Information System (INIS)

Hoang Minh Giang; Ha Thi Anh Dao; Hoang Tan Hung; Bui Thi Hoa; Nguyen Thi Tu Oanh; Dinh Anh Tuan; Pham Tuan Nam

2017-01-01

The advanced VVER-1200/V491 reactor designed with passive safety systems to deal with design extension conditions is primarily selected as priority candidate for Ninh Thuan 1 nuclear power plant project. So that, in order to enhance competence of nuclear safety and toward participation on review Safety Analysis Report (SAR) of Ninh Thuan nuclear Power project the study on safety analysis of VVER-1200/V491 in scenario of Loss of Coolant Accidents along with partly failure of ECCS is implemented. As requirement of the study, the input deck file of VVER-1200/V491 for RELAP5 and analysis report for some special case of LOCAs along with partly failure of ECCS are issued. (author)

Relational Perspectives on Leading

DEFF Research Database (Denmark)

Relational Perspectives on Leading discusses leadership from a relational and social constructionism perspective as practiced on an everyday basis between people. The book pursues a fast growing, practice-based approach - particularly within the Anglo-Saxon parts of the world - to organization...

Transporting spent fuel - considerations for safety. From the United States, a review of why the past promotes high standards for the future

International Nuclear Information System (INIS)

Jefferson, R.M.

1985-01-01

Background information that might be useful to a broad range of individuals in developing their own perspectives about the transport of radioactive materials is presented. The safety of transporting spent fuel is addressed from a technical standpoint without the emotional content frequently a part of this argument. Three approaches are adopted. (1) Past history is examined and safety is evaluated on the basis of experience. (2) The subject is approached analytically by combining the various elements of risk involved and assessing them in light of consequences attached to each risk level. (3) Available safety research is reviewed to determine if it might reveal information that would either augment or alter the experience or analysis

Interaction between systems and software engineering in safety-critical systems

International Nuclear Information System (INIS)

Knight, J.

1994-01-01

There are three areas of concern: when is software to be considered safe; what, exactly, is the role of the software engineer; and how do systems, or sometimes applications, engineers and software engineers interact with each other. The author presents his perspective on these questions which he feels differ from those of many in the field. He argues for a clear definition of safety in the software arena, so the engineer knows what he is engineering toward. Software must be viewed as part of the entire system, since it does not function on its own, or isolation. He argues for the establishment of clear specifications in this area

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

Directory of Open Access Journals (Sweden)

Yogendra Bhattacharya

2015-12-01

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

Occupational Health and Safety: reflection on potential risks and the safety handling of nanomaterials

Directory of Open Access Journals (Sweden)

Guilherme Frederico Bernardo Lenz e Silva

2013-11-01

Full Text Available Every day the nanotechnology, that refers to a field whose theme is the control of matter on an atomic and molecular scale working with nanometric structures (<100 nm, is more present in the development of products and industrial processes. The particle manipulation of nanometric structures has created opportunities in the development of new products and materials. However, synthesis, handling, storage, stabilization and the incorporation of these materials, with nanometric dimensions, demand a new perspective of analysis and evaluation of old manufacturing processes, procedures and industrial devices, in order to guarantee collective and individual protection to workers and society. With the increasing of scale and production of nanoestrutuctured materials, a big part of labour community starts to be in contact with different nanomaterials (forms and ways. In this work the main aspects and involved risks of manufacture, storage, synthesis, stabilization and incorporation of nanomaterials on new products are evaluated in order to reduce, decrease and eliminate chemical, physical and biological risks for the employees. A bibliographic review was conducted about risk, safety and nanotechnology based on available English literature focusing safety and environmental agencies from different countries such as USA, Canada, EU (France, UK, Germany, Den-mark, Australia and Japan.

A Global Perspective on Vaccine Safety and Public Health: The Global Advisory Committee on Vaccine Safety

Science.gov (United States)

Folb, Peter I.; Bernatowska, Ewa; Chen, Robert; Clemens, John; Dodoo, Alex N. O.; Ellenberg, Susan S.; Farrington, C. Patrick; John, T. Jacob; Lambert, Paul-Henri; MacDonald, Noni E.; Miller, Elizabeth; Salisbury, David; Schmitt, Heinz-J.; Siegrist, Claire-Anne; Wimalaratne, Omala

2004-01-01

Established in 1999, the Global Advisory Committee on Vaccine Safety advises the World Health Organization (WHO) on vaccine-related safety issues and enables WHO to respond promptly, efficiently, and with scientific rigor to issues of vaccine safety with potential global importance. The committee also assesses the implications of vaccine safety for practice worldwide and for WHO policies. We describe the principles on which the committee was established, its modus operandi, and the scope of the work undertaken, both present and future. We highlight its recent recommendations on major issues, including the purported link between the measles–mumps–rubella vaccine and autism and the safety of the mumps, influenza, yellow fever, BCG, and smallpox vaccines as well as that of thiomersal-containing vaccines. PMID:15514229

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)

Microbiological food safety in Malaysia from the academician’s perspective

Directory of Open Access Journals (Sweden)

New, C.Y.,

2017-07-01

Full Text Available Food safety in Malaysia is not considered an issue yet. From the previous year (2005- 2015 records, the incidence rate of food poisoning had been fluctuating and despite that, cases continue to occur especially among school students. As a developing nation, it is high-time that Malaysia begins to emphasize on food safety to reduce the burden of foodborne illness in the socio-economic development of the country, and at the same time, gain benefits in terms of economic returns and trade through food safety enforcement. Most importantly, public health is achieved through food safety implementation and accentuation. The current standing point of the Malaysia’s food safety is discussed in this review. In addition, the review will also discuss the role of academicians as intervention contributions in tackling food safety issues. The review is hoped to provide valuable and concentrated information and knowledge to readers in the light to drive Malaysia into ensuring safer food for the public.

The Health and Safety Executive's strategy for nuclear safety research 1996

International Nuclear Information System (INIS)

1996-01-01

This brochure illustrates HSE's nuclear safety research strategy for 1996. It is divided into two parts. The first part presents HSE's overall strategy. The second contains short strategy statements for the individual areas detailed above, providing a rationale and objectives for the particular safety issues in the NRI, where greater detail can be found. (author)

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.

History of aviation safety; the satisfying sighs of relief due to developments in Aviation safety

NARCIS (Netherlands)

Stoop, J.A.A.M.

2014-01-01

”Aviation safety is an Integral part of my career. Being part of TU Delft’s impressive record of research on Aviation safety, my career has been with a sense of purpose and a responsibility to equip students to deal with the status quo challenges on Aviation safety, developments, Investigations and

A perspective of food safety laws in Mexico.

Science.gov (United States)

Leon, Marco A; Paz, Esmeralda

2014-08-01

Mexico, with a population of 112 million, is one of the most interesting countries in the world with regard to food, hunger, domestic food consumption, tourism and international trade, and it deserves an in-depth study to explain the status of its food safety laws. Mexico has a strong and stable emerging economy and is the second country worldwide with regard to the number of free-trade agreements. Nevertheless, more than half the population lives in poverty. However, Mexico is a huge market for food consumption because, in addition to its own population, it receives 20 million international tourists per year. So, multi-national food companies have representatives and facilities throughout the country. This scenario may explain the evolution of food safety laws in Mexico, as well as the challenges that must be faced in order to achieve food safety. © 2013 Society of Chemical Industry.

Nuclear safety review 1992. Part D of the IAEA Yearbook 1992

International Nuclear Information System (INIS)

1992-09-01

Activities aimed at upgrading the safety of nuclear power plants in countries of eastern Europe, the birth of the concept of an international nuclear safety convention and the new recommendations of the International Commission on Radiological Protection (ICRP) made 1991 a very important year in the fields of radiation protection and nuclear safety. Following the political changes in eastern Europe, attention is now centred on the safety of Soviet designed reactors. It has become apparent that the safety approach adopted in the design and operation of the older reactors (WWER-440/230s) was different from that which has been prevalent in western countries for many years and does not meet present safety standards. In addition to continuing its project on the safety of WWER-440/230s, the IAEA is proceeding with activities relating to the other reactor types operating in eastern European countries: WWER-440/213s, WWER-l000s and RBMKs. Concern for nuclear safety led the decision makers participating in the International Conference on the Safety of Nuclear Power: Strategy for the Future to support the concept of an international nuclear safety convention - a concept later endorsed by the IAEA General Conference and Board of Governors, the latter authorizing the Director General to set up an open ended working group with the task of carrying out the necessary preparations for such a convention. The radiation protection area was dominated by work on the revision of regulations and standards in the light of the new ICRP recommendations. The revision of the Basic Safety Standards for Radiation Protection, which is well under way, reflects a major international consensus on the basic requirements for restricting the risks from practices which could expose people to radiation. Co-operation between interested international organizations through a Joint Secretariat has proved to be efficient. Major lessons can be learned from experience with the utilization of nuclear technology

SKI's and SSI's review of SKB's safety report SR-Can

International Nuclear Information System (INIS)

Dverstorp, Bjoern; Stroemberg, Bo

2008-03-01

This report summarises SKI's and SSI's joint review of the Swedish Nuclear Fuel and Waste Management Co's (SKB) safety report SR-Can (SKB TR-06-09). SR-Can is the first assessment of post-closure safety for a KBS-3 spent nuclear fuel repository at the candidate sites Forsmark and Laxemar, respectively. The analysis builds on data from the initial stage of SKB's surface-based site investigations and on data from full-scale manufacturing and testing of buffer and copper canisters. SR-Can can be regarded as a preliminary version of the safety report that will be required in connection with SKB's planned licence application for a final repository in late 2009. The main purpose of the authorities' review is to provide feedback to SKB on their safety reporting as part of the pre-licensing consultation process. However, SR-Can is not part of the formal licensing process. In support of the authorities' review three international peer review teams were set up to make independent reviews of SR-Can from three perspectives, namely integration of site data, representation of the engineered barriers and safety assessment methodology, respectively. Further, several external experts and consultants have been engaged to review detailed technical and scientific issues in SR-Can. The municipalities of Oesthammar and Oskarshamn where SKB is conducting site investigations, as well NGOs involved in SKB's programme, have been invited to provide their views on SR-Can as input to the authorities' review. Finally, the authorities themselves, and with the help of consultants, have used independent models to reproduce part of SKB's calculations and to make complementary calculations. All supporting review documents are published in SKI's and SSI's report series. The main findings of the review are: -SKB's safety assessment methodology is overall in accordance with applicable regulations, but part of the methodology needs to be further developed for the licence application. -SKB's quality

Perspectives on the development of next generation reactor systems safety analysis codes

International Nuclear Information System (INIS)

Zhang, H.

2015-01-01

'Full text:' Existing reactor system analysis codes, such as RELAP5-3D and TRAC, have gained worldwide success in supporting reactor safety analyses, as well as design and licensing of new reactors. These codes are important assets to the nuclear engineering research community, as well as to the nuclear industry. However, most of these codes were originally developed during the 1970s', and it becomes necessary to develop next-generation reactor system analysis codes for several reasons. Firstly, as new reactor designs emerge, there are new challenges emerging in numerical simulations of reactor systems such as long lasting transients and multi-physics phenomena. These new requirements are beyond the range of applicability of the existing system analysis codes. Advanced modeling and numerical methods must be taken into consideration to improve the existing capabilities. Secondly, by developing next-generation reactor system analysis codes, the knowledge (know how) in two phase flow modeling and the highly complex constitutive models will be transferred to the young generation of nuclear engineers. And thirdly, all computer codes have limited shelf life. It becomes less and less cost-effective to maintain a legacy code, due to the fast change of computer hardware and software environment. There are several critical perspectives in terms of developing next-generation reactor system analysis codes: 1) The success of the next-generation codes must be built upon the success of the existing codes. The knowledge of the existing codes, not just simply the manuals and codes, but knowing why and how, must be transferred to the next-generation codes. The next-generation codes should encompass the capability of the existing codes. The shortcomings of existing codes should be identified, understood, and properly categorized, for example into model deficiencies or numerical method deficiencies. 2) State-of-the-art models and numerical methods must be considered to

Perspectives on the development of next generation reactor systems safety analysis codes

Energy Technology Data Exchange (ETDEWEB)

Zhang, H., E-mail: Hongbin.Zhang@inl.gov [Idaho National Laboratory, Idaho Falls, ID (United States)

2015-07-01

'Full text:' Existing reactor system analysis codes, such as RELAP5-3D and TRAC, have gained worldwide success in supporting reactor safety analyses, as well as design and licensing of new reactors. These codes are important assets to the nuclear engineering research community, as well as to the nuclear industry. However, most of these codes were originally developed during the 1970s', and it becomes necessary to develop next-generation reactor system analysis codes for several reasons. Firstly, as new reactor designs emerge, there are new challenges emerging in numerical simulations of reactor systems such as long lasting transients and multi-physics phenomena. These new requirements are beyond the range of applicability of the existing system analysis codes. Advanced modeling and numerical methods must be taken into consideration to improve the existing capabilities. Secondly, by developing next-generation reactor system analysis codes, the knowledge (know how) in two phase flow modeling and the highly complex constitutive models will be transferred to the young generation of nuclear engineers. And thirdly, all computer codes have limited shelf life. It becomes less and less cost-effective to maintain a legacy code, due to the fast change of computer hardware and software environment. There are several critical perspectives in terms of developing next-generation reactor system analysis codes: 1) The success of the next-generation codes must be built upon the success of the existing codes. The knowledge of the existing codes, not just simply the manuals and codes, but knowing why and how, must be transferred to the next-generation codes. The next-generation codes should encompass the capability of the existing codes. The shortcomings of existing codes should be identified, understood, and properly categorized, for example into model deficiencies or numerical method deficiencies. 2) State-of-the-art models and numerical methods must be considered to

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

Science.gov (United States)

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

2016-10-01

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

Integrating Occupational Health and Safety into TAFE Courses: Curriculum Topics.

Science.gov (United States)

Hall, Bob; Mageean, Pauline

This guide is designed to help technical and further education (TAFE) curriculum writers in Australia integrate safety education into vocational education courses. It provides a general overview of occupational health and safety from the perspective of TAFE trade training and a brief summary of the major health and safety issues that might be…

75 FR 45591 - Pipeline Safety: Notice of Technical Pipeline Safety Advisory Committee Meetings

Science.gov (United States)

2010-08-03

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part... Committee Meetings AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA); DOT. ACTION... safety standards, risk assessments, and safety policies for natural gas pipelines and for hazardous...

Perspective on food irradiation

International Nuclear Information System (INIS)

Anon.

1987-01-01

Recent US Food and Drug Administration approval of irradiation treatment for fruit, vegetables and pork has stimulated considerable discussion in the popular press on the safety and efficacy of irradiation processing of food. This perspective is designed to summarize the current scientific information available on this issue

National young-driver survey: teen perspective and experience with factors that affect driving safety.

