Regulatory review of safety cases and safety assessments - associated challenges

International Nuclear Information System (INIS)

Bennett, D.G.; Ben Belfadhel, M.; Metcalf, P.E.

2006-01-01

Regulatory reviews of safety cases and safety assessments are essential for credible decision making on the licensing or authorization of radioactive waste disposal facilities. Regulatory review also plays an important role in developing the safety case and in establishing stakeholders' confidence in the safety of the facility. Reviews of safety cases for radioactive waste disposal facilities need to be conducted by suitably qualified and experienced staff, following systematic and well planned review processes. Regulatory reviews should be sufficiently comprehensive in their coverage of issues potentially affecting the safety of the disposal system, and should assess the safety case against clearly established criteria. The conclusions drawn from a regulatory review, and the rationale for them should be reproducible and documented in a transparent and traceable way. Many challenges are faced when conducting regulatory reviews of safety cases. Some of these relate to issues of project and programme management, and resources, while others derive from the inherent difficulties of assessing the potential long term future behaviour of engineered and environmental systems. The paper describes approaches to the conduct of regulatory reviews and discusses some of the challenges faced. (author)

Development and Evaluation of a Multi-Institutional Case Studies-Based Course in Food Safety

Science.gov (United States)

Pleitner, Aaron M.; Chapin, Travis K.; Hammons, Susan R.; Stelten, Anna Van; Nightingale, Kendra K.; Wiedmann, Martin; Johnston, Lynette M.; Oliver, Haley F.

2015-01-01

Developing novel, engaging courses in food safety is necessary to train professionals in this discipline. Courses that are interactive and case-based encourage development of critical thinking skills necessary for identifying and preventing foodborne disease outbreaks. The purpose of this study was to assess the efficacy of a case study…

Integrated safety case development for deep geological repositories

International Nuclear Information System (INIS)

Kawamura, Hideki; McKinley, Ian G.

2008-01-01

The paper will illustrate an 'integrated safety case', which involves combining both pre-closure and post-closure safety arguments from the point of view of a repository implementer, who must also ensure that projects are practical, acceptable and economic. The post-closure safety case is based on the performance of a number of barriers, which are established during construction, operation and closure. Such barriers must be confirmed using quality assured methods, supported, as required, by inspection and monitoring. The requirement for integrated assessment means that even the final process to end institutional control and transfer any liabilities from the implementer needs to be considered at present, even though this will undoubtedly be refined and tailored to the site characteristics over the many decades that will pass before this occurs. To illustrate the practical application of this approach, assessment of variants for remote-handled emplacement of the EBS for disposal of HLW in Japan will be discussed. (author)

Monitoring road safety development at regional level: A case study in the ASEAN region.

Science.gov (United States)

Chen, Faan; Wang, Jianjun; Wu, Jiaorong; Chen, Xiaohong; Zegras, P Christopher

2017-09-01

Persistent monitoring of progress, evaluating the results of interventions and recalibrating to achieve continuous improvement over time is widely recognized as being crucial towards the successful development of road safety. In the ASEAN (Association of Southeast Asian Nations) region there is a lack of well-resourced teams that contain multidisciplinary safety professionals, and specialists in individual countries, who are able to carry out this work effectively. In this context, not only must the monitoring framework be effective, it must also be easy to use and adapt. This paper provides a case study that can be easily reproduced; based on an updated and refined Road Safety Development Index (RSDI), by means of the RSR (Rank-sum ratio)-based model, for monitoring/reporting road safety development at regional level. The case study was focused on the road safety achievements in eleven Southeast Asian countries; identifying the areas of poor performance, potential problems and delays. These countries are finally grouped into several classes based on an overview of their progress and achievements regarding to road safety. The results allow the policymakers to better understand their own road safety progress toward their desired impact; more importantly, these results enable necessary interventions to be made in a quick and timely manner. Keeping action plans on schedule if things are not progressing as desired. This would avoid 'reinventing the wheel' and trial and error approaches to road safety, making the implementation of action plans more effective. Copyright © 2017 Elsevier Ltd. All rights reserved.

Development of the NUMO pre-selection, site-specific safety case

International Nuclear Information System (INIS)

Fujiyama, Tetsuo; Suzuki, Satoru; Deguchi, Akira; Umeki, Hiroyuki

2016-01-01

Key conclusions: ◆ “The NUMO pre-selection, site-specific safety case” provides the basic structure for subsequent safety cases that will be applied to any selected site, emphasising practical approaches and methodology which will be applicable for the conditions/constraints during an actual siting process. ◆ The preliminary results of the design and safety assessment would underpin the feasibility and safety of geological disposal in Japan.

Automating the Generation of Heterogeneous Aviation Safety Cases

Science.gov (United States)

Denney, Ewen W.; Pai, Ganesh J.; Pohl, Josef M.

2012-01-01

A safety case is a structured argument, supported by a body of evidence, which provides a convincing and valid justification that a system is acceptably safe for a given application in a given operating environment. This report describes the development of a fragment of a preliminary safety case for the Swift Unmanned Aircraft System. The construction of the safety case fragment consists of two parts: a manually constructed system-level case, and an automatically constructed lower-level case, generated from formal proof of safety-relevant correctness properties. We provide a detailed discussion of the safety considerations for the target system, emphasizing the heterogeneity of sources of safety-relevant information, and use a hazard analysis to derive safety requirements, including formal requirements. We evaluate the safety case using three classes of metrics for measuring degrees of coverage, automation, and understandability. We then present our preliminary conclusions and make suggestions for future work.

The 2002 Drigg post-closure safety case: implementation of a multiple factor safety case

International Nuclear Information System (INIS)

Lean, C.B.; Grimwood, P.D.; Watts, L.; Fowler, L.; Thomson, G.; Kelly, E.; Hodgkinson, D.

2004-01-01

British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site, which is the UK's principal facility for the disposal of low level radioactive waste (LLW). Disposals are carried out under the terms of an authorization granted by the UK Environment Agency (the Agency). The Agency periodically reviews the authorization to take account of new information and any revisions to regulatory requirements. In September 2002 new Operational Environmental and Post-Closure Safety Cases (OESC and PCSC respectively) were submitted to the Agency to support the next authorization review. The OESC assesses radiological safety aspects up until closure of the site, including a post-operational management phase, whilst the PCSC considers the longer-term radiological safety. The Drigg disposal facility has been operational since 1959. For the first 3 decades of operations, disposals were solely by tumble tipping wastes into excavated trenches. This was phased out in favour of vault disposal and disposals to the trenches were completed in 1995. The first vault (Vault 8) commenced operations in 1988 and construction of future vaults is planned up to the estimated end of disposal operations in about 50 years time. This paper describes the main components of the 2002 Drigg PCSC and how they relate to each other. Central to the safety case is a systematic comprehensive post-closure radiological safety assessment (PCRSA). However, the importance of the more qualitative aspects of the safety case, including a demonstration of optimisation, is also highlighted. In addition, other confidence-building activities which are key to developing and presenting the safety case are discussed. (author)

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)

Regulatory review of safety cases and safety assessments for near surface

International Nuclear Information System (INIS)

Nys, V.

2003-01-01

The activities of the ASAM Regulatory Review Working Group are presented. Regulatory review of the safety assessment is made. It includes the regulatory review of post-closure safety assessment; safety case development and confidence building. The ISAM methodology is reviewed and SA system description is presented. Recommendations on the review process management are given

Performance assessment and the safety case: Lessons from recent international projects and areas for further development

International Nuclear Information System (INIS)

Galson, Daniel A.; Bailey, Lucy

2014-01-01

The European Commission (EC) PAMINA project - Performance Assessment Methodologies in Application to Guide the Development of the Safety Case - was conducted over the period 2006-2009 and brought together 27 organisations from 10 countries. PAMINA had the aim of improving and developing a common understanding of performance assessment (PA) methodologies for disposal concepts for spent fuel and other long-lived radioactive wastes in a range of geological environments. This was followed by a Nuclear Energy Agency (NEA) sponsored project on Methods for Safety Assessment of Geological Disposal Facilities for Radioactive Waste (MeSA), which was completed in 2012. This paper presents a selection of conclusions from these projects, in the context of general understanding developed on what would constitute an acceptable safety case for a geological disposal facility, and outlines areas for further development. The paper also introduces a new project on PA that is under consideration within the context of the EC Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP). (authors)

Safety cases and siting processes

International Nuclear Information System (INIS)

Metlay, Daniel; Ewing, Rodney

2014-01-01

Central to any process for building a deep-mined geologic repository for high-activity radioactive waste is the development of a safety case. To date, such cases, in various forms have been elaborated for a variety of concepts for geologic disposal, including in salt, clay, argillite, crystalline rock (granite and gneiss) and volcanic tuff formations. In addition to the technical effort required to develop a safety case, increasingly nations have come to believe that it is also critical to obtain the consent of the region or community where the facility might be located. The purpose of this paper is to explore issues associated with just one aspect of consent-based siting: How can such a process be designed so that willingness to accept a site for a repository continues to be meaningful even as new technical knowledge and insights emerge during site characterisation? In short, what is the meaning of 'informed consent' in the context of repository development? (authors)

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)

The safety case for deep geological disposal of radioactive waste

International Nuclear Information System (INIS)

Kwong, Gloria

2014-01-01

The concept of a 'safety case' for a deep geological repository for radioactive waste was first introduced by the NEA Expert Group on Integrated Performance Assessment (IPAG). It was further developed in the NEA report entitled Confidence in the Long-term Safety of Deep Geological Repositories (1999), and since then it has been taken up in international safety standards as promulgated by the International Atomic Energy Agency (IAEA, 2006, 2011) and more recently in recommendations by the International Commission on Radiological Protection on the application of the system of radiological protection in geological disposal (ICRP, 2013). Many national radioactive waste disposal programmes and regulatory guides are also applying this concept. The NEA has used the safety case as a guide in several international peer reviews of national repository programmes and safety documentation. In Europe, the EU Directive 2011/70/ Euratom (EU, 2011) establishes a framework to ensure responsible and safe management of spent fuel and radioactive waste by member states that, inter alia, requires a decision-making process based on safety evidence and arguments that mirror the safety case concept. In 2007, the NEA, the IAEA and the European Commission (EC) organised a symposium on Safety Cases for the Deep Disposal of Radioactive Waste: Where Do We Stand? Since this time, however, there have been some major developments in a number of national geological disposal programmes and significant experience in preparing and reviewing cases for the operational and long-term safety of proposed and operating geological repositories. A symposium on The Safety Case for Deep Geological Disposal of Radioactive Waste: 2013 State of the Art was thus organised to assess developments since 2007 in the practice, understanding and roles of the safety case, as applied internationally at all stages of repository development, including the interplay of technical, regulatory and societal issues. The symposium

Model-Driven Development of Safety Architectures

Science.gov (United States)

Denney, Ewen; Pai, Ganesh; Whiteside, Iain

2017-01-01

We describe the use of model-driven development for safety assurance of a pioneering NASA flight operation involving a fleet of small unmanned aircraft systems (sUAS) flying beyond visual line of sight. The central idea is to develop a safety architecture that provides the basis for risk assessment and visualization within a safety case, the formal justification of acceptable safety required by the aviation regulatory authority. A safety architecture is composed from a collection of bow tie diagrams (BTDs), a practical approach to manage safety risk by linking the identified hazards to the appropriate mitigation measures. The safety justification for a given unmanned aircraft system (UAS) operation can have many related BTDs. In practice, however, each BTD is independently developed, which poses challenges with respect to incremental development, maintaining consistency across different safety artifacts when changes occur, and in extracting and presenting stakeholder specific information relevant for decision making. We show how a safety architecture reconciles the various BTDs of a system, and, collectively, provide an overarching picture of system safety, by considering them as views of a unified model. We also show how it enables model-driven development of BTDs, replete with validations, transformations, and a range of views. Our approach, which we have implemented in our toolset, AdvoCATE, is illustrated with a running example drawn from a real UAS safety case. The models and some of the innovations described here were instrumental in successfully obtaining regulatory flight approval.

Strategy for safety case development: impact of a volunteering approach to siting a japanese HLW repository

International Nuclear Information System (INIS)

Kitayama, K.; Ishiguro, K.; Takeuchi, M.; Tsuchi, H.; Kato, T.; Sakabe, Y.; Wakasugi, K.

2008-01-01

NUMO strategy for safety case development is constrained by a staged siting approach, which has been initiated by a call for volunteer municipalities to host the HLW repository. For each site, the safety case is an important factor to be considered at the selection steps which narrow down towards the preferred repository location. This is particularly challenging, however, as every site requires a tailored repository concept, with associated performance assessment and an individual site evaluation programme all of which evolve with gradually increasing understanding of the host environment. In order to maintain flexibility without losing focus, NUMO has developed a formalized tailoring procedure, termed the NUMO Structured Approach (NSA). The NSA guides the interaction of the key site characterisation, repository design and performance assessment groups and is facilitated by tools to help the decision making associated with the tailoring process (e.g. a requirements management system) and with comparison of siting and design options (e.g. multi-attribute analysis). Pragmatically, the post-closure safety case will initially emphasize near-field processes and a robust engineering barrier system, considering the limited geological information at early stages. This will be complemented by a more realistic assessment of total system performance, as needed to compare options. In addition, efforts to rigorously assess operational phase safety and the practicality of assuring quality of the constructed engineered barriers are components of the total safety case which are receiving particular attention now, as they may better discriminate between sites while information is still limited. (authors)

The development of international safety standards on geological disposal

International Nuclear Information System (INIS)

McCartin, T.

2005-01-01

The IAEA is developing a set of safety requirements for geologic disposal to be used by both developers and regulators for planning, designing, operating, and closing a geologic disposal facility. Safety requirements would include quantitative criteria for assessing safety of geologic disposal facilities as well as requirements for development of the facility and the safety strategy including the safety case. Geologic disposal facilities are anticipated to be developed over a period of at least a few decades. Key decisions, e.g., on the disposal concept, siting, design, operational management and closure, are expected to be made in a series of steps. Decisions will be made based on the information available at each step and the confidence that may be placed in that information. A safety strategy is important for ensuring that at each step during the development of the disposal facility, an adequate understanding of the safety implications of the available options is developed such that the ultimate goal of providing an acceptable level of operational and post closure safety will be met. A safety case for a geologic disposal facility would present all the safety relevant aspects of the site, the facility design and the managerial and regulatory controls. The safety case and its supporting assessments illustrates the level of protection provided and shall give reasonable assurance that safety standards will be met. Overall, the safety case provides confidence in the feasibility of implementing the disposal system as designed, convincing estimates of the performance of the disposal system and a reasonable assurance that safety standards will be met. (author)

Definition of the OPERA safety case for radioactive waste disposal in the Netherlands

International Nuclear Information System (INIS)

Hart, Jaap; Wildenborg, Ton; Davis, Paul; Becker, Dirk-Alexander; Verhoef, Ewoud

2014-01-01

This paper first gives a short introduction on OPERA, the current Dutch five-year research programme on disposal of radioactive waste. It then zooms in on OPERA WP (Work Package) 2 Safety Case - the OSCAR project, and presents (preliminary) results on the structure of the OPERA safety case, the subject of safety statements, and the OPERA safety assessment methodology. The structure of the initial long-term, post-closure safety case for a disposal facility for radioactive waste in Boom Clay in the Netherlands is being developed in the OSCAR project. Hereto a selection of relevant national and international efforts concerning the set-up of a safety case for geological disposal of radioactive waste (safety case structure, safety assessment methodology, FEP database) has been reviewed considering the objectives and outlines of the OPERA programme described in the OPERA research plan. Not surprisingly, it turned out that the guidelines and databases of the IAEA and NEA developed by the international community pretty well covered all aspects of nationally developed safety cases. Although in OPERA only 'initial and conditional' safety cases (for disposal in low permeable clay and rock salt) will be developed, the programme objective is detailing a first road-map for the long-term research on geological disposal of radioactive waste in the Netherlands. The safety case being developed will serve as a basis for the further development of the subsequent stages of the Dutch radioactive waste disposal programme. The focus of OSCAR is, therefore, to develop and propose a 'future proof' structure for the safety case, drawing on the NEA and IAEA/PRISM methodologies. The OPERA safety case structure being developed will encompass all relevant aspects, or components, of a modern safety case and will link the different components in a practical and transparent way. It will assist in steering the flow of information generated within the different OPERA and as such provide a structured

Development of a methodology for an environmental safety case in the United Kingdom

International Nuclear Information System (INIS)

Bailey, L.E.F.

2008-01-01

This presentation introduced the notion of an environmental safety case that focuses on the protection of both humans and the environment. The UK safety case will address operational, transport and post-closure safety for intermediate-level waste (ILW) and high-level waste (HLW). As there is yet no agreed site or design for a deep geological repository in the UK, the first iteration of the safety case will be generic, drawing on examples from international repository concepts. These concepts will be considered in appropriate generic geological environments typical of those found in the UK. The performance of these example concepts will be assessed using a time frames-based approach that focuses on the evolution of the multiple barriers and their associated safety functions. This approach recognizes that the relative importance of the different barriers in providing safety will evolve over time. For example, at early times the engineered barriers provide containment and the geological barriers protect the engineered barriers and provide isolation of the wastes. At later times, as the engineered barriers degrade, the geosphere provides the major barrier to radionuclide migration back to the surface and ensures the long-term stability of the system. A multi-factor safety case will be presented, using multiple lines of reasoning, including comparisons with natural and anthropogenic analogues, to provide assurance of the intrinsic safety functions of the system and their evolution over time. (author)

A new look on the safety case for geologic disposal

International Nuclear Information System (INIS)

Pescatore, Claudio; Riotte, Hans; Voinis, Sylvie

2005-01-01

It has become evident that the development of a geologic repository 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 and scientific arguments that will help in giving confidence in the feasibility and safety of a proposed concept. A detailed safety assessment is typically required at major decision points in repository planning and implementation, including decisions that require the granting of licenses. In recent years the scope of the safety assessment has broadened to include the collation of a broad range of evidence and arguments that complement and support the reliability of the results of quantitative analyses, and the broader term 'post-closure safety case' or simply 'safety case' is used to refer to these studies. This paper reflects the historical development from integrated safety assessment to modern safety cases and outlines the main elements of a safety case for geologic disposal. The presentation of the safety strategy, multiple barrier concept and strategies to deal with uncertainties are analysed and the importance of an explicit statement of confidence is emphasized. (author)

Making the Postclosure Safety Case for the Proposed Yucca Mountain Repository

Energy Technology Data Exchange (ETDEWEB)

P. Swift; A.V. Luik

2006-08-28

The International Atomic Energy Agency (IAEA), in its advisory standard for geological repositories promulgated jointly with the Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development, explicitly distinguishes between the concepts of a safety case and a safety assessment. As defined in the advisory standard, the safety case is a broader set of arguments that provide confidence and substantiate the formal analyses of system safety made through the process of safety assessment. Although the IAEAYs definitions include both preclosure (i.e., operational) safety and post-closure performance in the overall safety assessment and safety case, the emphasis in here is on long-term performance after waste has been emplaced and the repository has been closed. This distinction between pre- and postclosure aspects of the repository is consistent with the U.S. regulatory framework defined by the U.S. Environmental Protection Agency (Chapter 40 of the Code of Federal Regulations, Part 197, or 40 CFR 197) [2] and implemented by the U.S. Nuclear Regulatory Commission (Chapter 10 of the Code of Federal Regulations, Part 63, or 10 CFR 63) [3]. The separation of the pre- and postclosure safety cases is also consistent with the way in which the U.S. Department of Energy has assigned responsibilities for developing the safety case. Bechtel SAIC Company is the Management and Operating contractor responsible for the design and operation of the Yucca Mountain facility and is therefore responsible for the preparation of the preclosure aspects of the safety case. Sandia National Laboratories has lead responsibility for scientific work evaluating post-closure performance, and therefore is responsible for developing the post-closure aspects of the safety case. In the context of the IAEA definitions, both preclosure and postclosure safety, including safety assessment and the safety case, will be documented in the license application being prepared for the

Making the Postclosure Safety Case for the Proposed Yucca Mountain Repository

International Nuclear Information System (INIS)

P. Swift; A.V. Luik

2006-01-01

The International Atomic Energy Agency (IAEA), in its advisory standard for geological repositories promulgated jointly with the Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development, explicitly distinguishes between the concepts of a safety case and a safety assessment. As defined in the advisory standard, the safety case is a broader set of arguments that provide confidence and substantiate the formal analyses of system safety made through the process of safety assessment. Although the IAEAYs definitions include both preclosure (i.e., operational) safety and post-closure performance in the overall safety assessment and safety case, the emphasis in here is on long-term performance after waste has been emplaced and the repository has been closed. This distinction between pre- and postclosure aspects of the repository is consistent with the U.S. regulatory framework defined by the U.S. Environmental Protection Agency (Chapter 40 of the Code of Federal Regulations, Part 197, or 40 CFR 197) [2] and implemented by the U.S. Nuclear Regulatory Commission (Chapter 10 of the Code of Federal Regulations, Part 63, or 10 CFR 63) [3]. The separation of the pre- and postclosure safety cases is also consistent with the way in which the U.S. Department of Energy has assigned responsibilities for developing the safety case. Bechtel SAIC Company is the Management and Operating contractor responsible for the design and operation of the Yucca Mountain facility and is therefore responsible for the preparation of the preclosure aspects of the safety case. Sandia National Laboratories has lead responsibility for scientific work evaluating post-closure performance, and therefore is responsible for developing the post-closure aspects of the safety case. In the context of the IAEA definitions, both preclosure and postclosure safety, including safety assessment and the safety case, will be documented in the license application being prepared for the

Nuclear Electric flask design and safety case development during the last ten years

International Nuclear Information System (INIS)

Dougall, I.; Jones, D.K.

1994-01-01

The scope of Nuclear Electric's (NE) requirements for irradiated fuel transport and the relevant safety and regulatory compliance standards are outlined. To illustrate NE's approach to demonstrating package design compliance the basis of the safety case for unbottled Magnox fuel transport in the Mk M2 Magnox flask is described. The considerations which lay behind the development of the Mk A2 AGR Flask are indicated and a description is given of the main design features of this flask. Finally there is a summary of progress in obtaining Type B(M) approvals, based on the 1985 IAEA Regulations, for the requisite range of flask contents. (author)

Safety Case for Service Contracts

Energy Technology Data Exchange (ETDEWEB)

Martinez, Israel L.

2014-07-01

Safety cases developed for the Facilities Management and Operations Center (FMOC) are based on the requirements in MN471021, Work Planning and Control Criteria for Safe Design and Operations. The FMOC performs maintenance activities in various locations at Sandia National Laboratories, New Mexico (SNL/NM). SNL/NM consists of more than 6,000,000 square feet of buildings, structures, and site infrastructure on approximately 13,000 acres of land. The FMOC performs approximately 7500 service contract work orders a year to assist with operations and maintenance at the SNL/NM site and facilities. As part of the continual improvement process, this Safety Case will be reviewed and updated, as needed, or at a minimum every three years.

Towards a Formal Basis for Modular Safety Cases

Science.gov (United States)

Denney, Ewen; Pai, Ganesh

2015-01-01

Safety assurance using argument-based safety cases is an accepted best-practice in many safety-critical sectors. Goal Structuring Notation (GSN), which is widely used for presenting safety arguments graphically, provides a notion of modular arguments to support the goal of incremental certification. Despite the efforts at standardization, GSN remains an informal notation whereas the GSN standard contains appreciable ambiguity especially concerning modular extensions. This, in turn, presents challenges when developing tools and methods to intelligently manipulate modular GSN arguments. This paper develops the elements of a theory of modular safety cases, leveraging our previous work on formalizing GSN arguments. Using example argument structures we highlight some ambiguities arising through the existing guidance, present the intuition underlying the theory, clarify syntax, and address modular arguments, contracts, well-formedness and well-scopedness of modules. Based on this theory, we have a preliminary implementation of modular arguments in our toolset, AdvoCATE.

A new approach to preparing safety cases for existing nuclear plant (COSR)

International Nuclear Information System (INIS)

Rice, S.A.; Buchan, A.B.

2000-01-01

BNFL is committed to achieving world class safety performance, through a process of continuously reviewing and improving its safety practices. In the mid 1990s, as part of this process, the company began to develop a new type of safety case, for existing non-reactor nuclear plants, called the continued operation safety report (COSR). Following a significant amount of development work from experts within BNFL and important contributions from its regulators, the first approved COSR was recently completed and submitted to the Nuclear Installations Inspectorate. The COSR aims to provide a visibly integrated safety and engineering case for the adequacy of continued operation of a nuclear facility. It achieves this by identifying the main plant structures, systems and components that have a safety function and provides the appropriate supporting engineering substantiation. The COSR aims to explore plant safety and identify worthwhile improvements. The document also aims to be reader-friendly by focusing on the main safety issues. It is therefore a slim safety summary which provides operators, safety specialists and regulators with an overview and introduction into the broader, more detailed safety case. This paper provides an overview of the COSR and its production process, describing the safety case improvements that have been made by comparing it to its predecessor, the fully developed safety case. The paper also illustrates the benefits of the COSR by providing current examples of its application on existing BNFL plant. Finally, the paper describes ongoing development work aimed at further improving the COSR and its production process. (author)

Proceedings on safety case - IGSC Topical Session held 25 November 2001, Paris-France

International Nuclear Information System (INIS)

O'Sullivan, Patrik; Voinis, Sylvie; Ouzounian, Gerald; Van Luik, Abraham

2002-01-01

It is accepted universally that an assessment of the safety of proposed geological repositories is a key input to the decision-making process regarding the development of these facilities. Accordingly, implementing and regulatory organisations in many of the OECD/NEA countries are involved in the investigation and resolution of issues associated with repository safety and NEA has been concerned with this issue for several years. Most current repository development programmes envisage that repository development will occur in an incremental fashion, with decisions being taken by national authorities at several steps in the development process. It may be envisaged that safety assessments will become progressively more refined at successive stages of the development process, with an expectation of increasing levels of confidence that the assessed levels of safety can be realised in practice. Different countries are at different stages and therefore opinions can be expected to vary on where the key issues remain. In accordance with current terminology the Safety Case for a proposed facility should present the results of the safety assessment together with an illustration of the level of confidence in the results. The safety case should also discuss how levels of uncertainty would be reduced in succeeding development phases. The establishment of the IGSC (Integration Group for the Safety Case), to bring together all activities relating to the safety case, recognised its key role of the latter in the process of repository development. Initiatives currently being pursued by the IGSC include the development of a 'Safety Case Brochure', to synthesise current understanding about the requirements of the Safety Case. The IGSC has a role to develop common views on such key aspects of the Safety Case but should not be prescriptive. To go further in establishments of the safety case brochure, a 'Topical Session' on the Safety Case was organised as part of the

Topical session proceedings of the 5. IGSC meeting on: observations regarding the safety case in recent safety assessment studies

International Nuclear Information System (INIS)

Hooper, Alan J.; Voinis, Sylvie; Van Luik, Abraham E.

2004-01-01

Within the NEA, the IGSC (Integration Group for the Safety Case) has, as an essential role, to develop common views on such key aspects of the safety case. Therefore, since the inauguration of the IGSC in 2000, four meetings were organised with topical sessions to explore various of these key aspects. This is a report on the fifth such topical session, held as part of the 5. plenary meeting of the IGSC. The session was attended by 36 participants, representing waste management organisations and regulatory authorities from 16 NEA member countries, the IAEA and the European Commission. The purpose of this topical session was to provide support to the finalising of the IGSC safety case brochure by getting a description of the safety case content of the IAEA Draft Safety Requirements document and by getting an overview of progress that could be observed from national organisations on developing their cases for system safety and/or developing the required methodologies. The objective was that the IGSC safety case brochure should be supportive of the IAEA/NEA document, and be reflective of the experience of the IGSC member programmes and organisations. The topical session was mainly aimed at exchanging information on: - The safety case related content of the proposed IAEA/NEA document (currently titled: 'IAEA Safety Standards Series, Geological Disposal of Radioactive Waste, Draft Safety Requirements (DS-154)'). - National programmes where safety assessments have recently been completed, e.g. ONDRAF/NIRAS, Nagra and Andra. - Feedback from international peer reviews, e.g. the Andra Dossier 2001 Argile, the Belgian SAFIR 2 report, the SR 97 report and the US-DOE Yucca Mountain TSPA. - The evolution of some national assessment methods and approaches e.g. SKB and Nagra. - The content of the draft IGSC safety case brochure entitled: 'The Nature and Purpose of the Post-closure Safety Case in Geological Disposal'. This document presents the various

IRSN safety research carried out for reviewing geological disposal safety case

International Nuclear Information System (INIS)

Serres, Christophe; Besnus, Francois; Gay, Didier

2010-01-01

The Radiation Protection and Nuclear Safety Institute develops a research programme on scientific issues related to geological disposal safety in order to supporting the technical assessment carried out in the framework of the regulatory review process. This research programme is organised along key safety questions that deal with various scientific disciplines as geology, hydrogeology, mechanics, geochemistry or physics and is implemented in national and international partnerships. It aims at providing IRSN with sufficient independent knowledge and scientific skills in order to be able to assess whether the scientific results gained by the waste management organisation and their integration for demonstrating the safety of the geological disposal are acceptable with regard to the safety issues to be dealt with in the Safety Case. (author)

Interim summary report of the safety case 2009

International Nuclear Information System (INIS)

2010-03-01

Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. The present Interim Summary Report represents a major contribution to the development of this safety case. The report has been compiled in accordance with Posiva's current plan for preparing this safety case. A full safety case for the KBS-3V variant will be developed to support the Preliminary Safety Assessment Report (PSAR) in 2012. The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository. Current understanding of the evolution of the disposal system indicates that, except a few unlikely circumstances affecting a small number of canisters, spent fuel will remain isolated, and the radionuclides contained within the canisters, for hundreds of thousands of years or more, in accordance with the base scenario. Confidence in this base scenario derives, in the first place, from the

Impact of biomarker development on drug safety assessment

International Nuclear Information System (INIS)

Marrer, Estelle; Dieterle, Frank

2010-01-01

Drug safety has always been a key aspect of drug development. Recently, the Vioxx case and several cases of serious adverse events being linked to high-profile products have increased the importance of drug safety, especially in the eyes of drug development companies and global regulatory agencies. Safety biomarkers are increasingly being seen as helping to provide the clarity, predictability, and certainty needed to gain confidence in decision making: early-stage projects can be stopped quicker, late-stage projects become less risky. Public and private organizations are investing heavily in terms of time, money and manpower on safety biomarker development. An illustrative and 'door opening' safety biomarker success story is the recent recognition of kidney safety biomarkers for pre-clinical and limited translational contexts by FDA and EMEA. This milestone achieved for kidney biomarkers and the 'know how' acquired is being transferred to other organ toxicities, namely liver, heart, vascular system. New technologies and molecular-based approaches, i.e., molecular pathology as a complement to the classical toolbox, allow promising discoveries in the safety biomarker field. This review will focus on the utility and use of safety biomarkers all along drug development, highlighting the present gaps and opportunities identified in organ toxicity monitoring. A last part will be dedicated to safety biomarker development in general, from identification to diagnostic tests, using the kidney safety biomarkers success as an illustrative example.

Use of the safety case to focus KMS applications - 16348

International Nuclear Information System (INIS)

Osawa, Hideaki; Hioki, Kazumasa; Umeki, Hiroyuki; Takase, Hiroyasu; McKinley, Ian

2009-01-01

The safety case, as defined in Japan, is an integrated set of arguments to show that a repository is sufficiently safe during both operational and post-closure phases. It explicitly includes the findings of a safety assessment and a demonstration of confidence in these findings. It is developed in a stepwise manner, with provisional cases used to support decisions at major project milestones. Social acceptance is acknowledged to be critical and hence a safety case includes not only technical components, but also the arguments required to explain fundamental issues to all key stakeholders. In the JAEA KMS project, the safety case has been found useful as a framework that allows all supporting R and D to be seen in the context of its applicability. Various tools have been examined to develop associated argumentation models and they have been seen to provide an overview that is valuable to both the users and producers of knowledge. The paper will review progress to date in this work, with illustrative examples of argumentation networks and an outline of future developments and challenges. (authors)

Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

Science.gov (United States)

Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

2013-12-01

This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

A systematic approach to safety case maintenance

International Nuclear Information System (INIS)

Kelly, T.P.; McDermid, J.A.

2001-01-01

A crucial aspect of safety case management is the ongoing maintenance of the safety argument through life. Throughout the operational life of any system, changing regulatory requirements, additional safety evidence and a changing design can challenge the corresponding safety case. In order to maintain an accurate account of the safety of the system, all such challenges must be assessed for their impact on the original safety argument. This is increasingly being recognised by many safety standards. However, many safety engineers are experiencing difficulties with safety case maintenance at present, the prime reason being that they do not have a systematic and methodical approach by which to examine the impact of change on safety argument. The size and complexity of safety arguments and evidence being presented within safety cases is increasing. Nowhere is this more apparent than for Electrical, Electronic and Programmable Electronic systems attempting to comply with the requirements and recommendations of software and hardware safety standards such as and UK Defence Standards 00-54 [MoD. 00-54 Requirements of Safety Related Electronic Hardware in Defence Equipment. Ministry of Defence, Interim Defence Standard, 1999], 00-55 []. However, this increase in safety case complexity exacerbates problems of comprehension and maintainability later on in the system lifecycle. This paper defines and describes a tool-supported process, based upon the principles of goal structuring, that attempts to address these difficulties through facilitating the systematic impact assessment of safety case challenges

Contents and Sample Arguments of a Safety Case for Near Surface Disposal of Radioactive Waste

International Nuclear Information System (INIS)

2017-06-01

This publication arises from the results of two projects to assist Member States in understanding and developing safety cases for near-surface radioactive waste disposal facilities. The objective of the publication is to give detailed information on the contents of safety cases for radioactive waste disposal and the types of arguments that may be included. It is written for technical experts preparing a safety case, and decision makers in the regulatory body and government. The publication outlines the key uses and aspects of the safety case, its evolution in parallel with that of the disposal facility, the key decision steps in the development of the waste disposal facility, the components of the safety case, their place in the Matrix of Arguments for a Safety Case (the MASC matrix), and a detailed description of the development of sample arguments that might be included in a safety case for each of two hypothetical radioactive waste disposal facilities.

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.

Dynamic Safety Cases for Through-Life Safety Assurance

Science.gov (United States)

Denney, Ewen; Pai, Ganesh; Habli, Ibrahim

2015-01-01

We describe dynamic safety cases, a novel operationalization of the concept of through-life safety assurance, whose goal is to enable proactive safety management. Using an example from the aviation systems domain, we motivate our approach, its underlying principles, and a lifecycle. We then identify the key elements required to move towards a formalization of the associated framework.

The use of case tools in OPG safety analysis code qualification

International Nuclear Information System (INIS)

Pascoe, J.; Cheung, A.; Westbye, C.