Science.gov (United States)

Ginsburg, Kenneth R; Winston, Flaura K; Senserrick, Teresa M; García-España, Felipe; Kinsman, Sara; Quistberg, D Alex; Ross, James G; Elliott, Michael R

2008-05-01

Motor vehicle crashes are the leading cause of fatality and acquired disability in adolescents. Young, inexperienced drivers are overrepresented in crashes. Our goal was to explore the adolescent perspective on driving safety to provide a better understanding of factors that influence safety and teenagers' exposure to driving hazards. Adolescents generated, prioritized, and explained their viewpoint by using the teen-centered method. These viewpoints were obtained from a school-based nationally representative survey of 9th-, 10th-, and 11th-graders (N = 5665) from 68 high schools, conducted in spring 2006, that included teen-generated items. The main outcome measures were rating of risk and prevalence of witnessing driving hazards. Drinking while driving was ranked as the greatest hazard (87% of the respondents reported that it made a lot of difference), although only 12% witnessed it often. Ranked next as dangers while driving were text-messaging, racing, impairment from marijuana, and road rage. Sixty percent viewed inexperience as a significant hazard, although only 15% reported seeing it often. Cell phone use was viewed as a significant hazard by 28%, although 57% witnessed it frequently. Only 10% viewed peer passengers as hazardous, but 64% frequently observed them. Distracting peer behaviors, among other distractions, were viewed as more dangerous. Subpopulations varied in the degree they perceived hazards. For example, black and Hispanic adolescents viewed substance use while driving as less hazardous than did white adolescents but witnessed it more frequently. Adolescents generally understand the danger of intoxicated driving. However, some groups need to better recognize this hazard. Distractions take teenagers' focus off the road, but not all are viewed as hazardous. Although inexperience is the key factor that interacts with other conditions to cause crashes, adolescents do not recognize what merits experience. Future research is needed to explore how to

Identifying research priorities for patient safety in mental health: an international expert Delphi study

Science.gov (United States)

Murray, Kevin; Thibaut, Bethan; Ramtale, Sonny Christian; Adam, Sheila; Darzi, Ara; Archer, Stephanie

2018-01-01

Objective Physical healthcare has dominated the patient safety field; research in mental healthcare is not as extensive but findings from physical healthcare cannot be applied to mental healthcare because it delivers specialised care that faces unique challenges. Therefore, a clearer focus and recognition of patient safety in mental health as a distinct research area is still needed. The study aim is to identify future research priorities in the field of patient safety in mental health. Design Semistructured interviews were conducted with the experts to ascertain their views on research priorities in patient safety in mental health. A three-round online Delphi study was used to ascertain consensus on 117 research priority statements. Setting and participants Academic and service user experts from the USA, UK, Switzerland, Netherlands, Ireland, Denmark, Finland, Germany, Sweden, Australia, New Zealand and Singapore were included. Main outcome measures Agreement in research priorities on a five-point scale. Results Seventy-nine statements achieved consensus (>70%). Three out of the top six research priorities were patient driven; experts agreed that understanding the patient perspective on safety planning, on self-harm and on medication was important. Conclusions This is the first international Delphi study to identify research priorities in safety in the mental field as determined by expert academic and service user perspectives. A reasonable consensus was obtained from international perspectives on future research priorities in patient safety in mental health; however, the patient perspective on their mental healthcare is a priority. The research agenda for patient safety in mental health identified here should be informed by patient safety science more broadly and used to further establish this area as a priority in its own right. The safety of mental health patients must have parity with that of physical health patients to achieve this. PMID:29502096

Safety and licensing: the British perspective

Energy Technology Data Exchange (ETDEWEB)

Anthony, R D

1986-02-01

The legal framework of British regulatory practice is described, with emphasis on its flexibility and the fact that responsibility rests with the licensee, leaving the NII to monitor his implementation of that duty. The UK regulatory philosophy, the mixture of selective and random sampling used and the organization of the regulatory bodies as it interacts with that of the nuclear industry are outlined. This is followed by a resume of the current nuclear safety issues and of the NII's attitude to them, including the continued operation of the aging Magnox reactors, the extended transition of the AGR from the prototype to the 'tried and tested' stage of its existence, the problems of licensing nuclear chemical plant, the CEGB's proposed introduction of the PWR into this country, the availability of increasingly sophisticated means of assessing safety, and the steadily rising public interest in nuclear power issues. The Lecture ends by noting the problems of risk perception and cost/benefit analysis, emphasizing that in striking the right balance the regulatory body must be open, prepared to justify its reasoning, and productive of conclusions which are acceptable to the public.

Influences on Young Children's Knowledge: The Case of Road Safety Education.

Science.gov (United States)

Cullen, Joy

1998-01-01

Argues that effective road safety education for young children needs to incorporate constructivist and socio-cultural perspectives on learning. Excerpts interviews with young children highlighting the variety of influences affecting children's road safety knowledge and examination of a road safety curriculum to illustrate the value of a dual…

Safety parameter display system functions are integrated parts of the KWU KONVOI process information system (SPDS functions are parts of the KWU-PRINS)

International Nuclear Information System (INIS)

Aleite, W.; Geyer, K.H.

1984-01-01

The desirability of having flexible overview as well as extended detail information with pictorial and abstraction features and easy and quick access throughout the large-size control rooms in German plants has been recognized. Developments over the last years now make it possible to add on extensive computer driven VDU-systems to the three German KONVOI NPPs (Isar II, Emsland and Neckarwestheim II) thereby creating the Process Information System ''PRINS''. The new system is driven by multiple computers at different locations controlling about 30 full-graphic, high resolution Video Display Units. They are arranged singly and in three ''mxn - Information Panels'' distributed about the control room and present all thinkable kinds of display formats with more than 1000 separate pictures. The display of only single ''Safety Parameters'' or even complete ''Safety Goal Information'' on single or multiple VDUs in parallel is only one aspect of this computerized part of the entire integrated Information System. (orig./HP)

Categorization of reactor safety issues from a risk perspective

International Nuclear Information System (INIS)

1985-03-01

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

Infant-Guided, Co-Regulated Feeding in the Neonatal Intensive Care Unit. Part I: Theoretical Underpinnings for Neuroprotection and Safety.

Science.gov (United States)

Shaker, Catherine S

2017-04-01

The rapid progress in medical and technical innovations in the neonatal intensive care unit (NICU) has been accompanied by concern for outcomes of NICU graduates. Although advances in neonatal care have led to significant changes in survival rates of very small and extremely preterm neonates, early feeding difficulties with the transition from tube feeding to oral feeding are prominent and often persist beyond discharge to home. Progress in learning to feed in the NICU and continued growth in feeding skills after the NICU may be closely tied to fostering neuroprotection and safety. The experience of learning to feed in the NICU may predispose preterm neonates to feeding problems that persist. Neonatal feeding as an area of specialized clinical practice has grown considerably in the last decade. This article is the first in a two-part series devoted to neonatal feeding. Part 1 explores factors in NICU feeding experiences that may serve to constrain or promote feeding skill development, not only in the NICU but long after discharge to home. Part II describes approaches to intervention that support neuroprotection and safety. Thieme Medical Publishers 333 Seventh Avenue, New York, NY 10001, USA.

RA reactor safety analysis, Part II - Accident analysis; Analiza sigurnosti rada Reaktora RA I-III, Deo II - Analiza akcidenta

Energy Technology Data Exchange (ETDEWEB)

Raisic, N; Radanovic, Lj; Milovanovic, M; Afgan, N; Kulundzic, P [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1963-02-15

This part of the RA reactor safety analysis includes analysis of possible accidents caused by failures of the reactor devices and errors during reactor operation. Two types of accidents are analyzed: accidents resulting from uncontrolled reactivity increase, and accidents caused by interruption of cooling.

Special characteristics of safety critical organizations. Work psychological perspective

Energy Technology Data Exchange (ETDEWEB)

Oedewald, P.; Reiman, T.

2007-03-15

This book deals with organizations that operate in high hazard industries, such as the nuclear power, aviation, oil and chemical industry organizations. The society puts a great strain on these organizations to rigorously manage the risks inherent in the technology they use and the products they produce. In this book, an organizational psychology view is taken to analyse what are the typical challenges of daily work in these environments. The analysis is based on a literature review about human and organizational factors in safety critical industries, and on the interviews of Finnish safety experts and safety managers from four different companies. In addition to this, personnel interviews conducted in the Finnish nuclear power plants are utilised. The authors come up with eight themes that seem to be common organizational challenges cross the industries. These include e.g. how does the personnel understand the risks and what is the right level for rules and procedures to guide the work activities. The primary aim of this book is to contribute to the nuclear safety research and safety management discussion. However, the book is equally suitable for risk management, organizational development and human resources management specialists in different industries. The purpose is to encourage readers to consider how the human and organizational factors are seen in the field they work in. (orig.)

41 CFR 50-204.75 - Transportation safety.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 1 2010-07-01 2010-07-01 true Transportation safety. 50... Transportation Safety § 50-204.75 Transportation safety. Any requirements of the U.S. Department of Transportation under 49 CFR Parts 171-179 and Parts 390-397 and 14 CFR Part 103 shall be applied to...

Research for enhancing reactor safety

International Nuclear Information System (INIS)

1989-05-01

Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

Safety and health annual report 1996

International Nuclear Information System (INIS)

1997-01-01

The 1996 report on the Health and Safety performance of the nuclear fuel cycle company BNFL at its sites in the United Kingdom demonstrates a continuing improvement. The site locations and developments are briefly described and international developments in subsidiary organisations noted. Other sections of the report cover health and safety policy, radiological and industrial safety, emergency planning, incidents, occupational health services, compensation scheme developments, transport, putting radiation in perspective, and safety and health research. Data are provided on: radioactive discharges; industrial safety of BNFL and contractors' employees; radiation dose summaries for BNFL and contractors' employees. There is evidence of the expected plateauing out of doses to BNFL employees at a level less than or similar to background radiation. (UK)

Components for containment enclosures. Part 4: Ventilation and gas-cleaning systems such as filters, traps, safety and regulation valves, control and protection devices

International Nuclear Information System (INIS)

2001-01-01

ISO 11933 consists of the following parts, under the general title Components for containment enclosures: Part 1: Glove/bag ports, bungs for glove/bag ports, enclosure rings and interchangeable units; Part 2: Gloves, welded bags, gaiters for remote-handling tongs and for manipulators; Part 3: Transfer systems such as plain doors, airlock chambers, double door transfer systems, leaktight connections for waste drums; Part 4: Ventilation and gas-cleaning systems such as filters, traps, safety and regulation valves, control and protection devices; Part 5: Penetrations for electrical and fluid circuits. This part of ISO 11933 specifies the design criteria and the characteristics of various components used for ventilation and gas-cleaning in containment enclosures. These components are either directly fixed to the containment enclosure wall, or used in the environment of a shielded or unshielded containment enclosure or line of such enclosures. They can be used alone or in conjunction with other mechanical components, including those specified in ISO 11933-1 and ISO 11933-3. This part of ISO 11933 is applicable to: filtering devices, including high-efficiency particulate air (HEPA) filters and iodine traps; safety valves and pressure regulators; systems ensuring the mechanical protection of containment enclosures; control and pressure-measurement devices

ITER safety

International Nuclear Information System (INIS)

Raeder, J.; Piet, S.; Buende, R.

1991-01-01

As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

75 FR 63774 - Pipeline Safety: Safety of On-Shore Hazardous Liquid Pipelines

Science.gov (United States)

2010-10-18

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part... Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), Department of... Gas Pipeline Safety Act of 1968, Public Law 90-481, delegated to DOT the authority to develop...

Pacific Northwest Laboratory annual report for 1983 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. Part 5. Overview and assessment

International Nuclear Information System (INIS)

Bair, W.J.

1984-02-01

The 1983 annual report from Pacific Northwest Laboratory (PNL) to the Department of Energy (DOE) describes research in environment, health, and safety conducted during fiscal year 1983. The report again consists of five parts, each in a separate volume. Part 5 of the 1983 Annual Report to the Department of Energy's Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety and the Office of Operational Safety. For each project, as identified by the Field Task Proposal/Agreement, articles describe progress made during FY 1983. Authors of these articles represent a broad spectrum of capabilities derived from various segments of the Laboratory, reflecting the interdisciplinary nature of the work

The communicative construction of safety in wildland firefighting (Proceedings)

Science.gov (United States)

Jody Jahn

2012-01-01

This dissertation project used a two-study mixed methods approach, examining the communicative accomplishment of safety from two perspectives: high reliability organizing (Weick, Sutcliffe, & Obstfeld 1999), and safety climate (Zohar 1980). In Study One, 27 firefighters from two functionally similar wildland firefighting crews were interviewed about their crew-...

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1, Revision 1 (Chinese Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication establishes requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

Adolescent drivers: a developmental perspective on risk, proficiency, and safety.

Science.gov (United States)

Keating, Daniel P; Halpern-Felsher, Bonnie L

2008-09-01

Despite considerable improvement in the rates of crashes, injuries, and fatalities among adolescent drivers, attributable in part to effective interventions such as graduated driver licensing, these rates and their associated health risks remain unacceptably high. To understand the sources of risky driving among teens, as well as to identify potential avenues for further advances in prevention, this article presents a review of the relevant features of contemporary research on adolescent development. Current research offers significant advances in the understanding of the sources of safe driving, proficient driving, and risky driving among adolescents. This multifaceted perspective--as opposed to simple categorization of good versus bad driving--provides new opportunities for using insights on adolescent development to enhance prevention. Drawing on recent work on adolescent physical, neural, and cognitive development, we argue for approaches to prevention that recognize both the strengths and the limitations of adolescent drivers, with particular attention to the acquisition of expertise, regulatory competence, and self-regulation in the context of perceived risk. This understanding of adolescent development spotlights the provision of appropriate and effective scaffolding, utilizing the contexts of importance to adolescents--parents, peers, and the broader culture of driving--to support safe driving and to manage the inherent risks in learning to do so.

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

Accomplishments and needs in safety research

International Nuclear Information System (INIS)

Beckjord, E.S.

1988-01-01

My purpose today is to review recent accomplishments in water reactor safety research and to point out important tasks that remain to be done. I will also comment on the changes of focus that I see ahead in reactor safety research. I speak from a U.S. perspective on the subject, but note that the program of the U.S. Nuclear Regulatory Commission and also that of the U.S. industry's Electric Power Research Institute include many international collaborative research efforts. Without any doubt, nuclear safety research today is international in scope, and the collaborative movement is gaining in strength

Railway safety climate: a study on organizational development.

Science.gov (United States)

Cheng, Yung-Hsiang

2017-09-07

The safety climate of an organization is considered a leading indicator of potential risk for railway organizations. This study adopts the perceptual measurement-individual attribute approach to investigate the safety climate of a railway organization. The railway safety climate attributes are evaluated from the perspective of railway system staff. We identify four safety climate dimensions from exploratory factor analysis, namely safety communication, safety training, safety management and subjectively evaluated safety performance. Analytical results indicate that the safety climate differs at vertical and horizontal organizational levels. This study contributes to the literature by providing empirical evidence of the multilevel safety climate in a railway organization, presents possible causes of the differences under various cultural contexts and differentiates between safety climate scales for diverse workgroups within the railway organization. This information can be used to improve the safety sustainability of railway organizations and to conduct safety supervisions for the government.

76 FR 303 - Pipeline Safety: Safety of On-Shore Hazardous Liquid Pipelines

Science.gov (United States)

2011-01-04

... leak detection requirements for all pipelines; whether to require the installation of emergency flow... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 195 [Docket ID PHMSA-2010-0229] RIN 2137-AE66 Pipeline Safety: Safety of On-Shore Hazardous Liquid...

Management of safety, safety culture and self assessment

International Nuclear Information System (INIS)

Carnino, A.