2001-01-01

Ontario Power Generation (OPG) is currently qualifying its critical safety analysis software. The software quality assurance (SQA) framework is described. Given the legacy nature of much of the safety analysis software the reverse engineering methodology has been adopted. The safety analysis suite of codes was developed over a period of many years to differing standards of quality and had sparse or incomplete documentation. Key elements of the reverse engineering process require recovery of design information from existing coding. This recovery, if performed manually, could represent an enormous effort. Driven by a need to maximize productivity and enhance the repeatability and objectivity of software qualification activities the decision was made to acquire or develop and implement Computer Aided Software Engineering (CASE) tools. This paper presents relevant background information on CASE tools and discusses how the OPG SQA requirements were used to assess the suitability of available CASE tools. Key findings from the application of CASE tools to the qualification of the OPG safety analysis software are discussed. (author)

Comprehensive safety cases for radioactive waste management facilities

International Nuclear Information System (INIS)

Woollam, P.B.; Cameron, H.M.; Davies, A.R.; Hiscox, A.W.

1995-01-01

Probabilistic safety assessment methodology has been applied by Nuclear Electric plc (NE) to the development of comprehensive safety cases for the radioactive waste management processing and accumulation facilities associated with its 26 reactor systems. This paper describes the methodology and the safety case assessment criteria employed by NE. An overview of the results is presented, together with more detail of a specific safety analysis: storage of fuel element debris. No risk to the public greater than 10 -6 /y has been identified and the more significant risks arise from the potential for radioactive waste fires. There are no unacceptable risks from external hazards such as flooding, aircrash or seismic events. Some operations previously expected to have significant risks in fact have negligible risks, while the few faults with risks exceeding the assessment criteria were only identified as a result of this study

Development of the international status of science and technology concerning methods and tools for operational and long-term safety cases

International Nuclear Information System (INIS)

Seher, Holger; Beuth, Thomas; Bracke, Guido; Kock, Ingo; Mayer, Kim-Marisa; Moog, Helge C.; Uhlmann, Stephan; Weyand, Torben

2016-09-01

The project ''development of the international status of science and technology concerning methods and tools for operational and long-term safety cases'' covers the following key aspects: global aspects of the methodology for scenario assumption for the operational phase following closure, potential analysis of the derives safety cases for the project Gorleben, determination of the solid phase composition of high-level radioactive wastes using geochemical modeling calculations, search for an adequate approach for the calculation of density and viscosity of saline solutions for the future use in GRS computer codes, international approaches for an integral analysis for the host rocks clay and granite in relation to the safety requirements of BMUB.

The LMFBR safety case

International Nuclear Information System (INIS)

Smith, D.

1990-01-01

The main objective of this report is to review the present status of the safety case for the liquid metal cooled fast reactor (FBR). A particular emphasis is placed on activities in Europe where the FBR has been progressively developed for many years during which time systems have passed from small experimental plants to the 1200 MWe SPX-1. The FBR has been found to be an easily controlled plant with low impact on the environment and low dose rates to operational personnel. Aspects of reactor design and associated R and D that are required for FBRs to be licensed and the progress made to meet these requirements are described. Fault conditions in the credible range can be dealt with safely, the FBR having several advantageous characteristics which assist safety. Also measures are foreseen to mitigate potential consequences of more severe but improbable accidents. This study sponsored by the Commission of the European Communities was carried out by Colenco Ltd in vlose collaboration with the Safety Working Group (SWG) which is a subgroup of the CEC Fast Reactor Coordinating Committee (FRCC)

Comprehensive safety cases for radioactive waste management facilities

International Nuclear Information System (INIS)

Woollam, P.B.

1993-01-01

Probabilistic safety assessment methodology is being applied by Nuclear Electric plc (NE) to the development of comprehensive safety cases for the radioactive waste management processing and accumulation facilities associated with its 26 reactor systems. This paper describes the methodology and the safety case assessment criteria employed by NE. An overview of the results from facilities used by the first 16 reactors is presented, together with more detail of a specific safety analysis: storage of fuel element debris. No risk to the public greater than 10 -6 /y has been identified and the more significant risks arise from the potential for radioactive waste fires. There are no unacceptable risks from external hazards such as flooding, aircrash or seismic events. Some operations previously expected to have significant risks in fact have negligible risks, while the few faults with risks exceeding the assessment criteria were only identified as a result of this study

Technology and Tool Development to Support Safety and Mission Assurance

Science.gov (United States)

Denney, Ewen; Pai, Ganesh

2017-01-01

The Assurance Case approach is being adopted in a number of safety-mission-critical application domains in the U.S., e.g., medical devices, defense aviation, automotive systems, and, lately, civil aviation. This paradigm refocuses traditional, process-based approaches to assurance on demonstrating explicitly stated assurance goals, emphasizing the use of structured rationale, and concrete product-based evidence as the means for providing justified confidence that systems and software are fit for purpose in safely achieving mission objectives. NASA has also been embracing assurance cases through the concepts of Risk Informed Safety Cases (RISCs), as documented in the NASA System Safety Handbook, and Objective Hierarchies (OHs) as put forth by the Agency's Office of Safety and Mission Assurance (OSMA). This talk will give an overview of the work being performed by the SGT team located at NASA Ames Research Center, in developing technologies and tools to engineer and apply assurance cases in customer projects pertaining to aviation safety. We elaborate how our Assurance Case Automation Toolset (AdvoCATE) has not only extended the state-of-the-art in assurance case research, but also demonstrated its practical utility. We have successfully developed safety assurance cases for a number of Unmanned Aircraft Systems (UAS) operations, which underwent, and passed, scrutiny both by the aviation regulator, i.e., the FAA, as well as the applicable NASA boards for airworthiness and flight safety, flight readiness, and mission readiness. We discuss our efforts in expanding AdvoCATE capabilities to support RISCs and OHs under a project recently funded by OSMA under its Software Assurance Research Program. Finally, we speculate on the applicability of our innovations beyond aviation safety to such endeavors as robotic, and human spaceflight.

Plan for safety case of spent fuel repository at Olkiluoto

International Nuclear Information System (INIS)

Vieno, T.; Ikonen, A.T.K.

2005-02-01

Posiva aims to present the Safety Case supporting the construction license application of the spent fuel repository at Olkiluoto by 2012. An outline and preliminary assessments will be presented in 2009. Interim reporting and an update of the Safety Case plan will be presented in 2006, as required by the authorities. The KBS-3 disposal concept aims at long-term isolation and containment of spent fuel assemblies in durable copper-iron canisters emplaced in a repository to be constructed at a depth between 400 and 600 metres in crystalline bedrock. By 2012, studies on the KBS-3 disposal concept and site investigations at Olkiluoto will have been continued over about thirty years. The construction of an underground rock characterisation facility (called ONKALO) was started in June 2004. The investigations are carried out in close cooperation with the Swedish SKB developing and assessing the same disposal concept at candidate sites, resembling Olkiluoto, at the other side of the Baltic Sea. A safety case is the synthesis of evidence, analyses and arguments that quantify and substantiate the safety, and the level of expert confidence in the safety, of a planned repository. Posiva's Safety Case will be organised in a portfolio including ten main reports, which will be periodically updated according the overall schedule presented in the plan. The Site report describing the present state and past evolution of the Olkiluoto site, as well as the disturbances caused by the construction of ONKALO and the first stage of the repository, forms the geoscientific basis of the Safety Case. The engineering basis is provided by the reports on the Characteristics of spent fuel, Canister design, and Repository design. The Process report containing descriptions and analyses of features, events and processes potentially affecting the disposal system, and the report on the Evolution of site and repository form the scientific basis of the Safety Case. The latter report will describe and

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)

Scientific basis for a safety case of deep geological repositories

Energy Technology Data Exchange (ETDEWEB)

Noseck, Ulrich; Becker, Dirk-Alexander; Brasser, Thomas [and others

2012-11-15

Within this project strategies and methods to build a safety case for deep geological repositories are further developed. This includes also the scientific fundamentals as a basis of the safety case. In the international framework the methodology of the Safety Case is frequently applied and continuously improved. According to definitions from IAEA and NEA the Safety Case is a compilation of arguments and facts, which describe, quantify and support the safety and the degree of confidence in the safety of the geological repository. The safety of the geological repository should be demonstrated by the safety case. The safety case is the basis for essential decisions during a repository programme. It comprises the results of safety assessments in combination with additional information like multiple lines of evidence and a discussion of robustness and quality of the repository, its design and the quality of all safety assessments including the basic assumptions. A crucial element of the Safety Case is the long-term safety analysis, i.e. the systematic analysis of the hazards connected with the facility and the capability of site and repository design to ensure the required safety functions and to fulfill the technical claims. Long-term safety analysis requires a powerful and qualified programme package, which contains appropriate hardware and software as well as well trained and experienced modellers performing the model calculations. The calculation tools used within safety cases need to be checked and verified and continuously adapted to the state-of-the-art science and technology. Especially it needs to be applicable to a real repository system. For the assessment of safety a deep process understanding is necessary. The R and D work performed within this project will contribute to the improvement of process and system understanding as well as to the further development of methods and strategies applied in the safety case. Emphasis was put on the following aspects

Scientific basis for a safety case of deep geological repositories

International Nuclear Information System (INIS)

Noseck, Ulrich; Becker, Dirk-Alexander; Brasser, Thomas

2012-11-01

Within this project strategies and methods to build a safety case for deep geological repositories are further developed. This includes also the scientific fundamentals as a basis of the safety case. In the international framework the methodology of the Safety Case is frequently applied and continuously improved. According to definitions from IAEA and NEA the Safety Case is a compilation of arguments and facts, which describe, quantify and support the safety and the degree of confidence in the safety of the geological repository. The safety of the geological repository should be demonstrated by the safety case. The safety case is the basis for essential decisions during a repository programme. It comprises the results of safety assessments in combination with additional information like multiple lines of evidence and a discussion of robustness and quality of the repository, its design and the quality of all safety assessments including the basic assumptions. A crucial element of the Safety Case is the long-term safety analysis, i.e. the systematic analysis of the hazards connected with the facility and the capability of site and repository design to ensure the required safety functions and to fulfill the technical claims. Long-term safety analysis requires a powerful and qualified programme package, which contains appropriate hardware and software as well as well trained and experienced modellers performing the model calculations. The calculation tools used within safety cases need to be checked and verified and continuously adapted to the state-of-the-art science and technology. Especially it needs to be applicable to a real repository system. For the assessment of safety a deep process understanding is necessary. The R and D work performed within this project will contribute to the improvement of process and system understanding as well as to the further development of methods and strategies applied in the safety case. Emphasis was put on the following aspects

The Dynamics of Agile Practices for Safety-Critical Software Development

DEFF Research Database (Denmark)

Nielsen, Peter Axel; Tordrup Heeager, Lise

2017-01-01

This short paper reports from a case study of the agile development of safety-critical software. It utilizes a framework of dynamic relationships between agile practices with the purpose of demonstrating the utility of the framework to understand a case in its context, and it shows significant...... dynamics. The study is concluded by pointing at which further research on the framework is required to use the framework in managing the agile development of safety-critical software....

Knowledge management: the cornerstone of a 21. century safety case

International Nuclear Information System (INIS)

Umeki, H.; Osawa, H.; Naito, M.; Nakano, K.; Makino, H.; Mc Kinley, I.G.

2008-01-01

The safety case for a radioactive waste repository involves many complex, multi-disciplinary issues; these must be summarised in a comprehensive and concise manner, with links to all supporting information. The safety case can thus be considered an edifice built on structured knowledge. Knowledge is defined here in the very widest sense; including all of the information underpinning a repository project. Knowledge management covers all aspects of the development, integration, quality assurance, communication and maintenance/archiving of such knowledge. When seen from this perspective, the exponential expansion of the knowledge base represents a little-discussed challenge to safety case development. Indeed, knowledge production rates in this area are rapidly reaching, if not already surpassing, the limits of traditional management methods. This problem has been recognised in Japan and thus a project has been initiated to develop a next generation knowledge management system (KMS). This will utilize advanced electronic information management technology to handle the vast quantity of material involved. Autonomic systems will perform many of the information processing functions, helping ensure that required knowledge is accessible to all stakeholders and that gaps can be identified and supporting R and D prioritized. In a departure from conventional structuring by technical discipline, the prototype KMS utilizes a safety case structure. This should facilitate use of the core of neutral scientific and technical knowledge by both the implementer and the regulator. Flexibility is built into the system, to allow it to be restructured to match the user needs or even interfaced directly to a formal requirements management system. (authors)

Pursuing for the case of safety

Energy Technology Data Exchange (ETDEWEB)

Hansen, H; Salaber, A [Geco-Prakla, Paris (France); Myers, S [Sedco Forex, Montrouge (France); Redd, E [Sedco Forex, Aberdeen (United Kingdom); Shannon, R [Anadrill HSE, London (United Kingdom)

1993-01-01

Ever since the Piper Alpha disaster, safety has become one of the industry's hottest issues. Attention to safety leads to improved communication within organizations as well as between operators and contractors, and ultimately to more efficient operations. In this article descriptions are given of safety management systems, the safety-case philosophy and legislative changes hat are helping promote these new safety tools. 6 figs., 4 ills., 3 refs.

Pursuing for the case of safety

Energy Technology Data Exchange (ETDEWEB)

Hansen, H.; Salaber, A. (Geco-Prakla, Paris (France)); Myers, S. (Sedco Forex, Montrouge (France)); Redd, E. (Sedco Forex, Aberdeen (United Kingdom)); Shannon, R. (Anadrill HSE, London (United Kingdom))

1993-01-01

Ever since the Piper Alpha disaster, safety has become one of the industry's hottest issues. Attention to safety leads to improved communication within organizations as well as between operators and contractors, and ultimately to more efficient operations. In this article descriptions are given of safety management systems, the safety-case philosophy and legislative changes hat are helping promote these new safety tools. 6 figs., 4 ills., 3 refs.

An Integrated Development Tool for a safety application using FBD language

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Jun; Lee, Jang Soo; Lee, Dong Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Regarding digitalizing the Nuclear Instrumentation and Control Systems, the application program responsible for the safety functions of Nuclear I and C Systems shall ensure the robustness of the safety function through development, testing, and validation roles for a life cycle process during software development. The importance of software in nuclear systems increases continuously. The integrated engineering tools to develop, test, and validate safety application programs require increasingly more complex parts among a number of components within nuclear digital I and C systems. This paper introduces the integrated engineering tool (SafeCASE-PLC) developed by our project. The SafeCASE-PLC is a kind of software engineering tool to develop, test, and validate the nuclear application program performed in an automatic controller

Development of nuclear safety issues program

Energy Technology Data Exchange (ETDEWEB)

Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K

2006-12-15

The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants.

Development of nuclear safety issues program

International Nuclear Information System (INIS)

Cho, J. C.; Yoo, S. O.; Yoon, Y. K.; Kim, H. J.; Jeong, M. J.; Noh, K. W.; Kang, D. K.

2006-12-01

The nuclear safety issues are defined as the cases which affect the design and operation safety of nuclear power plants and also require the resolution action. The nuclear safety issues program (NSIP) which deals with the overall procedural requirements for the nuclear safety issues management process is developed, in accordance with the request of the scientific resolution researches and the establishment/application of the nuclear safety issues management system for the nuclear power plants under design, construction or operation. The NSIP consists of the following 4 steps; - Step 1 : Collection of candidates for nuclear safety issues - Step 2 : Identification of nuclear safety issues - Step 3 : Categorization and resolution of nuclear safety issues - Step 4 : Implementation, verification and closure The NSIP will be applied to the management directives of KINS related to the nuclear safety issues. Through the identification of the nuclear safety issues which may be related to the potential for accident/incidents at operating nuclear power plants either directly or indirectly, followed by performance of regulatory researches to resolve the safety issues, it will be possible to prevent occurrence of accidents/incidents as well as to cope with unexpected accidents/incidents by analyzing the root causes timely and scientifically and by establishing the proper flow-up or remedied regulatory actions. Moreover, the identification and resolution of the safety issues related to the new nuclear power plants completed at the design stage are also expected to make the new reactor licensing reviews effective and efficient as well as to make the possibility of accidents/incidents occurrence minimize. Therefore, the NSIP developed in this study is expected to contribute for the enhancement of the safety of nuclear power plants

JET Tokamak, preparation of a safety case for tritium operations

Energy Technology Data Exchange (ETDEWEB)

Boyer, Helen, E-mail: helen.boyer@ccfe.ac.uk [CCFE, Culham Science Centre (United Kingdom); Plummer, David; Johnston, Jane [CCFE, Culham Science Centre (United Kingdom)

2016-11-01

Highlights: • A safety case incorporating technical and ITER related upgrades. • Hazard analysis reworked to include new modelling assessments. • Fitness for purpose assessment of safety controls. - Abstract: A new Safety Case is required to permit tritium operations on JET during the forthcoming DTE2 campaign. The outputs, benefits and lessons learned associated with the production of this Safety Case are presented. The changes that have occurred to the Safety Case methodology since the last JET tritium Safety Case are reviewed. Consideration is given to the effects of modifications, particularly ITER related changes, made to the JET and the impact these have on the hazard assessments as well as normal operations. Several specialized assessments, including recent MELCOR modelling, have been undertaken to support the production of this Safety Case and the impact of these assessments is outlined. Discussion of the preliminary actions being taken to progress implementation of this Safety Case is provided, highlighting new methods to improve the dissemination of the key Safety Case results to the plant operators. Finally, the work required to complete this Safety Case, before the next tritium campaign, is summarized.

Sun Safety at Work Canada: a multiple case-study protocol to develop sun safety and heat protection programs and policies for outdoor workers.

Science.gov (United States)

Kramer, Desre M; Tenkate, Thomas; Strahlendorf, Peter; Kushner, Rivka; Gardner, Audrey; Holness, D Linn

2015-07-10

CAREX Canada has identified solar ultraviolet radiation (UV) as the second most prominent carcinogenic exposure in Canada, and over 75 % of Canadian outdoor workers fall within the highest exposure category. Heat stress also presents an important public health issue, particularly for outdoor workers. The most serious form of heat stress is heat stroke, which can cause irreversible damage to the heart, lungs, kidneys, and liver. Although the need for sun and heat protection has been identified, there is no Canada-wide heat and sun safety program for outdoor workers. Further, no prevention programs have addressed both skin cancer prevention and heat stress in an integrated approach. The aim of this partnered study is to evaluate whether a multi-implementation, multi-evaluation approach can help develop sustainable workplace-specific programs, policies, and procedures to increase the use of UV safety and heat protection. This 2-year study is a theory-driven, multi-site, non-randomized study design with a cross-case analysis of 13 workplaces across four provinces in Canada. The first phase of the study includes the development of workplace-specific programs with the support of the intensive engagement of knowledge brokers. There will be a three-points-in-time evaluation with process and impact components involving the occupational health and safety (OHS) director, management, and workers with the goal of measuring changes in workplace policies, procedures, and practices. It will use mixed methods involving semi-structured key informant interviews, focus groups, surveys, site observations, and UV dosimetry assessment. Using the findings from phase I, in phase 2, a web-based, interactive, intervention planning tool for workplaces will be developed, as will the intensive engagement of intermediaries such as industry decision-makers to link to policymakers about the importance of heat and sun safety for outdoor workers. Solar UV and heat are both health and safety hazards

Improving safety culture through the health and safety organization: a case study.

Science.gov (United States)

Nielsen, Kent J

2014-02-01

International research indicates that internal health and safety organizations (HSO) and health and safety committees (HSC) do not have the intended impact on companies' safety performance. The aim of this case study at an industrial plant was to test whether the HSO can improve company safety culture by creating more and better safety-related interactions both within the HSO and between HSO members and the shop-floor. A quasi-experimental single case study design based on action research with both quantitative and qualitative measures was used. Based on baseline mapping of safety culture and the efficiency of the HSO three developmental processes were started aimed at the HSC, the whole HSO, and the safety representatives, respectively. Results at follow-up indicated a marked improvement in HSO performance, interaction patterns concerning safety, safety culture indicators, and a changed trend in injury rates. These improvements are interpreted as cultural change because an organizational double-loop learning process leading to modification of the basic assumptions could be identified. The study provides evidence that the HSO can improve company safety culture by focusing on safety-related interactions. © 2013. Published by Elsevier Ltd and National Safety Council.

Communication on the Safety Case for a Deep Geological Repository

International Nuclear Information System (INIS)

Bailey, Lucy; Bernier, Frederik; Bollingerfehr, Wilhelm; Cunado, Miguel; Ilett, Doug; Kwong, Gloria; ); Noseck, Ulrich; Roehlig, Klaus; Van Luik, Abe; Weber, Jan; Weetjens, Eef

2017-01-01

Communication has a specific role to play in the development of deep geological repositories. Building trust with the stakeholders involved in this process, particularly within the local community, is key for effective communication between the authorities and the public. There are also clear benefits to having technical experts hone their communication skills and having communication experts integrated into the development process. This report has compiled lessons from both failures and successes in communicating technical information to non-technical audiences. It addresses two key questions in particular: what is the experience base concerning the effectiveness or non-effectiveness of different tools for communicating safety case results to a non-technical audience and how can communication based on this experience be improved and included into a safety case development effort from the beginning? (authors)

Confidence in the long-term safety of deep geological repositories. Its development and communication

International Nuclear Information System (INIS)

1999-01-01

The technical aspects of confidence have been the subject of considerable debate, especially the concept of model validation. The safety case that is provided at a particular stage in the planning, construction, operation or closure of a deep geological repository is a part of a broader decision basis that guides the repository-development process. The basic steps for deriving the safety case at various stages of repository development involve: a safety assessment; and the documentation of the safety assessment, a statement of confidence in the safety indicated by the assessment, and the confirmation of the appropriateness of the safety strategy. The approaches to establish confidence in the evaluation of safety should aim to ensure that the decisions taken within the incremental process of repository development are well-founded. Various aspects of confidence in the evaluation of safety, and their integration within a safety case, are presented in detail in the present report. When communicating confidence in the findings of a safety assessment, clarity in the communication of concepts is always required. Consistent with this requirement, key concepts are specifically defined in the main text of the report. (R.P.)

Safety case for license application for a final repository: The French example

International Nuclear Information System (INIS)

Boissier, Fabrice; Voinis, Sylvie

2014-01-01

The reversible repository in a deep geological formation is the French reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste (HLW and ILW). Twenty years of R and D work and conceptual and basic studies since the first French Act of 1991 led, in particular, to a feasibility demonstration in 2005. According to the French Act on Radioactive Waste of 28 of June 2006, Andra shall design a reversible repository in order to apply for license in 2015. In response to this demand, Andra developed the industrial project known as 'Cigeo', a reversible geological disposal facility for HLW and ILW located in Meuse/Haute-Marne. Two years before applying for authorisation, Andra's project is now focusing on three main targets: developing Cigeo's industrial design, preparing the authorisation process through increased exchanges with stakeholders and the preparation of a safety case to support authorisation application. The latter draws on the previous safety cases of 2005 and 2009, which give a sound basis to assess Cigeo's safety, both for the operational and post-closure periods. In this new stage of the project, the challenging issues for the preparation of the safety case are the following: - to identify the various regulatory frameworks (nuclear and non-nuclear) and guides applicable to the facility; - to ensure that the industrial design complies in particular with the safety requirements as presented in the safety case and its supporting safety assessment; - to identify crucial inputs (R and D, tests,...) needed to support the authorisation application, in particular, to bring convincing arguments to assess the technical feasibility of the design and when appropriate its ability to meet the safety requirements; - to ensure that all the requirements from previous regulatory and peer reviews (national and international?) are taken into account. (authors)

Developing safety in the nuclear fuel cycle

International Nuclear Information System (INIS)

Brown, M.L.

1996-01-01

The nuclear fuel cycle had its origins in the new technology developed in the 1940s and 50s involving novel physical and chemical processes. At the front end of the cycle, mining, milling and fuel fabrication all underwent development, but in general the focus of process development and safety concerns was the reprocessing stage, with radiation, contamination and criticality the chief hazards. Safety research is not over and there is still work to be done in advancing technical knowledge to new generation nuclear fuels such as Mixed Oxide Fuel and in refining knowledge of margins and of potential upset conditions. Some comments are made on potential areas for work. The NUCEF facility will provide many useful data to aid safety analysis and accident prevention. The routine operations in such plants, basically chemical factories, requires industrial safety and in addition the protection of workers against radiation or contamination. The engineering and management measures for this were novel and the early operation of such plants pioneering. Later commissioning and operating experience has improved routine operating safety, leading to a new generation of factories with highly developed worker protection, engineering safeguards and safety management systems. Ventilation of contamination control zones, remote operation and maintenance, and advanced neutron shielding are engineering examples. In safety management, dose control practices, formally controlled operating procedures and safety cases, and audit processes are comparable with, or lead, best industry practice in other hazardous industries. Nonetheless it is still important that the knowledge and experience from operating plants continue to be gathered together to provide a common basis for improvement. The NEA Working Group on Fuel Cycle Safety provides a forum for much of this interchange. Some activities in the Group are described in particular the FINAS incident reporting system. (J.P.N.)

Case study of physician leaders in quality and patient safety, and the development of a physician leadership network.

Science.gov (United States)

Hayes, Chris; Yousefi, Vandad; Wallington, Tamara; Ginzburg, Amir

2010-01-01

There is increasing recognition of the need for physician leadership in quality and patient safety, and emerging evidence that physician leadership contributes to improved care. Hospitals are beginning to establish physician leader positions; however, there is little guidance on how to define these roles and the strategies physician leaders can use toward improving care. This case study examines the roles of four physician leaders, describes their contribution to the design and implementation of hospital quality and patient safety agendas and discusses the creation of a physician network to support these activities. The positions were established between July 2006 and April 2009. All are corporate roles with varying reporting and accountability structures. The physician leads are involved in strategic planning, identifying and leading quality and safety initiatives, physician engagement and culture change. All have significantly contributed to the implementation of hospital improvement activities and are seen as influential among their peers as resources and mentors for local project success. Despite their accomplishments, these physician leads have been challenged by ambiguous role descriptions and difficulty identifying effective improvement strategies. As such, an expanding physician network was created with the goal of sharing approaches and tools and creating new strategies. Physician leaders are an important factor in the improvement of safety and quality within hospitals. This case study provides a template for the creation of such positions and highlights the importance of networking as an effective strategy for improving local care and advancing professional development of physician leaders in quality and patient safety.

A food recall case study in Australia – Towards the development of food safety applications for consumers

Directory of Open Access Journals (Sweden)

Adeola Bamgboje-Ayodele

2016-04-01

Full Text Available Changes in consumer attitudes, behaviours and purchasing preferences towards different types of food highlight the increased demand for better quality information on safety, quality and provenance of food products and on sustainability of food production processes. These changes offer both new opportunities and risks for food producers who require mechanisms to better understand and respond to changing consumers’ decision-making trends on food.  In the area of food safety, investigation of consumer and producer responses during recall incidents provide an opportunity to holistically understand existing information flows and elicit user requirements necessary for the development of more effective consumer food safety applications.This paper reports on a case study conducted with an Australian premium manufacturing company that experienced a food recall in 2014. The investigation confirms that current Australian food recall response mechanisms do not guarantee a closed loop of communication with all purchasers of a recalled product. It also highlights that producers still face difficulties in understanding how best to effectively understand and respond to different types of consumers. It emerges that recovery from a food incident relies on many factors including pre-existing brand reputation, effective information management, control mechanisms and supply chain partner response. From a consumer perspective, it is evident that consumers’ responses are influenced by various factors that require sensitivity around the choice of information modality and information platform adopted to enhance communications during food recall. The paper highlights the need for further research into understanding consumer food safety behaviours post-purchase to improve the development of consumer food safety applications.

Development of a Reality-Based Multimedia Case Study Teaching Method and Its Effect on Students' Planned Food Safety Behaviors

Science.gov (United States)

Alberts, Caitlin M.; Stevenson, Clinton D.

2017-01-01

There is opportunity to decrease the frequency of foodborne illnesses by improving food safety competencies and planned behaviors of college students before they begin careers in the food industry. The objectives of this study were to (1) develop a multimedia case study teaching method that provides real world context for food science education;…

Safety, safety case and society - Lessons from the experience of the Forum on Stakeholder Confidence and other NEA initiatives

International Nuclear Information System (INIS)

Pescatore, Claudio

2014-01-01

A vast amount of literature on radioactive waste management (RWM) and its governance is available on the web page of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA), in particular on the pages of the Forum on Stakeholder Confidence (FSC), the Reversibility and Retrievability (R and R) Project and the Project on Records, Knowledge and Memory (RK and M) Preservation across Generations. The FSC literature alone likely represents the largest collection of literature on RWM governance presently available on any single site. The safety case developed for any deep geological repository project deals with technical safety. A license is to be granted based on the repository being, after closure, safe 'by itself', i.e. without the need to watch it, independent of the existence of the implementer, regulator and others. The main legal requirement of the safety case is that it needs to show convincingly that the technical regulatory criteria are met. The latter are both qualitative and quantitative. Qualitative criteria are technical, but not in a strong sense, e.g. one requirement may simply be the use of 'sound technical and managerial principles'. The safety case also needs to argue robustness upon human intrusion. The human intrusion analyses, however, are only used to make a qualitative judgement on the robustness of the system. The international guidance suggests that their results need not be tested, by the authorities, for compliance against a numerical yardstick. The technical regulator will have an important role in decision making, but others aside from the technical regulator will also play a decision-making role in the development of a repository project and with regard to its safety. For instance, the technical regulator is largely removed from the initial choice of site. Safety nowadays is brought about by a system of actors comprising the implementer, technical regulators, specialist groups in various advisory roles and the

Behavior-based safety on construction sites: a case study.

Science.gov (United States)

Choudhry, Rafiq M

2014-09-01

This work presents the results of a case study and describes an important area within the field of construction safety management, namely behavior-based safety (BBS). This paper adopts and develops a management approach for safety improvements in construction site environments. A rigorous behavioral safety system and its intervention program was implemented and deployed on target construction sites. After taking a few weeks of safety behavior measurements, the project management team implemented the designed intervention and measurements were taken. Goal-setting sessions were arranged on-site with workers' participation to set realistic and attainable targets of performance. Safety performance measurements continued and the levels of performance and the targets were presented on feedback charts. Supervisors were asked to give workers recognition and praise when they acted safely or improved critical behaviors. Observers were requested to have discussions with workers, visit the site, distribute training materials to workers, and provide feedback to crews and display charts. They were required to talk to operatives in the presence of line managers. It was necessary to develop awareness and understanding of what was being measured. In the process, operatives learned how to act safely when conducting site tasks using the designed checklists. Current weekly scores were discussed in the weekly safety meetings and other operational site meetings with emphasis on how to achieve set targets. The reliability of the safety performance measures taken by the company's observers was monitored. A clear increase in safety performance level was achieved across all categories: personal protective equipment; housekeeping; access to heights; plant and equipment, and scaffolding. The research reveals that scores of safety performance at one project improved from 86% (at the end of 3rd week) to 92.9% during the 9th week. The results of intervention demonstrated large decreases in

Development of IFC based fire safety assesment tools

DEFF Research Database (Denmark)

Taciuc, Anca; Karlshøj, Jan; Dederichs, Anne

2016-01-01

Due to the impact that the fire safety design has on the building's layout and on other complementary systems, as installations, it is important during the conceptual design stage to evaluate continuously the safety level in the building. In case that the task is carried out too late, additional...... changes need to be implemented, involving supplementary work and costs with negative impact on the client. The aim of this project is to create a set of automatic compliance checking rules for prescriptive design and to develop a web application tool for performance based design that retrieves data from...... Building Information Models (BIM) to evacuate the safety level in the building during the conceptual design stage. The findings show that the developed tools can be useful in AEC industry. Integrating BIM from conceptual design stage for analyzing the fire safety level can ensure precision in further...

Improving occupational safety and health by integration into product development

DEFF Research Database (Denmark)

Broberg, Ole

1996-01-01

A cross-sectional case study was performed in a large company producing electro-mechanical products for industrial application. The objectives were: (i) to study the product development process and the role of key actors', (ii) to identify current practice on integrating occupational safety and h...... and studies of documents. A questionnaire regarding product development tasks and occupational safety and health were distributed to 30 design and production engineers. A total of 27 completed the questionnaire corresponding to a response rate of 90 per cent.......A cross-sectional case study was performed in a large company producing electro-mechanical products for industrial application. The objectives were: (i) to study the product development process and the role of key actors', (ii) to identify current practice on integrating occupational safety...... and health into the development process, especially the efforts and attitudes of design and production engineers', and (iii) to identify key actors'reflections on how to improve this integration. The study was based on qualitative as well as quantitative methods including interviews, questionnaires...

A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

Energy Technology Data Exchange (ETDEWEB)

Sevougian, S. David [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); MacKinnon, Robert J. [Advanced Nuclear Energy Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Leigh, Christi D. [Defense Waste Management Programs Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States); Hansen, Frank D. [Geoscience Research and Applications Group, Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185 (United States)

2013-07-01

The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

A Safety Case Approach for Deep Geologic Disposal of DOE HLW and DOE SNF in Bedded Salt - 13350

International Nuclear Information System (INIS)

Sevougian, S. David; MacKinnon, Robert J.; Leigh, Christi D.; Hansen, Frank D.

2013-01-01

The primary objective of this study is to investigate the feasibility and utility of developing a defensible safety case for disposal of United States Department of Energy (U.S. DOE) high-level waste (HLW) and DOE spent nuclear fuel (SNF) in a conceptual deep geologic repository that is assumed to be located in a bedded salt formation of the Delaware Basin [1]. A safety case is a formal compilation of evidence, analyses, and arguments that substantiate and demonstrate the safety of a proposed or conceptual repository. We conclude that a strong initial safety case for potential licensing can be readily compiled by capitalizing on the extensive technical basis that exists from prior work on the Waste Isolation Pilot Plant (WIPP), other U.S. repository development programs, and the work published through international efforts in salt repository programs such as in Germany. The potential benefits of developing a safety case include leveraging previous investments in WIPP to reduce future new repository costs, enhancing the ability to effectively plan for a repository and its licensing, and possibly expediting a schedule for a repository. A safety case will provide the necessary structure for organizing and synthesizing existing salt repository science and identifying any issues and gaps pertaining to safe disposal of DOE HLW and DOE SNF in bedded salt. The safety case synthesis will help DOE to plan its future R and D activities for investigating salt disposal using a risk-informed approach that prioritizes test activities that include laboratory, field, and underground investigations. It should be emphasized that the DOE has not made any decisions regarding the disposition of DOE HLW and DOE SNF. Furthermore, the safety case discussed herein is not intended to either site a repository in the Delaware Basin or preclude siting in other media at other locations. Rather, this study simply presents an approach for accelerated development of a safety case for a potential

A systematic approach and tool support for GSN-based safety case assessment

NARCIS (Netherlands)

Luo, Y.; Brand, M. van den; Li, Z.; Saberi, A.K.