2000-01-01

Safety management is the term used for the measures required to ensure that an acceptable level of safety is maintained throughout the life of an installation, including decommissioning. The safety culture concept and its implementation are described in part one of the paper. The principles of safety are now quite well known and are implemented worldwide. It leads to a situation where harmonization is being achieved as indicated by the entry into force of the Convention on Nuclear Safety. To go beyond the present nuclear safety levels, management of safety and safety culture will be the means for achieving progress. Recent events which took place in major nuclear power countries have shown the importance of the management and the consequences on safety. At the same time, electricity deregulation is coming and will impact on safety through reductions in staffing and in operation and maintenance cost at nuclear installations. Management of safety as well as its control and monitoring by the safety authorities become a key to the future of nuclear energy.(author)

Motor Vehicle Safety

Science.gov (United States)

... these crashes is one part of motor vehicle safety. Here are some things you can do to ... speed or drive aggressively Don't drive impaired Safety also involves being aware of others. Share the ...

Information security as part of the nuclear safety culture

Energy Technology Data Exchange (ETDEWEB)

Sitnica, A., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Co., 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2016-09-15

No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

Information security as part of the nuclear safety culture

International Nuclear Information System (INIS)

Sitnica, A.

2016-09-01

No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

USA perspectives. Safety and security of radioactive sources

International Nuclear Information System (INIS)

Dicus, G.J.

1999-01-01

In contrast to the 103 licensed nuclear power plants in the United States, there are about 157,000 licenses that authorize the use of radioactive materials subject to US Atomic Energy Act. as amended. Each year the NRC receives about 200 reports of lost, stolen or abandoned radioactive sources and devices. The NRC has established a programme to review and analyze reports and other information on losses, thefts, abandonments, and discoveries of radioactive sources that helped to identify and characterize the problem with safety and security of radioactive sources in devices used under the general license programme. In summary, a large number of radioactive sources in use in the USA have a very good safety record. When used properly by trained personnel with effective regulatory oversight, the many uses of radioactive sources are safe and provide a net benefit to society. If problems occur such as overexposures or contamination of property, it is essential that hey are promptly reported to the regulatory authority. If necessary appropriate emergency response measures can be taken, and the problems analysed. In that way, effective risk-informed regulatory measures can be activated to assure the continued safety and security of radioactive sources

Safety and reliability in Europe

International Nuclear Information System (INIS)

Colombo, A.G.

1985-01-01

This volume contains the papers presented at the ESRA Pre-Launching Meeting. The meeting was attended by about eighty European reliability and safety experts from industry, research organizations and universities. This meeting was dealing with the following subjects: the historical perspective of safety and reliability in Europe and to the aims of ESRA. Status and Trends in Research and Development; Codes, Standards and Regulations; Academic and Technical Training. National and international Organizations. Twenty six papers have been analyzed and abstracted for inclusion in the data base

Safety culture in a pharmacy setting using a pharmacy survey on patient safety culture: a cross-sectional study in China.

Science.gov (United States)

Jia, P L; Zhang, L H; Zhang, M M; Zhang, L L; Zhang, C; Qin, S F; Li, X L; Liu, K X

2014-06-30

To explore the attitudes and perceptions of patient safety culture for pharmacy workers in China by using a Pharmacy Survey on Patient Safety Culture (PSOPSC), and to assess the psychometric properties of the translated Chinese language version of the PSOPSC. Cross-sectional study. Data were obtained from 20 hospital pharmacies in the southwest part of China. We performed χ(2) test to explore the differences on pharmacy staff in different hospital and qualification levels and countries towards patient safety culture. We also computed descriptive statistics, internal consistency coefficients and intersubscale correlation analysis, and then conducted an exploratory factor analysis. A test-retest was performed to assess reproducibility of the items. A total of 630 questionnaires were distributed of which 527 were responded to validly (response rate 84%). The positive response rate for each item ranged from 37% to 90%. The positive response rate on three dimensions ('Teamwork', 'Staff Training and Skills' and 'Staffing, Work Pressure and Pace') was higher than that of Agency for Healthcare Research and Quality (AHRQ) data (pculture at different hospital and qualification levels. The internal consistency of the total survey was comparatively satisfied (Cronbach's α=0.89). The results demonstrated that among the pharmacy staffs surveyed in China, there was a positive attitude towards patient safety culture in their organisations. Identifying perspectives of patient safety culture from pharmacists in different hospital and qualification levels are important, since this can help support decisions about action to improve safety culture in pharmacy settings. The Chinese translation of the PSOPSC questionnaire (V.2012) applied in our study is acceptable. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

14 CFR Appendix B of Part 415 - Safety Review Document Outline

Science.gov (United States)

2010-01-01

... Performance Graphs 2.0Launch Operator Organization (§ 415.111) 2.1Launch Operator Organization (§ 415.111 and... Plan 4.3.1Flight Safety Personnel 4.3.2Flight Safety Rules 4.3.3Flight Safety System Summary and... Instrumentation Plan 6.2Configuration Management and Control Plan 6.3Frequency Management Plan 6.4Flight...

Perspective on safety case to support a possible site recommendation decision

International Nuclear Information System (INIS)

Gil, A.V.; Gamble, R.P.

2002-01-01

The mission of the US Department of Energy (DOE) is to provide the basis for a national decision regarding the development of a geological repository for spent nuclear fuel and high-level radioactive waste at the Yucca Mountain site in Nevada. There are a number of steps in the decision process defined by US law that must be completed prior to development of a repository at this site. The DOE's focus is currently on the first two steps in this process: characterization of the site to support a determination by the DOE on whether the site is suitable for a geologic repository and a decision by the Secretary of Energy (the Secretary) on whether to recommend to the President that the site be approved for a repository. To enhance the confidence of multiple audiences in the basis for these actions, and to provide a basis for subsequent action by the President and the US Congress, information supporting the decision process must include the elements of a safety case consistent with the statutory and regulatory framework for these decisions. The idea of a safety case is to broaden the basis for confidence by decision-makers and the public in conclusions about safety. A safety case should cite multiple lines of evidence, or reasoning, beyond the results of a safety assessment to support the demonstration of safety, which includes compliance with applicable safety criteria. The multiple lines of evidence should show the basis for confidence in safety. To be most effective, such evidence requires information not directly used in the safety assessment. (author)

Learning from no-fault treatment injury claims to improve the safety of older patients.

Science.gov (United States)

Wallis, Katharine Ann

2015-09-01

New Zealand's treatment injury compensation claims data set provides an uncommon no-fault perspective of patient safety incidents. Analysis of primary care claims data confirmed medication as the leading threat to the safety of older patients in primary care and drew particular attention to the threat posed by antibiotics. For most injuries there was no suggestion of error. The no-fault perspective reveals the greatest threat to the safety of older patients in primary care to be, not error, but the risk posed by treatment itself. To improve patients' safety, in addition to reducing error, clinicians need to reduce patients' exposure to treatment risk, where appropriate. © 2015 Annals of Family Medicine, Inc.

General safety aspects

International Nuclear Information System (INIS)

1998-01-01

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

SRP reactor safety evolution

International Nuclear Information System (INIS)

Rankin, D.B.

1984-01-01

The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

PWR: 10 years after and perspectives

International Nuclear Information System (INIS)

1990-01-01

These proceedings of the SFEN days on PWR (Ten years after and perspectives) comprise 13 conferences bearing on: - From the occurential approach to the state approach - Evolution of calculating tools - Human factors and safety - Reactor safety in the PWR 2000 - The PWR and the electrical power grid load follow - Fuel aspect of PWR management - PWR chemistry evolution - Balance of radiation protection - PWR modifications balance and influence on reactor operation - Design and maintenance of reactor components: 4 conferences [fr

Anatomy of safety-critical computing problems

International Nuclear Information System (INIS)

Swu Yih; Fan Chinfeng; Shirazi, Behrooz

1995-01-01

This paper analyzes the obstacles faced by current safety-critical computing applications. The major problem lies in the difficulty to provide complete and convincing safety evidence to prove that the software is safe. We explain this problem from a fundamental perspective by analyzing the essence of safety analysis against that of software developed by current practice. Our basic belief is that in order to perform a successful safety analysis, the state space structure of the analyzed system must have some properties as prerequisites. We propose the concept of safety analyzability, and derive its necessary and sufficient conditions; namely, definability, finiteness, commensurability, and tractability. We then examine software state space structures against these conditions, and affirm that the safety analyzability of safety-critical software developed by current practice is severely restricted by its state space structure and by the problem of exponential growth cost. Thus, except for small and simple systems, the safety evidence may not be complete and convincing. Our concepts and arguments successfully explain the current problematic situation faced by the safety-critical computing domain. The implications are also discussed

LISA package user guide. Part II: LISA (Long Term Isolation Safety Assessment) program description and user guide

International Nuclear Information System (INIS)

Prado, P.; Saltelli, A.; Homma, T.

1992-01-01

This manual is subdivided into three parts. In this second part, this document describes the LISA (Long term Isolation Safety Assessment) Code and its submodels. LISA is a tool for analysis of the safety of an underground disposal of nuclear waste. It has the capability to handle nuclide chain of arbitrary length and to evaluate the migration of nuclide through a geosphere medium composed of an arbitrary number of segments. LISA makes use of Monte Carlo methodology to evaluate the uncertainty in the quantity being assessed (eg dose) arising from the uncertainty in the model input parameters. In the present version LISA is equipped with a very simple source term submodel, a relatively complex geosphere and a simplified biosphere. The code is closely associated with its statistical pre-processor code (PREP), which generates the input Monte Carlo sample from the assigned parameter probability density functions and with its post-processor code (SPOP) which provides useful statistics on the output sample (uncertainty and sensitivity analysis). This report describes the general structure of LISA, its subroutines and submodels, the code input ant output files. It is intended to provide the user with enough information to know and run the code as well as the capacity to incorporate different submodels. 15 refs., 6 figs

Awareness of eSafety and Potential Online Dangers among Children and Teenagers

Science.gov (United States)

Zilka, Gila Cohen

2017-01-01

Aim/Purpose: Awareness of eSafety and potential online dangers for children and teenagers. Background: The study examined eSafety among children and teenagers from their own perspectives, through evaluations of their awareness level of eSafety and of potential online dangers. Methodology: This is a mixed-method study with both quantitative and…

The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety

International Nuclear Information System (INIS)

1992-01-01

The purpose of this Safety Report is to provide guidelines on the role of probabilistic safety assessment (PSA) and a range of associated reference points, collectively referred to as probabilistic safety criteria (PSC), in nuclear safety. The application of this Safety Report and the supporting Safety Practice publication should help to ensure that PSA methodology is used appropriately to assess and enhance the safety of nuclear power plants. The guidelines are intended for use by nuclear power plant designers, operators and regulators. While these guidelines have been prepared with nuclear power plants in mind, the principles involved have wide application to other nuclear and non-nuclear facilities. In Section 2 of this Safety Report guidelines are established on the role PSA can play as part of an overall safety assurance programme. Section 3 summarizes guidelines for the conduct of PSAs, and in Section 4 a PSC framework is recommended and guidance is provided for the establishment of PSC values

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

Relational approach in managing construction project safety: a social capital perspective.

Science.gov (United States)

Koh, Tas Yong; Rowlinson, Steve

2012-09-01

Existing initiatives in the management of construction project safety are largely based on normative compliance and error prevention, a risk management approach. Although advantageous, these approaches are not wholly successful in further lowering accident rates. A major limitation lies with the approaches' lack of emphasis on the social and team processes inherent in construction project settings. We advance the enquiry by invoking the concept of social capital and project organisational processes, and their impacts on project safety performance. Because social capital is a primordial concept and affects project participants' interactions, its impact on project safety performance is hypothesised to be indirect, i.e. the impact of social capital on safety performance is mediated by organisational processes in adaptation and cooperation. A questionnaire survey was conducted within Hong Kong construction industry to test the hypotheses. 376 usable responses were received and used for analyses. The results reveal that, while the structural dimension is not significant, the mediational thesis is generally supported with the cognitive and relational dimensions affecting project participants' adaptation and cooperation, and the latter two processes affect safety performance. However, the cognitive dimension also directly affects safety performance. The implications of these results for project safety management are discussed. Copyright © 2011 Elsevier Ltd. All rights reserved.

Safety requirements in the design of research reactors: A Canadian perspective

International Nuclear Information System (INIS)

Lee, A.G.; Langman, V.J.

2000-01-01

In Canada, the formal development of safety requirements for the design of research reactors in general began under an inter-organizational Small Reactor Criteria Committee. This committee developed safety and licensing criteria for use by several small reactor projects in their licensing discussions with the Atomic Energy Control Board. The small reactor projects or facilities represented included the MAPLE-X10 reactor, the proposed SES-10 heating reactor and its prototype, the SDR reactor at the Whiteshell Laboratories, the Korea Multipurpose Research Reactor (a.k.a., HANARO) in Korea, the SCORE project, and the McMaster University Nuclear Reactor. The top level set of criteria which form a safety philosophy and serve as a framework for more detailed developments was presented at an IAEA Conference in 1989. AECL continued this work to develop safety principles and design criteria for new small reactors. The first major application of this work has been to the design, safety analysis and licensing of the MAPLE 1 and 2 reactors for the MDS Nordion Medical Isotope Reactor Project. This paper provides an overview of the safety principles and design criteria. Examples of an implementation of these safety principles and design criteria are drawn from the work to design the MAPLE 1 and 2 reactors. (author)

Incorporation of Safety into Design Process : A Systems Engineering Perspective

NARCIS (Netherlands)

Rajabalinejad, M.

2018-01-01

This paper suggests integrating the best safety practices with the design process. This integration enriches the exploration experience for designers and adds extra values and competitor advantages for customers. The paper introduces the safety cube for combining common blocks for design, hazard

Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

International Nuclear Information System (INIS)

Baalman, R.W.; Hays, I.D.

1981-02-01

Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis of criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications

Resolution of the Task A-11 reactor-vessel materials-toughness safety issue. Part I. Main report. Part II. Staff responses to public comments, and Appendices A and B

International Nuclear Information System (INIS)

Johnson, R.

1982-10-01

This report provides the NRC position with respect to the reactor pressure vessel safety analysis required according to the rules given in the Code of Federal Regulations, Title 10 (10 CFR). An analysis is required whenever neutron irradiation reduces the Charpy V-notch upper shelf energy level in the vessel steel to 50 ft-lb or less. Task A-11 was needed because the available engineering methodology for such an analysis utilized linear elastic fracture mechanics principles, which could not fully account for the plastic deformation or stable crack extension expected at upper shelf temperatures. The Task A-11 goal was to develop an elastic-plastic fracture mechanics methodology, applicable to the beltline region of a pressurized water reactor vessel, which could be used in the required safety analysis. The goal was achieved with the help of a team of recognized experts. Part I of this volume contains the For Comment NUREG-0744, originally published in September 1981 and edited to accommodate comments from the public and the NRC staff. Edited segments are noted by vertical marginal lines. Part II of this volume contains the staff's responses to, and resolution of, the public comments received

Hospital board oversight of quality and safety: a stakeholder analysis exploring the role of trust and intelligence.