2017-01-01

Context. In safety-critical domains, safety cases are widely used to demonstrate the safety of systems. A safety case is an argumentation for showing confidence in the claimed safety assurance of a system, which should be comprehensible and well-structured. Typically, safety cases can be represented

Safety case for the disposal of spent nuclear fuel at Olkiluoto - Synthesis 2012

International Nuclear Information System (INIS)

2012-12-01

TURVA-2012 is Posiva's safety case in support of the Preliminary Safety Analysis Report (PSAR 2012) and application for a construction licence for a spent nuclear fuel repository. Consistent with the Government Decisions-in- Principle, this foresees a repository developed in bedrock at the Olkiluoto site according to the KBS-3 method, designed to accept spent nuclear fuel from the lifetime operations of the Olkiluoto and Loviisa reactors. Synthesis 2012 presents a synthesis of Posiva Oy's Safety Case 'TURVA-2012' portfolio. It summarises the design basis for the repository at the Olkiluoto site, the assessment methodology and key results of performance and safety assessments. It brings together all the lines of argument for safety, evaluation of compliance with the regulatory requirements, and statement of confidence in long-term safety and Posiva's safety analyses. The TURVA-2012 safety case demonstrates that the proposed repository design provides a safe solution for the disposal of spent nuclear fuel, and that the performance and safety assessments are fully consistent with all the legal and regulatory requirements related to long-term safety as set out in Government Decree 736/2008 and in guidance from the nuclear regulator - the STUK. Moreover, Posiva considers that the level of confidence in the demonstration of safety is appropriate and sufficient to submit the construction licence application to the authorities. The assessment of long-term safety includes uncertainties, but these do not affect the basic conclusions on the long-term safety of the repository. (orig.)

Consideration of social scientific issues in a safety case. Final report

International Nuclear Information System (INIS)

Sailer, Michael; Kallenbach-Herbert, Beate; Brohmann, Bettina; Spieth-Achtnich, Angelika

2010-01-01

The research outcome presented here - a model for identifying and describing safety-relevant social scientific issues - provides a scientific basis for addressing these issues in a safety case. In order for them to be implemented in a repository process, it would be necessary to elaborate in greater detail the initial conceptual foundations that have been laid in this research project in line with the project's terms of reference. The requisite elaboration relates to binding rules for designing the repository process, particularly with regard to the stages in which the safety case is to be developed during planning, approval, construction and operation through to repository closure. Such detailed elaboration also needs to involve specifying the extent to which each social scientific issue and sub-issue is to be addressed in the different stages. Consideration would need to be given not only to the relevance of the issue for a given stage but also to the various options and methods for providing proof of safety. It would be possible to draw on experiences with handling safety management in nuclear power plants - a sphere in which over the last ten years efforts have been ongoing to develop methods for presentation by the operator and review by the authorities. Furthermore, it is likely that the social scientific issues relevant to a safety case cannot be defined once and for all in a single process, but that the need for continual revision and adaptation will arise due to both the increasing knowledge acquired during the course of the repository process and the experiences and expectations of stakeholders (similarly to experiences in the sphere of scientific-technological requirements). Appropriate conditions need to be defined for such a process. This process could be supported by implementing the option mentioned above whereby a regulatory definition of safety management for geological disposal is formulated which encompasses all safety-relevant social scientific

Natural safety indicators and their application to repository safety cases

International Nuclear Information System (INIS)

Miller, B.

2002-01-01

Radiological dose and risk are the standard end-points calculated in all performance assessments. Their calculation requires, however, assumptions to be made for future human behaviour. To complement dose and risk, other safety indicators have been suggested which do not require such assumptions to be made. One proposed set of safety indicators are the concentrations and fluxes of naturally-occurring chemical species in the environment which may be compared with the performance assessment predictions of repository releases. Such comparisons can be valid because both the natural and repository species would occur in the same system and their transport behaviour would be controlled by exactly the same processes at the same rates. Although simple in concept, there is currently no consensus on the most appropriate comparisons to make or on the interpretation of such comparisons. A number of national and international research projects are evaluating this proposed approach, including an IAEA Co-ordinated Research Programme. These projects suggest that that the approach appears to be workable and that it may be a valuable component of a safety case, complementing the dose and risk presentations. Further work is, however, necessary to develop the approach to a level where it may be confidently applied in further performance assessments in a consistent and methodical manner. (author)

Development of Strategic Goals of Road Safety Management: A Case Study of Montenegro

Directory of Open Access Journals (Sweden)

Milenko Čabarkapa

2016-12-01

Full Text Available Evaluation of the results of road safety management at the national level is carried out with a number of predefined indicators. These, predefined indicators should be measurable objectives of road safety management. They are set by national road safety strategies. This paper presents the control implementation of the Strategy to improve road safety in Montenegro for the period 2010-2019. The research showed that the five-year objectives of the National Strategy were achieved in the first years and significantly surmounted. This efficiency is achieved for two main reasons: the development of road safety management, and setting an unambitious, easily attainable goal. These findings are indicators that generally and globally set goals of reducing traffic fatalities cannot comprise at the same time national objectives in all countries. In this context, the methodological improvements of setting national strategic objectives established by the evidences on the national traffic safety issue are proposed.

Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 2-Domino Hazard Index and case study.

Science.gov (United States)

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

2008-12-15

The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design.

A framework for elaborating a geological disposal safety case: Main issues to be addressed

International Nuclear Information System (INIS)

Besnus, F.; Gay, D.

2002-01-01

International guidance on safety standards for the geological disposal of radioactive waste is being elaborated by IAEA. A comparison of experiences acquired in developing deep repository projects shows that many important issues related to the progressive building of confidence in the safety demonstration of such facilities are commonly addressed by the various organisations involved in radioactive waste management. However, there is still some discrepancies in defining the steps that form the staged elaboration of a safety case. This paper intends to propose a framework for defining the safety case in describing the main issues to be addressed and highlighting questions of consistency between former steps. (author)

Safety case for the disposal of spent nuclear fuel at Olkiluoto - Synthesis 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

TURVA-2012 is Posiva's safety case in support of the Preliminary Safety Analysis Report (PSAR 2012) and application for a construction licence for a spent nuclear fuel repository. Consistent with the Government Decisions-in- Principle, this foresees a repository developed in bedrock at the Olkiluoto site according to the KBS-3 method, designed to accept spent nuclear fuel from the lifetime operations of the Olkiluoto and Loviisa reactors. Synthesis 2012 presents a synthesis of Posiva Oy's Safety Case 'TURVA-2012' portfolio. It summarises the design basis for the repository at the Olkiluoto site, the assessment methodology and key results of performance and safety assessments. It brings together all the lines of argument for safety, evaluation of compliance with the regulatory requirements, and statement of confidence in long-term safety and Posiva's safety analyses. The TURVA-2012 safety case demonstrates that the proposed repository design provides a safe solution for the disposal of spent nuclear fuel, and that the performance and safety assessments are fully consistent with all the legal and regulatory requirements related to long-term safety as set out in Government Decree 736/2008 and in guidance from the nuclear regulator - the STUK. Moreover, Posiva considers that the level of confidence in the demonstration of safety is appropriate and sufficient to submit the construction licence application to the authorities. The assessment of long-term safety includes uncertainties, but these do not affect the basic conclusions on the long-term safety of the repository. (orig.)

The safety case for a HLW repository in Opalinus clay: aims, methodology, first results

International Nuclear Information System (INIS)

Zuidema, Piet

2002-01-01

Piet Zuidema (Nagra, Switzerland) described the development of the safety case for a high level waste repository in Opalinus clay in which canisters would be placed in large vaults. The current phase of work was concerned with demonstrating the feasibility of the disposal concept. The Safety Case is taken to mean a set of arguments to support a statement that the proposed facility will meet relevant safety criteria and will include arguments giving the basis for confidence that those arguments are correct and properly taking account of uncertainties. The safety strategy was concerned both with the inherent robustness of the disposal concept and the adequacy of the assessment capability. As regards the former, the arguments being advanced were primarily qualitative. Key issues in terms of the documentation of the Safety Case were traceability and transparency of information, including how to ensure that key arguments did not become obscured because of the need to make available very large quantities of information

Safety cases for radioactive waste disposal facilities: guidance on confidence building and regulatory review IAEA-ASAM co-ordinated research project

International Nuclear Information System (INIS)

Ben Belfadhel, M.; Bennett, D.G.; Metcalf, P.; Nys, V.; Goldammer, W.

2008-01-01

The IAEA has been conducting two co-ordinated research programmes (CRPs) projects to develop and apply improved safety assessment methodologies for near-surface radioactive waste disposal facilities. The more recent of these projects, ASAM (application of safety assessment methodologies), included a Regulatory Review Working Group (RRWG) which has been working to develop guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides an overview of the ASAM project, focusing on the safety case and regulatory review. (authors)

Safety training parks – A case study on the effectiveness of the trainings

DEFF Research Database (Denmark)

Räsänen, Tuula; Sormunen, E.; Reiman, Arto

The Safety Training Park (STP) concept is a unique Finnish safety training innovation. The STP provides different actors of the construction industry and other branches a practical occupational safety and health (OSH) training area. To the authors’ knowledge, no such parks exist in Europe besides...... Finland. Objec-tive was to study the effectiveness of the STP trainings at a large case company which participated in this study and which has actively trained its personnel in the park. The study was conducted from February 2015 to Feb-ruary 2017. Several key success factors were identified...... in the interviews of this case study. In addition, the company OSH statistics (2010 – 2016) showed a positive development at safety level. However, The Nordic Safety Climate Questionnaire did not show any significant change of results in a one year period. According to the results of the group interviews...

Application of software to development of reactor-safety codes

International Nuclear Information System (INIS)

Wilburn, N.P.; Niccoli, L.G.

1980-09-01

Over the past two-and-a-half decades, the application of new techniques has reduced hardware cost for digital computer systems and increased computational speed by several orders of magnitude. A corresponding cost reduction in business and scientific software development has not occurred. The same situation is seen for software developed to model the thermohydraulic behavior of nuclear systems under hypothetical accident situations. For all cases this is particularly noted when costs over the total software life cycle are considered. A solution to this dilemma for reactor safety code systems has been demonstrated by applying the software engineering techniques which have been developed over the course of the last few years in the aerospace and business communities. These techniques have been applied recently with a great deal of success in four major projects at the Hanford Engineering Development Laboratory (HEDL): 1) a rewrite of a major safety code (MELT); 2) development of a new code system (CONACS) for description of the response of LMFBR containment to hypothetical accidents, and 3) development of two new modules for reactor safety analysis

Development of safety related technology and infrastructure for safety assessment

International Nuclear Information System (INIS)

Venkat Raj, V.

1997-01-01

Development and optimum utilisation of any technology calls for the building up of the necessary infrastructure and backup facilities. This is particularly true for a developing country like India and more so for an advanced technology like nuclear technology. Right from the inception of its nuclear power programme, the Indian approach has been to develop adequate infrastructure in various areas such as design, construction, manufacture, installation, commissioning and safety assessment of nuclear plants. This paper deals with the development of safety related technology and the relevant infrastructure for safety assessment. A number of computer codes for safety assessment have been developed or adapted in the areas of thermal hydraulics, structural dynamics etc. These codes have undergone extensive validation through data generated in the experimental facilities set up in India as well as participation in international standard problem exercises. Side by side with the development of the tools for safety assessment, the development of safety related technology was also given equal importance. Many of the technologies required for the inspection, ageing assessment and estimation of the residual life of various components and equipment, particularly those having a bearing on safety, were developed. This paper highlights, briefly, the work carried out in some of the areas mentioned above. (author)

Geo-scientific Information in the Radioactive Waste Management Safety Case Main Messages from the AMIGO Project

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is associated with all phases of the nuclear fuel cycle as well as the use of radioactive materials in medicine, research and industry. For the most hazardous and long-lived waste, the solution being investigated worldwide is disposal in engineered repositories deep underground. The importance of geo-scientific information in selecting a site for geological disposal has long been recognised, but there has been growing acknowledgement of the broader role of this information in assessing and documenting the safety of disposal. The OECD/NEA Approaches and Methods for Integrating Geological Information in the Safety Case (AMIGO) project has demonstrated that geological data and understanding serve numerous roles in safety cases. The project, which ran from 2002 to 2008, underscored the importance of integrating geo-scientific information in the development of a disposal safety case and increasingly in the overall process of repository development, including, for example, siting decisions and ensuring the practical feasibility of repository layout and engineering. (authors)

Understanding lean & safety projects: analysis of case studies

Directory of Open Access Journals (Sweden)

Maria Crema

2017-12-01

Full Text Available Facing the current socio-economic contingency while guaranteeing a high level of care quality is particularly challenging in the field of healthcare. Through an integrated adoption of emerging managerial solutions, projects that allow organizations to achieve both efficiency and patient safety improvements could be implemented, thereby transposing policy directives towards a safer and more sustainable healthcare system. Therefore, the purpose of this paper is to investigate the features of Lean & Safety (L&S projects. Three Health Lean Management (HLM projects that had unexpected patient safety results were selected from the same region. Differences and similarities among the cases have been highlighted and interesting points of evidence have been noted. Despite the fact that the projects were pursuing similar objectives and benefiting from comparable support, the obtained changes had direct impact on patient safety enhancement in the cases that involved the front-office processes, and an indirect impact on patient safely for the L&S project that focused on back-office activities. The implementation processes and the Information and Communication Technologies (ICT adoption of the cases are also different.

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

International Nuclear Information System (INIS)

Sugawara, Shin-etsu; Inamura, Tomoaki

2016-01-01

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

Reactor safety research and development in Chalk River Laboratories

Energy Technology Data Exchange (ETDEWEB)

Nitheanandan, T. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

Atomic Energy of Canada Limited's Chalk River Laboratories provides three different services to stakeholders and customers. The first service provided by the laboratory is the implementation of Research and Development (R&D) programs to provide the underlying technological basis of safe nuclear power reactor designs. A significant portion of the Canadian R&D capability in reactor safety resides at Atomic Energy of Canada Limited's Chalk River Laboratories, and this capability was instrumental in providing the science and technology required to aid in the safety design of CANDU power reactors. The second role of the laboratory has been in supporting nuclear facility licensees to ensure the continued safe operation of nuclear facilities, and to develop safety cases to justify continued operation. The licensing of plant life extension is a key industry objective, requiring extensive research on degradation mechanisms, such that safety cases are based on the original safety design data and valid and realistic assumptions regarding the effect of ageing and management of plant life. Recently, Chalk River Laboratories has been engaged in a third role in research to provide the technical basis and improved understanding for decision making by regulatory bodies. The state-of-the-art test facilities in Chalk River Laboratories have been contributing to the R&D needs of all three roles, not only in Canada but also in the international community, thorough Canada's participation in cooperative programs lead by International Atomic Energy Agency and the OECD's Nuclear Energy Agency. (author)

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

Recent Cases: Administrative Law--Occupational Safety and Health Act

Science.gov (United States)

Harvard Law Review, 1976

1976-01-01

Implications of the Occupational Safety and Health Act of 1970 are described in two cases: Brennan v. Occupational Safety and Health Review Commission (Underhill Construction Corp.), and Anning-Johnson Co. v. United States Occupational Safety and Health Review Commission. (LBH)

Development of Safety-Critical Software for Nuclear Power Plant using a CASE Tool

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Ho; Oh, Do Young; Kim, Koh Eun; Choi, Woong Seock; Sohn, Se Do; Kim, Jae Hack; Kim, Hang Bae [KEPCO E and C, Daejeon (Korea, Republic of)

2011-08-15

The Integrated SOftware Development Environment (ISODE) is developed to provide the major S/W life cycle processes that are composed of development process, V/V process, requirements traceability process, and automated document generation process and target importing process to Programmable Logic Controller (PLC) platform. This provides critical safety software developers with a certified, domain optimized, model-based development environment, and the associated services to reduce time and efforts to develop software such as debugging, simulation, code generation and document generation. This also provides critical safety software verifiers with integrated V/V features of each phase of the software life cycle using appropriate tools such as model test coverage, formal verification, and automated report generation. In addition to development and verification, the ISODE gives a complete traceability solution from the SW design phase to the testing phase. Using this information, the coverage and impact analysis can be done easily whenever software modification is necessary. The final source codes of ISODE are imported into the newly developed PLC environment, as a module based after automatically converted into the format required by PLC. Additional tests for module and unit level are performed on the target platform.

Development of Safety-Critical Software for Nuclear Power Plant using a CASE Tool

International Nuclear Information System (INIS)

Kim, Chang Ho; Oh, Do Young; Kim, Koh Eun; Choi, Woong Seock; Sohn, Se Do; Kim, Jae Hack; Kim, Hang Bae

2011-01-01

The Integrated SOftware Development Environment (ISODE) is developed to provide the major S/W life cycle processes that are composed of development process, V/V process, requirements traceability process, and automated document generation process and target importing process to Programmable Logic Controller (PLC) platform. This provides critical safety software developers with a certified, domain optimized, model-based development environment, and the associated services to reduce time and efforts to develop software such as debugging, simulation, code generation and document generation. This also provides critical safety software verifiers with integrated V/V features of each phase of the software life cycle using appropriate tools such as model test coverage, formal verification, and automated report generation. In addition to development and verification, the ISODE gives a complete traceability solution from the SW design phase to the testing phase. Using this information, the coverage and impact analysis can be done easily whenever software modification is necessary. The final source codes of ISODE are imported into the newly developed PLC environment, as a module based after automatically converted into the format required by PLC. Additional tests for module and unit level are performed on the target platform

The Safety Case for Deep Geological Disposal of Radioactive Waste: 2013 State of the Art. Symposium Proceedings, 7-9 October 2013, Paris, France

International Nuclear Information System (INIS)

2014-01-01

In 2007, the Nuclear Energy Agency (NEA), in concert with the International Atomic Energy Agency (IAEA) and the European Commission (EC), organised a Symposium, entitled 'Safety Cases for the Deep Disposal of Radioactive Waste: Where Do We Stand?' (NEA, 2008). Since then, there have been major developments in a number of national geological disposal programmes and significant experience has been obtained in preparing and reviewing cases for the operational and long-term safety of proposed and operating geological repositories. Especially, three national programmes are now, or will shortly be, at the stage of licence application for a deep geological repository for the disposal of spent nuclear fuel or high-level and other long-lived radioactive waste. Thus, the purpose of this Symposium, 'The Safety Case for Deep Geological Disposal of Radioactive Waste: 2013 State of the Art', was to assess the practice, understanding and roles of the safety case, as applied internationally at all stages of repository development, including the interplay of technical, regulatory and societal issues, as they have developed since 2007. In particular, the symposium aims were: - to share experiences on preparing for, developing and documenting a safety case from both the implementer's and reviewer's perspectives; - to share developments in requirements, expectations and experience gained in judging the adequacy of safety cases; - to identify issues that may arise as repository programmes mature; - to understand the importance of a safety case in promoting and gaining societal confidence; - to gain experience from other fields of industry and technology in which concepts similar to the safety case are applied; - to receive indications useful to the future working programme of the NEA and other international organisations. The symposium was organised into main plenary sessions covering: - international activities and experience related to the safety case since 2007, including

Maximising workforce involvement in HSE (Health, Safety and Environment) case development

Energy Technology Data Exchange (ETDEWEB)

Vine, Mark D. (DNV Energy Middle East); Ingvarson, Johan [DNV Energy, Oslo (Norway)

2008-07-01

The development of HSE Cases demonstrating that HSE and particularly major accident hazard risks are being managed to an acceptable level is a requirement posed on many Oil and Gas facilities by regulators and stakeholders. In order to develop a demonstration case rather than a description and to ensure a truly live document, GASCO, one of the world's largest gas processing companies, turned to DNV to develop HSE Cases for all their facilities. The DNV approach included the use of Hazard and Effects Management Process (HEMP) and the development of a customised intranet solution to ensure a continuously living process. HEMP is a systematic method of identifying hazards, assessing risk, putting controls in place to guard against those risks and defining recovery measures should an incident happen. With GASCO, HEMP was implemented through workshops involving operation workforce from senior managers to supervisory level. A powerful and popular output of HEMP is the Bow Tie diagram which is used to graphically display HSE Critical Elements and the HSE Critical Activities and Tasks (i.e. operational systems) that support them. To ensure a living process, a dedicated GASCO intranet solution was developed where all users can easily access and contribute to the electronic HSE Case without any geographical constraints. The electronic case widens the user base and creates awareness among the workforce. The added value of the HEMP and intranet solution approach is that it focuses on capitalizing on knowledge and expertise present with those operating the facilities using a 'Cradle to the Grave' approach. It is essential to maximize the interface with the workforce in order to develop and maintain a comprehensive HSE Case. (author)

Rad waste disposal safety analysis / Integrated safety assessment of a waste repository

International Nuclear Information System (INIS)

Jeong, Jongtae; Choi, Jongwon; Kang, Chulhyung

2012-04-01

We developed CYPRUS+and adopted PID and RES method for the development of scenario. Safety performance assessment program was developed using GoldSim for the safety assessment of disposal system for the disposal of spnet fuels and wastes resulting from the pyrpoprocessing. Biosphere model was developed and verified in cooperation with JAEA. The capability to evaluate post-closure performance and safety was added to the previously developed program. And, nuclide migration and release to the biosphere considering site characteristics was evaluated by using deterministic and probabilistic approach. Operational safety assessment for drop, fire, and earthquake was also statistically evaluated considering well-established input parameter distribution. Conservative assessment showed that dose rate is below the limit value of low- and intermediate-level repository. Gas generation mechanism within engineered barrier was defined and its influence on safety was evaluated. We made probabilistic safety assessment by obtaining the probability distribution functions of important input variables and also made a sensitivity analysis. The maximum annual dose rate was shown to be below the safety limit value of 10 mSv/yr. The structure and element of safety case was developed to increase reliability of safety assessment methodology for a deep geological repository. Finally, milestone for safety case development and implementation strategy for each safety case element was also proposed

The safety case in support of the license application of the surface repository of low-level waste in Dessel, Belgium

International Nuclear Information System (INIS)

Wacquier, William; Cool, Wim

2014-01-01

The modern concept of the safety case, developed by the OECD/NEA for geological repositories of high- and medium-level waste has been successfully applied by ONDRAF/ NIRAS for a surface repository for Category A waste (i.e. low-level waste) in Belgium in the current project phase 2006-2012. This resulted in the submission on 31 January 2013 by ONDRAF/NIRAS of an application for a 'construction and operation license' to the safety authorities. The benefits of using the notion of the safety case have been that: i) safety has been incorporated in an integrated manner within all assessment basis, design and safety assessment activities; ii) the process of development of the license application has gained in clarity and traceability; iii) the documentation of the license application contains multiple lines of argumentation for safety rather than argumentation based only on quantitative radiological impact calculations. To offer a comprehensive view on the safety argumentation and its development, it has been found useful to develop the argumentation not only along a safety statements structure but also along the safety report structure. (authors)

Triangulating case-finding tools for patient safety surveillance: a cross-sectional case study of puncture/laceration.

Science.gov (United States)

Taylor, Jennifer A; Gerwin, Daniel; Morlock, Laura; Miller, Marlene R

2011-12-01

To evaluate the need for triangulating case-finding tools in patient safety surveillance. This study applied four case-finding tools to error-associated patient safety events to identify and characterise the spectrum of events captured by these tools, using puncture or laceration as an example for in-depth analysis. Retrospective hospital discharge data were collected for calendar year 2005 (n=48,418) from a large, urban medical centre in the USA. The study design was cross-sectional and used data linkage to identify the cases captured by each of four case-finding tools. Three case-finding tools (International Classification of Diseases external (E) and nature (N) of injury codes, Patient Safety Indicators (PSI)) were applied to the administrative discharge data to identify potential patient safety events. The fourth tool was Patient Safety Net, a web-based voluntary patient safety event reporting system. The degree of mutual exclusion among detection methods was substantial. For example, when linking puncture or laceration on unique identifiers, out of 447 potential events, 118 were identical between PSI and E-codes, 152 were identical between N-codes and E-codes and 188 were identical between PSI and N-codes. Only 100 events that were identified by PSI, E-codes and N-codes were identical. Triangulation of multiple tools through data linkage captures potential patient safety events most comprehensively. Existing detection tools target patient safety domains differently, and consequently capture different occurrences, necessitating the integration of data from a combination of tools to fully estimate the total burden.

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Terrain and ecosystems development modelling in the biosphere assessment BSA-2012

International Nuclear Information System (INIS)

2013-12-01

This report is one of the four supporting reports for the three main biosphere reports in the safety case for the disposal of spent nuclear fuel at Olkiluoto, 'TURVA-2012'. The focus of this report is to detail the scenario analysis of terrain and ecosystems development at the Olkiluoto repository site within a time frame of 10 000 years, whereas the input data to this modelling is detailed in the Data Basis report. The results are used further especially in the surface and near-surface hydrological modelling and in the biosphere radionuclide transport and dose modelling, both part of the biosphere assessment 'BSA-2012' feeding into the safety case. Based on the results of the 18 cases simulated in the scenario analysis, it can be outlined that the most significant differences in respect of the dose implications of the repository arise from the inputs and settings affecting the rate of coastline retreat (i.e. land uplift and sea level) and determining whether there are croplands or not in the area. (orig.)

Developing and implementing safety culture in the uses of radiation sources

International Nuclear Information System (INIS)

Rojkind, R.H.

1998-01-01

This paper presents an approach to develop and implement safety culture in the uses of radiation sources in medicine, industry, agriculture, research and teaching, and makes reference to the experience gained by the industries where that culture has been developed and improved, i.e. the nuclear industry. Suggestions to assist progress toward safety culture are here described for regulators, organisations using those sources, and professional associations. Even though emphasis is given to small organisations or teams of workers, this approach may be also useful to greater organisations like industrial irradiation companies or governmental research laboratories. In each case, parties being the principal focus of the learning process toward a progressive safety culture should be identified. (author)

IRSN safety research carried out for reviewing safety cases

International Nuclear Information System (INIS)

Serres, Ch.

2010-01-01

Christophe Serres from IRSN (France) described the independent role of the IRSN regarding research related to nuclear safety in the context of the French Planning Act of 28 June 2006 foreseeing a licence application to be submitted in 2015 for the creation of a deep geological repository. IRSN research programme is organised along research activities devoted to addressing independently-identified k ey safety issues . These 'key issues' should also be of prime concern for the implementer since they relate to the demonstration of the overall safety of the repository, and the level of funding that the implementer should afford to research activities of concern for safety. He explained that the quality and independency of the research programme carried out by IRSN allow building and improving a set of scientific knowledge and technical skills that serves the public mission of delivering technical appraisal and advice, e.g., on behalf of the national safety authority. In particular they contribute to improving the decisional process by making possible scientific dialogue with stakeholders independently from regulator or implementer. The current IRSN R and D programme is developed along the following lines: - Test the adequacy of experimental methods for which feedback is not sufficient. - Develop basic scientific knowledge in the fields where there is a need for better understanding of complex phenomena and interactions. - Develop and use numerical modelling tools to support studies on complex phenomena and interactions. - Perform specific experimental tests aiming at assessing the key parameters that may warrant the performances of the different components of the repository. These studies are carried out by means of experiments performed either at IRSN surface laboratories, or in the Tournemire Experimental Station (TES), an underground facility operated by IRSN in the south-east of France. Targeted actions on research related to operational safety and reversibility

Development of a Safety Management Web Tool for Horse Stables.

Science.gov (United States)

Leppälä, Jarkko; Kolstrup, Christina Lunner; Pinzke, Stefan; Rautiainen, Risto; Saastamoinen, Markku; Särkijärvi, Susanna

2015-11-12

Managing a horse stable involves risks, which can have serious consequences for the stable, employees, clients, visitors and horses. Existing industrial or farm production risk management tools are not directly applicable to horse stables and they need to be adapted for use by managers of different types of stables. As a part of the InnoEquine project, an innovative web tool, InnoHorse, was developed to support horse stable managers in business, safety, pasture and manure management. A literature review, empirical horse stable case studies, expert panel workshops and stakeholder interviews were carried out to support the design. The InnoHorse web tool includes a safety section containing a horse stable safety map, stable safety checklists, and examples of good practices in stable safety, horse handling and rescue planning. This new horse stable safety management tool can also help in organizing work processes in horse stables in general.

Statistical modelling of traffic safety development

DEFF Research Database (Denmark)

Christens, Peter

2004-01-01

there were 6861 injury trafficc accidents reported by the police, resulting in 4519 minor injuries, 3946 serious injuries, and 431 fatalities. The general purpose of the research was to improve the insight into aggregated road safety methodology in Denmark. The aim was to analyse advanced statistical methods......, that were designed to study developments over time, including effects of interventions. This aim has been achieved by investigating variations in aggregated Danish traffic accident series and by applying state of the art methodologies to specific case studies. The thesis comprises an introduction...

Safety Case for Safe-store

International Nuclear Information System (INIS)

Woollam, Paul B.

2002-01-01

Magnox Electric plc (Magnox), a wholly owned subsidiary of BNFL, owns 26 gas-cooled, graphite-moderated units on 11 sites in the UK. Eight units have been permanently shutdown and the remainder will shut this decade in a currently declared closure programme. The first of these reactors went to power in 1952 and the fleet has generated typically 9% of the UK's electricity during the last five decades. In accordance with UK Government policy, BNFL aims for a systematic and progressive reduction in hazards on its decommissioning sites. The end-point of the decommissioning process is that the reactors will be dismantled and their sites de-licensed. This will be done through minimising both the risks to the public, workers and the environment and also the lifetime cost, consistent with world class safety. There will be passive safe storage during deferment periods and it is BNFL's clear intent that the reactors will not be Safe-stored indefinitely. The main hazard associated with any decommissioned nuclear site is the spent fuel. Hence the reactors will be de-fuelled as soon as practicable after shutdown. After this work is complete, Cs-137 contaminated plant (e.g. fuel pools, effluent plant, and drains) will be dismantled when it is no longer needed. All other plant and buildings will also be dismantled when they are no longer needed, except for the reactor buildings which will be put into passive safe storage. Co-60 contaminated plant, such as steam generators, will be dismantled with the reactors. The reactors will be dismantled in a sequenced programme, with a notional start time around 100 years from shutdown. Magnox Electric is ensuring that the reactors and primary circuits on all its sites are well characterised. We have carried out a detailed, peer reviewed hazard identification on the lead site from which we have generated a rolling 25-year basic safety case. We have then searched for cliff edge effects and possible long-term changes to generate the 100-year

Patient involvement in patient safety: Protocol for developing an intervention using patient reports of organisational safety and patient incident reporting

Directory of Open Access Journals (Sweden)

Armitage Gerry

2011-05-01

Full Text Available Abstract Background Patients have the potential to provide a rich source of information on both organisational aspects of safety and patient safety incidents. This project aims to develop two patient safety interventions to promote organisational learning about safety - a patient measure of organisational safety (PMOS, and a patient incident reporting tool (PIRT - to help the NHS prevent patient safety incidents by learning more about when and why they occur. Methods To develop the PMOS 1 literature will be reviewed to identify similar measures and key contributory factors to error; 2 four patient focus groups will ascertain practicality and feasibility; 3 25 patient interviews will elicit approximately 60 items across 10 domains; 4 10 patient and clinician interviews will test acceptability and understanding. Qualitative data will be analysed using thematic content analysis. To develop the PIRT 1 individual and then combined patient and clinician focus groups will provide guidance for the development of three potential reporting tools; 2 nine wards across three hospital directorates will pilot each of the tools for three months. The best performing tool will be identified from the frequency, volume and quality of reports. The validity of both measures will be tested. 300 patients will be asked to complete the PMOS and PIRT during their stay in hospital. A sub-sample (N = 50 will complete the PMOS again one week later. Health professionals in participating wards will also be asked to complete the AHRQ safety culture questionnaire. Case notes for all patients will be reviewed. The psychometric properties of the PMOS will be assessed and a final valid and reliable version developed. Concurrent validity for the PIRT will be assessed by comparing reported incidents with those identified from case note review and the existing staff reporting scheme. In a subsequent study these tools will be used to provide information to wards/units about their

Safety of Silicone Oil Removal in Cases of Gunshot Perforating Eye Injuries.

Science.gov (United States)

Ghoraba, Hammouda Hamdy; Elgouhary, Sameh Mohamed; Mansour, Hosam Osman; Abdel-Fattah, Hitham Mamoun; Heikal, Mohamed Amin; Elgemaey, Emad Mohamed

2017-03-01

To evaluate the feasibility and safety of silicone oil (SO) removal in cases of gunshot perforating eye injuries (PEI). A retrospective, consecutive, interventional study from medical records regarding cases of gunshot PEI during the periods of Egyptian political instability (January 2011 until December 2013). The main outcomes were to evaluate the feasibility of SO removal in cases of gunshot PEI and management of retinal detachment (RD) after SO removal in such cases. One hundred ninety-six eyes of 193 patients were reviewed. SO was removed in 72 eyes of 70 patients (36.7%). After SO removal, five eyes (6.9%) developed RD. One case refused any other intervention. RD in the remaining four cases was treated with revision surgery and SO reinjection. The retina remained stable throughout follow-up. None of the eyes developed phthisis bulbi after SO removal. Mean follow-up after SO removal was 10.86 months (range: 3 months to 30 months). Mean follow-up after management of RD after SO removal was 17.7 months (range: 13 months to 21 months). Patients aged younger than 20 years were associated with extensive fibrous proliferation, which might affect the safety profile of SO removal in cases of gunshot PEI. Rate of RD after SO removal in cases of apparent retinal stability and localized fibrous proliferation was 6.9%. Retinal detachment after SO removal in such cases can be treated with revision surgery and SO reinjection. [Ophthalmic Surg Lasers Imaging Retina. 2017;48:242-250.]. Copyright 2017, SLACK Incorporated.

The Safety Case and the Risk-Informed Performance-Based Approach for Management of US Commercial Low Level Radioactive Waste (LLRW)

International Nuclear Information System (INIS)

Abu-Eid, Rateb; Esh, David; Grossman, Chrisopher

2016-01-01

Summary/Conclusion Safety Case & 10 CFR Part 61: • Safety Case is an integrated approach to risk assessment and risk management. • NRC staff explicitly added “the safety case” concept in the ongoing amendment of 10 CFR Part 61, at the direction of Commission. • Plain language description the safety arguments and evidence to demonstrate the overall safety of a land disposal facility were developed. • It describes all safety relevant aspects of the disposal site, the design of the facility, and the managerial control measures and regulatory controls to inform the decision whether to grant a license. • It includes the same type of information that the original 10 CFR Part 61 required to be submitted as part of a license application (i.e., 10 CFR 61.10 – 10 CFR 61.16). • The safety case will be updated over time as a new information is gained during the various phases of the facility’s development, inspection, and operation. • 10 CFR Part 61 SC is quite consistent with IAEA SSG-23 with more detailed technical analysis.