Science.gov (United States)

Millar, Ross; Freeman, Tim; Mannion, Russell

2015-06-16

Hospital boards, those executive members charged with developing appropriate organisational strategies and cultures, have an important role to play in safeguarding the care provided by their organisation. However, recent concerns have been raised over boards' ability to enact their duty to ensure the quality and safety of care. This paper offers critical reflection on the relationship between hospital board oversight and patient safety. In doing so it highlights new perspectives and suggestions for developing this area of study. The article draws on 10 interviews with key informants and policy actors who form part of the 'issue network' interested in the promotion of patient safety in the English National Health Service. The interviews surfaced a series of narratives regarding hospital board oversight of patient safety. These elaborated on the role of trust and intelligence in highlighting the potential dangers and limitations of approaches to hospital board oversight which have been narrowly focused on a risk-based view of organisational performance. In response, a need to engage with the development of trust based organisational relationships is identified, in which effective board oversight is built on 'trust' characterised by styles of leadership and behaviours that are attentive to the needs and concerns of both staff and patients. Effective board oversight also requires the gathering and triangulating of 'intelligence' generated from both national and local information sources. We call for a re-imagination of hospital board oversight in the light of these different perspectives and articulate an emerging research agenda in this area.

14 CFR 417.109 - Ground safety.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Ground safety. 417.109 Section 417.109... TRANSPORTATION LICENSING LAUNCH SAFETY Launch Safety Responsibilities § 417.109 Ground safety. (a) Ground safety... 417.115(c), and subpart E of this part provide launch operator ground safety requirements. ...

Proceedings of the seminar on nuclear safety research and the workshop on reactor safety research

International Nuclear Information System (INIS)

2001-07-01

The seminar on the nuclear safety research was held on November 20, 2000 according to the start of new five year safety research plan (FY2001-2005: established by Nuclear Safety Commission) with 79 participants. In the seminar, Commissioner Dr. Kanagawa gave the outline of the next five year safety research plan. Following this presentation, progresses and future scopes of safety researches in the fields of reactor facility, fuel cycle facility, radioactive waste and environmental impact on radiation at Japan Atomic Energy Research Institute (JAERI) were reported. After the seminar, the workshop on reactor safety research was held on November 21-22, 2000 with 141 participants. In the workshop, four sessions titled safety of efficient and economic utilization of nuclear fuel, safety related to long-term utilization of power reactors, research on common safety-related issues and toward further improvement of nuclear safety were organized and, outcomes and future perspectives in these wide research R and D in the related area at other organizations including NUPEC, JAPEIC and Kansai Electric Power Co. was presented in each session. This report compiles outlines of the presentations and used materials in the seminar and the workshop to form the proceedings for the both meetings. (author)

Safety of Cargo Aircraft Handling Procedure

Directory of Open Access Journals (Sweden)

Daniel Hlavatý

2017-07-01

Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

H12: Examination of safety assessment aims, procedures and results from a wider perspective

International Nuclear Information System (INIS)

Neall, F.B; Smith, P.A.

2004-04-01

Safety assessment (SA) are a familiar tool for the evaluation of disposal concepts for radioactive waste. There is, however, often confusion in the wider community about the aims, methods and results used in SA. This report aims to present the H12 SA in a way that makes the assessment process clearer and the implications of the results more meaningful both to workers within the SA field and to a wider technical audience. The reasonableness of the assessment results, the quality of the models and databases and redundancy within the natural and engineered barrier system have been considered. A number of recent and somewhat older SAs that address a range of different waste types, host rocks and disposal concepts have been considered, and comparisons made to H12. A further aim is to put both doses and timescales in a more meaningful context. It has been necessary to: consider ways of demonstrating the meaningfulness of calculations that give results for many thousands of years in the future; provide a framework timescale as a context for SA results over long times; demonstrate the smallness of the risk associated with the doses by comparison with other radiological and non-radiological risks. The perception of risk, which is a critical issue for public acceptance of radioactive waste disposal and must be considered when seeking to present safety assessment results 'in perspective' to a wider audience, is also discussed. It is concluded that H12 is comparable in many ways to assessments carried out internationally. Some assumptions are somewhat arbitrary reflecting the generic stage of the Japanese programme, and are likely to become better founded in future exercises. Nevertheless, H12 provides a clear and well-founded message that it is feasible to site and construct a safe repository from HLW in Japan. (author)

Measuring safety in aviation : empirical results about the relation between safety outcomes and safety management system processes, operational activities and demographic data

NARCIS (Netherlands)

Kaspers, Steffen; Karanikas, Nektarios; Piric, Selma; van Aalst, Robbert; de Boer, Robert Jan; Roelen, Alfred

2017-01-01

A literature review conducted as part of a research project named “Measuring Safety in Aviation – Developing Metrics for Safety Management Systems” revealed several challenges regarding the safety metrics used in aviation. One of the conclusions was that there is limited empirical evidence about the

Elements of a nuclear criticality safety program

International Nuclear Information System (INIS)

Hopper, C.M.

1995-01-01

Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance

Improving patient safety in Libya: insights from a British health system perspective.

Science.gov (United States)

Elmontsri, Mustafa; Almashrafi, Ahmed; Dubois, Elizabeth; Banarsee, Ricky; Majeed, Azeem

2018-04-16

Purpose Patient safety programmes aim to make healthcare safe for both patients and health professionals. The purpose of this paper is to explore the UK's patient safety improvement programmes over the past 15 years and explore what lessons can be learnt to improve Libyan healthcare patient safety. Design/methodology/approach Publications focusing on UK patient safety were searched in academic databases and content analysed. Findings Several initiatives have been undertaken over the past 15 years to improve British healthcare patient safety. Many stakeholders are involved, including regulatory and professional bodies, educational providers and non-governmental organisations. Lessons can be learnt from the British journey. Practical implications Developing a national patient safety strategy for Libya, which reflects context and needs is paramount. Above all, Libyan patient safety programmes should reference internationally approved guidelines, evidence, policy and learning from Britain's unique experience. Originality/value This review examines patient safety improvement strategies adopted in Britain to help developing country managers to progress local strategies based on lessons learnt from Britain's unique experience.

Safety Analysis in Design and Assessment of the Physical Protection of the OKG NPP

Energy Technology Data Exchange (ETDEWEB)

Lindahl, P., E-mail: par.lindahl@okg.eon.se [OKG Aktiebolag, Oskarshamn (Sweden)

2014-10-15

OKG AB operates a three unit nuclear power plant in the southern parts of Sweden. As a result of recent development of the legislation regarding physical protection of nuclear facilities, OKG has upgraded the protection against antagonistic actions. The new legislation includes requirements both on specific protective measures and on the performance of the physical protection as a whole. In short, the performance related requirements state that sufficient measures shall be implemented to protect against antagonistic actions, as defined by the regulator in the “Design Basis Threat” (DBT). Historically, physical protection and nuclear safety has been managed much as separate issues with different, sometimes contradicting, objectives. Now, insights from the work with the security upgrade have emphasized that physical protection needs to be regarded as an important part of the Defence-In-Depth (DiD) against nuclear accidents. Specifically, OKG has developed new DBT-based analysis methods, which may be characterized as probabilistically informed deterministic analysis, conformed to a format similar to the one used for conventional internal events analysis. The result is a powerful tool for design and assessment of the performance of the protection against antagonistic actions, using a nuclear safety perspective. (author)

Safety Culture Perspective. Managing the pre Managing the pre-operational phases of new NPPs and creating the safety culture

International Nuclear Information System (INIS)

Cowan, Pamela B.; Oh, Chaewoon; Dahlgren Persson, Kerstin; Carnino, Annick

2008-01-01

Nuclear safety is a key for the revival of nuclear energy future programmes. Lots of competent people will be needed worldwide for ensuring the safety of the installations both existing ones and future ones. Their expertise should range from design to operation, from regulatory role to operators, from fuel fabrication to waste disposal. The challenge in front of us will be to prepare for the right recruitment, the development of the needed expertise in order to face the demand in developed countries, in countries with economies in transition and in developing countries. Time allocated for the panel does not allow for covering all aspects but the panelists will cover some of the important aspects of the challenge in terms of needs, of new competencies, of learning from operation and licensing requirements including for new designs. The key objectives of the panel are: 1- Maintaining safe operation, learning from experience, licensing including aging management and re-licensing with safety improvements for existing installations: - Presentation by Junko Ogawa of the experience and lessons learned from the earthquake on Kashiwasaki Kariwa NPP: effects in terms of manpower involved in the investigation, effects on regulations and licensing, expertise used. - Presentation by Pamela Cowan of her experience in preparing licensing actions, regulatory compliance and interface with the Regulator for both operating plants and modern requirements for constructing new ones. 2 - Special training needed for the human aspect of safety: what are the challenges in areas of safety culture and management of safety: - Presentation by Chae Woon Oh of the Korean safety culture features developed nationally, at the regulator and at the operating organizations and their integration within the safety training programmes. - Presentation by Kerstin Dahlgren Person of the needs in terms of safety culture and safety management, in terms of expertise, practitioners and assessors. 3 - How to

Safety Culture Perspective. Managing the pre Managing the pre-operational phases of new NPPs and creating the safety culture

Energy Technology Data Exchange (ETDEWEB)

Cowan, Pamela B. [Exelon Generation, 200 Exelon Way, 19348 Kennett Square, PA 19348 (United States); Oh, Chaewoon [Korea Institute of Nuclear Safety, 19 Gusung-Dong, Yuseong-Ku, 305-338 Daejeon (Korea, Republic of); Dahlgren Persson, Kerstin [International Atomic Energy Agency, Wagramer Strasse 5, PO BOX 100 A-1400 Vienna (Austria); Carnino, Annick [IAEA, Division of Nuclear Installation Safety, Wagramer Strasse 5, PO BOX 100 A-1400 Vienna (Austria)

2008-07-01

Nuclear safety is a key for the revival of nuclear energy future programmes. Lots of competent people will be needed worldwide for ensuring the safety of the installations both existing ones and future ones. Their expertise should range from design to operation, from regulatory role to operators, from fuel fabrication to waste disposal. The challenge in front of us will be to prepare for the right recruitment, the development of the needed expertise in order to face the demand in developed countries, in countries with economies in transition and in developing countries. Time allocated for the panel does not allow for covering all aspects but the panelists will cover some of the important aspects of the challenge in terms of needs, of new competencies, of learning from operation and licensing requirements including for new designs. The key objectives of the panel are: 1- Maintaining safe operation, learning from experience, licensing including aging management and re-licensing with safety improvements for existing installations: - Presentation by Junko Ogawa of the experience and lessons learned from the earthquake on Kashiwasaki Kariwa NPP: effects in terms of manpower involved in the investigation, effects on regulations and licensing, expertise used. - Presentation by Pamela Cowan of her experience in preparing licensing actions, regulatory compliance and interface with the Regulator for both operating plants and modern requirements for constructing new ones. 2 - Special training needed for the human aspect of safety: what are the challenges in areas of safety culture and management of safety: - Presentation by Chae Woon Oh of the Korean safety culture features developed nationally, at the regulator and at the operating organizations and their integration within the safety training programmes. - Presentation by Kerstin Dahlgren Person of the needs in terms of safety culture and safety management, in terms of expertise, practitioners and assessors. 3 - How to

Safety and security profiles of industry networks used in safety- critical applications

Directory of Open Access Journals (Sweden)

Mária FRANEKOVÁ

2008-01-01

Full Text Available The author describes the mechanisms of safety and security profiles of industry and communication networks used within safety – related applications in technological and information levels of process control recommended according to standards IEC 61784-3,4. Nowadays the number of vendors of the safety – related communication technologies who guarantees besides the standard communication, the communication amongst the safety – related equipment according to IEC 61508 is increasing. Also the number of safety – related products is increasing, e. g. safety Fieldbus, safety PLC, safety curtains, safety laser scanners, safety buttons, safety relays and other. According to world survey the safety Fieldbus denoted the highest growth from all manufactured safety products.The main part of this paper is the description of the safety-related Fieldbus communication system, which has to guaranty Safety Integrity Level.

ITER-FEAT safety

International Nuclear Information System (INIS)

Gordon, C.W.; Bartels, H.-W.; Honda, T.; Raeder, J.; Topilski, L.; Iseli, M.; Moshonas, K.; Taylor, N.; Gulden, W.; Kolbasov, B.; Inabe, T.; Tada, E.

2001-01-01

Safety has been an integral part of the design process for ITER since the Conceptual Design Activities of the project. The safety approach adopted in the ITER-FEAT design and the complementary assessments underway, to be documented in the Generic Site Safety Report (GSSR), are expected to help demonstrate the attractiveness of fusion and thereby set a good precedent for future fusion power reactors. The assessments address ITER's radiological hazards taking into account fusion's favourable safety characteristics. The expectation that ITER will need regulatory approval has influenced the entire safety design and assessment approach. This paper summarises the ITER-FEAT safety approach and assessments underway. (author)

Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

Energy Technology Data Exchange (ETDEWEB)

Baalman, R.W.; Hays, I.D. (eds.)

1981-02-01

Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis of criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications. (DLS)

Safety management of a complex R and D ground operating system

Science.gov (United States)

Connors, J. F.; Maurer, R. A.

1975-01-01

A perspective on safety program management was developed for a complex R&D operating system, such as the NASA-Lewis Research Center. Using a systems approach, hazardous operations are subjected to third-party reviews by designated-area safety committees and are maintained under safety permit controls. To insure personnel alertness, emergency containment forces and employees are trained in dry-run emergency simulation exercises. The keys to real safety effectiveness are top management support and visibility of residual risks.

14 CFR 417.107 - Flight safety.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Flight safety. 417.107 Section 417.107... TRANSPORTATION LICENSING LAUNCH SAFETY Launch Safety Responsibilities § 417.107 Flight safety. (a) Flight safety... safety system that satisfies subpart D of this part as follows, unless § 417.125 applies. (1) In the...

National Machine Guarding Program: Part 2. Safety management in small metal fabrication enterprises.

Science.gov (United States)

Parker, David L; Yamin, Samuel C; Brosseau, Lisa M; Xi, Min; Gordon, Robert; Most, Ivan G; Stanley, Rodney

2015-11-01

Small manufacturing businesses often lack important safety programs. Many reasons have been set forth on why this has remained a persistent problem. The National Machine Guarding Program (NMGP) was a nationwide intervention conducted in partnership with two workers' compensation insurers. Insurance safety consultants collected baseline data in 221 business using a 33-question safety management audit. Audits were completed during an interview with the business owner or manager. Most measures of safety management improved with an increasing number of employees. This trend was particularly strong for lockout/tagout. However, size was only significant for businesses without a safety committee. Establishments with a safety committee scored higher (55% vs. 36%) on the safety management audit compared with those lacking a committee (P < 0.0001). Critical safety management programs were frequently absent. A safety committee appears to be a more important factor than business size in accounting for differences in outcome measures. © 2015 The Authors. American Journal of Industrial Medicine Published by Wiley Periodicals, Inc.

IRSN research programs concerning reactor safety

International Nuclear Information System (INIS)

Bardelay, J.

2005-01-01

This paper is made up of 3 parts. The first part briefly presents the missions of IRSN (French research institute on nuclear safety), the second part reviews the research works currently led by IRSN in the following fields : -) the assessment of safety computer codes, -) thermohydraulics, -) reactor ageing, -) reactivity accidents, -) loss of coolant, -) reactor pool dewatering, -) core meltdown, -) vapor explosion, and -) fission product release. In the third part, IRSN is shown to give a major importance to experimental programs led on research or test reactors for collecting valid data because of the complexity of the physical processes that are involved. IRSN plans to develop a research program concerning the safety of high or very high temperature reactors. (A.C.)

Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective

International Nuclear Information System (INIS)

Jinil Mok; Poong Hyun Seong

1996-01-01

In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which are calculated with proposed model differ from those used in Wolsung NPP Unit 1 by about a few days or months, whereas the optimal inspection periods are in about the same range. (author)

Safety assessment for spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Practice has been prepared as part of the IAEA's programme on the safety assessment of interim spent fuel storage facilities which are not an integral part of an operating nuclear power plant. This report provides general guidance on the safety assessment process, discussing both deterministic and probabilistic assessment methods. It describes the safety assessment process for normal operation and anticipated operational occurrences and also related to accident conditions. 10 refs, 2 tabs

Applicability of RELAP5 for safety analysis of AP600 and PIUS reactors

International Nuclear Information System (INIS)

Motloch, C.G.; Modro, S.M.

1990-01-01

An assessment of the applicability of using RELAP5 for performing safety analyses of the AP600 and PIUS advanced reactor concepts is being performed. This ongoing work is part of a larger safety assessment of advanced reactors sponsored by the United States Nuclear Regulatory Commission. RELAP5 models and correlations are being reviewed from the perspective of the new AP600 and PIUS phenomena and features that could be important to reactor safety. The purpose is to identify those areas in which new mathematical models of physical phenomena would be required to be added to RELAP5. In most cases, the AP600 and PIUS designs and systems and the planned and off-normal operations are similar enough to current Pressurized Water Reactors (PWR) that RELAP5 safety analysis applicability is unchanged. However, for AP600 the single most important systemic and phenomenological difference between it and current PWRs is in the close coupling between the reactor system and the containment during postulated Loss of Coolant Accident (LOCA) events. This close coupling may require the addition of some thermal-hydraulic models to RELAP5. And for PIUS, the most important new feature is the thermal density locks. These and other important safety-related features are discussed. This document presents general descriptions of RELAP5, AP600, and PIUS, describes the new features and phenomena of the reactors, and discusses the code/reactors safety-related issues. 32 refs., 4 figs., 2 tabs

Nuclear safety review for the year 2001

International Nuclear Information System (INIS)

2002-07-01

The Nuclear Safety Review for the Year 2001 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts. Part 1 describes those events in 2001 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety. Part 2 describes some of the IAEA's efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2001. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2001. Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2001 was presented to the March 2002 session of IAEA's Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2002 that were considered pertinent to the discussion of events during 2001

Safety Concepts for Workers from an OSHA Perspective

Science.gov (United States)

2017-10-01

Highway construction and maintenance workers face numerous hazards on job sites, many of which are unique by industry standards. Despite the exposure of state transportation agency employees and contractors to these hazards, there are few safety stan...

Spare parts classification and procurement program

International Nuclear Information System (INIS)

Adlon, K.L.; Hassaballa, M.M.

1986-01-01

The cost benefits have been demonstrated for an integrated program, which is currently being implemented for two PWR stations with two 1100-MW units each. The component classification efforts reduced the number of safety-related components in several systems. Furthermore, the knowledge of the component specific function has contributed to the reduction of many safety-related parts per component, in addition to ensuring the procurement of parts to the correct safety level. The use of qualified commercial grade parts and components with their lower cost and reasonable procurement lead time compared to their 10 CFR 21 counterparts has a pronounced economic effect on the utility balance sheets

Procurement in the Nuclear Industry, Quality, Safety and Decision Making

International Nuclear Information System (INIS)

Jakobsson, Marianne; Svenson, Ola; Salo, Ilkka

2010-03-01

The major purpose of the present study is partly to map and partly to make an analysis of the decision processes in the procurement routines in the nuclear industry in order to provide a basis for: 1. further development of safety inspections about procurements for Swedish Radiation Safety Authority 2. improvements of safety management in connection with procurement within a nuclear-power plant, 3 improvements of procurement routines in general in a nuclear power plant. The procurement processes at a nuclear power plant were analyzed from a decision theoretic perspective. Key staff at the plant was interviewed and written instructions as well as digitalized processes were used in the analysis. The results illustrate the most important moments during the procurement process with descriptions from interviews and documents. The staff at the nuclear power plant used a multi-attribute utility decision theory MAUT-inspired model in evaluation of alternatives and both compensatory (in which negative aspects can be compensated by positive aspects) and non-compensatory (in which certain 'pass' levels of attributes have to be exceeded for a choice) decision rules were used in the procurement process. Not surprising, nuclear safety was evaluated in a non-compensatory manner following regulatory criteria while costs were evaluated in trade-off compensatory rules, which means that a weakness in one consideration might be compensated by strength in another consideration. Thus, nuclear safety above the regulator's and law requirements are not integrated in a compensatory manner when procurement alternatives are evaluated. The nuclear plant assessed an organization's safety culture at an early stage of the purchasing process. A successful and a less successful procurement case were reported with the lessons learned from them. We find that the existing written instructions for purchase were well elaborated and adequate. There is a lack of personal resources when procurement teams

Understanding middle managers' influence in implementing patient safety culture.

Science.gov (United States)

Gutberg, Jennifer; Berta, Whitney

2017-08-22

The past fifteen years have been marked by large-scale change efforts undertaken by healthcare organizations to improve patient safety and patient-centered care. Despite substantial investment of effort and resources, many of these large-scale or "radical change" initiatives, like those in other industries, have enjoyed limited success - with practice and behavioural changes neither fully adopted nor ultimately sustained - which has in large part been ascribed to inadequate implementation efforts. Culture change to "patient safety culture" (PSC) is among these radical change initiatives, where results to date have been mixed at best. This paper responds to calls for research that focus on explicating factors that affect efforts to implement radical change in healthcare contexts, and focuses on PSC as the radical change implementation. Specifically, this paper offers a novel conceptual model based on Organizational Learning Theory to explain the ability of middle managers in healthcare organizations to influence patient safety culture change. We propose that middle managers can capitalize on their unique position between upper and lower levels in the organization and engage in 'ambidextrous' learning that is critical to implementing and sustaining radical change. This organizational learning perspective offers an innovative way of framing the mid-level managers' role, through both explorative and exploitative activities, which further considers the necessary organizational context in which they operate.

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

Science.gov (United States)

Withrow, Colleen A.; Reveley, Mary S.

2015-01-01

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

Nuclear safety and the European Community: Broadening perspectives

International Nuclear Information System (INIS)

Brinkhorst, L.J.

1992-01-01

The European Community's activities in harmonizing of regulations and practices in the field of nuclear safety are described. The issues of aid to Central and Eastern European countries as well as of public information, within this context, are discussed

Safety assessment, safety performance indicators at the Paks Nuclear Power Plant

International Nuclear Information System (INIS)

Baji, C.; Vamos, G.; Toth, J.

2001-01-01

The Paks Nuclear Power Plant has been using different methods of safety assessment (event analysis, self-assessment, probabilistic safety analysis), including performance indicators characterizing both operational and safety performance since the early years of operation of the plant. Regarding the safety performance, the indicators include safety system performance, number of scrams, release of radioactive materials, number of safety significant events, industrial safety indicator, etc. The Paks NPP also reports a set of ten indicators to WANO Performance Indicator Programme which, among others, include safety related indicators as well. However, a more systematic approach to structuring and trending safety indicators is needed so that they can contribute to the enhancement of the operational safety. A more comprehensive set of indicators and a systematic evaluation process was introduced in 1996. The performance indicators framework proposed by the IAEA was adapted to Paks in this year to further improve the process. Safety culture assessment and characterizing safety culture is part of the assessment process. (author)

Management of safety and safety culture at the NPPs of Ukraine

International Nuclear Information System (INIS)

Koltakov, Vladimir

2002-01-01

The report contains general aspects of safety and safety culture. The brief description of operational characteristics and basic indexes of atomic power plants at the Ukraine are represented. The information referring to structure of NPPs of Operation organization license-holder, safety responsibility of both Regulatory and Utility Bodies also is given. The main part of the report include seven sections: 1. Practical application of safety management models; 2. erspective on the relationship between safety management and safety culture; 3. The role of leadership in achieving high standards of safety; 4. Current and future challengers that impact on safety culture and safety management (e.g. the impact of competition, changing, economic and political circumstances, workforce demographics, etc.); 5. Key lessons learned from major events; 6. Practical applications of safety culture concepts (e.g. learning organizations, training staff communications, etc.); 7. dvance in human performance. Some of the main pending safety and safety culture problems that are necessary to achieve in the near future are mentioned

Safety culture: the concept and its practical application

International Nuclear Information System (INIS)

Edmondson, B.

1994-01-01

This paper draws together a number of topics concerned with safety culture: the first part of the paper describe the characteristics of an organisation giving rise to a good safety culture as suggested in INSAG-4. The second part of the paper examines sources of information on the characteristics of organisations giving rise to good and poor safety performance including a study into the causes of a number of recent severe accidents such as Clapham Junction and Piper Alpha. The final part of the paper describes the means by which safety culture within an organisation may be measured and therefore controlled. This enables an organisation to provide for a good safety culture and improve commercial performance by a process of continuous safety improvement eliminating the losses arising from poor safety standards. (author) 6 tabs., 5 refs

Progress of nuclear safety research, (1)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

Transformational Leadership: The Chief Nursing Officer Role in Leading Quality and Patient Safety.

Science.gov (United States)

Jones, Pam; Polancich, Shea; Steaban, Robin; Feistritzer, Nancye; Poe, Terri

This department column highlights leadership perspectives of quality and patient safety practice. The purpose of this article is to provide strategic direction for transformational quality and safety leadership as the chief nursing officer (CNO) within the academic medical center environment.

Part-time Jobs : What Women Want?

NARCIS (Netherlands)

Booth, A.L.; van Ours, J.C.

2010-01-01

Part-time jobs are popular among partnered women in many countries. In the Netherlands the majority of partnered working women have a part-time job. Our paper investigates, from a supply-side perspective, if the current situation of abundant part-time work in the Netherlands is likely to be a

Challenges and Enhancements to the Safety Culture of the Regulatory Body

International Nuclear Information System (INIS)

Niel, Jean-Christophe; Chevet, Pierre Franck; Sheron, Brian; Boyd, Michael; Carlsson, Lennart; Tiippana, Petteri; Burns, Stephen; Jamieson, Terry; Fuketa, Toyoshi; Rzentkowski, Greg; Weiss, Frank Peter; Le Guen, Bernard

2015-06-01

The workshop opened with presentations by both the NEA Director-General and the chair of the three committees directly involved with the safety culture of the regulatory body (SCRB). The opening session set the scene and gave an overview of the SCRB together with presentations and discussions on priorities and challenges. The main session focused on the principles of the SCRB, its implementation and the challenges and enhancements that are being raised and considered. The workshop concluded with a session that looked at findings and conclusions, the way forward and an agreed position on the SCRB. This document brings together the available presentations (slides) given at the workshop: 1 - Introduction: Challenges and Enhancements to the Safety Culture of the Regulatory Body (J-C. Niel); 2 - Thoughts on Safety Culture from a CSNI Perspective (B. Sheron); 3 - Radiological Protection Culture: CRPPH Work (M. Boyd); 4 - Challenges and Enhancements to Safety Culture of the Regulatory Body (L. Carlsson); 5 - Principles for the safety culture of the regulatory body (P. Tiippana); 6 - NRC's Internal Safety Culture: Successes, Challenges, and the Path Forward (S.G. Burns); 7 - Insights on the Canadian Nuclear Safety Commission's Safety Culture Journey (T. Jamieson); 8 - Lessons Learned from the Fukushima Dai-ichi Accident regarding Safety Culture of Regulatory Body (T. Fuketa); 9 - Challenges to Regulatory Bodies' safety culture (P-F. Chevet); 10 - Regulatory Safety Culture: International Perspective (G. Rzentkowski); 11 - Integration of Safety Research into Safety Culture Concepts (F-P. Weiss); 12 - Radiation Protection and Emergency Management Aspects: Culture drawn up by RP professionals (B. Le Guen); 13 - Closing session panel (L. Carlsson)

Construction of Earthquake - Proof Safety Evaluaiton Methods for Pipes with Wall Thinning

International Nuclear Information System (INIS)

Miyano, H.; Sekimura, N.; Takizawa, M.; Mastumoto, M.

2012-01-01

Since the Fukushima Dai-ichi accident, the importance of 'system safety' has been recognized anew. Particularly, system safety assessment of plants in operation from the various degradation perspectives, specifically, transition of time is very important. Accordingly, assessment on degradation will focus on the degradation of functions with passing of time, combined with the changes in the safety standards and concept of safety. Reliability assessment will be made on the consolidation of important functions, and not on individual components. The boundary function of the system will be one of the focus of this study. For the purpose of reliability assessment on the system by evaluating and quantifying the damage (or rupture) risk of piping - method for confirming the integrity of the system through the assessment on the damage (rupture) risk of the system when an external force caused by an earthquake is applied (the system is sound if the damage (rupture) risk is small) was examined on the basis of the prediction results for each of the parts in pipe wall thinning. In the next phase, the prediction results will be verified by tests, whereby, the improvement in reliability will be confirmed, and a combined assessment will be made in relation to the degradation factors of other systems. 'System safety' assessment method of plants in operation will be developed in a manner where a comprehensive assessment on the safety of the entire plant can be made. Specifically, the changes in the conditions, such as material degradations that degrade performance will be assessed on the entire system. Whereby, the risk caused by functional failure (damage) due to degradation will be regarded as the total of risk in the assessment. A framework on safety assessment will be structured, where the degree of safety will be measured by functional degradation, taking into consideration the changes made in the safety standards up to present. (author)

Radiation safety in nuclear medicine procedures

International Nuclear Information System (INIS)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun

2017-01-01

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed

Radiation safety in nuclear medicine procedures

Energy Technology Data Exchange (ETDEWEB)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

2017-03-15

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

Pacific Northwest Laboratory annual report for 1981 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. Part 5. Environmental and occupational protection, assessment, and engineering

International Nuclear Information System (INIS)

Glass, W.A.