Work safety and sustainable development in enterprise

Institute of Scientific and Technical Information of China (English)

TANG Min-kang; ZHOU Yue; XU Jian-hong

2005-01-01

The nature of work safety and the way insisting on sustainable development in enterprise were analyzed. It indicates that problem of work safety in enterprise is closely related to the public's consciousness, to the development of science and technology, and to the weakening of safety management during the economic transition period. However, it is the people's questions concerned in the final analysis for the forming and development of the problem of work safety. Therefore, in order to solve the problem of work safety radically, the most basic way of insisting on the sustainable development in safety administration is to do a good job of every aspect about people. We should improve all people quality in science and culture and strengthen their safety and legal consciousness to form correct safety value concept. We should fortify safety legislation and bring close attention to approach and apply new safety technology.

Developing a strong safety culture - a safety management challenge

International Nuclear Information System (INIS)

Low, M.; Gipson, G. P.; Williams, M.

1995-01-01

The approach is presented adapted by Nuclear Electric to build a strong safety culture through the development of its safety management system. Two features regarded as critical to a strong safety culture are: provision of effective communications to promote an awareness and ownership of safety among craft, and commitment to continuous improvement with a genuine willingness to learn from own experiences and those from others. (N.T.) 5 refs., 4 figs., 1 tab

Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project

International Nuclear Information System (INIS)

Duro, L.; Bruno, J.; Grivé, M.; Montoya, V.; Kienzler, B.; Altmaier, M.; Buckau, G.

2014-01-01

Highlights: • The RECOSY project produced results relevant for the Safety Case of nuclear disposal. • We classify the safety related features where RECOSY has contributed. • Redox processes effect the retention of radionuclides in all repository subsystems. - Abstract: Redox processes influence key geochemical characteristics controlling radionuclide behaviour in the near and far field of a nuclear waste repository. A sound understanding of redox related processes is therefore of high importance for developing a Safety Case, the collection of scientific, technical, administrative and managerial arguments and evidence in support of the safety of a disposal facility. This manuscript presents the contribution of the specific research on redox processes achieved within the EURATOM Collaborative Project RECOSY (REdox phenomena COntrolling SYstems) to the Safety Case of nuclear waste disposal facilities. Main objectives of RECOSY were related to the improved understanding of redox phenomena controlling the long-term release or retention of radionuclides in nuclear waste disposal and providing tools to apply the results to Performance Assessment and the Safety Case. The research developed during the project covered aspects of the near-field and the far-field aspects of the repository, including studies relevant for the rock formations considered in Europe as suitable for hosting an underground repository for radioactive wastes. It is the intention of this paper to highlight in which way the results obtained from RECOSY can feed the scientific process understanding needed for the stepwise development of the Safety Case associated with deep geological disposal of radioactive wastes

RADON-type disposal facility safety case for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Guskov, A.; Batanjieva, B.; Kozak, M.W.; Torres-Vidal, C.

2002-01-01

The ISAM safety assessment methodology was applied to RADON-type facilities. The assessments conducted through the ISAM project were among the first conducted for these kinds of facilities. These assessments are anticipated to lead to significantly improved levels of safety in countries with such facilities. Experience gained though this RADON-type Safety Case was already used in Russia while developing national regulatory documents. (author)

Road safety in developing countries.

NARCIS (Netherlands)

Schreuder, D.A.

1991-01-01

This paper presents a classification of countries (developing and developed alike), divided into two main categories: an economical and historical entry. When road safety problems are placed into the economical context, it then appears that, among other things: (1) The road safety problem in the

Development of the status of W and T for the realization of a long-term safety demonstration for the final repository using the examples VSG and Konrad. Report on the Working package 2. Review and development of safety-related assessments of disposal facilities of wastes with negligible heat generation; development and provision of the necessary set of tools using the example of the final repository Konrad

International Nuclear Information System (INIS)

Larue, Juergen; Fischer-Appelt, Klaus; Hartwig-Thurat, Eva

2015-09-01

In the research project on the ''Review and development of safety-related assessments of disposal facilities with negligible heat generation; development and provision of the necessary set of tools, using the example of the Konrad disposal facility'' (3612R03410), the state of the art in science and technology of the safety-related assessments and sets of tools for building a safety case was examined. The reports pertaining to the two work packages described the further development of the methodology for accident analyses (WP 1) and of building a safety case (WP 2); also, comparisons were drawn on a national and international scale with the methods applied in the licensing procedure of the Konrad disposal facility. A safety case as well as its underlying analyses and methods always has to be brought up to date with the development of the state of the art in science and technology. In Germany, two safety cases regarding the long-term safety of disposal facilities have been prepared. These are the licensing documentation for the Konrad disposal facility in the year 1990 and the research project regarding the preliminary safety case for the Gorleben site (Vorlaeufige Sicherheitsanalyse Gorleben - VSG) in the year 2013, both reflecting the state of development of building a safety case at the respective time. Comparing the two above-mentioned examples of safety cases and taking recent international recommendations and national regulations into account, this report on Work Package 2 presents the development of the international state of the art in science and technology. This has been done by summarising the essential differences and similarities of each element of the safety case for the Konrad disposal facility on the one hand and the VSG and the international status on the other hand.

Discussion on the Criterion for the Safety Certification Basis Compilation - Brazilian Space Program Case

Science.gov (United States)

Niwa, M.; Alves, N. C.; Caetano, A. O.; Andrade, N. S. O.

2012-01-01

The recent advent of the commercial launch and re- entry activities, for promoting the expansion of human access to space for tourism and hypersonic travel, in the already complex ambience of the global space activities, brought additional difficulties over the development of a harmonized framework of international safety rules. In the present work, with the purpose of providing some complementary elements for global safety rule development, the certification-related activities conducted in the Brazilian space program are depicted and discussed, focusing mainly on the criterion for certification basis compilation. The results suggest that the composition of a certification basis with the preferential use of internationally-recognized standards, as is the case of ISO standards, can be a first step toward the development of an international safety regulation for commercial space activities.

Setting clear expectations for safety basis development

International Nuclear Information System (INIS)

MORENO, M.R.

2003-01-01

DOE-RL has set clear expectations for a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (10 CFR 830, Nuclear Safety Rule) which will ensure long-term benefit to Hanford. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development resulting in a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was issued to standardized methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was issued for the evaluation of radiological consequences for accident scenarios often postulated for Hanford. A standard Site Documented Safety Analysis (DSA) detailing the safety management programs was issued for use as a means of compliance with a majority of 3009 Standard chapters. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. As a result of setting expectations and providing safety analysis tools, the four Hanford Site waste management nuclear facilities were able to integrate into one Master Waste Management Documented Safety Analysis (WM-DSA)

Sustainable Development of Food Safety

DEFF Research Database (Denmark)

Fabech, B.; Georgsson, F.; Gry, Jørn

to food safety - Strengthen efforts against zoonoses and pathogenic microorganisms - Strengthen safe food handling and food production in industry and with consumers - Restrict the occurrence of chemical contaminants and ensure that only well-examined production aids, food additives and flavours are used...... - Strengthen scientific knowledge of food safety - Strengthen consumer knowledge The goals for sustainable development of food safety are listed from farm to fork". All of the steps and areas are important for food safety and consumer protection. Initiatives are needed in all areas. Many of the goals...... in other areas. It should be emphasized that an indicator will be an excellent tool to assess the efficacy of initiatives started to achieve a goal. Conclusions from the project are: - Sustainable development in food safety is important for humanity - Focus on the crucial goals would optimize the efforts...

Technical organization of safety authorities in case of accident in a nuclear installation

International Nuclear Information System (INIS)

Scherrer, J.; Evrard, J.M.; Ney, J.

1985-11-01

The Central safety Service of Nuclear Facilities of the French industry Department and the CEA Protection and Nuclear Safety Institut (IPSN) are organized to estimate in real time, the evolution of an accidental situation with a sufficient margin in time to allow the local government representative to develop, in case of necessity, efficient procedures for the protection of the population. This paper presents the principles of this organization and the precautions taken to cope as well with problems of mobilization of experts as the full occupation of current telecommunication lines. The example of the organization concerning the installations of Electricite de France is detailed. The CEA IPSN has developed means widely advanced, concerning the atmospheric transfer of radioactivity. For PWRs, a method allowing to forecast releases in case of accidental situation is presented. Finally, the knowledge acquired with the accident simulations realized during the last years is described [fr

Bow tie methodology: a tool to enhance the visibility and understanding of nuclear safety cases

International Nuclear Information System (INIS)

Vannerem, Marc

2013-01-01

There is much common ground between the nuclear industry and other major hazard industries such as those subject to the Seveso II regulations, e.g. oil, gas and chemicals. They are all subject to legal requirements to identify and control hazards, and to demonstrate that all necessary measures have been taken to minimise risks posed by the site with regard to people and the environment. This places a requirement on the Operators of major hazard installations, whether nuclear or conventional, to understand and identify the hazards of their operations, the initiating events, the consequences, the prevention and mitigation measures. However, in the UK, nuclear and 'Seveso' type facilities seem to adopt a different approach to the presentation of their safety cases. Given the magnitude of the hazards, safety cases developed for nuclear fuel cycle facilities are rigorous, detailed and complex, which can have the effect of reducing the visibility of the key hazards and corresponding protective measures. In contrast, on installations in the oil and gas and chemical industries, a real attempt has been made over recent years to improve the visibility and accessibility of the safety case to all operating personnel, through the use of visual aids / diagrams. In particular, many Operators are choosing to use 'bow tie methodology', in which very simple overview diagrams are produced to illustrate, in a form understandable by all: - what the key hazards are; - the initiating events; - the consequences of an incident; - the barriers or 'Layers of Protection' which prevent an initiating event from developing into an incident; - the barriers or 'Layers of Defence' which mitigate the consequences of an incident, i.e. which prevent the incident from escalating into major consequences. The bow tie method is one of a number of methodologies that can be used to make safety cases more accessible. It is used in this paper to illustrate ways to

Cementitious Materials in Safety Cases for Geological Repositories for Radioactive Waste: Role, Evolution and Interactions. A Workshop organised by the OECD/NEA Integration Group for the Safety Case and hosted by ONDRAF/NIRAS. Cementitious materials in safety cases for radioactive waste: role, evolution and interactions

International Nuclear Information System (INIS)

2012-01-01

The OECD Nuclear Energy Agency (NEA) Integration Group for the Safety Case (IGSC) organised a workshop to assess current understanding on the use of cementitious materials in radioactive waste disposal. The workshop was hosted by the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (Ondraf/Niras), in Brussels, Belgium on 17-19 November 2009. The workshop brought together a wide range of people involved in supporting safety case development and having an interest in cementitious materials: namely, cement and concrete experts, repository designers, scientists, safety assessors, disposal programme managers and regulators. The workshop was designed primarily to consider issues relevant to the post-closure safety of radioactive waste disposal, but also addressed some related operational issues, such as cementitious barrier emplacement. Where relevant, information on cementitious materials from analogous natural and anthropogenic systems was also considered. This report provides a synthesis of the workshop, and summarises its main results and findings. The structure of this report follows the workshop agenda: - Section 2 summarises plenary and working group discussions on the uses, functions and evolution of cementitious materials in geological disposal, and highlights key aspects and discussions points. - Section 3 summarises plenary and working group discussions on interactions of cementitious materials with other disposal system components, and highlights key aspects and discussions points. - Section 4 summarises the workshop session on the integration of issues related to cementitious materials using the safety case. - Section 5 presents the main conclusions from the workshop. - Section 6 contains a list of references. - Appendix A presents the workshop agenda. - Appendix B contains the abstracts and, where provided, technical papers supporting oral presentations at the workshop. - Appendix C contains the abstracts and, where provided, technical

Safety guides development process in Spain

International Nuclear Information System (INIS)

Butragueno, J.L.; Perello, M.

1979-01-01

Safety guides have become a major factor in the licensing process of nuclear power plants and related nuclear facilities of the fuel cycle. As far as the experience corroborates better and better engineering methodologies and procedures, the results of these are settled down in form of standards, guides, and similar issues. This paper presents the actual Spanish experience in nuclear standards and safety guides development. The process to develop a standard or safety guide is shown. Up to date list of issued and on development nuclear safety guides is included and comments on the future role of nuclear standards in the licensing process are made. (author)

The development of safety requirements

International Nuclear Information System (INIS)

Jorel, M.

2009-01-01

This document describes the safety approach followed in France for the design of nuclear reactors. This safety approach is based on safety principles from which stem safety requirements that set limiting values for specific parameters. The improvements in computerized simulation, the use of more adequate new materials, a better knowledge of the concerned physical processes, the changes in the reactor operations (higher discharge burnups for instance) have to be taken into account for the definition of safety criteria and the setting of limiting values. The developments of the safety criteria linked to the risks of cladding failure and loss of primary coolant are presented. (A.C.)

Safety standards for near surface disposal and the safety case and supporting safety assessment for demonstrating compliance with the standards

International Nuclear Information System (INIS)

Metcalf, P.

2003-01-01

The report presents the safety standards for near surface disposal (ICRP guidance and IAEA standards) and the safety case and supporting safety assessment for demonstrating compliance with the standards. Special attention is paid to the recommendations for disposal of long-lived solid radioactive waste. The requirements are based on the principle for the same level of protection of future individuals as for the current generation. Two types of exposure are considered: human intrusion and natural processes and protection measures are discussed. Safety requirements for near surface disposal are discussed including requirements for protection of human health and environment, requirements or safety assessments, waste acceptance and requirements etc

Development of safety analysis technology for integral reactor

Energy Technology Data Exchange (ETDEWEB)

Sim, Suk K.; Song, J. H.; Chung, Y. J. and others

1999-03-01

Inherent safety features and safety system characteristics of the SMART integral reactor are investigated in this study. Performance and safety of the SMART conceptual design have been evaluated and confirmed through the performance and safety analyses using safety analysis system codes as well as a preliminary performance and safety analysis methodology. SMART design base events and their acceptance criteria are identified to develop a preliminary PIRT for the SMART integral reactor. Using the preliminary PIRT, a set of experimental program for the thermal hydraulic separate effect tests and the integral effect tests was developed for the thermal hydraulic model development and the system code validation. Safety characteristics as well as the safety issues of the integral reactor has been identified during the study, which will be used to resolve the safety issues and guide the regulatory criteria for the integral reactor. The results of the performance and safety analyses performed during the study were used to feedback for the SMART conceptual design. The performance and safety analysis code systems as well as the preliminary safety analysis methodology developed in this study will be validated as the SMART design evolves. The performance and safety analysis technology developed during the study will be utilized for the SMART basic design development. (author)

The case for nuclear energy. Chapter 2. Nuclear safety and energy security

International Nuclear Information System (INIS)

Trosman, G.

2010-01-01

The U.S. nuclear safety assistance activities have had a direct and substantial impact on improving safe operations of 67 Soviet-designed commercial nuclear power plants in Armenia, Bulgaria, Czech Republic, Hungary, Kazakhstan, Lithuania, Russia, Slovakia, and Ukraine. The U.S. Department of Energy worked with these host countries both to improve safe nuclear operations and in some cases assist in plant shutdown. Independent international safety reviews have identified significant progress in the Eastern European countries to improve the safety of their nuclear power plants since the early 1990s. In addition, all of the probabilistic risk assessments conducted at these plants show a major reduction in the frequency of core damage accidents since U.S. assistance to improve safety at these reactors began. Improved operational safety follows from the combined efforts to improve operator performance. These efforts include providing simulators for operators to practice handling emergency scenarios, developing emergency operating instructions that guide operators calmly through emergencies, providing safety parameter display systems that give operators immediate graphical information on the status of plant systems and training the operators on the safety basis for the plants they operate

Chinese consumers concerns about food safety: Case of Tianjin

NARCIS (Netherlands)

Zhang XiaoYong, Xiaoyong

2005-01-01

The objective of this study is to gain an insight to Chinese consumers' knowledge and concerns over food safety from a case study in Tianjin city. The results indicate that Chinese consumers are very much concerned about food safety, particularly with regard to vegetables and dairy products. Chinese

Safety cases for the co-ordinated research project on improvement of safety assessment methodologies for near surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Kozak, M.W.; Torres-Vidal, C.; Kelly, E.; Guskov, A.; Blerk, J. van

2002-01-01

A Co-ordinated Research Project (CRP) has recently been completed on the Improvement of Safety Assessment Methodologies for Near-Surface Radioactive Waste Disposal Facilities (ISAM). A major aspect of the project was the use of safety cases for the practical application of safety assessment. An overview of the ISAM safety cases is given in this paper. (author)

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

Science.gov (United States)

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

2017-07-01

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

Experience of Tecnatom in Developing a Strong Leadership for Safety and Performance

International Nuclear Information System (INIS)

González, F.; Villadóniga, J. I.

2016-01-01

This paper presents experience and insights of Tecnatom in the support of internal and external clients to develop a strong Leadership for Safety. Several cases are presented briefly: (a) The leadership and culture change activities for a utility, a radwaste company, and for Tecnatom itself. One important characteristic of the work performed is the detailed consideration of the underlying organizational culture that underpins the safety culture. Measurable improvements have been achieved and some of the key insights are shared in this paper. (b) The development and implementation of a leadership model with 17 competencies, including safety explicitly. One benefit of this model is that allows to perform a quantitative assessment of leadership effectiveness, something vital to be able to ensure that leadership development actions are truly supporting safety. The model uses an approach to development oriented to strengths and the use of companion competencies to further develop leadership. Moreover it aims to produce significant improvements on safety but also on performance, since both are not competing goals when the proper leadership model is selected. The training material prepared was shortlisted in the 2014 Nuclear Training Awards. (c) The design and implementation of a training development program on Safety Culture, and required competencies of Leadership, for Top Managers of the nuclear industry, as part of the project NUSHARE of the European Commission’s 7th research framework program. The program is sensible to the reduced time availability of Top Managers and uses a combination of learning approaches (webinars, micro-elearnings, web meetings) that provide higher flexibility for the learner, but complemented with other proven methods (group dialog, journaling, mentoring, etc.) to ensure that the program is effective. All these experiences reveal that to improve the organizational Safety Culture we need to enhance Leadership for Safety and Performance

Sign up to Safety: developing a safety improvement plan.

Science.gov (United States)

Dight, Carol; Peters, Hayley

2015-04-01

The Sign up to Safety (SutS) programme was launched in June 2014 by health secretary Jeremy Hunt. It focuses on listening to patients, carers and staff, learning from what they say when things go wrong, and then taking action to improve patient safety. The programme aims to make the NHS the safest healthcare system in the world by creating a culture devoted to continuous learning and improvement (NHS England 2014). Musgrove Park Hospital, part of Taunton and Somerset NHS Foundation Trust, was one of 12 NHS organisations that signed up to the SutS programme, making public its commitment to the national pledges to be 'open and transparent' and to develop a safety improvement plan. This paper describes the development of the strategy.

A Comparison of Two Approaches to Safety Analysis Based on Use Cases

Science.gov (United States)

Stålhane, Tor; Sindre, Guttorm

Engineering has a long tradition in analyzing the safety of mechanical, electrical and electronic systems. Important methods like HazOp and FMEA have also been adopted by the software engineering community. The misuse case method, on the other hand, has been developed by the software community as an alternative to FMEA and preliminary HazOp for software development. To compare the two methods misuse case and FMEA we have run a small experiment involving 42 third year software engineering students. In the experiment, the students should identify and analyze failure modes from one of the use cases for a commercial electronic patient journals system. The results of the experiment show that on the average, the group that used misuse cases identified and analyzed more user related failure modes than the persons using FMEA. In addition, the persons who used the misuse cases scored better on perceived ease of use and intention to use.

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

Energy Technology Data Exchange (ETDEWEB)

RYAN GW

2007-09-24

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

International Nuclear Information System (INIS)

RYAN GW

2007-01-01

'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents

Key natural analogue input required to build a safety case for direct disposal of spent nuclear fuel in Japan

Energy Technology Data Exchange (ETDEWEB)

McKinley, I.G.; Hardie, S.M.L.; Klein, E. [MCM Consulting, Baden-Dättwil (Switzerland); Kawamura, H. [Obayashi Corporation, Nuclear Facilities Division, Tokyo (Japan); Beattie, T.M. [MCM Consulting, Bristol (United Kingdom)

2015-06-15

Natural analogues have been previously used to support the safety case for direct disposal of spent nuclear fuel, but the focus of such work was very dependent on the key barriers of specific national disposal concepts. Investigations of the feasibility of such disposal in Japan are at an early stage but, nevertheless, it is clear that building a robust safety case will be very challenging and would benefit from focused support from natural analogue studies—both in terms of developing/testing required models and, as importantly, presenting safety arguments to a wide range of stakeholders. This paper identifies key analogues that support both longevity and spread of failure times of massive steel overpacks, the effectiveness of buffering of radiolytic oxidants and the chemical and physical mechanisms retarding release of radionuclides from the engineered barriers. It is concluded that, for countries like Japan where performance needs to be assessed as realistically as possible, natural analogues can complement the existing laboratory and theoretical knowledge base and contribute towards development of a robust safety case. (authors)

Validation test case generation based on safety analysis ontology

International Nuclear Information System (INIS)

Fan, Chin-Feng; Wang, Wen-Shing

2012-01-01

Highlights: ► Current practice in validation test case generation for nuclear system is mainly ad hoc. ► This study designs a systematic approach to generate validation test cases from a Safety Analysis Report. ► It is based on a domain-specific ontology. ► Test coverage criteria have been defined and satisfied. ► A computerized toolset has been implemented to assist the proposed approach. - Abstract: Validation tests in the current nuclear industry practice are typically performed in an ad hoc fashion. This study presents a systematic and objective method of generating validation test cases from a Safety Analysis Report (SAR). A domain-specific ontology was designed and used to mark up a SAR; relevant information was then extracted from the marked-up document for use in automatically generating validation test cases that satisfy the proposed test coverage criteria; namely, single parameter coverage, use case coverage, abnormal condition coverage, and scenario coverage. The novelty of this technique is its systematic rather than ad hoc test case generation from a SAR to achieve high test coverage.

Lessons learned from measuring safety culture: an Australian case study.

Science.gov (United States)

Allen, Suellen; Chiarella, Mary; Homer, Caroline S E

2010-10-01

adverse events in maternity care are relatively common but often avoidable. International patient safety strategies advocate measuring safety culture as a strategy to improve patient safety. Evidence suggests it is necessary to fully understand the safety culture of an organisation to make improvements to patient safety. this paper reports a case study examining the safety culture in one maternity service in Australia and considers the benefits of using surveys and interviews to understand safety culture as an approach to identify possible strategies to improve patient safety in this setting. the study took place in one maternity service in two public hospitals in NSW, Australia. Concurrently, both hospitals were undergoing an organisational restructure which was part of a major health reform agenda. The priorities of the reform included improving the quality of care and patient safety; and, creating a more efficient health system by reducing administration inefficiencies and duplication. a descriptive case study using three approaches: the safety culture was identified to warrant improvement across all six safety culture domains. There was reduced infrastructure and capacity to support incident management activities required to improve safety, which was influenced by instability from the organisational restructure. There was a perceived lack of leadership at all levels to drive safety and quality and improving the safety culture was neither a key priority nor was it valued by the organisation. the safety culture was complex as was undertaking this study. We were unable to achieve a desired 60% response rate highlighting the limitations of using safety culture surveys in isolation as a strategy to improve safety culture. Qualitative interviews provided greater insight into the factors influencing the safety culture. The findings of this study provide evidence of the benefits of including qualitative methods with quantitative surveys when examining safety culture

Deep Borehole Disposal Safety Analysis.

Energy Technology Data Exchange (ETDEWEB)

Freeze, Geoffrey A. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Stein, Emily [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Price, Laura L. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); MacKinnon, Robert J. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Tillman, Jack Bruce [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2016-10-01

This report presents a preliminary safety analysis for the deep borehole disposal (DBD) concept, using a safety case framework. A safety case is an integrated collection of qualitative and quantitative arguments, evidence, and analyses that substantiate the safety, and the level of confidence in the safety, of a geologic repository. This safety case framework for DBD follows the outline of the elements of a safety case, and identifies the types of information that will be required to satisfy these elements. At this very preliminary phase of development, the DBD safety case focuses on the generic feasibility of the DBD concept. It is based on potential system designs, waste forms, engineering, and geologic conditions; however, no specific site or regulatory framework exists. It will progress to a site-specific safety case as the DBD concept advances into a site-specific phase, progressing through consent-based site selection and site investigation and characterization.

Safety culture development at Daya Bay NPP

International Nuclear Information System (INIS)

Zhang Shanming

2001-01-01

From view on Organization Behavior theory, the concept, development and affecting factors of safety culture are introduced. The focuses are on the establishment, development and management practice for safety culture at Daya Bay NPP. A strong safety culture, also demonstrated, has contributed greatly to improving performance at Daya Bay

Safety, codes and standards for hydrogen installations. Metrics development and benchmarking

Energy Technology Data Exchange (ETDEWEB)

Harris, Aaron P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dedrick, Daniel E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaFleur, Angela Christine [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); San Marchi, Christopher W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-04-01

Automakers and fuel providers have made public commitments to commercialize light duty fuel cell electric vehicles and fueling infrastructure in select US regions beginning in 2014. The development, implementation, and advancement of meaningful codes and standards is critical to enable the effective deployment of clean and efficient fuel cell and hydrogen solutions in the energy technology marketplace. Metrics pertaining to the development and implementation of safety knowledge, codes, and standards are important to communicate progress and inform future R&D investments. This document describes the development and benchmarking of metrics specific to the development of hydrogen specific codes relevant for hydrogen refueling stations. These metrics will be most useful as the hydrogen fuel market transitions from pre-commercial to early-commercial phases. The target regions in California will serve as benchmarking case studies to quantify the success of past investments in research and development supporting safety codes and standards R&D.

Development of a safety parameter supervision system for Angra-1

International Nuclear Information System (INIS)

Silva, R.A. da; Thome Filho, Z.D.; Schirru, R.; Martinez, A.S.; Oliveira, L.F.S. de

1986-01-01

The Safety Parameter Supervision System (SSPS) which is a computerized system for monitoring essential parameters in real time, determining the safety status and emergency procedures for returning normal reactor operation, in case of an anomaly occurrence, is presented. The SSPS consists of three sub-systems: Integrated parameter monitoring system which gives to operators an integrated vision of values of a parameter set, able to detect any deviation of normal reactor operation; safety critical function system which evaluates safety status in terms of a safety critical function set appointed in advance, and in case of violation of any critical function, it initiates the adequate emergency procedure to return normal operation; and safety parameter computer system which carries out the arquirement of analogic and digital control signals of nuclear power plant. (M.C.K.) [pt

The Role of the Biosphere in a Safety Case. IGSC topical session at the third IGSC Meeting

International Nuclear Information System (INIS)

Russell, Sean; Voinis, Sylvie; Alonso, Jesus; Van Luik, Abraham E.

2002-01-01

The safety case is a collection of arguments at a given stage of repository development in support of the long-term safety of the repository. The safety case comprises the findings of a safety assessment and a statement of confidence in these findings. The biosphere is one of the features of a geologic repository system for the long-term management of radioactive waste. The biosphere is important in a safety assessment since it is the place where humans and most organisms live and where regulations are made. Generally speaking, the biosphere is more dynamic than the geosphere and its evolution with time can significantly affect dose estimations and potential impacts of a geologic repository (e.g., climate change, glaciation, civilisation movement, etc.). That is, other parts of the repository system (vault, geosphere) are more robust or constant in time than the ever changing biosphere. Most of the variability associated with future events in the biosphere is driven by climate change. Climatic change and the characteristics of future societies are important sources of uncertainties Biosphere. Uncertainty can be addressed using reference or example biospheres, or alternative safety indicators such as radionuclide concentration or radionuclide flux from the geosphere to the surface biosphere (as indicated by the recent regulatory guidance in Finland), or by comparing predicted radionuclide concentrations from a repository with background levels in the environment. Thus, a Topical Session that focused on the 'Role of the Biosphere in a Safety Case' was organised in the framework of the 3. plenary meeting of the IGSC. This Topical Session reviewed the role of the biosphere in a safety case for geologic disposal of radioactive waste and discusses recent developments in international programs (IAEA Biomass, EC Bioclim), the views of regulators and the strategies being adopted by several implementers for incorporating the biosphere in their safety assessments

Safety culture development in nuclear electric plc

International Nuclear Information System (INIS)

Gibson, G.P.; Low, M.B.J.

1995-01-01

Nuclear Electric plc (NE) has always given the highest priority to safety. However, past emphasis has been directed towards ensuring safety thorough engineering design and hazard control procedures. Whilst the company did achieve high safety standards, particularly with respect to accidents, it was recognized that further improvements could be obtained. Analysis of the safety performance across a wide range of industries showed that the key to improving safety performance lay in developing a strong safety culture within the company. Over the last five years, NE has made great strides to improve its safety culture. This has resulted in a considerable improvement in its measured safety performance indicators, such as the number of incidents at international nuclear event scale (INES) rating 1, the number of lost time accidents and the collective radiation dose. However, despite this success, the company is committed to further improvement and a means by which this process becomes self-sustaining. In this way the company will achieve its prime goal, to ''ensure the safety of people, plant and the environment''. The paper provides an overview of the development of safety culture in NE since its formation in November 1989. It describes the research and international developments that have influenced the company's understanding of safety culture, the key initiatives that the company has undertaken to enhance its safety culture and the future initiatives being considered to ensure continual improvement. (author). 5 refs, 2 figs, 2 tabs

Preparation of the initial safety case

International Nuclear Information System (INIS)

Hensley, G.

1987-01-01

In British Nuclear Fuels plc (BNFL), the design of nuclear chemical plants for construction and subsequent operation at Sellafield Works is carried out by the Engineering Division of the Spent Fuel Management Services Group based at Risley, Warrington. Plant construction cannot take place, nor plant commissioning, until it has been demonstrated in the initial (design) safety case that the chosen design will allow the plant to be operated in an adequately safe manner, corresponding to an extremely low level of risk. The safety documentation procedure is described. A Preliminary Design Safety Appraisal is made of the initial design proposal to give an early indication of the order of risk that might prevail. The risk from each hazard is compared with an allocated risk target which makes up a proportion of the total plant risk which is quantified in BNFL's risk criteria. Where the risk appears unacceptable, appropriate modifications are made to the design. Prior to commissioning, a comprehensive, detailed risk assessment is carried out. The methodology of probabilistic risk assessment is described and examples given of how different hazards are assessed. (author)

TOOKUIL: A case study in user interface development for safety code application

International Nuclear Information System (INIS)

Gray, D.L.; Harkins, C.K.; Hoole, J.G.

1997-01-01

Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today's safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL

TOOKUIL: A case study in user interface development for safety code application

International Nuclear Information System (INIS)

Gray, D.L.; Harkins, C.K.; Hoole, J.G.; Peebles, R.C.; Smith, R.J.

1996-11-01

Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today's safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL

Developing safety culture in nuclear power engineering

International Nuclear Information System (INIS)

Tevlin, S.A.

2000-01-01

The new issue (no. 11) of the IAEA publications series Safety Reports, devoted to the safety culture in nuclear engineering Safety culture development in the nuclear activities. Practical recommendations to achieve success, is analyzed. A number of recommendations of international experts is presented and basic general indicators of satisfactory and insufficient safety culture in the nuclear engineering are indicated. It is shown that the safety culture has two foundations: human behavior and high quality of the control system. The necessity of creating the confidence by the management at all levels of the enterprise, development of individual initiative and responsibility of the workers, which make it possible to realize the structural hierarchic system, including technical, human and organizational constituents, is noted. Three stages are traced in the process of introducing the safety culture. At the first stage the require,emts of scientific-technical documentation and provisions of the governmental, regional and control organs are fulfilled. At the second stage the management of the organization accepts the safety as an important direction in its activities. At the third stage the organization accomplishes its work, proceeding from the position of constant safety improvement. The general model of the safety culture development is considered [ru

A Method to Select Test Input Cases for Safety-critical Software

International Nuclear Information System (INIS)

Kim, Heeeun; Kang, Hyungook; Son, Hanseong

2013-01-01

This paper proposes a new testing methodology for effective and realistic quantification of RPS software failure probability. Software failure probability quantification is important factor in digital system safety assessment. In this study, the method for software test case generation is briefly described. The test cases generated by this method reflect the characteristics of safety-critical software and past inputs. Furthermore, the number of test cases can be reduced, but it is possible to perform exhaustive test. Aspect of software also can be reflected as failure data, so the final failure data can include the failure of software itself and external influences. Software reliability is generally accepted as the key factor in software quality since it quantifies software failures which can make a powerful system inoperative. In the KNITS (Korea Nuclear Instrumentation and Control Systems) project, the software for the fully digitalized reactor protection system (RPS) was developed under a strict procedure including unit testing and coverage measurement. Black box testing is one type of Verification and validation (V and V), in which given input values are entered and the resulting output values are compared against the expected output values. Programmable logic controllers (PLCs) were used in implementing critical systems and function block diagram (FBD) is a commonly used implementation language for PLC

Safety culture assessment developed by JANTI

International Nuclear Information System (INIS)

Hamada, Jun

2009-01-01

Japan's JCO accident in September 1999 provided a real-life example of what can happen when insufficient attention is paid to safety culture. This accident brought to light the importance of safety culture and reinforced the movement to foster a safety culture. Despite this, accidents and inappropriate conduct have continued to occur. Therefore, there is a strong demand to instill a safety culture throughout the nuclear power industry. In this context, Japan's nuclear power regulator, the Nuclear and Industrial Safety Agency (NISA), decided to include in its safety inspections assessments of the safety culture found in power utilities' routine safety operations to get signs of deterioration in the organizational climate. In 2007, NISA constructed guidelines for their inspectors to carry out these assessments. At the same time, utilities have embarked on their own independent safety culture initiatives, such as revising their technical specifications and building effective PDCA cycle to promote safety culture. In concert with these developments, JANTI has also instituted safety culture assessments. (author)

Development of a Generic Environmental Safety Case for the Disposal of Higher Activity Wastes in the UK

International Nuclear Information System (INIS)

Bailey, Lucy; Hicks, Tim

2016-01-01

The UK generic ESC demonstrates safe disposal of higher activity wastes, by providing: • A demonstration of how environmental safety can be achieved by a variety of disposal concepts based on systems of multiple engineered and natural barriers, providing multiple safety functions; • An understanding of expected barrier performance and how conditions in a disposal system will evolve, based on research findings presented in RWM’s knowledge base; • An approach to safety assessment based on multiple lines of reasoning, involving both qualitative and quantitative analysis; • Complementary insight modelling and total system modelling used to develop understanding of how different components of the engineered and natural barrier system contribute to safety

Regulatory review and confidence building in post-closure safety assessments and safety cases for near surface disposal facilities-IAEA ASAM coordinated research programme

International Nuclear Information System (INIS)

Gonzales, A.; Simeonov, G.; Bennett, D.G.; Nys, V.; Ben Belfadhel, M.