1982-02-01

This report describes research in environment, health, and safety conducted during fiscal year 1981. The five parts of the report are oriented to particular segments of the program. Parts 1 to 4 report on research performed for the DOE Office of Health and Environmental Research in the Office of Energy Research. Part 5 reports progress on all research performed for the Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. The parts are: Part 1: Biomedical Sciences under Program Manager, H. Drucker; Part 2: Ecological Sciences, under Program Manager, B.E. Vaughan; Part 3: Atmospheric Sciences under Program Manager, C.E. Elderkin; Part 4: Physical Sciences under Program Manager, J.M. Nielsen; and Part 5: Environmental and Occupational Protection, Assessment, and Engineering under Program Managers, D.L. Hessel, S. Marks, and W.A. Glass

Nuclear safety review for the year 2000

International Nuclear Information System (INIS)

2001-06-01

The nuclear safety review for the year 2000 reports on worldwide efforts to strengthen nuclear and radiation safety, including radioactive waste safety. It is in three parts: Part 1 describes those events in 2000 that have, or may have, significance for nuclear, radiation and waste safety worldwide. It includes developments such as new initiatives in international cooperation, events of safety significance and events that may be indicative of trends in safety; Part 2 describes some of the IAEA efforts to strengthen international co-operation in nuclear, radiation and waste safety during 2000. It covers legally binding international agreements, non-binding safety standards, and provisions for the application of safety standards. This is done in a very brief manner, because these issues are addressed in more detail in the Agency's Annual Report for 2000; Part 3 presents a brief look ahead to some issues that are likely to be prominent in the coming year(s). The topics covered were selected by the IAEA Secretariat on the basis of trends observed in recent years, account being taken of planned or expected future developments. A draft of the Nuclear Safety Review for the Year 2000 was presented to the March 2001 session of the IAEA Board of Governors. This final version has been prepared taking account of the discussion in the Board. In some places, information has been added to describe developments early in 2001 that were considered pertinent to the discussion of events during 2000. In such cases, a note containing the more recent information has been provided in the form of a footnote

Comments on nuclear reactor safety in Ontario

International Nuclear Information System (INIS)

1987-08-01

The Chalk River Technicians and Technologists Union representing 500 technical employees at the Chalk River Nuclear Laboratories of AECL submit comments on nuclear reactor safety to the Ontario Nuclear Safety Review. Issues identified by the Review Commissioner are addressed from the perspective of both a labour organization and experience in the nuclear R and D field. In general, Local 1568 believes Ontario's CANDU nuclear reactors are not only safe but also essential to the continued economic prosperity of the province

National machine guarding program: Part 2. Safety management in small metal fabrication enterprises

Science.gov (United States)

Yamin, Samuel C.; Brosseau, Lisa M.; Xi, Min; Gordon, Robert; Most, Ivan G.; Stanley, Rodney

2015-01-01

Background Small manufacturing businesses often lack important safety programs. Many reasons have been set forth on why this has remained a persistent problem. Methods The National Machine Guarding Program (NMGP) was a nationwide intervention conducted in partnership with two workers' compensation insurers. Insurance safety consultants collected baseline data in 221 business using a 33‐question safety management audit. Audits were completed during an interview with the business owner or manager. Results Most measures of safety management improved with an increasing number of employees. This trend was particularly strong for lockout/tagout. However, size was only significant for businesses without a safety committee. Establishments with a safety committee scored higher (55% vs. 36%) on the safety management audit compared with those lacking a committee (P management programs were frequently absent. A safety committee appears to be a more important factor than business size in accounting for differences in outcome measures. Am. J. Ind. Med. 58:1184–1193, 2015. © 2015 The Authors. American Journal of Industrial Medicine Published by Wiley Periodicals, Inc. PMID:26345591

Implementing the Comprehensive Unit-Based Safety Program (CUSP) to Improve Patient Safety in an Academic Primary Care Practice.

Science.gov (United States)

Pitts, Samantha I; Maruthur, Nisa M; Luu, Ngoc-Phuong; Curreri, Kimberly; Grimes, Renee; Nigrin, Candace; Sateia, Heather F; Sawyer, Melinda D; Pronovost, Peter J; Clark, Jeanne M; Peairs, Kimberly S

2017-11-01

While there is growing awareness of the risk of harm in ambulatory health care, most patient safety efforts have focused on the inpatient setting. The Comprehensive Unit-based Safety Program (CUSP) has been an integral part of highly successful safety efforts in inpatient settings. In 2014 CUSP was implemented in an academic primary care practice. As part of CUSP implementation, staff and clinicians underwent training on the science of safety and completed a two-question safety assessment survey to identify safety concerns in the practice. The concerns identified by team members were used to select two initial safety priorities. The impact of CUSP on safety climate and teamwork was assessed through a pre-post comparison of results on the validated Safety Attitudes Questionnaire. Ninety-six percent of staff completed science of safety training as part of CUSP implementation, and 100% of staff completed the two-question safety assessment. The most frequently identified safety concerns were related to medications (n = 11, 28.2), diagnostic testing (n = 9, 25), and communication (n = 5, 14). The CUSP team initially prioritized communication and infection control, which led to standardization of work flows within the practice. Six months following CUSP implementation, large but nonstatistically significant increases were found for the percentage of survey respondents who reported knowledge of the proper channels for questions about patient safety, felt encouraged to report safety concerns, and believed that the work setting made it easy to learn from the errors of others. CUSP is a promising tool to improve safety climate and to identify and address safety concerns within ambulatory health care. Copyright © 2017 The Joint Commission. Published by Elsevier Inc. All rights reserved.

Human Factors and Safety Culture in Maritime Safety (revised

Directory of Open Access Journals (Sweden)

Heinz Peter Berg

2013-09-01

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

Safety at CERN

CERN Document Server

2009-01-01

Safety is an integral part of our working lives, and should be in our minds whatever job we do at CERN. Ultimately, safety is the responsibility of the Director General – your safety is my concern. That’s why I have this week appointed a new Safety Policy Committee (SAPOCO) that reflects the new Organizational structure of CERN. CERN’s Staff Rules and Regulations clearly lay out in chapter 3 the scope of safety at CERN as well as my responsibilities and yours in safety matters. At CERN, safety is considered in the broadest sense, encompassing occupational Health and Safety, environmental protection, and the safety of equipment and installations. It is my responsibility to put appropriate measures in place to ensure that these conditions are met. And it is the responsibility of us all to ensure that we are fully conversant with safety provisions applicable in our areas of work and that we comply with them. The appointment of a n...

Safe operation of nuclear power plants - Is safety culture an adequate management method?

International Nuclear Information System (INIS)

Piirto, A.

2012-01-01

One of the characteristics of a good safety culture is a definable commitment to the improvement of safety behaviours and attitudes at all organisational levels. A second characteristic of an organisation with excellent safety culture is free and open communication. The general understanding has been that safety culture is a part of organisation culture. In addition to safety culture thinking, proactive programmes and displays of proactive work to improve safety are required. This work needs to include, qt a minimum, actions aiming at reducing human errors, the development of human error prevention tools, improvements in training, and the development of working methods and the organisation's activities. Safety depends not only on the technical systems, but also on the organisation. There is a need for better methods and tools for organisational assessment and development. Today there is universal acceptance of the significant impact that management and organisational factors have over the safety significance of complex industrial installations such as nuclear power plants. Many events with significant economic and public impact had causes that have been traced to management deficiencies. The objective of this study is development of new methods to increase safety of nuclear power plant operation. The research has been limited to commercial nuclear power plants that are intended for electrical power generation in Finland. Their production activities, especially operation and maintenance, are primarily reviewed from a safety point of view, as well as human performance and organisational factors perspective. This defines the scope and focus of the study. The research includes studies related to knowledge management and tacit knowledge in the project management context and specific studies related to transfer of tacit knowledge in the maintenance organization and transfer of tacit knowledge between workers of old generation and young generation. The empirical results

Safe operation of nuclear power plants - Is safety culture an adequate management method?

Energy Technology Data Exchange (ETDEWEB)

Piirto, A.

2012-07-01

One of the characteristics of a good safety culture is a definable commitment to the improvement of safety behaviours and attitudes at all organisational levels. A second characteristic of an organisation with excellent safety culture is free and open communication. The general understanding has been that safety culture is a part of organisation culture. In addition to safety culture thinking, proactive programmes and displays of proactive work to improve safety are required. This work needs to include, qt a minimum, actions aiming at reducing human errors, the development of human error prevention tools, improvements in training, and the development of working methods and the organisation's activities. Safety depends not only on the technical systems, but also on the organisation. There is a need for better methods and tools for organisational assessment and development. Today there is universal acceptance of the significant impact that management and organisational factors have over the safety significance of complex industrial installations such as nuclear power plants. Many events with significant economic and public impact had causes that have been traced to management deficiencies. The objective of this study is development of new methods to increase safety of nuclear power plant operation. The research has been limited to commercial nuclear power plants that are intended for electrical power generation in Finland. Their production activities, especially operation and maintenance, are primarily reviewed from a safety point of view, as well as human performance and organisational factors perspective. This defines the scope and focus of the study. The research includes studies related to knowledge management and tacit knowledge in the project management context and specific studies related to transfer of tacit knowledge in the maintenance organization and transfer of tacit knowledge between workers of old generation and young generation. The empirical

Assessment of Contributions to Patient Safety Knowledge by the Agency for Healthcare Research and Quality-Funded Patient Safety Projects

Science.gov (United States)

Sorbero, Melony E S; Ricci, Karen A; Lovejoy, Susan; Haviland, Amelia M; Smith, Linda; Bradley, Lily A; Hiatt, Liisa; Farley, Donna O

2009-01-01

Objective To characterize the activities of projects funded in Agency for Healthcare Research and Quality (AHRQ)' patient safety portfolio and assess their aggregate potential to contribute to knowledge development. Data Sources Information abstracted from proposals for projects funded in AHRQ' patient safety portfolio, information on safety practices from the AHRQ Evidence Report on Patient Safety Practices, and products produced by the projects. Study Design This represented one part of the process evaluation conducted as part of a longitudinal evaluation based on the Context–Input–Process–Product model. Principal Findings The 234 projects funded through AHRQ' patient safety portfolio examined a wide variety of patient safety issues and extended their work beyond the hospital setting to less studied parts of the health care system. Many of the projects implemented and tested practices for which the patient safety evidence report identified a need for additional evidence. The funded projects also generated a substantial body of new patient safety knowledge through a growing number of journal articles and other products. Conclusions The projects funded in AHRQ' patient safety portfolio have the potential to make substantial contributions to the knowledge base on patient safety. The full value of this new knowledge remains to be confirmed through the synthesis of results. PMID:21456108

Periodic safety analyses; Les essais periodiques

Energy Technology Data Exchange (ETDEWEB)

Gouffon, A; Zermizoglou, R

1990-12-01

The IAEA Safety Guide 50-SG-S8 devoted to 'Safety Aspects of Foundations of Nuclear Power Plants' indicates that operator of a NPP should establish a program for inspection of safe operation during construction, start-up and service life of the plant for obtaining data needed for estimating the life time of structures and components. At the same time the program should ensure that the safety margins are appropriate. Periodic safety analysis are an important part of the safety inspection program. Periodic safety reports is a method for testing the whole system or a part of the safety system following the precise criteria. Periodic safety analyses are not meant for qualification of the plant components. Separate analyses are devoted to: start-up, qualification of components and materials, and aging. All these analyses are described in this presentation. The last chapter describes the experience obtained for PWR-900 and PWR-1300 units from 1986-1989.

Correlation of Safety Culture Attributes in Construction Industry

Directory of Open Access Journals (Sweden)

Pervez Shaikh

2013-07-01

Full Text Available The importance of construction industry can not be overemphasized because it is one of the biggest contributors toward economic activities of a country. It employs a countable number of workforce and it is prone to accidents, incidents, hazards and disasters, therefore, the safety factor is equally important. The current research explores safety culture in the perspective of its important attributes. The EFQM (European Foundation for Quality Management is taken as the bases for finding the ways and means of safety culture improvement of the construction industry. The correlation of pattern of responses is found for every attribute of the safety culture and the interrelationships and strengths are worked out to detect the involvement of the attribute.

Safety Culture Monitoring: How to Assess Safety Culture in Real Time?

International Nuclear Information System (INIS)

Zronek, B.; Maryska, J.; Treslova, L.

2016-01-01

Do you know what is current level of safety culture in your company? Are you able to follow trend changes? Do you know what your recent issues are? Since safety culture is understood as vital part of nuclear industry daily life, it is crucial to know what the current level is. It is common to perform safety culture survey or ad hoc assessment. This contribution shares Temelin NPP, CEZ approach how to assess safety culture level permanently. Using behavioral related outputs of gap solving system, observation program, dedicated surveys, regulatory assessment, etc., allows creating real time safety culture monitoring without the need to perform any other activities. (author)

Neurovirulence safety testing of mumps vaccines--historical perspective and current status.

Science.gov (United States)

Rubin, S A; Afzal, M A

2011-04-05

Many live, attenuated viral vaccines are derived from wild type viruses with known neurovirulent properties. To assure the absence of residual neurotoxicity, pre-clinical neurovirulence safety testing of candidate vaccines is performed. For mumps virus, a highly neurotropic virus, neurovirulence safety testing is performed in monkeys. However, laboratory studies suggest an inability of this test to correctly discern among virus strains of varying neurovirulence potential in man, and, further, some vaccines found to be neuroattenuated in monkeys were later found to be neurovirulent in humans when administered in large numbers. Over the past decade, concerted efforts have been made to replace monkey-based neurovirulence safety testing with more informative, alternative methods. This review summarizes the current status of mumps vaccine neurovirulence safety testing and insights into models currently approved and those under development. Published by Elsevier Ltd.

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

Population-based health promotion perspective for older driver safety: Conceptual framework to intervention plan

Science.gov (United States)

Classen, Sherrilene; Lopez, Ellen DS; Winter, Sandra; Awadzi, Kezia D; Ferree, Nita; Garvan, Cynthia W

2007-01-01

The topic of motor vehicle crashes among the elderly is dynamic and multi-faceted requiring a comprehensive and synergistic approach to intervention planning. This approach must be based on the values of a given population as well as health statistics and asserted through community, organizational and policy strategies. An integrated summary of the predictors (quantitative research), and views (qualitative research) of the older drivers and their stakeholders, does not currently exist. This study provided an explicit socio-ecological view explaining the interrelation of possible causative factors, an integrated summary of these causative factors, and empirical guidelines for developing public health interventions to promote older driver safety. Using a mixed methods approach, we were able to compare and integrate main findings from a national crash dataset with perspectives of stakeholders. We identified: 11 multi-causal factors for safe elderly driving; the importance of the environmental factors - previously underrated in the literature- interacting with behavioral and health factors; and the interrelatedness among many socio-ecological factors. For the first time, to our knowledge, we conceptualized the fundamental elements of a multi-causal health promotion plan, with measurable intermediate and long-term outcomes. After completing the detailed plan we will test the effectiveness of this intervention on multiple levels. PMID:18225470

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

PReSaFe: A model of barriers and facilitators to patients providing feedback on experiences of safety.

Science.gov (United States)

De Brún, Aoife; Heavey, Emily; Waring, Justin; Dawson, Pamela; Scott, Jason

2017-08-01

The importance of involving patients in reporting on safety is increasingly recognized. Whilst studies have identified barriers to clinician incident reporting, few have explored barriers and facilitators to patient reporting of safety experiences. This paper explores patient perspectives on providing feedback on safety experiences. Patients (n=28) were invited to take part in semi-structured interviews when given a survey about their experiences of safety following hospital discharge. Transcripts were thematically analysed using NVivo10. Patients were recruited from four hospitals in the UK. Three themes were identified as barriers and facilitators to patient involvement in providing feedback on their safety experiences. The first, cognitive-cultural, found that whilst safety was a priority for most, some felt the term was not relevant to them because safety was the "default" position, and/or because safety could not be disentangled from the overall experience of care. The structural-procedural theme indicated that reporting was facilitated when patients saw the process as straightforward, but that disinclination or perceived inability to provide feedback was a barrier. Finally, learning and change illustrated that perception of the impact of feedback could facilitate or inhibit reporting. When collecting patient feedback on experiences of safety, it is important to consider what may help or hinder this process, beyond the process alone. We present a staged model of prerequisite barriers and facilitators and hypothesize that each stage needs to be achieved for patients to provide feedback on safety experiences. Implications for collecting meaningful data on patients' safety experiences are considered. © 2016 The Authors. Health Expectations Published by John Wiley & Sons Ltd.