2005-01-01

Some years ago, the IAEA successfully concluded a Coordinated Research Program (CRP) called Islam, which focussed on the development of an Improved Safety Assessment Methodology for near-surface radioactive waste disposal facilities. In November 2002, and as an extension of ISAM, the IAEA launched a new CRP called ASAM, designed to test the Application of the Safety Assessment Methodology by considering a range of near-surface disposal facilities. The ASAM work programme is being implemented by three application working groups and two cross-cutting working groups. The application working groups are testing the applicability of the ISAM methodology by assessing an existing disposal facility in Hungary, a copper mine in South Africa, and a hypothetical facility containing heterogenous wastes, such as disused sealed sources. The first cross-cutting working group is addressing a number of technical issues that are common to all near-surface disposal facilities, while the second group, the Regulatory Review Working Group (RRWG) is developing guidance on how to gain confidence in safety assessments and safety cases, and on how to conduct regulatory reviews of safety assessments. This paper provides a brief overview of the work being conducted by the Regulatory Review Working Group. (author)

Design of safety-critical systems using the complementarities of success and failure domains with a case study

International Nuclear Information System (INIS)

Ahmed, Rizwan; Koo, June Mo; Jeong, Yong Hoon; Heo, Gyunyoung

2011-01-01

A safety-critical system has to qualify the performance-related requirements and the safety-related requirements simultaneously. Conceptually, design processes should consider both of them simultaneously but the practices do not and/or cannot follow such a theoretical approach due to the limitation of design resources. From our experience, we found that safety-related functions must be simultaneously resolved with the development of performance-related functions, particularly, in case of safety-critical systems. Since, success and failure domain analyses are essential for the investigation of performance-related and safety-related requirements, respectively, we articulated our perception to Axiomatic Design (AD), Fault Tree Analysis (FTA), and TRIZ. A design evolution procedure considering feedbacks from AD to identify functional couplings, TRIZ methodology to explore uncoupling solutions and FTA to improve reliability in a systematic way is presented here. A case study regarding design of safety injection tank installed in a nuclear power plant is also included to illustrate the proposed framework. It is expected that several iterations between AD-TRIZ-FTA would result into an optimized design which could be tested against the desired performance and safety criteria.

Design of safety-critical systems using the complementarities of success and failure domains with a case study

Energy Technology Data Exchange (ETDEWEB)

Ahmed, Rizwan; Koo, June Mo [Department of Nuclear Engineering, Kyung Hee University, Yongin-si, Gyeonggi-do 446-701 (Korea, Republic of); Jeong, Yong Hoon [Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.k [Department of Nuclear Engineering, Kyung Hee University, Yongin-si, Gyeonggi-do 446-701 (Korea, Republic of)

2011-01-15

A safety-critical system has to qualify the performance-related requirements and the safety-related requirements simultaneously. Conceptually, design processes should consider both of them simultaneously but the practices do not and/or cannot follow such a theoretical approach due to the limitation of design resources. From our experience, we found that safety-related functions must be simultaneously resolved with the development of performance-related functions, particularly, in case of safety-critical systems. Since, success and failure domain analyses are essential for the investigation of performance-related and safety-related requirements, respectively, we articulated our perception to Axiomatic Design (AD), Fault Tree Analysis (FTA), and TRIZ. A design evolution procedure considering feedbacks from AD to identify functional couplings, TRIZ methodology to explore uncoupling solutions and FTA to improve reliability in a systematic way is presented here. A case study regarding design of safety injection tank installed in a nuclear power plant is also included to illustrate the proposed framework. It is expected that several iterations between AD-TRIZ-FTA would result into an optimized design which could be tested against the desired performance and safety criteria.

Development of the major trauma case review tool.

Science.gov (United States)

Curtis, Kate; Mitchell, Rebecca; McCarthy, Amy; Wilson, Kellie; Van, Connie; Kennedy, Belinda; Tall, Gary; Holland, Andrew; Foster, Kim; Dickinson, Stuart; Stelfox, Henry T

2017-02-28

As many as half of all patients with major traumatic injuries do not receive the recommended care, with variance in preventable mortality reported across the globe. This variance highlights the need for a comprehensive process for monitoring and reviewing patient care, central to which is a consistent peer-review process that includes trauma system safety and human factors. There is no published, evidence-informed standardised tool that considers these factors for use in adult or paediatric trauma case peer-review. The aim of this research was to develop and validate a trauma case review tool to facilitate clinical review of paediatric trauma patient care in extracting information to facilitate monitoring, inform change and enable loop closure. Development of the trauma case review tool was multi-faceted, beginning with a review of the trauma audit tool literature. Data were extracted from the literature to inform iterative tool development using a consensus approach. Inter-rater agreement was assessed for both the pilot and finalised versions of the tool. The final trauma case review tool contained ten sections, including patient factors (such as pre-existing conditions), presenting problem, a timeline of events, factors contributing to the care delivery problem (including equipment, work environment, staff action, organizational factors), positive aspects of care and the outcome of panel discussion. After refinement, the inter-rater reliability of the human factors and outcome components of the tool improved with an average 86% agreement between raters. This research developed an evidence-informed tool for use in paediatric trauma case review that considers both system safety and human factors to facilitate clinical review of trauma patient care. This tool can be used to identify opportunities for improvement in trauma care and guide quality assurance activities. Validation is required in the adult population.

Making the post-closure safety case for the proposed yucca mountain repository

International Nuclear Information System (INIS)

Swift, P.; Van Luik, A.

2008-01-01

This presentation provided an overview of the Yucca Mountain repository post-closure safety case. The safety case concept is being integrated into the license application being prepared for Yucca Mountain, by giving particularly close attention to the treatment of uncertainties, thereby bringing available lines of evidence into the supporting information, as appropriate, to build a comprehensive argument for safety and regulatory compliance. For Yucca Mountain, it is expected that there will be open questions in the safety case to be presented to the regulator and a programme will be outlined on what information is to be gathered (and how) prior to the next iteration in the licensing process to address such open issues. A one-hundred year operational phase is foreseen and planned, and the changes in knowledge and approaches that occur over time will have to be accommodated through the formal licensing process. (authors)

Development of Safety Culture Indicators for HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Lee, Kye-Hong

2007-01-01

Safety culture is more important than a technical matter for the management of nuclear facilities. Some of the accidents that have occurred recently in nuclear plants are important as a social problem besides a technical problem. That's why the management of nuclear plants has been focused on the safety culture to improve confidence of nuclear facilities. As for a safety culture, there are difficulties in that a tangible result does not come out clearly in spite of an effort for a long time. Some IAEA guides and reports about a safety culture and its evaluation method for nuclear power plants (NPP) were published after the Chernobyl accident. Until now there is no tool to evaluate a safety culture of for research reactors. HANARO developed its own safety culture indicators based on the IAEA's documents. The purpose of the development of the safety culture indicators is to evaluate and enhance the safety attitude in HANARO

TOOKUIL: A case study in user interface development for safety code application

Energy Technology Data Exchange (ETDEWEB)

Gray, D.L.; Harkins, C.K.; Hoole, J.G. [and others

1997-07-01

Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today`s safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL.

Safety policy for nuclear power development

International Nuclear Information System (INIS)

Uchida, Hideo

1987-01-01

The report discusses various aspects of the safety policy for nuclear power development in Japan. Nuclear power development over three decades in Japan has led to operating performance which is highly safe and reliable. This has been appreciated internationally. Discussed here is the Japanese basic safety policy for nuclear power development that is essential first to design, manufacture and construction using high technology. The current careful quality assurance and reliable operation management by skilled operators are relied upon, on the basis of the fact that measures to prevent abnormal events are given first priority rather than those to mitigate consequences of abnormal events or accidents. Lessons learned from accidents and failures within or outside Japan such as the TMI accident and Chernobyl accident have been reflected in the improvement of safety through careful and thorough examinations of them. For further improvement in nuclear safety, deliberate studies and investigations on severe accidents and probabilistic safety assessment are considered to be important. Such efforts are currently being promoted. For this purpose, it is important to advance international cooperation and continue technical exchanges, based on operation experience in nuclear power stations in Japan. (Nogami, K.)

Sensitivity analysis: Theory and practical application in safety cases

International Nuclear Information System (INIS)

Kuhlmann, Sebastian; Plischke, Elmar; Roehlig, Klaus-Juergen; Becker, Dirk-Alexander

2014-01-01

The projects described here aim at deriving an adaptive and stepwise approach to sensitivity analysis (SA). Since the appropriateness of a single SA method strongly depends on the nature of the model under study, a top-down approach (from simple to sophisticated methods) is suggested. If simple methods explain the model behaviour sufficiently well then there is no need for applying more sophisticated ones and the SA procedure can be considered complete. The procedure is developed and tested using a model for a LLW/ILW repository in salt. Additionally, a new model for the disposal of HLW in rock salt will be available soon for SA studies within the MOSEL/NUMSA projects. This model will address special characteristics of waste disposal in undisturbed rock salt, especially the case of total confinement, resulting in a zero release which is indeed the objective of radioactive waste disposal. A high proportion of zero-output realisations causes many SA methods to fail, so special treatment is needed and has to be developed. Furthermore, the HLW disposal model will be used as a first test case for applying the procedure described above, which was and is being derived using the LLW/ILW model. How to treat dependencies in the input, model conservatism and time-dependent outputs will be addressed in the future project programme: - If correlations or, more generally, dependencies between input parameters exist, the question arises about the deeper meaning of sensitivity results in such cases: A strict separation between inputs, internal states and outputs is no longer possible. Such correlations (or dependencies) might have different reasons. In some cases correlated input parameters might have a common physically (well-)known fundamental cause but there are reasons why this fundamental cause cannot or should not be integrated into the model, i.e. the cause might generate a very complex model which cannot be calculated in appropriate time. In other cases the correlation may

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

Safety and security of radiation sources and radioactive materials: A case of Zambia - least developed country

International Nuclear Information System (INIS)

Banda, S.C.

1998-01-01

In Zambia, which is current (1998) classified as a Least Developed Country has applications of nuclear science and technology that cover the medical, industrial, education and research. However, the application is mainly in medical and industry. Through the responsibility of radiation source is within the mandate of the Radiation Protection Board. The aspects involving security fall on different stake holders some that have no technical knowledge on what radiation is about. The stake holders in this category include customs clearing and forwarding agents, state security/defence agencies and the operators. Such a situation demands a national system that should be instituted to meet the safety and security requirements but takes into account the involvement of the diverse stake holders. In addition such system should avoid unnecessary exposure, ensure safety of radioactive materials and sources, detect illicit trade and maintain integrity of such materials or sources. This paper will provide the status on issue in Zambia and the challenges that exist to ensure further development in application of Nuclear Science and Technology (S and T) in the country takes into account the safety and security requirements that avoid deliberate and accidental loss of radiation sources and radioactive materials. The Government has a responsibility to ensure that effective system is established and operated to protect radiation sources and radioactive materials from theft, sabotage and ensure safety. (author)

IMPLEMENTATION OF A SAFETY PROGRAM FOR THE WORK ACCIDENTS’ CONTROL. A CASE STUDY IN THE CHEMICAL INDUSTRY

Directory of Open Access Journals (Sweden)

Edison Cesar de Faria Nogueira

2015-03-01

Full Text Available This article presents a case study related to the implementation of a Work Safety Program in a chemical industry, based on the Process Safety Program, PSP, of a huge energy company. The research was applied, exploratory, qualitative and with and data collection method through documentary and bibliographical research. There will be presented the main practices adopted in order to make the Safety Program a reality inside a chemical industry, its results and contributions for its better development. This paper proposes the implementation of a Safety Program must be preceded by a diagnosis of occupational safety and health management system and with constant critical analysis in order to make the necessary adjustments.

Development of the Digital Reactor Safety System

International Nuclear Information System (INIS)

Lee, Dong Young; Lee, C. K.; Hwang, I. K.

2008-04-01

Objectives of Project - Development of Digital Safety Grade PLC and Licensing - Development of Safety System(RPS) and Licensing - Development of Safety System(ESF-CCS) and Licensing Content and Result of Project - POSAFE-Q PLC : Development of PLC platform for Shin-UCN unit 1 and 2 ·Development Scope : Processor module, Power module, 3 kinds of Communication module, Bus extension module(Master and Slave), 16 kinds of Input and Output module ·PLC application software development tool(pSET) - IDiPS RPS and IDiPS ESF-CCS : Development of PPS for Sin-UCN 1 and 2 ·Development Scope - 4-channels RPS with the KNICS inherent architecture - A part of 1-channels ESF-CCS with the KNICS inherent architecture - Licensing ·optical Report Submitted and Expected to finish the licensing process until Aug. 2008

HSE's safety assessment principles for criticality safety

International Nuclear Information System (INIS)

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

2008-01-01

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

Thermal-hydraulic analysis code development and application to passive safety reactor at JAERI

International Nuclear Information System (INIS)

Araya, F.

1995-01-01

After a brief overview of safety assessment process, the author describes the LOCA analysis code system developed in JAERI. It comprises audit calculation code (WREM, WREM-J2, Japanese own code and BE codes (2D/3D, ICAP, ROSA). The codes are applied to development of Japanese passive safety reactor concept JPSR. Special attention is paid to the passive heat removal system and phenomena considered to occur under loss of heat sink event. Examples of LOCA analysis based on operation of JPSR for the cases of heat removal by upper RHR and heat removal from core to atmosphere are given. Experiments for multi-dimensional flow field in RPV and steam condensation in water pool are used for understanding the phenomena in passive safety reactors. The report is in a poster form only. 1 tab., 13 figs

Accident simulator development for probabilistic safety analysis

International Nuclear Information System (INIS)

Cacciabue, P.C.; Amendola, A.; Mancini, G.

1985-01-01

This paper describes the basic features of a new concept of incident simulator, Response System Analyzed (RSA) which is being developed within the CEC JRC Research Program on Reactor Safety. Focusing on somewhat different aims than actual simulators, RSA development extends the field of application of simulators to the area of risk and reliability analysis and in particular to the identification of relevant sequences, to the modeling of human behavior and to the validation of operating procedures. The fundamental components of the project, i.e. the deterministic transient model of the plant, the automatic probabilistic driver and the human possible intervention modeling, are discussed in connection with the problem of their dynamic interaction. The analyses so far performed by separately testing RSA on significant study cases have shown encouraging results and have proven the feasibility of the overall program

Radiation Safety for Sustainable Development

International Nuclear Information System (INIS)

2015-10-01

The objective of radiation safety is Assessments of Natural Radioactivity and its Radiological. The following topics were discussed during the conference: AFROSAFE Championing Radiation Safety in Africa, Radiation Calibration, and Development and Validation of a Laser Induced Breakdown Spectrometry Method for Cancer Detection and Characterization. Young Generation in NUCLEAR Initiative to Promote Nuclear Science and Technology, Radiation Protection Safety Culture and Application of Nuclear Techniques in Industry and the Environment were discuss. Rapid Chemometric X-Ray Fluorescence approaches for spectral Diagnostics of Cancer utilizing Tissue Trace Metals and Speciation profiles. Fundamental role of medical physics in Radiation Therapy

Developing and maintaining national food safety control systems ...

African Journals Online (AJOL)

The establishment of effective food safety systems is pivotal to ensuring the safety of the national food supply as well as food products for regional and international trade. The development, structure and implementation of modern food safety systems have been driven over the years by a number of developments.

Ensuring ecology safety, furthering the development of nuclear energy

International Nuclear Information System (INIS)

Shang Zhaorong; Chen Xiaoqiu; Tang Senming

2008-01-01

Ecology safety is as important as political safety, national defense safety, economy safety, food safety, etc. The nuclear power development is an important step for the national energy structure optimization, ecology caring, and implementing sustainable development. The aquatic ecology is important on disposal of low-level liquid waste and cooling water from NPPs and nuclear fuel cycle facilities, and people pay more attention to ecology impact and human threat from the nuclear energy. The author describes relevant ecology problems correlated with nuclear energy such as impact of thermal discharge, ecology sensitive zone, ecology restoration, etc. in order to emphasis that development of nuclear energy should guarantee ecology safety for the sustainable development of nuclear energy. (authors)

Development of digital safety system logic and control

International Nuclear Information System (INIS)

Nishikawa, H.; Sakamoto, H.

1995-01-01

Advanced-BWR (ABWR) uses total digital control and instrumentation (C and I) system. In particular, ABWR adopts a newly developed safety system using advanced digital technology. In the presentation the digital safety system design, manufacturing and factory validation test method are shortly overviewed. The digital safety system consists of micro-processor based digital controllers, data and information transmission by optical fibers and human-machine interface using color flat displays. This new developed safety system meet the nuclear safety requirements such as high reliability, independence of divisions, operability and maintainability. (2 refs., 4 figs., 1 tab.)

Assessing progress in the development of safety culture

International Nuclear Information System (INIS)

Rotaru, I.; Ghita, S.; Biro, L.

2002-01-01

This paper is focussed on the organizational culture and learning processes required for the implementation of all aspects of safety culture. There is no prescriptive formula for improving safety culture. However, some common characteristics and practices are emerging that can be adopted by organizations in order to make progress. The paper refers to some approaches that have been successful in a number of countries. The experience of the international nuclear industry in the development and improvement of safety culture could be extended and found useful in other nuclear activities, irrespective of scale. The examples given of specific practice cover a wide range of activities including analysis of events, the regulatory approach on safety culture, employee participation and safety performance measures. Many of these practices may be relevant to smaller organizations and could contribute to improving safety culture, whatever the size of the organization. The most effective approach is to pursue a range of practices that can be mutually supportive in the development of a progressive safety culture, supported by professional standards, organizational and management commitment. Some guidance is also given on the assessment of safety culture and on the detection of a weakening safety culture. Few suggestions for accelerating the safety culture development and improvement process are also provided. (author)

Elements of the safety case for the Morsleben repository based on probabilistic modelling

International Nuclear Information System (INIS)

Wollrath, J.; Niemeyer, M.; Resele, G.; Becker, D.A.; Hirsekorn, P.

2008-01-01

The Morsleben nuclear waste repository (ERAM) for low- and intermediate-level mainly short-lived waste is located in a former salt mine. The closure concept was developed in parallel and interacting with the safety assessment. The safety concept is based on extensive backfilling with salt concrete complemented with seals between the main disposal areas and the rest of the mine building. Thus, the entire system exhibits a barrier effect through a partially redundant combination of several processes. However, in the formal safety assessment no credit is taken from the barrier effect of the extensive backfill. In the safety assessments, the different possibilities of system development, the resulting array of potential fluid movement and a large number of potential radionuclide migration pathways are mapped in the bandwidth of derived parameters. The calculated response of the system to parameter variations is non-linear. Different processes may compete and compensate each other. Hence, the common practice to choose a conservative parameter set for the safety assessment is a priori impossible. The safety assessment has been performed independently by two groups with different computer models, for the same closure concept and the same basic parameters but independent conceptual approaches. Both groups have performed deterministic and probabilistic dose calculations. The results match well; the differences can be explained on basis of the model approaches. Although a large bandwidth is considered for a number of parameters the maximum radiation exposure remains clearly below the applicable dose limit for nearly all calculations, demonstrating the robustness of the system. These aspects significantly contribute to confidence building in the Safety Case for ERAM. (authors)

Case Study on Influence Factor Trend Analysis of the Accidents and Events of Nuclear Power Plants by applying Nuclear Safety Culture Framework

International Nuclear Information System (INIS)

Park, J. Y.; Park, Y. W.; Park, H.G.

2016-01-01

This study 1) established the standard based on frameworks of safety culture principles that show safety culture promotion goals, 2) analyzed the linkages with the frameworks that were established by analyzing each incident cause and weak point from selected 268 cases(rating over INES grade 1) among 4,088 cases (as of April 1, 2015). The 4,088 cases were selected as a result of database analysis from 702 accidents recorded in accident and rating evaluation reports that were published in the National Nuclear Safety Commission and overseas IRS (International Reporting System for operating Experience), and 3) finally conducted a trend analysis studies with these comprehensive results. From the investigations, followings were concluded. 1) In order to analyze the safety culture, analysis methodology is required. 2) Analytical methodology for building sustainable safety culture promoting a virtuous cycle system was developed 3) Among variety of process input data, 970 domestic and overseas incidents were selected as targets and 502 accidents were classified as safety culture related events by utilizing screen filter of IAEA GS-G-3.5 Appendix I and Framework (Nuclear Safety Culture Base Frame) developed by BEES, Inc. for safety culture analysis method. 4) As a result, complex safety culture influence factors for the one reason which was difficult to separate by conventional methods was able to be analyzed. 5) The cumulative data through the system was results of virtuous trend analysis rather than temporary results. Thus, it could be unique cultural factors of the domestic industry and could derive trend differences for domestic safety culture factors accordingly

Case Study on Influence Factor Trend Analysis of the Accidents and Events of Nuclear Power Plants by applying Nuclear Safety Culture Framework

Energy Technology Data Exchange (ETDEWEB)

Park, J. Y.; Park, Y. W.; Park, H.G. [KAIST, Daejeon (Korea, Republic of)

2016-05-15

This study 1) established the standard based on frameworks of safety culture principles that show safety culture promotion goals, 2) analyzed the linkages with the frameworks that were established by analyzing each incident cause and weak point from selected 268 cases(rating over INES grade 1) among 4,088 cases (as of April 1, 2015). The 4,088 cases were selected as a result of database analysis from 702 accidents recorded in accident and rating evaluation reports that were published in the National Nuclear Safety Commission and overseas IRS (International Reporting System for operating Experience), and 3) finally conducted a trend analysis studies with these comprehensive results. From the investigations, followings were concluded. 1) In order to analyze the safety culture, analysis methodology is required. 2) Analytical methodology for building sustainable safety culture promoting a virtuous cycle system was developed 3) Among variety of process input data, 970 domestic and overseas incidents were selected as targets and 502 accidents were classified as safety culture related events by utilizing screen filter of IAEA GS-G-3.5 Appendix I and Framework (Nuclear Safety Culture Base Frame) developed by BEES, Inc. for safety culture analysis method. 4) As a result, complex safety culture influence factors for the one reason which was difficult to separate by conventional methods was able to be analyzed. 5) The cumulative data through the system was results of virtuous trend analysis rather than temporary results. Thus, it could be unique cultural factors of the domestic industry and could derive trend differences for domestic safety culture factors accordingly.

Comprehensive Lifecycle for Assuring System Safety

Science.gov (United States)

Knight, John C.; Rowanhill, Jonathan C.

2017-01-01

CLASS is a novel approach to the enhancement of system safety in which the system safety case becomes the focus of safety engineering throughout the system lifecycle. CLASS also expands the role of the safety case across all phases of the system's lifetime, from concept formation to decommissioning. As CLASS has been developed, the concept has been generalized to a more comprehensive notion of assurance becoming the driving goal, where safety is an important special case. This report summarizes major aspects of CLASS and contains a bibliography of papers that provide additional details.

Safety engineering with COTS components

International Nuclear Information System (INIS)

O'Halloran, Mark; Hall, Jon G.; Rapanotti, Lucia

2017-01-01

Safety-critical systems are becoming more widespread, complex and reliant on software. Increasingly they are engineered through (COTS) (Commercial Off The Shelf) components to alleviate the spiralling costs and development time, often in the context of complex supply chains. A parallel increased concern for safety has resulted in a variety of safety standards, with a growing consensus that a safety life cycle is needed which is fully integrated with the design and development life cycle, to ensure that safety has appropriate influence on the design decisions as system development progresses. In this article we explore the application of an integrated approach to safety engineering in which assurance drives the engineering process. The paper reports on the outcome of a case study on a live industrial project with a view to evaluate: its suitability for application in a real-world safety engineering setting; its benefits and limitations in counteracting some of the difficulties of safety engineering with (COTS) components across supply chains; and, its effectiveness in generating evidence which can contribute directly to the construction of safety cases. - Highlights: • Assurance as effective driver for COTS-based safety-critical system development. • Engages stakeholders, captures requirements and provides rich traceability. • Shares appropriate safety requirements across the supply chain.

Safety Design Approach for the Development of Safety Requirements for Design of Commercial HTGR

International Nuclear Information System (INIS)

Ohashi, Hirofumi; Sato, Hiroyuki; Nakagawa, Shigeaki; Tachibana, Yukio; Nishihara, Tetsuo; Yan, Xing; Sakaba, Nariaki; Kunitomi, Kazuhiko

2014-01-01

The research committee on “Safety requirements for HTGR design” was established in 2013 under the Atomic Energy Society of Japan to develop the draft safety requirements for the design of commercial High Temperature Gas-cooled Reactors (HTGRs), which incorporate the HTGR safety features demonstrated using the High Temperature Engineering Test Reactor (HTTR), lessons learned from the accident of Fukushima Daiichi Nuclear Power Station and requirements for the integration of the hydrogen production plants. The safety design approach for the commercial HTGRs which is a basement of the safety requirements is determined prior to the development of the safety requirements. The safety design approaches for the commercial HTGRs are to confine the radioactive materials within the coated fuel particles not only during normal operation but also during accident conditions, and the integrity of the coated fuel particles and other requiring physical barriers are protected by the inherent and passive safety features. This paper describes the main topics of the research committee, the safety design approaches and the safety functions of the commercial HTGRs determined in the research committee. (author)

Analysis of developed transition road safety barrier systems.

Science.gov (United States)

Soltani, Mehrtash; Moghaddam, Taher Baghaee; Karim, Mohamed Rehan; Sulong, N H Ramli

2013-10-01

Road safety barriers protect vehicles from roadside hazards by redirecting errant vehicles in a safe manner as well as providing high levels of safety during and after impact. This paper focused on transition safety barrier systems which were located at the point of attachment between a bridge and roadside barriers. The aim of this study was to provide an overview of the behavior of transition systems located at upstream bridge rail with different designs and performance levels. Design factors such as occupant risk and vehicle trajectory for different systems were collected and compared. To achieve this aim a comprehensive database was developed using previous studies. The comparison showed that Test 3-21, which is conducted by impacting a pickup truck with speed of 100 km/h and angle of 25° to transition system, was the most severe test. Occupant impact velocity and ridedown acceleration for heavy vehicles were lower than the amounts for passenger cars and pickup trucks, and in most cases higher occupant lateral impact ridedown acceleration was observed on vehicles subjected to higher levels of damage. The best transition system was selected to give optimum performance which reduced occupant risk factors using the similar crashes in accordance with Test 3-21. Copyright © 2013 Elsevier Ltd. All rights reserved.

Topical Session on the Decommissioning and Dismantling Safety Case

International Nuclear Information System (INIS)

2002-01-01

Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Cooperative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the NEA Committee on Nuclear Regulatory Activities, the Committee on Radiation Protection and Public Health, and the RWMC. The EC is a member of the WPDD and the IAEA also participates. This ensures co-ordination amongst activities in these international programmes. Participation from civil society organisations is considered on a case by case basis, and has already taken place through the active involvement of the Group of Municipalities with Nuclear Installations at the first meeting of the WPDD At its second meeting, in Paris, 5-7 December 2001, the WPDD held two topical sessions on the D and D Safety Case and on the Management of Materials from D and D, respectively. This report documents the topical session on the safety case. The topical session was meant to provide an exchange of information and experience on the following issues: What topics should be included in a safety case? Of what should it consist? Is there sufficient and complete guidance nationally and internationally? How do practices differ internationally? Main boundary condition to this session was that it would deal with plants where spent fuel has been removed. Also the topical sessions was kept at a level that makes the most of the varied constituency of the WPDD. Namely, interface issues are important, and issue-identification and discussion was the immediate goal. There was less interest in examining areas where variability amongst national

Development of Safety Culture Assessment Strategy for Korean NPP

International Nuclear Information System (INIS)

Park, Jung Hwan; Kim, Jong Hyun

2014-01-01

This paper aims at developing the requirements for a method to evaluate the operational safety culture, evaluating currently available methods based on the requirements, and suggesting a method to evaluate and improve the operational safety culture for Korean nuclear power plants. This paper reviews the widely-used methods to assess safety culture for NPPs and their basis. Then, this paper develops the requirements for the method to evaluate operational safety culture for Korean NPPs. Based on these requirements, Korean Safety Culture Indicators (KSCI) and evaluation measures are also suggested. Finally this paper proposes the guidelines to develop improvements to safety culture from the evaluation results

Development of Safety Culture Assessment Strategy for Korean NPP

Energy Technology Data Exchange (ETDEWEB)

Park, Jung Hwan; Kim, Jong Hyun [KEPCO, Ulsan (Korea, Republic of)

2014-08-15

This paper aims at developing the requirements for a method to evaluate the operational safety culture, evaluating currently available methods based on the requirements, and suggesting a method to evaluate and improve the operational safety culture for Korean nuclear power plants. This paper reviews the widely-used methods to assess safety culture for NPPs and their basis. Then, this paper develops the requirements for the method to evaluate operational safety culture for Korean NPPs. Based on these requirements, Korean Safety Culture Indicators (KSCI) and evaluation measures are also suggested. Finally this paper proposes the guidelines to develop improvements to safety culture from the evaluation results.

Collaborating with nurse leaders to develop patient safety practices.

Science.gov (United States)

Kanerva, Anne; Kivinen, Tuula; Lammintakanen, Johanna

2017-07-03

Purpose The organisational level and leadership development are crucial elements in advancing patient safety, because patient safety weaknesses are often caused by system failures. However, little is known about how frontline leader and director teams can be supported to develop patient safety practices. The purpose of this study is to describe the patient safety development process carried out by nursing leaders and directors. The research questions were: how the chosen development areas progressed in six months' time and how nursing leaders view the participatory development process. Design/methodology/approach Participatory action research was used to engage frontline nursing leaders and directors into developing patient safety practices. Semi-structured group interviews ( N = 10) were used in data collection at the end of a six-month action cycle, and data were analysed using content analysis. Findings The participatory development process enhanced collaboration and gave leaders insights into patient safety as a part of the hospital system and their role in advancing it. The chosen development areas advanced to different extents, with the greatest improvements in those areas with simple guidelines to follow and in which the leaders were most participative. The features of high-reliability organisation were moderately identified in the nursing leaders' actions and views. For example, acting as a change agent to implement patient safety practices was challenging. Participatory methods can be used to support leaders into advancing patient safety. However, it is important that the participants are familiar with the method, and there are enough facilitators to steer development processes. Originality/value Research brings more knowledge of how leaders can increase their effectiveness in advancing patient safety and promoting high-reliability organisation features in the healthcare organisation.

Child safety in parks' playgrounds (a case study in Tehran’s sub-district parks

Directory of Open Access Journals (Sweden)

A.H. Mirlouhi Falavarjani

2010-10-01

Full Text Available Background and aimsSafety is a complex concept and multidisciplinary science which is included some difference areas from industrial sectors to urban public arenas. Parks and playgrounds as important public places should be considered in terms of health and safety, especially for kids as prominent social vulnerable citizens. According to CPSC, 147 deaths havebeen reported for under 15 year old child during Jan 1990 to Aug 2000. Every 2.5 minute, kid suffers playground related accident. The main objective in this study is safety assessment ofplaygrounds among the selected parks.MethodsIn this case study, deductive approach and cross-sectional survey was followed, and some parks and playgrounds were selected among five urban counties in Tehran. Our volunteered samples were 160 parents. Playgrounds and related equipment were assessed in terms of safety, as well.ResultsOur findings show that more than 68% of playground equipment might create hazardous condition for kids. Lack of sustain maintenance for both of equipment and playground surface make some risky area for the mentioned group. Statistical analysis by SPSSWin 13 showed that more than 78 % of parents are worry about their child in terms of playground safetyproblems. Safety assessment of swings and slides showed that there are safety based problems in 89% of cases. Due to statistical reports of Tehran Emergency center, 10-12 and 8-10 year old kids suffer play based accident more than others. Reported traumas showed that face and skull and then feet suffered mechanical injury more than other limbs.ConclusionSurely, safety and health considerations are known as Municipality responsibilities, so for safety improvement in parks an integration safety system should be happened. HSE_MS seems a reliable approach for the mention goal. For improvement of exist parks and playground some related standard should be follows such as CPSC standards, EN 1176, and EN 1177. Also anthropometric data development

Development of safety analysis technology for LMR

International Nuclear Information System (INIS)

Hahn, Do Hee; Kwon, Y. M.; Kim, K. D.

2000-05-01

The analysis methodologies as well as the analysis computer code system for the transient, HCDA, and containment performance analyses, which are required for KALIMER safety analyses, have been developed. The SSC-K code has been developed based on SSC-L which is an analysis code for loop type LMR, by improving models necessary for the KALIMER system analysis, and additional models have been added to the code. In addition, HCDA analysis model has been developed and the containment performance analysis code has been also improved. The preliminary basis for the safety analysis has been established, and the preliminary safety analyses for the key design features have been performed. In addition, a state-of-art analysis for LMR PSA and overseas safety and licensing requirements have been reviewed. The design database for the systematic management of the design documents as well as design processes has been established as well

Development of safety analysis technology for LMR

Energy Technology Data Exchange (ETDEWEB)

Hahn, Do Hee; Kwon, Y. M.; Kim, K. D. [and others

2000-05-01

The analysis methodologies as well as the analysis computer code system for the transient, HCDA, and containment performance analyses, which are required for KALIMER safety analyses, have been developed. The SSC-K code has been developed based on SSC-L which is an analysis code for loop type LMR, by improving models necessary for the KALIMER system analysis, and additional models have been added to the code. In addition, HCDA analysis model has been developed and the containment performance analysis code has been also improved. The preliminary basis for the safety analysis has been established, and the preliminary safety analyses for the key design features have been performed. In addition, a state-of-art analysis for LMR PSA and overseas safety and licensing requirements have been reviewed. The design database for the systematic management of the design documents as well as design processes has been established as well.

Key aspects in managing safety when working with multiple contractors: A case study

NARCIS (Netherlands)

Drupsteen, L.; Rasmussen, H.B.; Ustailieva, E.; Kampen, J. van

2015-01-01

Working with multiple contractors in a shared workplace can introduce and increase safety risks due to complexity. The aim of this study was to explore how safety issues are recognized in a specific case and to identify whether clients and contractors perceive problems similarly. The safety issues

Safety Assessment Methodologies and Their Application in Development of Near Surface Waste Disposal Facilities--ASAM Project

International Nuclear Information System (INIS)

Batandjieva, B.; Metcalf, P.

2003-01-01

Safety of near surface disposal facilities is a primary focus and objective of stakeholders involved in radioactive waste management of low and intermediate level waste and safety assessment is an important tool contributing to the evaluation and demonstration of the overall safety of these facilities. It plays significant role in different stages of development of these facilities (site characterization, design, operation, closure) and especially for those facilities for which safety assessment has not been performed or safety has not been demonstrated yet and the future has not been decided. Safety assessments also create the basis for the safety arguments presented to nuclear regulators, public and other interested parties in respect of the safety of existing facilities, the measures to upgrade existing facilities and development of new facilities. The International Atomic Energy Agency (IAEA) has initiated a number of research coordinated projects in the field of development and improvement of approaches to safety assessment and methodologies for safety assessment of near surface disposal facilities, such as NSARS (Near Surface Radioactive Waste Disposal Safety Assessment Reliability Study) and ISAM (Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities) projects. These projects were very successful and showed that there is a need to promote the consistent application of the safety assessment methodologies and to explore approaches to regulatory review of safety assessments and safety cases in order to make safety related decisions. These objectives have been the basis of the IAEA follow up coordinated research project--ASAM (Application of Safety Assessment Methodologies for Near Surface Disposal Facilities), which will commence in November 2002 and continue for a period of three years

Development of web-based safety review advisory system

International Nuclear Information System (INIS)

Kim, M. W.; Lee, H. C.; Park, S. O.; Lee, K. H.; Hur, K. Y.; Lee, S. J.; Choi, S. S.; Kang, C. M.

2002-01-01

For the development of an expert system supporting the safety review of nuclear power plants, the application was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they are investigated by KINS (Korea Institute of Nuclear Safety). The Safety Review Advisory System(SRAS), this application on web-server environment was developed according to the above specifications. Reviews can do their safety reviewing regardless of their speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into four groups, administrator, project manager, project reviewer and general reviewer. Each user group is delegated appropriate access capability. The function and some screen shots of SRAS are described

The nuclear safety case for the replacement research reactor

International Nuclear Information System (INIS)

Willers, A.; Garea, V.

2003-01-01

This paper presents a broad overview of the safety case being used in the licensing of Australia's Replacement Research Reactor. The reactor is a 20 MW pool-type research reactor and is being constructed at the Lucas Heights Science and Technology Centre in Sydney's south. It will be owned and operated by the Australian Nuclear Science and Technology Organisation (ANSTO) and will take over the duties currently performed by HIFAR, a DIDO-type reactor currently operating at the site. The safety case for the RRR considers all aspects of normal operation and anticipated occurrences and will be subject to periodic review and updated in line with evolving methodologies and modifications to plant and procedures. Its scope and degree of detail ensure that the risk posed to members of the public, operators and environment are all adequately low and well in the regulatory limits

Assessing progress in the development of safety culture

International Nuclear Information System (INIS)

Rotaru, Ioan; Ghita, Sorin

1999-01-01

visible prescriptive formula for developing a strong safety culture. However, a prerequisite is genuine and consistent commitment by the top management of an organization to improving safety . Providing this commitment exists, the best recommendation is to due something tangible and visible to improve safety, preferably involving employees from the outset. The choice of practices for developing an improved safety culture should take account of the existing national and organizational culture in order to ensure effective implementation. The importance of the learning process has been emphasized. A mechanism is necessary to ensure that international experience of practices to develop a strong safety culture is shared on a regular and frequent basis. The maintenance and improvement of a safety culture is a process of continuous evolution. Indicators are available to assess positive progress in this evolution and to detect a weakening safety culture. (authors)

The business case for safety and health at work : cost-benefit analyses of interventions in small and medium-sized enterprises

NARCIS (Netherlands)

Targoutzidis, A.; Koukoulaki, T.; Schmitz-Felten, E.; Kuhl, K.; Oude Hengel, K.M.; Rijken, E.; Broek K. van den; Kluser, R.

2014-01-01

This report examines the economic aspects of occupational safety and health (OSH) interventions in small and medium-sized businesses (SMEs). First, case studies in the existing literature were identified and examined. Second, 13 new case studies on OSH initiatives in European SMEs were developed,

Development of the international status of science and technology concerning methods and tools for operational and long-term safety cases; Weiterentwicklung des internationalen Stands von Wissenschaft und Technik zu Methoden und Werkzeugen fuer Betriebs- und Langzeitsicherheitsnachweise

Energy Technology Data Exchange (ETDEWEB)

Seher, Holger; Beuth, Thomas; Bracke, Guido; Kock, Ingo; Mayer, Kim-Marisa; Moog, Helge C.; Uhlmann, Stephan; Weyand, Torben (eds.)

2016-09-15

The project ''development of the international status of science and technology concerning methods and tools for operational and long-term safety cases'' covers the following key aspects: global aspects of the methodology for scenario assumption for the operational phase following closure, potential analysis of the derives safety cases for the project Gorleben, determination of the solid phase composition of high-level radioactive wastes using geochemical modeling calculations, search for an adequate approach for the calculation of density and viscosity of saline solutions for the future use in GRS computer codes, international approaches for an integral analysis for the host rocks clay and granite in relation to the safety requirements of BMUB.

Development of web-based safety review advisory system

International Nuclear Information System (INIS)

Kim, M. W.; Hur, K. Y.; Lee, S. J.; Choi, S. J.

2002-01-01

For the development of an expert system supporting the safety review of nuclear power plants, the application was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they are investigated by KINS. Safety Review Advisory System (SRAS), this application on web-server environment was developed according to the above specifications. Reviews can do their safety reviewing regardless of their speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into four groups, administrator, project manager, project reviewer and general reviewer. Each user group is delegated appropriate access capability. The function and some screen shots of SRAS are described

Development of safety analysis technology for integral reactor; evaluation on safety concerns of integral reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Hee Chul; Kim, Woong Sik; Lee, J. H. [Korea Institute of Nuclear Safety, Taejeon (Korea)

2002-03-01

The Nuclear Desalination Plant (NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in this study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current light water reactor and advanced reactor designs, and user requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified and discussed. They include the use of proven technology for new safety features, systematic event classification and selection, strengthening containment function, and the safety impacts on desalination-related systems. The study presents the general safety requirements applicable to licensing of an integral reactor and suggests additional regulatory requirements, which need to be developed, based on the direction to resolution of the safety concerns. The efforts to identify and technically resolve the safety concerns in the design stage will provide the early confidence of SMART safety and the technical basis to evaluate the safety to designers and reviewers in the future. Suggestion on the development of additional regulatory requirements will contribute for the regulator to taking actions for licensing of an integral reactor. 66 refs., 5 figs., 24 tabs. (Author)

Feasibility and safety of on table extubation after corrective surgical repair of tetralogy of Fallot in a developing country: A case series

Directory of Open Access Journals (Sweden)

Mohammad Irfan Akhtar

2015-01-01

Full Text Available Fast-track extubation is an established safe practice in pediatric congenital heart disease (CHD surgical patients. On table extubation (OTE in acyanotic CHD surgical patients is well established with validated safety profile. This practice is not yet reported in tetralogy of Fallot (TOF cardiac surgical repair patients in developing countries. Evidence suggests that TOF total correction patients should be extubated early, as positive pressure ventilation has a negative impact on right ventricular function and the overall increase in post-TOF repair complications such as low cardiac output state and arrhythmias. The objective of the case series was to determine the safety and feasibility of OTE in elective TOF total correction cardiac surgical patients with an integrated team approach. To the best of our knowledge, this is the first reported case series. A total of 8 elective male and female TOF patients were included. Standard anesthetic, surgical and perfusion techniques were used in these procedures. All patients were extubated in the operating room safely without any complications with the exception of one patient who continued to bleed for 3 h of postextubation at 2-3 ml/kg/h which was managed with transfusion of fresh frozen plasma at 15 mL/kg, packed red blood cells 10 mL/kg and bolus of transamine at 20 mg/kg. Apart from better surgical and bypass techniques, the most important factor leading to successful OTE was an excellent analgesia. On the basis of the case series, it is suggested to extubate selected TOF cardiac surgery repair patients on table safely with integrated multidisciplinary approach.

The development of a safety analysis methodology for the optimized power reactor 1000

International Nuclear Information System (INIS)

Hwang-Yong, Jun; Yo-Han, Kim

2005-01-01

Korea Electric Power Research Institute (KEPRI) has been developing inhouse safety analysis methodology based on the delicate codes available to KEPRI to overcome the problems arising from currently used vendor oriented methodologies. For the Loss of Coolant Accident (LOCA) analysis, the KREM (KEPRI Realistic Evaluation Methodology) has been developed based on the RELAP-5 code. The methodology was approved for the Westinghouse 3-loop plants by the Korean regulatory organization and the project to extent the methodology to the Optimized Power Reactor 1000 (OPR1000) has been ongoing since 2001. Also, for the Non-LOCA analysis, the KNAP (Korea Non-LOCA Analysis Package) has been developed using the UNICORN-TM code system. To demonstrate the feasibility of these codes systems and methodologies, some typical cases of the design basis accidents mentioned in the final safety analysis report (FSAR) were analyzed. (author)

Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467

Energy Technology Data Exchange (ETDEWEB)

Van Luik, Abraham; Patterson, Russell; Nelson, Roger [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States); Leigh, Christi [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)

2013-07-01

The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA for re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)

Personnel radiation safety. A case of hand lesion in a radiologist

International Nuclear Information System (INIS)

Pilipenko, M.Yi.; Kulyinyich, G.V.; Stadnik, L.L.

2012-01-01

The work featured the questions of norma and rules of radiation safety at work with ionizing radiation. The history of the question about the permissible doses is dabbler's. The changes in the skin when exceeding the tolerant dose are described. A case of severe local lesions of the hand caused by chronic occupational over irradiation, when the safety rules were neglected, is described

The role of production and teamwork practices in construction safety: a cognitive model and an empirical case study.

Science.gov (United States)

Mitropoulos, Panagiotis Takis; Cupido, Gerardo

2009-01-01

In construction, the challenge for researchers and practitioners is to develop work systems (production processes and teams) that can achieve high productivity and high safety at the same time. However, construction accident causation models ignore the role of work practices and teamwork. This study investigates the mechanisms by which production and teamwork practices affect the likelihood of accidents. The paper synthesizes a new model for construction safety based on the cognitive perspective (Fuller's Task-Demand-Capability Interface model, 2005) and then presents an exploratory case study. The case study investigates and compares the work practices of two residential framing crews: a 'High Reliability Crew' (HRC)--that is, a crew with exceptional productivity and safety over several years, and an average performing crew from the same company. The model explains how the production and teamwork practices generate the work situations that workers face (the task demands) and affect the workers ability to cope (capabilities). The case study indicates that the work practices of the HRC directly influence the task demands and match them with the applied capabilities. These practices were guided by the 'principle' of avoiding errors and rework and included work planning and preparation, work distribution, managing the production pressures, and quality and behavior monitoring. The Task Demand-Capability model links construction research to a cognitive model of accident causation and provides a new way to conceptualize safety as an emergent property of the production practices and teamwork processes. The empirical evidence indicates that the crews' work practices and team processes strongly affect the task demands, the applied capabilities, and the match between demands and capabilities. The proposed model and the exploratory case study will guide further discovery of work practices and teamwork processes that can increase both productivity and safety in construction

Safety assessment methodologies for near surface disposal facilities. Results of a co-ordinated research project (ISAM). Volume 1: Review and enhancement of safety assessment approaches and tools. Volume 2: Test cases

International Nuclear Information System (INIS)

2004-07-01

For several decades, countries have made use of near surface facilities for the disposal of low and intermediate level radioactive waste. In line with the internationally agreed principles of radioactive waste management, the safety of these facilities needs to be ensured during all stages of their lifetimes, including the post-closure period. By the mid 1990s, formal methodologies for evaluating the long term safety of such facilities had been developed, but intercomparison of these methodologies had revealed a number of discrepancies between them. Consequently, in 1997, the International Atomic Energy Agency launched a Co-ordinated Research Project (CRP) on Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM). The particular objectives of the CRP were to provide a critical evaluation of the approaches and tools used in post-closure safety assessment for proposed and existing near-surface radioactive waste disposal facilities, enhance the approaches and tools used and build confidence in the approaches and tools used. The CRP ran until 2000 and resulted in the development of a harmonized assessment methodology (the ISAM project methodology), which was applied to a number of test cases. Over seventy participants from twenty-two Member States played an active role in the project and it attracted interest from around seven hundred persons involved with safety assessment in seventy-two Member States. The results of the CRP have contributed to the Action Plan on the Safety of Radioactive Waste Management which was approved by the Board of Governors and endorsed by the General Conference in September 2001. Specifically, they contribute to Action 5, which requests the IAEA Secretariat to 'develop a structured and systematic programme to ensure adequate application of the Agency's waste safety standards', by elaborating on the Safety Requirements on 'Near Surface Disposal of Radioactive Waste' (Safety Standards Series No. WS-R-1) and

Safety performance monitoring of autonomous marine systems

International Nuclear Information System (INIS)

Thieme, Christoph A.; Utne, Ingrid B.

2017-01-01

The marine environment is vast, harsh, and challenging. Unanticipated faults and events might lead to loss of vessels, transported goods, collected scientific data, and business reputation. Hence, systems have to be in place that monitor the safety performance of operation and indicate if it drifts into an intolerable safety level. This article proposes a process for developing safety indicators for the operation of autonomous marine systems (AMS). The condition of safety barriers and resilience engineering form the basis for the development of safety indicators, synthesizing and further adjusting the dual assurance and the resilience based early warning indicator (REWI) approaches. The article locates the process for developing safety indicators in the system life cycle emphasizing a timely implementation of the safety indicators. The resulting safety indicators reflect safety in AMS operation and can assist in planning of operations, in daily operational decision-making, and identification of improvements. Operation of an autonomous underwater vehicle (AUV) exemplifies the process for developing safety indicators and their implementation. The case study shows that the proposed process leads to a comprehensive set of safety indicators. It is expected that application of the resulting safety indicators consequently will contribute to safer operation of current and future AMS. - Highlights: • Process for developing safety indicators for autonomous marine systems. • Safety indicators based on safety barriers and resilience thinking. • Location of the development process in the system lifecycle. • Case study on AUV demonstrating applicability of the process.

Development and applications of a safety assessment system for promoting safety culture in nuclear power plants

International Nuclear Information System (INIS)

Takano, Ken-ichi; Hasegawa, Naoko; Hirose, Ayako; Hayase, Ken-ichi

2004-01-01

For past five years, CRIEPI has been continuing efforts to develop and make applications of a 'safety assessment system' which enable to measure the safety level of organization. This report describe about frame of the system, assessment results and its reliability, and relation between labor accident rate in the site and total safety index (TSI), which can be obtained by the principal factors analysis. The safety assessment in this report is based on questionnaire survey of employee. The format and concrete questionnaires were developed using existing literatures including organizational assessment tools. The tailored questionnaire format involved 124 questionnaire items. The assessment results could be considered as a well indicator of the safety level of organization, safety management, and safety awareness of employee. (author)

The Environmental Agency's Assessment of the Post-Closure Safety Case for the BNFL DRIGG Low Level Radioactive Waste Disposal Facility

International Nuclear Information System (INIS)

Streatfield, I. J.; Duerden, S. L.; Yearsley, R. A.

2002-01-01

The Environment Agency is responsible, in England and Wales, for authorization of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorized by the Environment Agency to dispose of solid low level radioactive waste at its site at Drigg, near Sellafield, NW England. As part of a planned review of this authorization, the Environment Agency is currently undertaking an assessment of BNFL's Post-Closure Safety Case Development Programme for the Drigg disposal facility. This paper presents an outline of the review methodology developed and implemented by the Environment Agency specifically for the planned review of BNFL's Post-Closure Safety Case. The paper also provides an overview of the Environment Agency's progress in its on-going assessment programme

Developments in safety and operations culture in BNFL's thorp reprocessing plant, Sellafield, Cumbria

International Nuclear Information System (INIS)

Kett, P.J.

2000-01-01

One of the best descriptions of Culture is 'how we do things around here'. In a stable organisation it is extremely difficult to change any type of culture, whether it is an operations, customer service or safety culture. To change culture one of two elements are essential. There must be either a significant external pressure felt by all in the organisation or a change in senior management, with authority to set a new direction for the organisation. BNFL had a unique opportunity through the commissioning and operation of the Thorp Reprocessing Plant at Sellafield to shape a new Safety and Operations Culture. Both the key elements for change were present. Thorp was a high profile flagship plant that had attracted multinational investment. It incorporated new technology. The workforce had volunteered to operate the plant. A strong senior management team was specially selected. The plant was being commissioned in an environment where there was significant opposition by 'anti nuclear' groups. It was essential to both BNFL and the wider international nuclear community that Thorp was commissioned and operated safely. A strong operating culture was developed with safety as the corner stone. The culture comprises three key components. Rigorous plant safety case and risk assessments before work commences and modifications to the plant occur; A high level of involvement by all levels of the workforce in both operations and safety matters; Strong supportive leadership which does not allow safety standards to be compromised and encourages open debate on how to improve. During commissioning and early operation of Thorp the robustness of the Safety and Operations Culture was demonstrated. On several occasions, despite intense commercial pressure, operations were halted until the situation was resolved both technically and procedurally. This paper describes how the Safety and Operations Culture was developed. The key factors for success include recruitment, team selection

Development of Safety Review Guide for the Periodic Safety Review of Reactor Vessel Internals

International Nuclear Information System (INIS)

Park, Jeongsoon; Ko, Hanok; Kim, Seonjae; Jhung, Myungjo

2013-01-01

Aging management of the reactor vessel internals (RVIs) is one of the important issues for long-term operation of nuclear power plants (NPPs). Safety review on the assessment and management of the RVI aging is conducted through the process of a periodic safety review (PSR). The regulatory body should check that reactor facilities sustain safety functions in light of degradation due to aging and that the operator of a nuclear power reactor establishes and implements management program to deal with degradation due to aging in order to guarantee the safety functions and the safety margin as a result of PSR. KINS(Korea Institute of Nuclear Safety) has utilized safety review guides (SRG) which provide guidance to KINS staffs in performing safety reviews in order to assure the quality and uniformity of staff safety reviews. The KINS SRGs for the continued operation of pressurized water reactors (PWRs) published in 2006 contain areas of review regarding aging management of RVIs in chapter 2 (III.2.15, Appendix 2.0.1). However unlike the SRGs for the continued operation, KINS has not officially published the SRGs for the PSR of PWRs, but published them as a form of the research report. In addition to that, the report provides almost same review procedures for aging assessment and management of RVIs with the ones provided in the SRGs for the continued operation, it cannot provide review guidance specific to PSRs. Therefore, a PSR safety review guide should be developed for RVIs in PWRs. In this study, a draft PSR safety review guide for reactor vessel internals in PWRs is developed and provided. In this paper, a draft PSR safety review guide for reactor vessel internals (PSR SRG-RVIs) in PWRs is introduced and main contents of the draft are provided. However, since the PSR safety review guides for areas other than RVIs in the pressurized water reactors (PWRs) are expected to be developed in the near future, the draft PSR SRG-RVIs should be revisited to be compatible with

Sanitary and phytosanitary measures and food safety: challenges and opportunities for developing countries.

Science.gov (United States)

Siméon, M

2006-08-01

Because of fast-growing demand, export markets can absorb high value added products and offer high returns; for many developing countries export market development is thus a key requirement for rural income generation and rural growth. Although developing countries face increasingly strict sanitary and phytosanitary standards in their export markets, they can maintain and improve market access--and improve domestic food safety and agricultural productivity--by adopting a strategic approach to food safety, agricultural health and trade. High-income countries should increase development flows to help developing countries build the capacity to plan and execute the necessary strategies. The first proposal in this paper is to make two existing sets of guidelines widely available to interested parties, in particular through the World Bank and the World Organisation for Animal Health (OIE). The first covers the broad process of problem assessment, strategy development and action plan formulation; the second set deals with institutional analysis and training of staff of the official sanitary control services. The second proposal is that interested countries and donors should speed up the ongoing development of guidelines, computer software tools and training material to help countries quantify the importance and impact of food safety issues. The focus here is on a 'multipurpose agricultural data analysis and modelization system'. The third proposal is to carry out a case study to help demonstrate that a number of animal health issues related to food safety should be treated as relating to 'global public goods' and thus require intervention on a global scale. Possible candidates are foot and mouth disease and highly pathogenic avian influenza.

Assuring consumer safety without animal testing: a feasibility case study for skin sensitisation.

Science.gov (United States)

Maxwell, Gavin; Aleksic, Maja; Aptula, Aynur; Carmichael, Paul; Fentem, Julia; Gilmour, Nicola; Mackay, Cameron; Pease, Camilla; Pendlington, Ruth; Reynolds, Fiona; Scott, Daniel; Warner, Guy; Westmoreland, Carl

2008-11-01

Allergic Contact Dermatitis (ACD; chemical-induced skin sensitisation) represents a key consumer safety endpoint for the cosmetics industry. At present, animal tests (predominantly the mouse Local Lymph Node Assay) are used to generate skin sensitisation hazard data for use in consumer safety risk assessments. An animal testing ban on chemicals to be used in cosmetics will come into effect in the European Union (EU) from March 2009. This animal testing ban is also linked to an EU marketing ban on products containing any ingredients that have been subsequently tested in animals, from March 2009 or March 2013, depending on the toxicological endpoint of concern. Consequently, the testing of cosmetic ingredients in animals for their potential to induce skin sensitisation will be subject to an EU marketing ban, from March 2013 onwards. Our conceptual framework and strategy to deliver a non-animal approach to consumer safety risk assessment can be summarised as an evaluation of new technologies (e.g. 'omics', informatics), leading to the development of new non-animal (in silico and in vitro) predictive models for the generation and interpretation of new forms of hazard characterisation data, followed by the development of new risk assessment approaches to integrate these new forms of data and information in the context of human exposure. Following the principles of the conceptual framework, we have been investigating existing and developing new technologies, models and approaches, in order to explore the feasibility of delivering consumer safety risk assessment decisions in the absence of new animal data. We present here our progress in implementing this conceptual framework, with the skin sensitisation endpoint used as a case study. 2008 FRAME.

Status of SPACE Safety Analysis Code Development

International Nuclear Information System (INIS)

Lee, Dong Hyuk; Yang, Chang Keun; Kim, Se Yun; Ha, Sang Jun

2009-01-01

In 2006, the Korean the Korean nuclear industry started developing a thermal-hydraulic analysis code for safety analysis of PWR(Pressurized Water Reactor). The new code is named as SPACE(Safety and Performance Analysis Code for Nuclear Power Plant). The SPACE code can solve two-fluid, three-field governing equations in one dimensional or three dimensional geometry. The SPACE code has many component models required for modeling a PWR, such as reactor coolant pump, safety injection tank, etc. The programming language used in the new code is C++, for new generation of engineers who are more comfortable with C/C++ than old FORTRAN language. This paper describes general characteristics of SPACE code and current status of SPACE code development

How stakeholders view the use of analogues in safety cases: PAMINA

International Nuclear Information System (INIS)

Atherton, Elizabeth; Bailey, Lucy

2008-01-01

The aim of this presentation is to provide an overview of some research that has been undertaken in the UK to investigate stakeholders' views of analogues. There are various reasons for using analogues including: to try and explain difficult concepts; to compare disposal facility features with familiar and/or natural systems; to provide an alternative, non-numerical line of reasoning to support the Safety Case conclusions; to provide evidence of behaviour over very long timescales, that cannot be achieved in the laboratory. There are some dangers when using analogues that people should be aware of: the analogue conditions may not be the same as those found in a disposal facility, so the analogue may have limited application. Some analogues may have negative implications, for example artefacts that have corroded. Analogues can be taken too far and used in inappropriate ways to try and support an assumption. So it is important to find out how stakeholders view the use of analogues in a safety case. NDA is involved in an EC funded project called Pamina (Performance Assessment Methodologies in Application). The project involves 26 partners from 11 European countries, plus other associated members and runs for 3 years from October 2006 to October 2009. The NDA is involved in several parts of the project: Exploring issues of modelling uncertainty; Evaluating effectiveness of approaches for communicating safety cases with stakeholders. NDA ran a workshop in October 2007 in Manchester. The aims of the workshop were to explore how different methods of communicating aspects of a safety case were received by stakeholders. The workshop presented stakeholders with: Examples of different repository concepts; Descriptions of barrier performance; Different ways of presenting numerical results; Use of natural analogues

The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

Energy Technology Data Exchange (ETDEWEB)

Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

2006-07-01

The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

Comprehensive development plans for the low- and intermediate-level radioactive waste disposal facility in Korea and preliminary safety assessment

Energy Technology Data Exchange (ETDEWEB)

Jung, Kang Il; Kim, Jin Hyeong; Kwon, Mi Jin; Jeong, Mi Seon; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

2016-12-15

The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

Developing safety culture-rocket science or common sense?

International Nuclear Information System (INIS)

Mahn, J.A.

1998-01-01

Despite evidence of significant management contributions to the causes of major accidents, recent events at Millstone Nuclear Power Station in the US and Ontario Hydro in Canada might lead one to conclude that the significance of safety culture, and the role of management in developing and maintaining an appropriate safety culture, is either not being understood or not being taken serious as integral to the safe operation of some complex, high-reliability operations. It is the purpose of this paper to address four aspects of management that are particularly important to safety culture, and to illustrate how development of an appropriate safety culture is more a matter of common sense than rocket science

Developing safety culture-rocket science or common sense?

Energy Technology Data Exchange (ETDEWEB)

Mahn, J.A.

1998-08-01

Despite evidence of significant management contributions to the causes of major accidents, recent events at Millstone Nuclear Power Station in the US and Ontario Hydro in Canada might lead one to conclude that the significance of safety culture, and the role of management in developing and maintaining an appropriate safety culture, is either not being understood or not being taken serious as integral to the safe operation of some complex, high-reliability operations. It is the purpose of this paper to address four aspects of management that are particularly important to safety culture, and to illustrate how development of an appropriate safety culture is more a matter of common sense than rocket science.

Development of Comprehensive Nuclear Safety Regulation Plan for 2007-2011

International Nuclear Information System (INIS)

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

2006-01-01

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

EXPLORATORY STUDY OF OBSTACLES IN SAFETY CULTURE DEVELOPMENT IN THE CONSTRUCTION INDUSTRY: A GROUNDED THEORY APPROACH

Directory of Open Access Journals (Sweden)

Bonaventure H.W. Hadikusumo

2010-06-01

Full Text Available The aim of this paper is to analyse the obstacles that prevent the development of a safety culture in Thailand’s large construction industry from various managerial points of view. Qualitative research methods were used by performing a series of semi-structured interviews of eight case studies selected from six prominent construction firms to investigate the obstacles they face. Glaser’s keyword coding from Grounded Theory was used to reduce the information load after the interviews. Our findings revealed that the factors influencing the successful development of a safety culture in the construction industry are the workers, the characteristics of construction, the subcontractors, the supervisors, and external factors. Based on the frequency analysis, the main obstacles in developing a safety culture result from problems related to the workers themselves. The three most frequently discussed problems are unskilled workers, unsafe worker habits, and high worker turnover. Our results also suggest that managers should encourage engagement from their workers to optimise the successful implementation of safety programs and their long-term improvement.

Thermodynamic sorption modelling in support of radioactive waste disposal safety cases - NEA sorption project phase III

International Nuclear Information System (INIS)

2012-01-01

A central safety function of radioactive waste disposal repositories is the prevention or sufficient retardation of radionuclide migration to the biosphere. Performance assessment exercises in various countries, and for a range of disposal scenarios, have demonstrated that one of the most important processes providing this safety function is the sorption of radionuclides along potential migration paths beyond the engineered barriers. Thermodynamic sorption models (TSMs) are key for improving confidence in assumptions made about such radionuclide sorption when preparing a repository's safety case. This report presents guidelines for TSM development as well as their application in repository performance assessments. They will be of particular interest to the sorption modelling community and radionuclide migration modellers in developing safety cases for radioactive waste disposal Contents: 1 - Thermodynamic sorption models and radionuclide migration: Sorption and radionuclide migration; Applications of TSMs in radioactive waste disposal studies; Requirements for a scientifically defensible, calibrated TSM applicable to radioactive waste disposal; Current status of TSMs in radioactive waste management; 2 - Theoretical basis of TSMs and options in model development: Conceptual building blocks of TSMs and integration with aqueous chemistry; The TSM representation of sorption and relationship with Kd values; Theoretical basis of TSMs; Example of TSM for uranyl sorption; Options in TSM development; Illustration of TSM development and effects of modelling choices; Summary: TSMs for constraining Kd values - impact of modelling choices; 3 - Determination of parameters for TSMs: Overview of experimental determination of TSM parameters; Theoretical estimation methods of selected model parameters; Case study: sorption modelling of trivalent lanthanides/actinides on illite; Indicative values for certain TSM parameters; Parameter uncertainty; Illustration of parameter sensitivity

Maintaining and Researching Port Safety: A Case Study of the Port of Kaohsiung

OpenAIRE

Tseng, Po-Hsing.; Pilcher, Nick.

2017-01-01

Maintaining port safety in full conformity with IMO standards is a requisite for every port and country. To do this, understanding the challenges and human factors involved is key. To date, much research has shed valuable light on these factors and considered how to address them. One aspect that is often noted is that both maintaining port safety and researching port safety presents numerous challenges. This paper considers both these aspects in the context of a case study of port safety in K...

Determination of Seismic Safety Zones during the Surface Mining Operation Development in the Case of the “Buvač” Open Pit

Directory of Open Access Journals (Sweden)

Vladimir Malbasic

2018-02-01

Full Text Available Determination of the blasting safety area is a very important step in the process of drilling and blasting works, and the preparation of solid rock materials for loading. Through monitoring and analysis of the negative seismic effects to the objects and infrastructures around and at the mine area, we were able to adapt the drilling and blasting parameters and organization of drilling and blasting operation according to the mining progress so that the affected infrastructures could be protected. This paper analyses the safety distances and model safety zones of drilling and blasting for the period 2013–2018 at the open pit at “Buvač”, Omarska. This mathematical calculation procedure can be used during the whole life of the mine. By monitoring of the blasting seismic influence in first years of the mine's work, as well as by using recorded vibration velocities, mathematical dependence of the important parameters can be defined. Additionally, the level and laws of distribution and intensity of the seismic activity can be defined. On one hand, those are known quantities of the explosive and the distances between blasting location and endangered objects. On the other hand, those are coefficients of the manner of blasting and the environment where blasting is done, K, as well as the coefficient of the weakening of seismic waves as they spread, n. With the usage of the allowed vibration velocities, based on certain safety criteria and mathematical formulas of laws of spreading and intensity of seismic influence for a concrete case, it is possible to calculate explosive quantities and distances, with numerically-defined values of parameter K and n. Minimum distances are calculated based on defined or projected explosive quantities. Additionally, we calculate the maximum allowed explosive quantities based on known distances which can be used based on projected drilling-blasting parameters. For the purpose of the planning of drilling and blasting

Developing IAM for Life Cycle Safety Assessment

NARCIS (Netherlands)

Toxopeus, Marten E.; Lutters, Diederick; Nee, Andrew Y.C.; Song, Bin; Ong, Soh-Khim

2013-01-01

This publication discusses aspects of the development of an impact assessment method (IAM) for safety. Compared to the many existing IAM’s for environmentally oriented LCA, this method should translate the impact of a product life cycle on the subject of safety. Moreover, the method should be

Initial development of a practical safety audit tool to assess fleet safety management practices.

Science.gov (United States)

Mitchell, Rebecca; Friswell, Rena; Mooren, Lori

2012-07-01

Work-related vehicle crashes are a common cause of occupational injury. Yet, there are few studies that investigate management practices used for light vehicle fleets (i.e. vehicles less than 4.5 tonnes). One of the impediments to obtaining and sharing information on effective fleet safety management is the lack of an evidence-based, standardised measurement tool. This article describes the initial development of an audit tool to assess fleet safety management practices in light vehicle fleets. The audit tool was developed by triangulating information from a review of the literature on fleet safety management practices and from semi-structured interviews with 15 fleet managers and 21 fleet drivers. A preliminary useability assessment was conducted with 5 organisations. The audit tool assesses the management of fleet safety against five core categories: (1) management, systems and processes; (2) monitoring and assessment; (3) employee recruitment, training and education; (4) vehicle technology, selection and maintenance; and (5) vehicle journeys. Each of these core categories has between 1 and 3 sub-categories. Organisations are rated at one of 4 levels on each sub-category. The fleet safety management audit tool is designed to identify the extent to which fleet safety is managed in an organisation against best practice. It is intended that the audit tool be used to conduct audits within an organisation to provide an indicator of progress in managing fleet safety and to consistently benchmark performance against other organisations. Application of the tool by fleet safety researchers is now needed to inform its further development and refinement and to permit psychometric evaluation. Copyright © 2012 Elsevier Ltd. All rights reserved.

Development and Execution of the RUNSAFE Runway Safety Bayesian Belief Network Model

Science.gov (United States)

Green, Lawrence L.

2015-01-01

One focus area of the National Aeronautics and Space Administration (NASA) is to improve aviation safety. Runway safety is one such thrust of investigation and research. The two primary components of this runway safety research are in runway incursion (RI) and runway excursion (RE) events. These are adverse ground-based aviation incidents that endanger crew, passengers, aircraft and perhaps other nearby people or property. A runway incursion is the incorrect presence of an aircraft, vehicle or person on the protected area of a surface designated for the landing and take-off of aircraft; one class of RI events simultaneously involves two aircraft, such as one aircraft incorrectly landing on a runway while another aircraft is taking off from the same runway. A runway excursion is an incident involving only a single aircraft defined as a veer-off or overrun off the runway surface. Within the scope of this effort at NASA Langley Research Center (LaRC), generic RI, RE and combined (RI plus RE, or RUNSAFE) event models have each been developed and implemented as a Bayesian Belief Network (BBN). Descriptions of runway safety issues from the literature searches have been used to develop the BBN models. Numerous considerations surrounding the process of developing the event models have been documented in this report. The event models were then thoroughly reviewed by a Subject Matter Expert (SME) panel through multiple knowledge elicitation sessions. Numerous improvements to the model structure (definitions, node names, node states and the connecting link topology) were made by the SME panel. Sample executions of the final RUNSAFE model have been presented herein for baseline and worst-case scenarios. Finally, a parameter sensitivity analysis for a given scenario was performed to show the risk drivers. The NASA and LaRC research in runway safety event modeling through the use of BBN technology is important for several reasons. These include: 1) providing a means to clearly

Global road safety online course development.

Science.gov (United States)

2017-06-01

The Global Road Safety Online Curriculum Development project involved the adaptation of in-person classroom materials and development of new materials to be used in an online setting. A short-course format was selected to pilot the course, and four t...

Development of fusion safety standards

International Nuclear Information System (INIS)

Longhurst, G.R.; Petti, D.A.; Dinneen, G.A.; Herring, J.S.; DeLooper, J.; Levine, J.D.; Gouge, M.J.

1996-01-01

Two new U.S. Department of Energy (DOE) standards have been prepared to assist in the design and regulation of magnetic fusion facilities. They are DOE-STD-6002-96, 'Safety of Magnetic Fusion Facilities - Requirements,' and DOE-STD-6003-96 'Safety of Magnetic Fusion Facilities - Guidance.' The first standard sets forth requirements, mostly based on the Code of Federal Regulations, deemed necessary for the safe design and operation of fusion facilities and a set of safety principles to use in the design. The second standard provides guidance on how to meet the requirements identified in DOE-STD-6002-96. It is written specifically for a facility such as the International Thermonuclear Experimental Reactor (ITER) in the DOE regulatory environment. As technical standards, they are applicable only to the extent that compliance with these standards is included in the contracts of the developers. 7 refs., 1 fig

You can't improve what you don't measure: Safety climate measures available in the German-speaking countries to support safety culture development in healthcare.