The safety evaluation guide for laboratories and plants a tool for enhancing safety

International Nuclear Information System (INIS)

Lhomme, Veronique; Daubard, Jean-Paul

2013-01-01

The Institute for Radioprotection and Nuclear Safety (IRSN) acts as technical support for the French government Authorities competent in nuclear safety and radiation protection for civil and defence activities. In this frame, the Institute's performs safety assessments of the safety cases submitted by operators to these Authorities for each stage in the life cycle of a nuclear facility, including dismantling operations, which is subjected to a licensing procedure. In the fuel cycle field, this concerns a large variety of facilities. Very often, depending on facilities and on safety cases, safety assessment to be performed is multidisciplinary and involves the supervisor in charge of the facility and several safety experts, particularly to cover the whole set of risks (criticality, exposure to radiation, fire, handling, containment, human and organisational factors...) encountered during facility's operations. Taking these into account, and in order to formalize the assessment process of the fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management, the 'Plants, Laboratories, Transports and Waste Safety' Division of IRSN has developed an internal guide, as a tool: - To present the methodological framework, and possible specificities, for the assessment according to the 'Defence in Depth Concept' (Part 1); - To provide key questions associated to the necessary contradictory technical review of the safety cases (Part 2); - To capitalise on experience on the basis of technical examples (coming from incident reports, previous safety assessments...) demonstrating the questioning (Part 3). The guide is divided in chapters, each dedicated to a type of risk (dissemination of radioactive material, external or internal exposure from ionising radiation, criticality, radiolysis mechanisms, handling operations, earthquake, human or organisational factors...) or to a type

MODERN AND PERSPECTIVE ON-BOARD NTELLECTUAL TRANSPORT SYSTEMS

Directory of Open Access Journals (Sweden)

V. Topalidi

2011-01-01

Full Text Available For the purpose of systematization of modern and perspective intellectual transport sides systems (ITВS it is suggested their classification and planning of new ITВS for realization of safety control of vehicle technical condition.

Guidelines for nuclear reactor equipments safety-analysis

International Nuclear Information System (INIS)

1978-01-01

The safety analysis in approving the applications for nuclear reactor constructions (or alterations) is performed by the Committee on Examination of Reactor Safety in accordance with various guidelines prescribed by the Atomic Energy Commission. In addition, the above Committee set forth its own regulations for the safety analysis on common problems among various types of nuclear reactors. This book has collected and edited those guidelines and regulations. It has two parts: Part I includes the guidelines issued to date by the Atomic Energy Commission: and Part II - regulations of the Committee. Part I has collected 8 categories of guidelines which relate to following matters: nuclear reactor sites analysis guidelines and standards for their applications; standard exposure dose of plutonium; nuclear ship operation guidelines; safety design analysis guidelines for light-water type, electricity generating nuclear reactor equipments; safety evaluation guidelines for emergency reactor core cooling system of light-water type power reactors; guidelines for exposure dose target values around light-water type electricity generating nuclear reactor equipments, and guidelines for evaluation of above target values; and meteorological guidelines for the safety analysis of electricity generating nuclear reactor equipments. Part II includes regulations of the Committee concerning - the fuel assembly used in boiling-water type and in pressurized-water type reactors; techniques of reactor core heat designs, etc. in boiling-water reactors; and others

Building the safety case for a hypothetical underground repository in crystalline rock. Final report. Vol. 2. Safety file

International Nuclear Information System (INIS)

Biurrun, E.; Engelmann, H.J.; Jobmann, M.; Lommerzheim, A.; Popp, W.; Frentz, R.R. v.; Wahl, A.

1996-10-01

The study was intended as a desk simulation of the process of preparing a licensing application for a deep repository for spent fuel and high level waste in crystalline rock. After clarifying of organizational aspects of table of contents specifying all aspects in a safety life for license application were considered. The volume II is subdivided in two parts. Part A describes the general information, waste description, site characteristics, disposal facility design, reporitory construction and operation, quality assurance, operational safety, repository closure, organization and financial aspects, and long-term safety assessment. Part B deals with the impact of retrievability. (DG)

Consumer trust in food safety--a multidisciplinary approach and empirical evidence from Taiwan.

Science.gov (United States)

Chen, Mei-Fang

2008-12-01

Food scandals that happened in recent years have increased consumers' risk perceptions of foods and decreased their trust in food safety. A better understanding of the consumer trust in food safety can improve the effectiveness of public policy and allow the development of the best practice in risk communication. This study proposes a research framework from a psychometric approach to investigate the relationships between the consumer's trust in food safety and the antecedents of risk perceptions of foods based on a reflexive modernization perspective and a cultural theory perspective in the hope of benefiting the future empirical study. The empirical results from a structural equation modeling analysis of Taiwan as a case in point reveal that this research framework based on a multidisciplinary perspective can be a valuable tool for a growing understanding of consumer trust in food safety. The antecedents in the psychometric research framework comprised reflexive modernization factors and cultural theory factors have all been supported in this study except the consumer's perception of pessimism toward food. Moreover, the empirical results of repeated measures analysis of variance give more detailed information to grasp empirical implications and to provide some suggestions to the actors and institutions involved in the food supply chain in Taiwan.

Plant designer's view of the operator's role in nuclear plant safety

International Nuclear Information System (INIS)

Corcoran, W.R.; Church, J.F.; Cross, M.T.; Porter, N.J.

1981-01-01

The nuclear plant operator's role supports the design assumptions and equipment with four functional tasks. He must set up th plant for predictable response to disturbances, operate the plant so as to minimize the likelihood and severity of event initiators, assist in accomplishing the safety functions, and feed back operating experiences to reinforce or redefine the safety analyses' assumptions. The latter role enhances the operator effectiveness in the former three roles. The Safety Level Concept offers a different perspective that enables the operator to view his roles in nuclear plant safety. This paper outlines the operator's role in nuclear safety and classifies his tasks using the Safety Level Concept

Nordic perspectives on safety management in high reliability organizations: Theory and applications

International Nuclear Information System (INIS)

Svenson, Ola; Salo, I.; Sjerve, A.B.; Reiman, T.; Oedewald, P.

2006-04-01

The chapters in this volume are written on a stand-alone basis meaning that the chapters can be read in any order. The first 4 chapters focus on theory and method in general with some applied examples illustrating the methods and theories. Chapters 5 and 6 are about safety management in the aviation industry with some additional information about incident reporting in the aviation industry and the health care sector. Chapters 7 through 9 cover safety management with applied examples from the nuclear power industry and with considerable validity for safety management in any industry. Chapters 10 through 12 cover generic safety issues with examples from the oil industry and chapter 13 presents issues related to organizations with different internal organizational structures. Although the many of the chapters use a specific industry to illustrate safety management, the messages in all the chapters are of importance for safety management in any high reliability industry or risky activity. The interested reader is also referred to, e.g., a document by an international NEA group (SEGHOF), who is about to publish a state of the art report on Systematic Approaches to Safety Management (cf., CSNI/NEA/SEGHOF, home page: www.nea.fr). (au)

Nordic perspectives on safety management in high reliability organizations: Theory and applications

Energy Technology Data Exchange (ETDEWEB)

Svenson, Ola; Salo, I; Sjerve, A B; Reiman, T; Oedewald, P [Stockholm Univ. (Sweden)

2006-04-15

The chapters in this volume are written on a stand-alone basis meaning that the chapters can be read in any order. The first 4 chapters focus on theory and method in general with some applied examples illustrating the methods and theories. Chapters 5 and 6 are about safety management in the aviation industry with some additional information about incident reporting in the aviation industry and the health care sector. Chapters 7 through 9 cover safety management with applied examples from the nuclear power industry and with considerable validity for safety management in any industry. Chapters 10 through 12 cover generic safety issues with examples from the oil industry and chapter 13 presents issues related to organizations with different internal organizational structures. Although the many of the chapters use a specific industry to illustrate safety management, the messages in all the chapters are of importance for safety management in any high reliability industry or risky activity. The interested reader is also referred to, e.g., a document by an international NEA group (SEGHOF), who is about to publish a state of the art report on Systematic Approaches to Safety Management (cf., CSNI/NEA/SEGHOF, home page: www.nea.fr). (au)

Idaho Safety Manual.

Science.gov (United States)

Idaho State Dept. of Education, Boise. Div. of Vocational Education.

This manual is intended to help teachers, administrators, and local school boards develop and institute effective safety education as a part of all vocational instruction in the public schools of Idaho. This guide is organized in 13 sections that cover the following topics: introduction to safety education, legislation, levels of responsibility,…

Nuclear Safety Review for the Year 2003

International Nuclear Information System (INIS)

2004-08-01

The Nuclear Safety Review reports on worldwide efforts to strengthen nuclear, radiation and transport safety and the safety of radioactive waste management. In line with the suggestions made by the Board of Governors in March 2002, the first part is more analytical and less descriptive. This short analytical overview is supported by a second part, which describes significant safety related events and issues worldwide during 2003. A Draft Nuclear Safety Review for the Year 2003 was submitted to the March 2004 session of the Board of Governors in document GOV/2004/3. The final version of the Nuclear Safety Review for the Year 2003 was prepared in the light of the discussion by the Board.

Safety and Mission Assurance: A NASA Perspective

Science.gov (United States)

Higginbotham, Scott A.

2016-01-01

Manned spaceflight is an incredibly complex and inherently risky human endeavor. As the result of the lessons learned through years of triumph and tragedy, the National Aeronautics and Space Administration (NASA) has embraced a comprehensive and integrated approach to the challenge of ensuring safety and mission success. This presentation will provide an overview of some of the techniques employed in this effort, with a focus on the processing operations performed at the Kennedy Space Center (KSC).

Practice and innovation on safety management of Haiyang Nuclear Power Project

International Nuclear Information System (INIS)

Wei Guohu

2011-01-01

From the perspective of owner, this article has introduced the safety management model and practice of Haiyang Nuclear Power Project, one of AP1000 Self-reliance Program supporting projects of China. And the article has summarized characteristics of the safety management of Haiyang Project for reference and communication with nuclear or other projects. (author)

Additional safety assessments. Report by the Nuclear Safety Authority - December 2011

International Nuclear Information System (INIS)

2011-12-01

The first part of this voluminous report proposes an assessment of targeted audits performed in French nuclear installations (water pressurized reactors on the one hand, laboratories, factories and waste and dismantling installations on the other hand) on issues related to the Fukushima accident. The examined issues were the protection against flooding and against earthquake, and the loss of electricity supplies and of cooling sources. The second part addresses the additional safety assessments of the reactors and the European resistance tests: presentation of the French electronuclear stock, earthquake, flooding and natural hazards (installation sizing, safety margin assessment), loss of electricity supplies and cooling systems, management of severe accidents, subcontracting conditions. The third part addresses the same issues for nuclear installations other than nuclear power reactors

Safety aspects of neutron noise diagnostics and loose parts monitoring in WWER reactors

International Nuclear Information System (INIS)

Por, G.

1997-01-01

In this paper our aim is to give very short introduction on different types of well selected noise diagnostics methods and then mentioning their occurrence in WWER reactors we analyze what impact they might have to operational safety and for ageing (which also affects on safety of the installations). We do not deny, that one of our main aim is to call the attention of management staff of NPP, which deals with safety, safety culture, maintenance and operation proving, that such methods and system can give not only benefit to economy but also impact on safety of nuclear installations. 14 refs, 6 figs

Progress of nuclear safety research, (2)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

Safety rule evolution for future LMFBRs

International Nuclear Information System (INIS)

Justin, F.; Wiesner

1986-06-01

After safety rules for operating reactors and for built reactors in France and Germany, this report presents the main points of the safety rules for future reactors. It is generally agreed that future LMFBRs will have to show the same safety level as other commercial nuclear power plants. The demonstration is to be partly based on deterministic criteria, or ''safety rules'', and partly on risk considerations, for rare events. In that respect, a high effort on preventive measures, especially to reinforce the reliability of essential safety functions (shutdown, decay heat removal) could be sufficient, if all conditions are considered. So the containment of a hypothetical core disruptive accident is no longer required. Nevertheless, low probability events gave some feedback on the SPX.2 design

Ink dating part II: Interpretation of results in a legal perspective.

Science.gov (United States)

Koenig, Agnès; Weyermann, Céline

2018-01-01

The development of an ink dating method requires an important investment of resources in order to step from the monitoring of ink ageing on paper to the determination of the actual age of a questioned ink entry. This article aimed at developing and evaluating the potential of three interpretation models to date ink entries in a legal perspective: (1) the threshold model comparing analytical results to tabulated values in order to determine the maximal possible age of an ink entry, (2) the trend tests that focusing on the "ageing status" of an ink entry, and (3) the likelihood ratio calculation comparing the probabilities to observe the results under at least two alternative hypotheses. This is the first report showing ink dating interpretation results on a ballpoint be ink reference population. In the first part of this paper three ageing parameters were selected as promising from the population of 25 ink entries aged during 4 to 304days: the quantity of phenoxyethanol (PE), the difference between the PE quantities contained in a naturally aged sample and an artificially aged sample (R NORM ) and the solvent loss ratio (R%). In the current part, each model was tested using the three selected ageing parameters. Results showed that threshold definition remains a simple model easily applicable in practice, but that the risk of false positive cannot be completely avoided without reducing significantly the feasibility of the ink dating approaches. The trend tests from the literature showed unreliable results and an alternative had to be developed yielding encouraging results. The likelihood ratio calculation introduced a degree of certainty to the ink dating conclusion in comparison to the threshold approach. The proposed model remains quite simple to apply in practice, but should be further developed in order to yield reliable results in practice. Copyright © 2017 The Chartered Society of Forensic Sciences. Published by Elsevier B.V. All rights reserved.

Enhancement of Nuclear Safety in Korea: A Regulatory Perspective

International Nuclear Information System (INIS)

Chung, K.Y.

2016-01-01

In the aftermath of Fukushima Daiichi accident in 2011 Korean regulatory body immediately performed special inspections on nuclear power plants (NPPs) and a research reactor in Korea, and issued an enforcement order for the licensees to implement fifty Fukushima action items to address the safety issues identified by the inspections. Subsequently, the licensees have established the implementation plans for resolution of the action items. By the implementation of the action items, the possibility of severe accident due to the extreme hazards has been greatly reduced and the capabilities to mitigate the severe accident, should it occur, have been upgraded. To improve the consistency and predictability of the regulation on severe accidents, Nuclear Safety and Security Commission (NSSC) the regulatory body in Korea, is revising the regulatory framework for severe accidents. The new framework will require the licensee to enhance the capabilities for prevention and mitigation of severe accidents in view of the defence in depth principle, to assess the radiological effects from the severe accidents, and to improve current accident management procedures and guidelines necessary for the prevention and mitigation of severe accidents. This rulemaking also considers the safety principles provided by the IAEA Vienna Declaration in 2015, which require new NPPs to prevent large radioactive releases. (author)

Current status of safety analysis report for ANPP

International Nuclear Information System (INIS)

Amirjanyan, A.

1999-01-01

Current situation concerning Armenian NPP safety analysis report is considered within the frame of accepted safety practice. Licensing procedure is being developed. Technical support group was established in the Armenian Nuclear Regulatory Authority (ANRA). The task of the group is to study modern methods of NPP in depth safety analysis for technical assistance for the ANRA, and perform independent safety assessments. ANRA will be obliged to demand assistance from various foreign organisations for preparation of different parts of the Safety Analysis Report like determination though certain parts can be prepared in Armenia

Research notes : are safety corridors really safe? Evaluation of the corridor safety improvement program.

Science.gov (United States)

1998-08-26

High accident frequencies on Oregons highway corridors are of concern to the Oregon Department of Transportation (ODOT). : ODOT adopted the Corridor Safety Improvement Program as part of an overall program of safety improvements using federal and ...

77 FR 51943 - Procedures for Safety Investigations

Science.gov (United States)

2012-08-28

... rule, Procedures for Safety Investigations, which published July 27, 2012 in the Federal Register, 77... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1708 Procedures for Safety Investigations AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Proposed rule; extension of comment period...

Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1 (Spanish Edition); Marco gubernamental, juridico y regulador para la seguridad. Requisitos de Seguridad Generales. Parte 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-11-15

The objective of this publication is to establish requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered.

Safety cost management in construction companies: A proposal classification.

Science.gov (United States)

López-Alonso, M; Ibarrondo-Dávila, M P; Rubio, M C

2016-06-16

Estimating health and safety costs in the construction industry presents various difficulties, including the complexity of cost allocation, the inadequacy of data available to managers and the absence of an accounting model designed specifically for safety cost management. Very often, the costs arising from accidents in the workplace are not fully identifiable due to the hidden costs involved. This paper reviews some studies of occupational health and safety cost management and proposes a means of classifying these costs. We conducted an empirical study in which the health and safety costs of 40 construction worksites are estimated. A new classification of the health and safety cost and its categories is proposed: Safety and non-safety costs. The costs of the company's health and safety policy should be included in the information provided by the accounting system, as a starting point for analysis and control. From this perspective, a classification of health and safety costs and its categories is put forward.

Safety issues in urban transit facilities for hydrogen-fueled buses

International Nuclear Information System (INIS)

Hay, R.H.; Ducharme, P.

2004-01-01

'Full text:' The Canadian Transportation Fuel Cell Alliance (CTFCA), created by the Canadian Government as part of its 2000 Climate Change Action Plan, has commissioned MARCON-DDM's Hydrogen Intervention Team (HIT) to provide a roadmap for urban transit systems that wish to move to hydrogen fuel cell-powered bus fleets. HIT is currently in the process of gathering information from hydrogen technology providers, bus manufacturers, fuelling system providers and urban transit systems in Canada, the US and Europe. In September, HIT will be in a position to provide a hands-on perspective of the introduction of fuel-cell buses in the Canadian environment. Part of the process of adding hydrogen-fueled busses to urban transit systems involves phasing in the new technology to minimize the economic cost. This involves substituting hydrogen buses into the normal bus procurement life cycle and maximizing the use of existing facilities for garaging, maintenance and fueling. Using a schematic outline of an urban transit system, this presentation will outline the safety issues specific to hydrogen in such systems, particularly for garaging, maintenance and fueling components. It will then outline how safety of these component is addressed in current and proposed codes, standards and recommended practices. Based on these requirements the impact of the introduction of hydrogen-fueled buses on each component of the transit system will be addressed in terms of the adaptations of current facilities and practices or the requirements for new facilities and practices. (author)

Conceptualizing Multicultural Perspective Taking Skills

Science.gov (United States)

2007-11-01

34 ( Fetterman , 1989, p. 27). This perspective highlights the cognitive aspects of culture at the exclusion of behavior. Kroeber and Parsons (1958... Fetterman , 1989; Kluckhohn, 1951; Ong, 1987). Sociologists have a similar perspective on culture and highlight that it is transmitted, is created, is...knowledge ( Fetterman , 1989). Cognition provides the cultural lens with acuity. In this regard, culture is conceptualized, in part, as a schema (organized

Agricultural occupational health and safety perspectives among Latino-American youth.

Science.gov (United States)

Perla, M E; Iman, Esmeralda; Campos, Leticia; Perkins, Alexandra; Liebman, Amy K; Miller, Mary E; Beaudet, Nancy J; Karr, Catherine J

2015-01-01

Agricultural work is one of the most dangerous jobs for adolescents. Through a university-community partnership, the authors surveyed young primarily acculturated Latino-American farmworkers 14 to 18 years of age regarding their agricultural work experience. Topics included occupational health and safety education, work history, and information sources. The authors also evaluated the Rapid Clinical Assessment Tool (RCAT), a pictorial tool for identifying agricultural tasks to enhance discussion with clinical providers. One hundred forty youth with farmwork experience completed the survey; 6% reported a previous work-related injury or illness and 53% reported receiving some workplace health and safety training. Correct identification of legally restricted duties for youth varied but were generally low: participants identified working alone past 8 pm (57%), driving a forklift (56%), doing roofing work (39%), working in freezers (34%), and driving a delivery vehicle (30%). The Internet was identified as the most likely and reliable place youth would go to find information on workplace health and safety. Few (15%) reported clinician-initiated conversations on occupational health; however, a high proportion responded positively to questions regarding the usefulness of the RCAT for this purpose. This study highlights the need for workplace health and safety guidance for youth employed in agriculture. The results support Internet-based outreach and use of the RCAT to help facilitate occupational health discussions in clinical settings.

Nuclear technology and reactor safety engineering. The situation ten years after the Chernobyl reactor accident

International Nuclear Information System (INIS)

Birkhofer, A.

1996-01-01

Ten years ago, on April 26, 1986 the most serious accident ever in the history of nuclear tgechnology worldwide happened in unit 4 of the nuclear power plant in Chernobyl in the Ukraine, this accident unveiling to the world at large that the Soviet reactor design lines are bearing unthought of safety engineering deficits. The dimensions of this reactor accident on site, and the radioactive fallout spreading far and wide to many countries in Europe, vividly nourished the concern of great parts of the population in the Western world about the safety of nuclear technology, and re-instigated debates about the risks involved and their justification. Now that ten years have elapsed since the accident, it is appropriate to strike a balance and analyse the situation today. The number of nuclear power plants operating worldwide has been growing in the last few years and this trend will continue, primarily due to developments in Asia. The Chernobyl reactor accident has pushed the international dimension of reactor safety to the foreground. Thus the Western world had reason enough to commit itself to enhancing the engineered safety of reactors in East Europe. The article analyses some of the major developments and activities to date and shows future perspectives. (orig.) [de

Practical Child Safety Education in England: A National Survey of the Child Safety Education Coalition

Science.gov (United States)

Mulvaney, Caroline A.; Watson, Michael C.; Walsh, Patrick

2013-01-01

Objective: To examine the provision of practical safety education by Child Safety Education Coalition (CSEC) organizations in England. Design: A postal survey. Setting: Providers of child practical safety education who were also part of CSEC. Methods: In February 2010 all CSEC organizations were sent a self-completion postal questionnaire which…

16 CFR Figure 1 to Part 1203 - Anatomical Planes

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Anatomical Planes 1 Figure 1 to Part 1203 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR BICYCLE HELMETS Pt. 1203, Fig. 1 Figure 1 to Part 1203—Anatomical Planes ER10MR98.001 ...

Nuclear criticality safety guide

International Nuclear Information System (INIS)

Ro, Seong Ki; Shin, Hee Seong; Park, Seong Won; Shin, Young Joon.

1997-06-01

Nuclear criticality safety guide was described for handling, transportation and storage of nuclear fissile materials in this report. The major part of the report was excerpted frp, TID-7016(revision 2) and nuclear criticality safety written by Knief. (author). 16 tabs., 44 figs., 5 refs

Microbiological food safety in Malaysia from the academician’s perspective

OpenAIRE

New, C.Y.,; Ubong, A.; Premarathne, J.M.K.J.K.,; Thung, T.Y.,; Lee, E.,; Chang, W.S.,; Loo, Y.Y.; Kwan, S.Y.; Tan, C.W.; Kuan, C.H.; Son, R.

2017-01-01

Food safety in Malaysia is not considered an issue yet. From the previous year (2005- 2015) records, the incidence rate of food poisoning had been fluctuating and despite that, cases continue to occur especially among school students. As a developing nation, it is high-time that Malaysia begins to emphasize on food safety to reduce the burden of foodborne illness in the socio-economic development of the country, and at the same time, gain benefits in terms of economic returns a...

Safety assessment of Novi Han radioactive waste repository - features, problems, results and perspectives

International Nuclear Information System (INIS)

Mateeva, M.

2000-01-01

This paper summarizes the work done and the achievements reached in the Novi Han radioactive waste repository safety assessment within the IAEA Model Project 'Increasing the safety of Novi Han radioactive waste repository BUL 4/005'. The overall safety assessment has a wide context, but the work reported here relates only to some details and results concerning the development and implementation of the appropriate methodology approach, model and computer code used for the calculations. Different steps and procedures are included for a better practical understanding of the obtained results during the safety assessment performance. The methodology approach is widely based on an international experience in safety analysis and implemented for evaluation computer code AMBER, which is one of the recommended from the safety assessments experts. (author)

A German perspective on advances in safety standards and regulations

International Nuclear Information System (INIS)

Berg, H.P.; Herttrich, P.M.

1993-01-01

At present, different proposals for evolutionary or innovative reactors are under consideration. Therefore, it is necessary that the regulators give guidance on the required safety characteristics of future designs of nuclear power plants. On the one hand, existing regulations have to be updated according to the current state of science and technology. Best available and adequately approved technology has to be used as a yardstick for the acceptability of future basic design features. On the other hand, potential safety features of innovative or revolutionary designs must be considered as serious competitors and potential technical solutions taking the state of maturity of the concepts, the extent of practical experience and the level of effort needed for realization into due account. On this background, recent developments of the Atomic Energy Act, of safety regulations and investigations of requirements for future designs in the Federal Republic of Germany and current projects of international cooperation are presented. (author)

ARIES-AT safety design and analysis

Energy Technology Data Exchange (ETDEWEB)

Petti, D.A. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States)]. E-mail: David.Petti@inl.gov; Merrill, B.J. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Moore, R.L. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Longhurst, G.R. [Idaho National Engineering and Environmental Laboratory, Fusion Safety Program, P.O. Box 1625, Idaho Falls, ID 83415 (United States); El-Guebaly, L. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Mogahed, E. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Henderson, D. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Wilson, P. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States); Abdou, A. [Fusion Technology Institute, 1500 Engineering Drive, University of Wisconsin-Madison, Madison, WI 53706 (United States)

2006-01-15

ARIES-AT is a 1000 MWe conceptual fusion power plant design with a very low projected cost of electricity. The design contains many innovative features to improve both the physics and engineering performance of the system. From the safety and environmental perspective, there is greater depth to the overall analysis than in past ARIES studies. For ARIES-AT, the overall spectrum of off-normal events to be examined has been broadened. They include conventional loss of coolant and loss of flow events, an ex-vessel loss of coolant, and in-vessel off-normal events that mobilize in-vessel inventories (e.g., tritium and tokamak dust) and bypass primary confinement such as a loss of vacuum and an in-vessel loss of coolant with bypass. This broader examination of accidents improves the robustness of the design from the safety perspective and gives additional confidence that the facility can meet the no-evacuation requirement under average weather conditions. We also provide a systematic assessment of the design to address key safety functions such as confinement, decay heat removal, and chemical energy control. In the area of waste management, both the volume of the component and its hazard are used to classify the waste. In comparison to previous ARIES designs, the overall waste volume is less because of the compact design.

Nuclear power plants and safety; Elektrownie jadrowe i bezpieczenstwo

Energy Technology Data Exchange (ETDEWEB)

Celinski, Z. [Politechnika Warszawska, Warsaw (Poland)

1995-12-31

The brief scope on the state of nuclear energetics worldwide as well as development perspectives have been presented. The safety problems, economic competitiveness and public acceptance have been shown and discussed. 55 refs, 3 figs, 2 tabs.

[Safety in physical education - a teacher's perspective].

Science.gov (United States)

Greier, K; Heinzle, A; Nepo, S; Ratschiller, J; Gafriller, R; Riechelmann, H

2015-03-01

A high percentage of all sports injuries occur during school sports. The aim of this study was to collect statements and opinions of sports teachers for safety in physical education. In a cross-sectional study, 296 teachers (202 with, 94 without a teaching qualification in "exercise and sports") at 77 Tyrolean "New Middle Schools" (former secondary schools) were interviewed. They judged various statements on school sports safety using a 5-point verbal rating scale. Irrespective of gender, teachers with a teaching qualification stated significantly more frequently (p = 0.015) that they have participated in continuing education on accident prevention than had their colleagues without qualification. The same applies to the checking of gymnastic and sports equipment before use (p sportswear in physical education than did their male counterparts. Of all respondents, 57 % knew about technical faults in sports halls, which have also been reported to the school administration. In more than half (58 %) of these, reported defects were repaired completely and in one-third (36 %), a partial repair was reported. Participants estimated that the major risk for school sports injuries was due to the low motor skills of the pupils, inhomogeneous groups, large numbers of pupils, outdated sports equipment, and ball games. Since about a third of all surveyed teachers had no teaching qualification in exercise and sports, this group should come into the focus of regular continuing education in accident prevention. © Georg Thieme Verlag KG Stuttgart · New York.

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.

Corrosion in PWR stainless steel components: a TSO perspective based on operating experience and expertises

International Nuclear Information System (INIS)

Curieres, I. de

2015-01-01

Stainless steels are used commonly in many circuits of a nuclear power plant. Particularly, they are the prime materials for the inside surface of the primary circuit. Their operating experience has been good, though a number of cases of degradations due to corrosion have been reported the last ten years. This number of events is increasing and many studies of damaged parts become available. Based on the operating experience and these studies, IRSN will provide its perspective on the safety-related issues associated with the corrosion of stainless steel components. It appears that today's knowledge is not sufficient to define relevant criteria or to determine the exact set of parameters which leads to SCC (Stress Corrosion Cracking) of stainless steels. As a consequence, the best strategy remains an inspection and repair/replacement one. Moreover many cases show the influence of pollutants in the SCC events. This emphasizes the fact that chemistry parameters are strongly connected to safety issues, with respect to the stainless steels integrity

NRC review of passive reactor design certification testing programs: Overview and regulatory perspective

International Nuclear Information System (INIS)

Levin, A.E.

1993-01-01

Reactor vendors are developing new designs for future deployment, including open-quotes passiveclose quotes light water reactors (LWRs), such as General Electric's (G.E.'s) simplified boiling water reactor (SBWR) and Westinghouse's AP600, which depend primarily on inherent processes, such as national convection and gravity feed, for safety injection and emergency core cooling. The U.S. Nuclear Regulatory Commission (NRC) has implemented a new process, certification of standardized reactor designs, for licensing these Plants. Part 52 of Title 10 of the Code of Federal Regulations (10CFR52) contains the requirements that vendors must meet for design certification. One important section, 10CFR52.47, reads open-quotes Certification of a standard design which . . . utilizes simplified, inherent, passive, or other innovative means to accomplish its safety functions will be granted only if: (1) The performance of each safety feature of the design has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof; (2) Interdependent effects among the safety features have been found acceptable by analysis, appropriate test programs, experience, or a combination thereof; and (3) Sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses. . . . The vendors have initiated programs to test innovative features of their designs and to develop data bases needed to validate their analytical codes, as required by the design certification rule. Accordingly, the NRC is reviewing and evaluating the vendors programs to ensure that they address adequately key issues concerning safety system performance. This paper provides an overview of the NRC's review process and regulatory perspective

Recent Economic Perspectives on Political Economy, Part II*

Science.gov (United States)

Dewan, Torun; Shepsle, Kenneth A.

2013-01-01

In recent years some of the best theoretical work on the political economy of political institutions and processes has begun surfacing outside the political science mainstream in high quality economics journals. This two-part paper surveys these contributions from a recent five-year period. In Part I, the focus is on elections, voting and information aggregation, followed by treatments of parties, candidates, and coalitions. In Part II, papers on economic performance and redistribution, constitutional design, and incentives, institutions, and the quality of political elites are discussed. Part II concludes with a discussion of the methodological bases common to economics and political science, the way economists have used political science research, and some new themes and arbitrage opportunities. PMID:23606754