Science.gov (United States)

Manser, Tanja; Brösterhaus, Mareen; Hammer, Antje

2016-01-01

Safety climate measurement is a key input into safety culture development. The aim of this review is to provide an overview of the safety climate measures that have been evaluated for their psychometric properties in a German-speaking country and to make recommendations on how to use them in quality and patient safety improvement. A systematic search strategy was implemented to obtain relevant articles. PubMed and Web of Science databases were searched, and 128 abstracts were identified. After application of limits, 33 full texts were retrieved for subsequent evaluation. Studies were included on the basis of predetermined inclusion criteria and independent assessment by two reviewers. Publications were reviewed concerning healthcare setting, target group, safety culture dimensions covered and results of their psychometric evaluation. This review identified 11 instruments for safety climate assessment in different healthcare settings (i. e. hospitals, nursing homes, primary care, dental care and community pharmacy) for which acceptable to good internal consistency was reported. We observed wide variability concerning the number of dimensions (1 to 14; in some cases including outcome dimensions) and items (9 to 128) that the instruments were comprised of. Nevertheless, consistency with regard to the thematic areas covered was rather high. While there is clear evidence that we can assess safety climate in healthcare, the application of safety climate measures by quality and patient safety practitioners has so far been rather limited. This review bridges this gap between research and improvement practice by highlighting the central role of safety climate assessment in a mixed methods approach to inform safety culture development. Copyright © 2016. Published by Elsevier GmbH.

DEVELOPING CITIZEN SAFETY

Directory of Open Access Journals (Sweden)

VRABIE Catalin

2013-12-01

Full Text Available Is it possible to involve citizens in the process of increasing public safety? Police used, even from its beginnings, the help of citizens, otherwise they would encounter problems in performing its duty - many of its successes were due to the unification of Police forces with the citizens. How citizens get involved? (1 They may be directly asked by the Police officers (a time consuming method because many police officers needs to go on the field to speak with the potential witnesses or (2 by using the mass-media channels (television can address to a large number of potential witnesses in a very short time. We still can see on TV portraits of missing persons, or some other kind of images with which the Police is trying to solve some of its cases (thieves, robbers or burglars surprised by surveillance cameras – why not Internet software application?!

Monitoring antimalarial safety and tolerability in clinical trials: A case study from Uganda

Directory of Open Access Journals (Sweden)

Mpimbaza Arthur

2008-06-01

Full Text Available Abstract Background New antimalarial regimens, including artemisinin-based combination therapies (ACTs, have been adopted widely as first-line treatment for uncomplicated malaria. Although these drugs appear to be safe and well-tolerated, experience with their use in Africa is limited and continued assessment of safety is a priority. However, no standardized guidelines for evaluating drug safety and tolerability in malaria studies exist. A system for monitoring adverse events in antimalarial trials conducted in Uganda was developed. Here the reporting system is described, and difficulties faced in analysing and interpreting the safety results are illustrated, using data from the trials. Case description Between 2002 and 2007, eleven randomized, controlled clinical trials were conducted to compare the efficacy, safety, and tolerability of different antimalarial regimens for treatment of uncomplicated malaria in Uganda. The approach to adverse event monitoring was similar in all studies. A total of 5,614 treatments were evaluated in 4,876 patients. Differences in baseline characteristics and patterns of adverse event reporting were noted between the sites, which limited the ability to pool and analyse data. Clinical failure following antimalarial treatment confounded associations between treatment and adverse events that were also common symptoms of malaria, particularly in areas of lower transmission intensity. Discussion and evaluation Despite prospectively evaluating for adverse events, limitations in the monitoring system were identified. New standardized guidelines for monitoring safety and tolerability in antimalarial trials are needed, which should address how to detect events of greatest importance, including serious events, those with a causal relationship to the treatment, those which impact on adherence, and events not previously reported. Conclusion Although the World Health Organization has supported the development of

Workshop on development and view on digital safety system of KNICS

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-05-15

The contents of this workshop are vision of KNICS, introduction of development of safety system of KNICS, development situation of safety class of PLC, view of software for safety-critical system in PLC, RTOS development by shaping, quality assurance and attestation of PLC, development situation of nuclear reactor system and development situation of ESF-CCS.

Workshop on development and view on digital safety system of KNICS

International Nuclear Information System (INIS)

2006-05-01

The contents of this workshop are vision of KNICS, introduction of development of safety system of KNICS, development situation of safety class of PLC, view of software for safety-critical system in PLC, RTOS development by shaping, quality assurance and attestation of PLC, development situation of nuclear reactor system and development situation of ESF-CCS

Development of an FPGA-based controller for safety critical application

International Nuclear Information System (INIS)

Xing, A.; De Grosbois, J.; Sklyar, V.; Archer, P.; Awwal, A.

2011-01-01

In implementing safety functions, Field Programmable Gate Arrays (FPGA) technology offers a distinct combination of benefits and advantages over microprocessor-based systems. FPGAs can be designed such that the final product is purely hardware, without any overhead runtime software, bringing the design closer to a conventional hardware-based solution. On the other hand, FPGAs can implement more complex safety logic that would generally require microprocessor-based safety systems. There are now qualified FPGA-based platforms available on the market with a credible use history in safety applications in nuclear power plants. Atomic Energy of Canada (AECL), in collaboration with RPC Radiy, has initiated a development program to define a vigorous FPGA engineering process suitable for implementing safety critical functions at the application development level. This paper provides an update on the FPGA development program along with the proposed design model using function block diagrams for the development of safety controllers in CANDU applications. (author)

SCALE Graphical Developments for Improved Criticality Safety Analyses

International Nuclear Information System (INIS)

Barnett, D.L.; Bowman, S.M.; Horwedel, J.E.; Petrie, L.M.

1999-01-01

New computer graphic developments at Oak Ridge National Ridge National Laboratory (ORNL) are being used to provide visualization of criticality safety models and calculational results as well as tools for criticality safety analysis input preparation. The purpose of this paper is to present the status of current development efforts to continue to enhance the SCALE (Standardized Computer Analyses for Licensing Evaluations) computer software system. Applications for criticality safety analysis in the areas of 3-D model visualization, input preparation and execution via a graphical user interface (GUI), and two-dimensional (2-D) plotting of results are discussed

Safety management in research and development organisation

International Nuclear Information System (INIS)

Nivedha, T.

2016-01-01

Health and safety is one of the most important aspects of an organizations smooth and effective functioning. It depends on the safety management, health management, motivation, leadership and training, welfare facilities, accident statistics, policy, organization and administration, hazard control and risk analysis, monitoring, statistics and reporting. Workplace accidents are increasingly common, main causes are untidiness, noise, too hot or cold environments, old or poorly maintained machines, and lack of training or carelessness of employees. One of the biggest issues facing employers today is the safety of their employees. This study aims at analyzing the occupational health and safety of Research organization in Indira Gandhi Centre for Atomic Research by gathering information on health management, safety management, motivation, leadership and training, welfare facilities, accident statistics, organization and administration, hazard control and risk analysis, monitoring, statistics and reporting. Data were collected by using questionnaires which were developed on health and safety management system. (author)

The regulatory review of construction license application and the supporting safety case

International Nuclear Information System (INIS)

Heinonen, Jussi

2014-01-01

at the end of 1999 when Posiva Ltd, the current implementer of the disposal programme, submitted the application for a decision-in-principle (DiP, 2000) for a spent fuel disposal facility in the Olkiluoto. The DiP was given by the government in late 2000, approved by the host municipality and ratified by the parliament in early 2001. It gave Posiva the authorisation to start to construct an underground rock characterisation facility, to the depth of the actual planned disposal, as required by regulation. The safety case to support the decision-in-principle application was compiled for 1999. The safety case included a concept description, proposed site characteristics, general facility layout and a safety assessment. The application was further supported by an environmental impact assessment report. Posiva has submitted a construction license application for a spent fuel encapsulation and disposal facility at the end of 2012. STUK is currently finalising the decisions related to the initial review phase and starting the detailed review. The preparatory phase has included among other things a systematic requirement and education programme, negotiation of framework agreements with external support experts and stepwise review of Posiva's developing safety case documents which included the draft construction license application documents. (authors)

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

HSE assessment of explosion risk analysis in offshore safety cases

Energy Technology Data Exchange (ETDEWEB)

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

1995-12-31

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

Science, safety, and trust: the case of transgenic food.

Science.gov (United States)

Martinelli, Lucia; Karbarz, Małgorzata; Siipi, Helena

2013-02-01

Genetically modified (GM) food is discussed as an example of the controversial relation between the intrinsic uncertainty of the scientific approach and the demand of citizen-consumers to use products of science innovation that are known to be safe. On the whole, peer-reviewed studies on GM food safety do not note significant health risks, with a few exceptions, like the most renowned "Pusztai affair" and the recent "Seralini case." These latter studies have been disregarded by the scientific community, based on incorrect experimental designs and statistic analysis. Such contradictory results show the complexity of risk evaluation, and raise concerns in the citizen-consumers against the GM food. A thoughtful consideration by scientific community and decision makers of the moral values that are present in risk evaluation and risk management should be the most trustable answer to citizen-consumers to their claim for clear and definitive answers concerning safety/un-safety of GM food.

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

Science.gov (United States)

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

2016-04-01

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

Nuclear Safety Culture Assessment for a Newcomer Country: Case Study of Jordan

International Nuclear Information System (INIS)

Khasawneh, Khalid; Park, Yun Woon

2016-01-01

For countries initiating or considering to start their nuclear power programs; developing a successful safety culture is of a great challenge, owing to lack of experience and the sensitive nature of the nuclear industry in general. The Jordanian case was chosen since Jordan is in the early stages of its nuclear program and the establishment of an effective safety culture is crucial to guarantee the safe operation of its future nuclear facilities. It also should be noted that Fukushima accident has adversely affected the progress of the Jordanian nuclear program driven by the negative public opinion. The government shifts the policies toward enhancing the nuclear safety by enforcing the communication between the engaged parties and openness and transparency with public. In the wake of Fukushima accident the Jordanian government reassured the appropriate siting criteria and siting review, the leadership and the organizations commitment to nuclear safety by adopting advanced reactor technology, the consideration of modern operator accident mitigation strategies and the increased and close cooperation with IAEA and adherence to evolving international safety standards. The progress in the Jordanian nuclear power project in order to satisfy the IAEA requirements was quantified and ranked. A good progress was shown in some aspects, for example in the multicultural and multi-national elements and the establishment of an independent and effective regulatory body. However, some elements, concerning the understanding of the safety culture, management system of the regulatory body and the cultural assessment was not satisfied and an urgent need to focus on and enhance those aspects are required by the Jordanian government. Some elements, for example the leadership, communication and competence, have partial fulfillment of the IAEA requirements. However enhancing those aspects is required in the short and the mid-term in order to guarantee a well-established nuclear power

Nuclear Safety Culture Assessment for a Newcomer Country: Case Study of Jordan

Energy Technology Data Exchange (ETDEWEB)

Khasawneh, Khalid; Park, Yun Woon [KAIST, Daejeon (Korea, Republic of)

2016-05-15

For countries initiating or considering to start their nuclear power programs; developing a successful safety culture is of a great challenge, owing to lack of experience and the sensitive nature of the nuclear industry in general. The Jordanian case was chosen since Jordan is in the early stages of its nuclear program and the establishment of an effective safety culture is crucial to guarantee the safe operation of its future nuclear facilities. It also should be noted that Fukushima accident has adversely affected the progress of the Jordanian nuclear program driven by the negative public opinion. The government shifts the policies toward enhancing the nuclear safety by enforcing the communication between the engaged parties and openness and transparency with public. In the wake of Fukushima accident the Jordanian government reassured the appropriate siting criteria and siting review, the leadership and the organizations commitment to nuclear safety by adopting advanced reactor technology, the consideration of modern operator accident mitigation strategies and the increased and close cooperation with IAEA and adherence to evolving international safety standards. The progress in the Jordanian nuclear power project in order to satisfy the IAEA requirements was quantified and ranked. A good progress was shown in some aspects, for example in the multicultural and multi-national elements and the establishment of an independent and effective regulatory body. However, some elements, concerning the understanding of the safety culture, management system of the regulatory body and the cultural assessment was not satisfied and an urgent need to focus on and enhance those aspects are required by the Jordanian government. Some elements, for example the leadership, communication and competence, have partial fulfillment of the IAEA requirements. However enhancing those aspects is required in the short and the mid-term in order to guarantee a well-established nuclear power

A systematic review of occupational safety and health business cases.

Science.gov (United States)

Verbeek, Jos; Pulliainen, Marjo; Kankaanpää, Eila

2009-12-01

Business cases are commonly developed as means to rationalize investment. We systematically reviewed 26 reported cases on occupational safety and health (OSH) interventions to assess if health and productivity arguments make a good business case. To be included in the review, studies had to analyze the costs and benefits, including productivity, of an OSH intervention at the enterprise level. We searched Medline and Embase for studies and used Google search in addition. Two reviewers independently selected studies and extracted data. The intervention profitability was calculated in euros (euro in 2008) as the first year's benefits minus the total intervention costs per worker. The payback period was calculated as the intervention costs divided by the first year's benefits. We found three ex-ante and 23 ex-post cases. In 20 cases, the study design was a before-after comparison without a control group. Generally a 100% reduction of injuries or sickness absence was assumed. In two cases, productivity and quality increases were very large. The main benefit was avoided sick leave. Depreciation or discounting was applied only in a minority of cases. The intervention profitability was negative in seven studies, up to euro 500 per employee in 12 studies and more than euro 500 per employee in seven studies. The payback period was less than half a year for 19 studies. Only a few studies included sensitivity analyses. Few ex-ante business cases for management decisions on OSH are reported. Guidelines for reporting and evaluation are needed. Business cases need more sound assumptions on the effectiveness of interventions and should incorporate greater uncertainty into their design. Ex-post evaluation should be based preferably on study designs that control for trends at a time different from that of the intervention.

Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

International Nuclear Information System (INIS)

Reyes, Susana; Anklam, Tom; Meier, Wayne; Campbell, Patrick; Babineau, Dave; Becnel, James; Taylor, Craig; Coons, Jim

2016-01-01

Highlights: • The safety characteristics and at risk inventories in an IFE facility are discussed. • The primary nuclear hazard is the potential exposure of workers and/or the public to tritium and/or neutronically activated products. • Recent technology developments in tritium processing are key for minimization of inventories. • Initial safety studies indicate that hazards associated to the use of liquid lithium can be appropriately managed. • Simulation of worst-case scenarios indicate that the accident consequences are limited and below the limit for public evacuation. - Abstract: Over the past five years, the fusion energy group at Lawrence Livermore National Laboratory (LLNL) has made significant progress in the area of safety and tritium research for Inertial Fusion Energy (IFE). Focus has been driven towards the minimization of inventories, accident safety, development of safety guidelines and licensing considerations. Recent technology developments in tritium processing and target fill have had a major impact on reduction of tritium inventories in the facility. A safety advantage of inertial fusion energy using indirect-drive targets is that the structural materials surrounding the fusion reactions can be protected from target emissions by a low-pressure chamber fill gas, therefore eliminating plasma-material erosion as a source of activated dust production. An important inherent safety advantage of IFE when compared to other magnetic fusion energy (MFE) concepts that have been proposed to-date (including ITER), is that loss of plasma control events with the potential to damage the first wall, such as disruptions, are non-conceivable, therefore eliminating a number of potential accident initiators and radioactive in-vessel source term generation. In this paper, we present an overview of the safety assessments performed to-date, comparing results to the US DOE Fusion Safety Standards guidelines and the recent lessons-learnt from ITER safety and

Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

Energy Technology Data Exchange (ETDEWEB)

Reyes, Susana, E-mail: reyes20@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA (United States); Anklam, Tom; Meier, Wayne; Campbell, Patrick [Lawrence Livermore National Laboratory, Livermore, CA (United States); Babineau, Dave; Becnel, James [Savannah River National Laboratory, Aiken, SC (United States); Taylor, Craig; Coons, Jim [Los Alamos National Laboratory, Los Alamos, NM (United States)

2016-11-01

Highlights: • The safety characteristics and at risk inventories in an IFE facility are discussed. • The primary nuclear hazard is the potential exposure of workers and/or the public to tritium and/or neutronically activated products. • Recent technology developments in tritium processing are key for minimization of inventories. • Initial safety studies indicate that hazards associated to the use of liquid lithium can be appropriately managed. • Simulation of worst-case scenarios indicate that the accident consequences are limited and below the limit for public evacuation. - Abstract: Over the past five years, the fusion energy group at Lawrence Livermore National Laboratory (LLNL) has made significant progress in the area of safety and tritium research for Inertial Fusion Energy (IFE). Focus has been driven towards the minimization of inventories, accident safety, development of safety guidelines and licensing considerations. Recent technology developments in tritium processing and target fill have had a major impact on reduction of tritium inventories in the facility. A safety advantage of inertial fusion energy using indirect-drive targets is that the structural materials surrounding the fusion reactions can be protected from target emissions by a low-pressure chamber fill gas, therefore eliminating plasma-material erosion as a source of activated dust production. An important inherent safety advantage of IFE when compared to other magnetic fusion energy (MFE) concepts that have been proposed to-date (including ITER), is that loss of plasma control events with the potential to damage the first wall, such as disruptions, are non-conceivable, therefore eliminating a number of potential accident initiators and radioactive in-vessel source term generation. In this paper, we present an overview of the safety assessments performed to-date, comparing results to the US DOE Fusion Safety Standards guidelines and the recent lessons-learnt from ITER safety and

Development of Safety Review Guidance for Research and Training Reactors

International Nuclear Information System (INIS)

Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

2007-01-01

The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

Development of safety analysis technology for integral reactor

International Nuclear Information System (INIS)

Kim, Hee Cheol; Kim, K. K.; Kim, S. H.

2002-04-01

The state-of-the-arts for the integral reactor was performed to investigate the safety features. The safety and performance of SMART were assessed using the technologies developed during the study. For this purpose, the computer code system and the analysis methodology were developed and the safety and performance analyses on SMART basic design were carried out for the design basis event and accident. The experimental facilities were designed for the core flow distribution test and the self-pressurizing pressurizer performance test. The tests on the 2-phase critical flow with non-condensable gas were completed and the results were used to assess the critical flow model. Probabilistic Safety Assessment(PSA) was carried out to evaluate the safety level and to optimize the design by identifying and remedying any weakness in the design. A joint study with KINS was carried out to promote licensing environment. The generic safety issues of integral reactors were identified and the solutions were formulated. The economic evaluation of the SMART desalination plant and the activities related to the process control were carried out in the scope of the study

75 FR 15485 - Pipeline Safety: Workshop on Guidelines for Integrity Assessment of Cased Pipe

Science.gov (United States)

2010-03-29

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID...: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of workshop. SUMMARY... ``Guidelines for Integrity Assessment of Cased Pipe in Gas Transmission Pipelines'' and related Frequently...

Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

2015-05-15

IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea.

Development of a Novel Nuclear Safety Culture Evaluation Method for an Operating Team Using Probabilistic Safety Analysis

International Nuclear Information System (INIS)

Han, Sangmin; Lee, Seung Min; Seong, Poong Hyun

2015-01-01

IAEA defined safety culture as follows: 'Safety Culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance'. Also, celebrated behavioral scientist, Cooper, defined safety culture as,'safety culture is that observable degree of effort by which all organizational members direct their attention and actions toward improving safety on a daily basis' with his internal psychological, situational, and behavioral context model. With these various definitions and criteria of safety culture, several safety culture assessment methods have been developed to improve and manage safety culture. To develop a new quantitative safety culture evaluation method for an operating team, we unified and redefined safety culture assessment items. Then we modeled a new safety culture evaluation by adopting level 1 PSA concept. Finally, we suggested the criteria to obtain nominal success probabilities of assessment items by using 'operational definition'. To validate the suggested evaluation method, we analyzed the collected audio-visual recording data collected from a full scope main control room simulator of a NPP in Korea

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

Science.gov (United States)

Hill, Janice; Victor, Daniel

2008-01-01

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

Stakeholder involvement in building and maintaining radiation safety infrastructure in Latvia: The case studies

International Nuclear Information System (INIS)

Eglajs, A.; Salmins, A.

2003-01-01

This paper comprises the assessment of interests for central and local governments, different authorities, public and commercial companies, political parties and non-governmental organizations, organised and ad-hock groups of public, which could contribute to development and maintenance of infrastructure for radiation safety, general environmental protection, as well as for public health among other similar fields. Understanding of these interests allows to be prepared for eventual demonstrations or publications against decisions about significant modifications of infrastructure and provides ideas how to explain needs of financial and human resources for maintaining of supervisory system and management of major facilities, which are vital for safety infrastructure. Two case studies are presented in this report related to modification of the framework law and the preparation of radioactive waste management strategy. (author)

ALARP considerations in criticality safety assessments

International Nuclear Information System (INIS)

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

2003-01-01

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

ENTREPRENEURSHIP ECONOMIC SAFETY AND DEVELOPMENT OF SECURITY SERVICES

Directory of Open Access Journals (Sweden)

G. V. Goudkov

2011-01-01

Full Text Available Successful functioning of the industry that provides for safety of organizations and physical entities exercises strategic impacts on development of society and economics of any state including Russia. Economic safety of Russia is directly linked with economic and information safety of itsbusiness structures. Extension of the scope and use of services offered by experienced state and private security enterprises including licensed individuals is one of most important directions of business safety perfection. Further improvement of Russian legislation on non-governmentalsecurity structures and coordination of their activities with those of state law enforcement bodies is obligatory condition of attaining higherpublic and economic safety levels.

The Development of child road safety competence : the new approach tо road safety education

OpenAIRE

Vilkonis, Rytis

2005-01-01

The education and information are the strategies of the Road safety. However, some of the documents and scientific findings revealed the chaotic, desultory and theoretically groundless Road safety education and it can be stated that Road safety education system in Lithuania is still being established. The shortage of the theoretical and empirical base of Road safety education is slowing down the process of the system development. Aim of the research is to disclose the assumptions for developm...

Formal model-based development for safety-critical embedded software

International Nuclear Information System (INIS)

Kim, Jin Hyun; Choi, Jin Young

2005-01-01

Safety-critical embedded software for nuclear I and C system is developed under the safety and reliability regulation. Programmable logic controller(PLC) is a computer system for instrumentation and control (I and C) system of nuclear power plants. PLC consists of various I and C logics in software, including real-time operating system (RTOS). Hence, errors related with RTOS should be detected and eliminated in development processes. Practically, the verification and validation for errors in RTOS is performed in test procedure, in which a lot of tasks for testing are embedded in RTOS and are running under a test environments. But the test process can not be enough to guarantee the safety and reliability of RTOS. Therefore, in this paper, we introduce to applying formal methods with the development of software for the PLC. We particularity apply formal methods to a development of RTOS for PLC, which is a safety critical level. In this development, we use the state charts of I-Logix to specify and verification and model checking to verify the specification

Formal model-based development for safety-critical embedded software

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Hyun; Choi, Jin Young [Korea University, seoul (Korea, Republic of)

2005-11-15

Safety-critical embedded software for nuclear I and C system is developed under the safety and reliability regulation. Programmable logic controller(PLC) is a computer system for instrumentation and control (I and C) system of nuclear power plants. PLC consists of various I and C logics in software, including real-time operating system (RTOS). Hence, errors related with RTOS should be detected and eliminated in development processes. Practically, the verification and validation for errors in RTOS is performed in test procedure, in which a lot of tasks for testing are embedded in RTOS and are running under a test environments. But the test process can not be enough to guarantee the safety and reliability of RTOS. Therefore, in this paper, we introduce to applying formal methods with the development of software for the PLC. We particularity apply formal methods to a development of RTOS for PLC, which is a safety critical level. In this development, we use the state charts of I-Logix to specify and verification and model checking to verify the specification.

Evolution of a holistic systems approach to planning and managing road safety: the Victorian case study, 1970-2015.

Science.gov (United States)

Muir, Carlyn; Johnston, Ian R; Howard, Eric

2018-06-01

The Victorian Safe System approach to road safety slowly evolved from a combination of the Swedish Vision Zero philosophy and the Sustainable Safety model developed by the Dutch. The Safe System approach reframes the way in which road safety is viewed and managed. This paper presents a case study of the institutional change required to underpin the transformation to a holistic approach to planning and managing road safety in Victoria, Australia. The adoption and implementation of a Safe System approach require strong institutional leadership and close cooperation among all the key agencies involved, and Victoria was fortunate in that it had a long history of strong interagency mechanisms in place. However, the challenges in the implementation of the Safe System strategy in Victoria are generally neither technical nor scientific; they are predominantly social and political. While many governments purport to develop strategies based on Safe System thinking, on-the-ground action still very much depends on what politicians perceive to be publicly acceptable, and Victoria is no exception. This is a case study of the complexity of institutional change and is presented in the hope that the lessons may prove useful for others seeking to adopt more holistic planning and management of road safety. There is still much work to be done in Victoria, but the institutional cultural shift has taken root. Ongoing efforts must be continued to achieve alert and compliant road users; however, major underpinning benefits will be achieved through focusing on road network safety improvements (achieving forgiving infrastructure, such as wire rope barriers) in conjunction with reviews of posted speed limits (to be set in response to the level of protection offered by the road infrastructure) and by the progressive introduction into the fleet of modern vehicle safety features. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights

Development of Network Protocol for the Integrated Safety System

Energy Technology Data Exchange (ETDEWEB)

Park, S. W.; Baek, J. I.; Lee, S. H.; Park, C. S.; Park, K. H.; Shin, J. M. [Hannam Univ., Daejeon (Korea, Republic of)

2007-06-15

Communication devices in the safety system of nuclear power plants are distinguished from those developed for commercial purposes in terms of a strict requirement of safety. The concept of safety covers the determinability, the reliability, and the separation/isolation to prevent the undesirable interactions among devices. The safety also requires that these properties be never proof less. Most of the current commercialized communication products rarely have the safety properties. Moreover, they can be neither verified nor validated to satisfy the safety property of implementation process. This research proposes the novel architecture and protocol of a data communication network for the safety system in nuclear power plants.

Development of Network Protocol for the Integrated Safety System

International Nuclear Information System (INIS)

Park, S. W.; Baek, J. I.; Lee, S. H.; Park, C. S.; Park, K. H.; Shin, J. M.

2007-06-01

Communication devices in the safety system of nuclear power plants are distinguished from those developed for commercial purposes in terms of a strict requirement of safety. The concept of safety covers the determinability, the reliability, and the separation/isolation to prevent the undesirable interactions among devices. The safety also requires that these properties be never proof less. Most of the current commercialized communication products rarely have the safety properties. Moreover, they can be neither verified nor validated to satisfy the safety property of implementation process. This research proposes the novel architecture and protocol of a data communication network for the safety system in nuclear power plants

Health and safety in clinical laboratories in developing countries: safety considerations.

Science.gov (United States)

Ejilemele, A A; Ojule, A C

2004-01-01

Clinical laboratories are potentially hazardous work areas. Health and safety in clinical laboratories is becoming an increasingly important subject as a result of the emergence of highly infectious diseases such as hepatitis and HIV. This is even more so in developing countries where health and safety have traditionally been regarded as low priority issues, considering the more important health problems confronting the health authorities in these countries. We conducted a literature search using the medical subheadings titles on the INTERNET over a period of twenty years and summarized our findings. This article identifies hazards in the laboratories and highlights measures to make the laboratory a safer work place. It also emphasizes the mandatory obligations of employers and employees towards the attainment of acceptable safety standards in clinical laboratories in Third World countries in the face of the current HIV/AIDS epidemic in many of these developing countries especially in the sub-Saharan Africa while accommodating the increasing work load in these laboratories. Both the employer and the employee have major roles to play in the maintenance of a safe working environment. This can be achieved if measures discussed are incorporated into everyday laboratory practice.

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

The design of layout plans requires adequate assessment tools for the quantification of safety performance. The general focus of the present work is to introduce an inherent safety perspective at different points of the layout design process. In particular, index approaches for safety assessment and decision-making in the early stages of layout design are developed and discussed in this two-part contribution. Part 1 (accompanying paper) of the current work presents an integrated index approach for safety assessment of early plant layout. In the present paper (Part 2), an index for evaluation of the hazard related to the potential of domino effects is developed. The index considers the actual consequences of possible escalation scenarios and scores or ranks the subsequent accident propagation potential. The effects of inherent and passive protection measures are also assessed. The result is a rapid quantification of domino hazard potential that can provide substantial support for choices in the early stages of layout design. Additionally, a case study concerning selection among various layout options is presented and analyzed. The case study demonstrates the use and applicability of the indices developed in both parts of the current work and highlights the value of introducing inherent safety features early in layout design

Implications of case managers' perceptions and attitude on safety of home-delivered care.

Science.gov (United States)

Jones, Sarahjane

2015-12-01

Perceptions on safety in community care have been relatively unexplored. A project that sought to understand the multiple perspectives on safety in the NHS case-management programme was carried out in relation to the structure, process, and outcome of care. This article presents a component of the nursing perspective that highlights an important element in the structure of nursing care that could potentially impede the nurses' ability to be fully effective and safe. A single case study of the case-management programme was undertaken. Three primary care organisations from three strategic health authorities participated, and three focus groups were conducted (one within each organisation). In total, 17 case management nurses participated. Data were audiotaped and transcribed verbatim and subjected to framework analysis. Nursing staff attitudes were identified as a structure of care that influence safety outcomes, particularly their perceptions of the care setting and the implications it has on their role and patient behaviour. Greater understanding of the expected role of the community nurse is necessary, and relevant training is required for nurses to be successful in empowering patients to perform more safely. In addition, efforts need to be made to improve patients' trust in the health-care system to prevent harm and promote more effective utilisation of resources.

Development and application of digital safety system in NPPs

International Nuclear Information System (INIS)

Kwon, Keechoon; Kim, Changhwoi; Lee, Dongyoung

2012-01-01

This paper describes the development of digital safety system in NPPs based on safety- grade programmable logic controller (PLC) platform and its application to real NPP construction. The digital safety system consists of a reactor protection system and an engineered safety feature-component control system. The safety-grade PLC platform was developed so that it meets the requirements of the regulation. The PLC consists of various modules such as a power module, a processor module, communication modules, digital input/output modules, analog input/output modules, a LOCA bus extension module, and a high-speed pulse counter module. The reactor protection system is designed with a redundant 4-channel architecture, and every channel is implemented with the same architecture. A single channel consists of a redundant bi-stable processor, a redundant coincidence processor, an automatic test and interface processor, and a cabinet operator module. The engineered safety feature-component control system is designed with four redundant divisions, and implemented with the PLC platform. The principal components of an individual division are fault tolerant group controllers, loop controllers, a test and interface processor, a cabinet operator module and a control channel gateway. The topical report is submitted to the regulatory body, and got safety evaluation report from the regulatory body. Also, the developed system is tested in the integrated performance validation facility. It is decided that the digital safety system applied to Shin-Uljin unit 1 and 2 after a topical report approval and validation test. Design changes occur in the digital safety system that is applied to an actual nuclear power plant construction, and the PLC has also been upgraded

Development and application of digital safety system in NPPs

Energy Technology Data Exchange (ETDEWEB)

Kwon, Keechoon; Kim, Changhwoi; Lee, Dongyoung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-03-15

This paper describes the development of digital safety system in NPPs based on safety- grade programmable logic controller (PLC) platform and its application to real NPP construction. The digital safety system consists of a reactor protection system and an engineered safety feature-component control system. The safety-grade PLC platform was developed so that it meets the requirements of the regulation. The PLC consists of various modules such as a power module, a processor module, communication modules, digital input/output modules, analog input/output modules, a LOCA bus extension module, and a high-speed pulse counter module. The reactor protection system is designed with a redundant 4-channel architecture, and every channel is implemented with the same architecture. A single channel consists of a redundant bi-stable processor, a redundant coincidence processor, an automatic test and interface processor, and a cabinet operator module. The engineered safety feature-component control system is designed with four redundant divisions, and implemented with the PLC platform. The principal components of an individual division are fault tolerant group controllers, loop controllers, a test and interface processor, a cabinet operator module and a control channel gateway. The topical report is submitted to the regulatory body, and got safety evaluation report from the regulatory body. Also, the developed system is tested in the integrated performance validation facility. It is decided that the digital safety system applied to Shin-Uljin unit 1 and 2 after a topical report approval and validation test. Design changes occur in the digital safety system that is applied to an actual nuclear power plant construction, and the PLC has also been upgraded.

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.

IT-CARES: an interactive tool for case-crossover analyses of electronic medical records for patient safety.

Science.gov (United States)

Caron, Alexandre; Chazard, Emmanuel; Muller, Joris; Perichon, Renaud; Ferret, Laurie; Koutkias, Vassilis; Beuscart, Régis; Beuscart, Jean-Baptiste; Ficheur, Grégoire

2017-03-01

The significant risk of adverse events following medical procedures supports a clinical epidemiological approach based on the analyses of collections of electronic medical records. Data analytical tools might help clinical epidemiologists develop more appropriate case-crossover designs for monitoring patient safety. To develop and assess the methodological quality of an interactive tool for use by clinical epidemiologists to systematically design case-crossover analyses of large electronic medical records databases. We developed IT-CARES, an analytical tool implementing case-crossover design, to explore the association between exposures and outcomes. The exposures and outcomes are defined by clinical epidemiologists via lists of codes entered via a user interface screen. We tested IT-CARES on data from the French national inpatient stay database, which documents diagnoses and medical procedures for 170 million inpatient stays between 2007 and 2013. We compared the results of our analysis with reference data from the literature on thromboembolic risk after delivery and bleeding risk after total hip replacement. IT-CARES provides a user interface with 3 columns: (i) the outcome criteria in the left-hand column, (ii) the exposure criteria in the right-hand column, and (iii) the estimated risk (odds ratios, presented in both graphical and tabular formats) in the middle column. The estimated odds ratios were consistent with the reference literature data. IT-CARES may enhance patient safety by facilitating clinical epidemiological studies of adverse events following medical procedures. The tool's usability must be evaluated and improved in further research. © The Author 2016. Published by Oxford University Press on behalf of the American Medical Informatics Association.

Challenges on innovations of newly-developed safety analysis codes

International Nuclear Information System (INIS)

Yang, Yanhua; Zhang, Hao

2016-01-01

With the development of safety analysis method, the safety analysis codes meet more challenges. Three challenges are presented in this paper, which are mathematic model, code design and user interface. Combined with the self-reliance safety analysis code named COSINE, the ways of meeting these requirements are suggested, that is to develop multi-phases, multi-fields and multi-dimension models, to adopt object-oriented code design ideal and to improve the way of modeling, calculation control and data post-processing in the user interface.

Challenges on innovations of newly-developed safety analysis codes

Energy Technology Data Exchange (ETDEWEB)

Yang, Yanhua [Shanghai Jiao Tong Univ. (China). School of Nuclear Science and Engineering; Zhang, Hao [State Nuclear Power Software Development Center, Beijing (China). Beijing Future Science and Technology City

2016-05-15

With the development of safety analysis method, the safety analysis codes meet more challenges. Three challenges are presented in this paper, which are mathematic model, code design and user interface. Combined with the self-reliance safety analysis code named COSINE, the ways of meeting these requirements are suggested, that is to develop multi-phases, multi-fields and multi-dimension models, to adopt object-oriented code design ideal and to improve the way of modeling, calculation control and data post-processing in the user interface.

Development of photovoltaic array and module safety requirements

Science.gov (United States)

1982-01-01

Safety requirements for photovoltaic module and panel designs and configurations likely to be used in residential, intermediate, and large-scale applications were identified and developed. The National Electrical Code and Building Codes were reviewed with respect to present provisions which may be considered to affect the design of photovoltaic modules. Limited testing, primarily in the roof fire resistance field was conducted. Additional studies and further investigations led to the development of a proposed standard for safety for flat-plate photovoltaic modules and panels. Additional work covered the initial investigation of conceptual approaches and temporary deployment, for concept verification purposes, of a differential dc ground-fault detection circuit suitable as a part of a photovoltaic array safety system.

The Health and Safety Executive's regulatory framework for control of nuclear criticality safety

International Nuclear Information System (INIS)

Smith, K.; Simister, D.N.

1991-01-01

In the United Kingdom the Health and Safety at Work Act, 1974 is the main legal instrument under which risks to people from work activities are controlled. Certain sections of the Nuclear Installations Act, 1965 which deal with the licensing of nuclear sites and the regulatory control of risks arising from them, including the risk from accidental criticality, are relevant statutory provisions of the Health and Safety at Work Act. The responsibility for safety rests with the operator who has to make and implement arrangements to prevent accidental criticality. The adequacy of these arrangements must be demonstrated in a safety case to the regulatory authorities. Operators are encouraged to treat each plant on its own merits and develop the safety case accordingly. The Nuclear Installations Inspectorate (NII), for its part, assesses the adequacy of the operator's safety case against the industry's own standards and criteria, but more particularly against the NII's safety assessment principles and guides, and international standards. Risks should be made as low as reasonably practicable. Generally, the NII seeks improvements in safety using an enforcement policy which operates at a number of levels, ranging from persuasion through discussion to the ultimate deterrent of withdrawal of a site licence. This paper describes the role of the NII, which includes a specialist criticality expertise, within the Health and Safety Executive, in regulating the nuclear sites from the criticality safety viewpoint. (Author)

Development of the safety PLC for plant protection system

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Hwoi; Lee, Dong Young [Korea Atomic Energy Research Institute, Taejeon (Korea, Republic of)

2005-11-15

The safety PLC (POSAFE-Q) is developing in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as RTOS and firmware are developed according to safety critical software life cycle. Especially, the formal method is applied to design SRS (Software Requirement Spec.) and SDS (Software Design Specification.) for error-free. The developed software according to software life cycle is verified by independent software V and V team. The overall response time from an input to the outputs shall be 50ms or less. The prototype for the POSAFE-Q was developed and functional testing and equipment qualification tests have been underway.

Development of safety review advisory system for nuclear power plants

International Nuclear Information System (INIS)

Kim, M. W.; Lee, H. C.; Park, S. O.; Park, W. J.; Lee, J. I.; Hur, K. Y.; Choi, S. S.; Lee, S. J.; Kang, C. M.

2001-01-01

For the development of an expert system supporting the safety review of nuclear power plants, the application program was implemented after gathering necessary theoretical background and practical requirements. The general and the detail functional specifications were established, and they were investigated by the safety review experts at KINS. Safety Review Advisory System (SRAS), the windows application on client-server environment was developed according to the above specifications. Reviewers can do their safety reviewing regardless of speciality or reviewing experiences because SRAS is operated by the safety review plans which are converted to standardized format. When the safety reviewing is carried out by using SRAS, the results of safety reviewing are accumulated in the database and may be utilized later usefully, and we can grasp safety reviewing progress. Users of SRAS are categorized into three groups, administrator, project manager, and reviewer. Each user group has appropriate access capability. The function and some screen shots of SRAS are described in this paper

Using systems thinking in patient safety: a case study on medicines management.

Science.gov (United States)

Brimble, Mandy; Jones, Aled

2017-06-29

Systems thinking is used as a way of understanding behaviours and actions in complex healthcare organisations. An important premise of the concept is that every action in a system causes a reaction elsewhere in that system. These reactions can lead to unintended consequences, sometimes long after the original action, and so are not always attributed to them. This article applies systems thinking to a medicines management case study, to highlight how quality-improvement practitioners can use the approach to underpin planning and implementation of patient-safety initiatives. The case study is specific to transcribing in children's hospices, but the strategies can be applied to other areas. The article explains that, while root cause analysis tools are useful for identifying the cause of, and possible solutions to, problems, they need to be considered carefully in terms of unintended consequences, and how the system into which the solution is implemented can be affected by the change. Analysis of problems using a systems-thinking approach can help practitioners to develop robust and well informed business cases to present to decision makers.

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

Science.gov (United States)

Chuang-Stein, Christy; Xia, H Amy

2013-01-01

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

Motorcycle safety among motorcycle taxi drivers and nonoccupational motorcyclists in developing countries: A case study of Maoming, South China.

Science.gov (United States)

Wu, Connor Y H; Loo, Becky P Y

2016-01-01

An increasing number of motorcycle taxis have been involved in traffic crashes in many developing countries. This study examines the characteristics of both motorcycle taxi drivers and nonoccupational motorcyclists, investigates the risks they pose to road safety, and provides recommendations to minimize their risks. Based on the data collected from a questionnaire survey of 867 motorcycle taxi drivers and 2,029 nonoccupational motorcyclists in Maoming, South China, comparisons were made to analyze differences of personal attributes, attitudes toward road safety, and self-reported behavior of the 2 groups. Results of the chi-square tests show that not only motorcycle taxi drivers but also nonoccupational motorcyclists in Maoming held poor attitudes toward road safety and both groups reported unsafe driving behavior. There is much room for improving local road safety education among all motorcyclists in Maoming. Yet, motorcycle taxi drivers were more likely to pose road safety risks than nonoccupational motorcyclists under some circumstances, such as speeding late at night or early in the morning, not requiring passengers to wear helmets, and running a red light. The results of the binary logistic regression model show that possessing a vehicle license for a motorcycle or not was the common significant predictor for unsafe driving behavior of motorcycle taxi drivers and nonoccupational motorcyclists. Therefore, enforcement against all motorcyclists not showing vehicle licenses for their motorcycles should be stepped up. Motorcycle safety is largely poor in Maoming. Therefore, efforts to improve motorcycle safety should be strengthened by targeting not only motorcycle taxi drivers but also nonoccupational motorcyclists.

Collaboration and patient safety at an emergency department - a qualitative case study.

Science.gov (United States)

Pedersen, Anna Helene Meldgaard; Rasmussen, Kurt; Grytnes, Regine; Nielsen, Kent Jacob

2018-03-19

Purpose The purpose of this paper is to examine how conflicts about collaboration between staff at different departments arose during the establishment of a new emergency department and how these conflicts affected the daily work and ultimately patient safety at the emergency department. Design/methodology/approach This qualitative single case study draws on qualitative semi-structured interviews and participant observation. The theoretical concepts "availability" and "receptiveness" as antecedents for collaboration will be applied in the analysis. Findings Close collaboration between departments was an essential precondition for the functioning of the new emergency department. The study shows how a lack of antecedents for collaboration affected the working relation and communication between employees and departments, which spurred negative feelings and reproduced conflicts. This situation was seen as a potential threat for the safety of the emergency patients. Research limitations/implications This study presents a single case study, at a specific point in time, and should be used as an illustrative example of how contextual and situational factors affect the working environment and through that patient safety. Originality/value Few studies provide an in-depth investigation of what actually takes place when collaboration between professional groups goes wrong and escalates, and how problems in collaboration may affect patient safety.

Safety analysis of DUPIC fuel development facility

International Nuclear Information System (INIS)

Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Baek, S. Y.; Ahn, J. Y.

2001-01-01

Various experimental facilities are necessary in order to perform experimental verification for development of DUPIC fuel fabrication technology. In special, since highly radioactive material such as spent PWR fuel is used for this experiment, DUPIC fuel fabrication has to be performed in hot cell by remote handling. Therefore, it should be provided with proper engineering requirement and safety. M6 hot cell of IMEF which is to used for DUPIC fuel fabrication experiment was constructed as an α-γ hot cell for material examination of small amount of high-burnup fuel. The characteristics and amount of spent fuel for DUPIC fuel fabrication experiment will be different from the original design criteria. Therefore, the increased amount of spent fuel and different characteristics of experiment result in not only change of shielding and enviornmental evaluation results but new requirement of nuclear criticality evaluation. Therefore, this study includes evaluation of shielding, environmental effect and nuclear criticality in case that IMEF M6 hot cell is used for DUPIC fuel fabrication

Diversity for security: case assessment for FPGA-based safety-critical systems

Directory of Open Access Journals (Sweden)

Kharchenko Vyacheslav

2016-01-01

Full Text Available Industrial safety critical instrumentation and control systems (I&Cs are facing more with information (in general and cyber, in particular security threats and attacks. The application of programmable logic, first of all, field programmable gate arrays (FPGA in critical systems causes specific safety deficits. Security assessment techniques for such systems are based on heuristic knowledges and the expert judgment. Main challenge is how to take into account features of FPGA technology for safety critical I&Cs including systems in which are applied diversity approach to minimize risks of common cause failure. Such systems are called multi-version (MV systems. The goal of the paper is in description of the technique and tool for case-based security assessment of MV FPGA-based I&Cs.

Safety evaluation in the development of medical devices and combination products

CERN Document Server

Gad, Shayne C

2008-01-01

Capturing the growth of the global medical device market in recent years, this practical new guide is essential for all who are responsible for ensuring safety in the use and manufacture of medical devices. It has been extensively updated to reflect significant advances, incorporating combination products and helpful case examples of current real-life problems in the field.The Third Edition explores these key current trends:global device marketscontinually advancing technologythe increasing harmonization of device safety regulation worldwideEach aspect of safety evaluation is considered in ter

Development of Safety Assessment Information System (SAIS)

International Nuclear Information System (INIS)

Park, Byung Shik; Lee, Kyung Jin; Lee, Byung Chul; Song, Tae Young; Lee, Chang Ho

2007-01-01

Many reports and documents about nuclear power plant safety analysis like a Periodic Safe Review (PSR), Periodic Safety Analysis (PSA) and Severe Accident Management Guideline (SAMG) come to be drawn up from KHNP. Since these are not arranged easy to look up, the systematic arrangement of data was necessary. The solution against hereupon is to store database, and it was developed with the name, SAIS, by FNC Tech. Co. together with NETEC KHNP. In this web program it is easy to manage (registration, search and statistics) data. And the authorized user can approach this system. This was developed, and was verified under the development environment of; - Web Server : Apache 2.2.5 - Program Language : PHP 5.2 - DBMS : Oracle 10g

Development of Safety Assessment Information System (SAIS)

Energy Technology Data Exchange (ETDEWEB)

Park, Byung Shik; Lee, Kyung Jin; Lee, Byung Chul [FNC Tech. Co. Ltd. SNU, Seoul (Korea, Republic of); Song, Tae Young; Lee, Chang Ho [KHNP, Daejeon (Korea, Republic of)

2007-10-15

Many reports and documents about nuclear power plant safety analysis like a Periodic Safe Review (PSR), Periodic Safety Analysis (PSA) and Severe Accident Management Guideline (SAMG) come to be drawn up from KHNP. Since these are not arranged easy to look up, the systematic arrangement of data was necessary. The solution against hereupon is to store database, and it was developed with the name, SAIS, by FNC Tech. Co. together with NETEC KHNP. In this web program it is easy to manage (registration, search and statistics) data. And the authorized user can approach this system. This was developed, and was verified under the development environment of; - Web Server : Apache 2.2.5 - Program Language : PHP 5.2 - DBMS : Oracle 10g.

Development of a new methodology for quantifying nuclear safety culture

International Nuclear Information System (INIS)

Han, Kiyoon; Jae, Moosung

2017-01-01

The present study developed a Safety Culture Impact Assessment Model (SCIAM) which consists of a safety culture assessment methodology and a safety culture impact quantification methodology. The SCIAM uses a safety culture impact index (SCII) to monitor the status of safety culture of NPPs periodically and it uses relative core damage frequency (RCDF) to present the impact of safety culture on the safety of NPPs. As a result of applying the SCIAM to the reference plant (Kori 3), the standard for the healthy safety culture of the reference plant is suggested. SCIAM might contribute to improve the safety of NPPs (Nuclear Power Plants) by monitoring the status of safety culture periodically and presenting the standard of healthy safety culture.

Development of a new methodology for quantifying nuclear safety culture

Energy Technology Data Exchange (ETDEWEB)

Han, Kiyoon; Jae, Moosung [Hanyang Univ., Seoul (Korea, Republic of). Dept. of Nuclear Engineering

2017-01-15

The present study developed a Safety Culture Impact Assessment Model (SCIAM) which consists of a safety culture assessment methodology and a safety culture impact quantification methodology. The SCIAM uses a safety culture impact index (SCII) to monitor the status of safety culture of NPPs periodically and it uses relative core damage frequency (RCDF) to present the impact of safety culture on the safety of NPPs. As a result of applying the SCIAM to the reference plant (Kori 3), the standard for the healthy safety culture of the reference plant is suggested. SCIAM might contribute to improve the safety of NPPs (Nuclear Power Plants) by monitoring the status of safety culture periodically and presenting the standard of healthy safety culture.

Regenerative braking strategies, vehicle safety and stability control systems: critical use-case proposals

Science.gov (United States)

Oleksowicz, Selim A.; Burnham, Keith J.; Southgate, Adam; McCoy, Chris; Waite, Gary; Hardwick, Graham; Harrington, Cian; McMurran, Ross

2013-05-01

The sustainable development of vehicle propulsion systems that have mainly focused on reduction of fuel consumption (i.e. CO2 emission) has led, not only to the development of systems connected with combustion processes but also to legislation and testing procedures. In recent years, the low carbon policy has made hybrid vehicles and fully electric vehicles (H/EVs) popular. The main virtue of these propulsion systems is their ability to restore some of the expended energy from kinetic movement, e.g. the braking process. Consequently new research and testing methods for H/EVs are currently being developed. This especially concerns the critical 'use-cases' for functionality tests within dynamic events for both virtual simulations, as well as real-time road tests. The use-case for conventional vehicles for numerical simulations and road tests are well established. However, the wide variety of tests and their great number (close to a thousand) creates a need for selection, in the first place, and the creation of critical use-cases suitable for testing H/EVs in both virtual and real-world environments. It is known that a marginal improvement in the regenerative braking ratio can significantly improve the vehicle range and, therefore, the economic cost of its operation. In modern vehicles, vehicle dynamics control systems play the principal role in safety, comfort and economic operation. Unfortunately, however, the existing standard road test scenarios are insufficient for H/EVs. Sector knowledge suggests that there are currently no agreed tests scenarios to fully investigate the effects of brake blending between conventional and regenerative braking as well as the regenerative braking interaction with active driving safety systems (ADSS). The paper presents seven manoeuvres, which are considered to be suitable and highly informative for the development and examination of H/EVs with regenerative braking capability. The critical manoeuvres presented are considered to be

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Models and data for the repository system 2012. Parts 1 and 2

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-09-15

TURVA-2012 is Posiva Oy's safety case in support of the Preliminary Safety Analysis Report (PSAR 2012) and application for a construction licence for a KBS-3V spent nuclear fuel repository. The present report is a key element of the TURVA-2012 report portfolio and has the objective of documenting the models, data, assumptions and treatment of uncertainties in the context of the safety case. This report is the main link between the safety case and the engineered barrier design and their development as well as between the safety case and the Olkiluoto site investigations. This report focuses on the models and data used in Performance Assessment and in Assessment of Radionuclide Release Scenarios for the Repository System, which are key reports of TURVA-2012. Models and data for the surface environment are discussed in dedicated biosphere modelling and data reports. This report describes the methodology for the identification of key models and data as well as the modelling chain with input and output data connections. Models and data are presented for all components of the repository system: spent nuclear fuel, canister, buffer, backfill, closure, underground openings and geosphere. The report is structured so that the modelling of external processes is discussed first, followed by the models and data used in the performance assessment to address the evolution of the repository system and finally the models and data used in the radionuclide release and transport assessment. Confidence in the models and data and the treatment of uncertainties are also discussed. The present report traces the path from data production to implementation in the modelling chain. During the compilation of the report, some discrepancies between the sources of data and data usage, as well as some inconsistencies in model assumptions, were identified. The consequences of the potentially most significant of these were checked through additional radionuclide release and transport

Safety case for the disposal of spent nuclear fuel at Olkiluoto. Models and data for the repository system 2012. Parts 1 and 2

International Nuclear Information System (INIS)

2013-09-01

TURVA-2012 is Posiva Oy's safety case in support of the Preliminary Safety Analysis Report (PSAR 2012) and application for a construction licence for a KBS-3V spent nuclear fuel repository. The present report is a key element of the TURVA-2012 report portfolio and has the objective of documenting the models, data, assumptions and treatment of uncertainties in the context of the safety case. This report is the main link between the safety case and the engineered barrier design and their development as well as between the safety case and the Olkiluoto site investigations. This report focuses on the models and data used in Performance Assessment and in Assessment of Radionuclide Release Scenarios for the Repository System, which are key reports of TURVA-2012. Models and data for the surface environment are discussed in dedicated biosphere modelling and data reports. This report describes the methodology for the identification of key models and data as well as the modelling chain with input and output data connections. Models and data are presented for all components of the repository system: spent nuclear fuel, canister, buffer, backfill, closure, underground openings and geosphere. The report is structured so that the modelling of external processes is discussed first, followed by the models and data used in the performance assessment to address the evolution of the repository system and finally the models and data used in the radionuclide release and transport assessment. Confidence in the models and data and the treatment of uncertainties are also discussed. The present report traces the path from data production to implementation in the modelling chain. During the compilation of the report, some discrepancies between the sources of data and data usage, as well as some inconsistencies in model assumptions, were identified. The consequences of the potentially most significant of these were checked through additional radionuclide release and transport calculations

Evaluation of methods and tools to develop safety concepts and to demonstrate safety for an HLW repository in salt. Final report

Energy Technology Data Exchange (ETDEWEB)

Bollingerfehr, W.; Buhmann, D.; Doerr, S.; and others

2017-03-15

Salt formations have been the preferred option as host rocks for the disposal of high level radioactive waste in Germany for more than 40 years. During this period comprehensive geological investigations have been carried out together with a broad spectrum of concept and safety related R and D work. The behaviour of an HLW repository in salt formations, particularly in salt domes, has been analysed in terms of assessment of the total system performance. This was first carried out for concepts of generic waste repositories in salt and, since 1998, for a repository concept with specific boundary conditions, taking the geology of the Gorleben salt dome as an example. Suitable repository concepts and designs were developed, the technical feasibility has been proven and operational and long-term safety evaluated. Numerical modelling is an important input into the development of a comprehensive safety case for a waste repository. Significant progress in the development of numerical tools and their application for long-term safe ty assessment has been made in the last two decades. An integrated approach has been used in which the repository concept and relevant scientific and engineering data are combined with the results from iterative safety assessments to increase the clarity and the traceability of the evaluation. A safety concept that takes full credit of the favourable properties of salt formations was developed in the course of the R and D project ISIBEL, which started in 2005. This concept is based on the safe containment of radioactive waste in a specific part of the host rock formation, termed the containment providing rock zone, which comprises the geological barrier, the geotechnical barriers and the compacted backfill. The future evolution of the repository system will be analysed using a catalogue of Features, Events and Processes (FEP), scenario development and numerical analysis, all of which are adapted to suit the safety concept. Key elements of the

Evaluation of methods and tools to develop safety concepts and to demonstrate safety for an HLW repository in salt. Final report

International Nuclear Information System (INIS)

Bollingerfehr, W.; Buhmann, D.; Doerr, S.

2017-03-01

Salt formations have been the preferred option as host rocks for the disposal of high level radioactive waste in Germany for more than 40 years. During this period comprehensive geological investigations have been carried out together with a broad spectrum of concept and safety related R and D work. The behaviour of an HLW repository in salt formations, particularly in salt domes, has been analysed in terms of assessment of the total system performance. This was first carried out for concepts of generic waste repositories in salt and, since 1998, for a repository concept with specific boundary conditions, taking the geology of the Gorleben salt dome as an example. Suitable repository concepts and designs were developed, the technical feasibility has been proven and operational and long-term safety evaluated. Numerical modelling is an important input into the development of a comprehensive safety case for a waste repository. Significant progress in the development of numerical tools and their application for long-term safe ty assessment has been made in the last two decades. An integrated approach has been used in which the repository concept and relevant scientific and engineering data are combined with the results from iterative safety assessments to increase the clarity and the traceability of the evaluation. A safety concept that takes full credit of the favourable properties of salt formations was developed in the course of the R and D project ISIBEL, which started in 2005. This concept is based on the safe containment of radioactive waste in a specific part of the host rock formation, termed the containment providing rock zone, which comprises the geological barrier, the geotechnical barriers and the compacted backfill. The future evolution of the repository system will be analysed using a catalogue of Features, Events and Processes (FEP), scenario development and numerical analysis, all of which are adapted to suit the safety concept. Key elements of the

Safety report content and development for test loop facility on MARIA reactor

International Nuclear Information System (INIS)

Konechko, A.; Shumskij, A.M.; Mikul'ahin, V.E.

1982-01-01

A 600 kW test loop facility for investigatin.o safety problems is realized on MARIA reactor in Poland together with USSR organizations. Safety reports have been developed in two steps at the designstage. The 1st report being essentially a preliminary safety analysis was developed within the scope of the feasibility study. At the engineering design stage the preliminary test loop facility safety report had been prepared considering measures excluding the possibility of the MARIA reactor damage. The test loop facility safety report is fulfilled for normal, transient and emergency operation regimes. Separate safety basing for each group of experiments will be prepared. The report presents the test loop facility safety criteria coordinated by the nuclear safety comission. They contains the preliminary reports on the test loop facility safety. At the final stage of construction and at thecommitioning stage the start-up safety report will be developed which after required correction and adding up the putting into operation data will turn into operation safety report [ru

Development of Safety Analysis Technology for Integral Reactor

Energy Technology Data Exchange (ETDEWEB)

Sim, S. K. [Korea Atomic Energy Research Institute, Taejeon (Korea); Seul, K. W.; Kim, W. S.; Kim, W. K.; Yun, Y. G.; Ahn, H. J.; Lee, J. S.; Sin, A. D. [Korea Institute of Nuclear Safety, Taejeon (Korea)

2000-03-01

The Nuclear Desalination Plant(NDP) is being developed to produce electricity and fresh water, and is expected to locate near population zone. In the aspect of safety, it is required to protect the public and environment from the possible releases of fission products and to prevent the fresh water from the contamination of radioactivity. Thus, in a present study, the safety characteristics of the integral reactor adopting passive and inherent safety features significantly different from existing nuclear power plants were investigated based on the design of foreign and domestic integral reactors. Also, safety requirements applicable to the NDP were analyzed based on the regulatory requirements for current and advanced reactor designs, and use requirements for small-medium size reactors. Based on these analyses, some safety concerns to be considered in the design stage have been identified. They includes the use of proven technology for new safety systems, the systematic classification and selection of design basis accidents, and the safety assurance of desalination-related systems. These efforts to identify and resolve the safety concerns in the design stage will provide the early confidence of SMART safety to designers, and the technical basis to evaluate the safety to reviewers in the future. 8 refs., 20 figs., 4 tabs. (Author)

Development of a safety management protocol.

Science.gov (United States)

2008-09-01

The UC Berkeley Traffic Safety Center (TSC) has produced this report under a contract from the California Department of Transportation : (Caltrans). The aim is to address workplace injuries and accidents among Caltrans employees and develop recommend...

Technical Issues and Proposes on the Legislation of Probabilistic Safety Assessment in Periodic Safety Review

International Nuclear Information System (INIS)

Hwang, Seok-Won; Jeon, Ho-Jun; Na, Jang-Hwan

2015-01-01

Korean Nuclear Power Plants have performed a comprehensive safety assessment reflecting design and procedure changes and using the latest technology every 10 years. In Korea, safety factors of PSR are revised to 14 by revision of IAEA Safety Guidelines in 2003. In the revised safety guidelines, safety analysis field was subdivided into deterministic safety analysis, PSA (Probabilistic safety analysis), and hazard analysis. The purpose to examine PSA as a safety factor on PSR is to make sure that PSA results and assumptions reflect the latest state of NPPs, validate the level of computer codes and analytical models, and evaluate the adequacy of PSA instructions. In addition, its purpose is to derive the plant design change, operating experience of other plants and safety enhancement items as well. In Korea, PSA is introduced as a new factor. Thus, the overall guideline development and long-term implementation strategy are needed. Today in Korea, full-power PSA model revision and low-power and shutdown (LPSD) PSA model development is being performed as a part of the post Fukushima action items for operating plants. The scope of the full-power PSA is internal/external level 1, 2 PSA. But in case of fire PSA, the scope is level 1 PSA using new method, NUREG/CR-6850. In case of LPSD PSA, level 1 PSA for all operating plants, and level 2 PSA for 2 demonstration plants are under development. The result of the LPSD PSA will be used as major input data for plant specific SAMG (Severe Accident Management Guideline). The scope of PSA currently being developed in Korea cannot fulfill 'All Mode, All Scope' requirements recommended in the IAEA Safety Guidelines. Besides the legislation of PSA, step-by-step development strategy for non-performed scopes such as level 3 PSA and new fire PSA is one of the urgent issues in Korea. This paper suggests technical issues and development strategies for each PSA technical elements.

Development of Strategic Technology Road map for Establishing Safety Infrastructure of Fusion Energy

International Nuclear Information System (INIS)

Han, B. S.; Cho, S. H.; Kam, S. C.; Kim, K. T.

2009-01-01

The Korean Government established an 'Act for the Promotion of Fusion Energy Development (APFED)' and formulated a 'Strategy Promotion Plan for Fusion Energy Development.' KINS has carried out a safety review of KSTAR (Korea Superconducting Tokamak Advanced Research), for which an application for use was received in 2002 and the license was issued in August 2007. With respect to the APFED, 'Atomic Energy Acts (AEAs)' shall apply in the fusion safety regulation. However the AEAs are not applicable because they aim for dealing with nuclear energy. In this regard, this study was planned to establish safety infrastructure for fusion energy and to develop technologies necessary for verifying the safety. The purpose of this study is to develop a 'Strategic Technology Roadmap (STR) for establishing safety infrastructure of the fusion energy', which displays the content and development schedule and strategy for developing the laws, safety goals and principles, and safety standards applicable for fusion safety regulation, and core technology required for safety regulation of fusion facilities

Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

Energy Technology Data Exchange (ETDEWEB)

Blakely, D [Alberta Environment, Edmonton, AB (Canada)

2009-07-01

Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

International Nuclear Information System (INIS)

Lee, Jang Soo; Kim, Jang Yeol; Eum, Heung Seop.

1997-07-01

Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs

KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Lee, Jang Soo; Kim, Jang Yeol; Eum, Heung Seop

1997-07-01

Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs.

Microbiological food safety: a dilemma of developing societies.

Science.gov (United States)

Akhtar, Saeed; Sarker, Mahfuzur R; Hossain, Ashfaque

2014-11-01

Current food safety issues are deleteriously reshaping the life style of the population in the developing world. Socioeconomic status of the population in poorer economies is one of the major determinants to delineate the availability of safe food to the vulnerable population. Assessment of the prevalence of foodborne illness in developing world is the most neglected area to control disease. Botulism, Shigellosis, Campylobacteriosis, Escherichia coli infection, Staphylococcus aureus infection, Salmonellosis, Listeriosis and Cholerae are extensively prevalent and pose a major threat to human health in underdeveloped communities. The existing food safety status of many African, South Asian, Central, and South American developing countries is distressing therefore; it seems much timely to highlight the areas for the improvement to ensure the supply of safe food to the population in these regions. Extensive literature search at PubMed, Science Direct and Medline was carried out during the current year to catch on relevant data from 1976 to date, using selective terms like food safety, South East Asia, Africa, Central and South America, and foodborne illness etc. Efforts were made to restrict the search to low income countries of these regions with reference to specific foodborne pathogens. This report briefly discusses the present food safety situation in these developing countries and associated consequences as prime issues, suggesting foodborne illness to be the most distressing threat for human health and economic growth.

Development of Safety Kit for Industrial Radiography Application

International Nuclear Information System (INIS)

Mohd Noorul Ikhsan Ahmad; Amry Amin Abas

2011-01-01

A safety kit for industrial radiography has been developed. The safety kit that consist of a set of technical rod and various size of base that can be used in radiograph of pipe with diameter between half and one and half inch with utilization of collimator. With the kit, radiographers will not having anymore problem to use collimator in their work. The paper discuss about the technical measures of the safety kit and the importance of introducing it to the industry. (author)

Preliminary Study on the Development of Quantitative Safety Culture Index

International Nuclear Information System (INIS)

Lee, Young Eal; Kim, Hun Sil; Ahn, Nam Sung

2005-01-01

Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Because it needs to be recognized as the most significant consciousness to achieve the nuclear safety performance, Korean government and nuclear power generation company have tried to develop the practical method to improve the safety culture from the long term point view. In this study, based on the site interviews to define the potential issues on organizational behavior for the safe operation and the survey on the level of safety culture of occupied workers are conducted. Survey results are quantified as a few indicators of nuclear safety by the statistical method and it can be simulated by the dynamic modeling as time goes on. Currently index and dynamic modeling are still being developed, however, results can be used to suggest the long term strategy which safety is clearly integrated into all activities in the nuclear organization

Formal methods and their applicability in the development of safety critical software systems

International Nuclear Information System (INIS)

Sievertsen, T.

1995-01-01

The OECD Halden Reactor Project has for a number of years been involved in the development and application of a formal software specification and development method based on algebraic specification and the HRP Prover. In parallel to this activity the Project has been evaluating and comparing different methods and approaches to formal software development by their application on realistic case examples. Recent work has demonstrated that algebraic specification and the HRP Prover can be used both in the specification and design of a software system, even down to a concrete model which can be translated into the chosen implementation language. The HRP Prover is currently being used in a case study on the applicability of the methodology in the development of a power range monitoring system for a nuclear power plant. The presentation reviews some of the experiences drawn from the Project's research activities in this area, with special emphasis on questions relating to applicability and limitations, and the role of formal methods in the development of safety-critical software systems. (14 refs., 1 fig.)

The structural integrity safety case for Sizewell B power station

International Nuclear Information System (INIS)

Gerachty, J.E.

1993-01-01

This paper presents the safety case approach adopted for the components of the Sizewell 'B' Power Station for which a high degree of structural integrity is required. Such components include the Reactor Pressure Vessel, Steam Generator and Pressuriser for which Incredibility of Failure is claimed. The two parts of the case involve achievement and demonstration of integrity. This is achieved by extensive measures involving design, manufacture, materials and inspection. The demonstration has required a fracture mechanics approach. The specific role of inspection validation and its relation to critical defect size is described. (author)

Nuclear safety culture in Finland and Sweden - Developments and challenges

International Nuclear Information System (INIS)

Reiman, T.; Pietikaeinen, E.; Kahlbom, U.; Rollenhagen, C.

2011-02-01

The project aimed at studying the concept of nuclear safety culture and the Nordic nuclear branch safety culture. The project also aimed at looking how the power companies and the regulators view the current responsibilities and role of subcontractors in the Nordic nuclear safety culture as well as to inspect the special demands for safety culture in subcontracting chains. Interview data was collected in Sweden (n = 14) and Finland (n = 16) during 2009. Interviewees represented the major actors in the nuclear field (regulators, power companies, expert organizations, waste management organizations). Results gave insight into the nature and evaluation of safety culture in the nuclear industry. Results illustrated that there is a wide variety of views on matters that are considered important for nuclear safety within the Nordic nuclear community. However, the interviewees considered quite uniformly such psychological states as motivation, mindfulness, sense of control, understanding of hazards and sense of responsibility as important for nuclear safety. Results also gave insight into the characteristics of Nordic nuclear culture. Various differences in safety cultures in Finland and Sweden were uncovered. In addition to the differences, historical reasons for the development of the nuclear safety cultures in Finland and Sweden were pointed out. Finally, results gave implications that on the one hand subcontractors can bring new ideas and improvements to the plants' practices, but on the other hand the assurance of necessary safety attitudes and competence of the subcontracting companies and their employees is considered as a challenge. The report concludes that a good safety culture requires a deep and wide understanding of nuclear safety including the various accident mechanisms of the power plants as well as a willingness to continuously develop one's competence and understanding. An effective and resilient nuclear safety culture has to foster a constant sense of

Patient safety challenges in a case study hospital--of relevance for transfusion processes?

Science.gov (United States)

Aase, Karina; Høyland, Sindre; Olsen, Espen; Wiig, Siri; Nilsen, Stein Tore

2008-10-01

The paper reports results from a research project with the objective of studying patient safety, and relates the finding to safety issues within transfusion medicine. The background is an increased focus on undesired events related to diagnosis, medication, and patient treatment in general in the healthcare sector. The study is designed as a case study within a regional Norwegian hospital conducting specialised health care services. The study includes multiple methods such as interviews, document analysis, analysis of error reports, and a questionnaire survey. Results show that the challenges for improved patient safety, based on employees' perceptions, are hospital management support, reporting of accidents/incidents, and collaboration across hospital units. Several of these generic safety challenges are also found to be of relevance for a hospital's transfusion service. Positive patient safety factors are identified as teamwork within hospital units, a non-punitive response to errors, and unit manager's actions promoting safety.

Determining supply chain safety stock level and location

Directory of Open Access Journals (Sweden)

Bahareh Amirjabbari

2014-01-01

Full Text Available Purpose: The lean methodology and its principles have widely been applied in supply chain management in recent decades. Manufacturers are one of the most important contributors in a supply chain and inventory plays a paramount role for them to become lean. Therefore, there should be appropriate management of inventory and all of its drivers in accordance with a lean strategy. Safety stock is one of the main drivers of inventory; it protects against increasing the stretch in the breaking points of the supply chain, which in turn can result in possible reduction of inventory. In this paper an optimization model and a simulation model are developed and applied in a real case to optimize the safety stock level with the objective of logistics cost minimization.Design/methodology/approach: In order to optimize the safety stock level while minimizing logistics costs, a nonlinear cost minimization safety stock model is developed in this paper and then it is applied in a real world manufacturing case company. A safety stock simulation model based on appropriate metrics in the case company’s supply chain performance is also provided.Findings: These models result in not only the optimum levels but also locations of safety stock within the supply chain.Originality/value: In this research, two models of cost minimization and simulation have been developed and also applied in a real case company to result in not only optimized levels but also optimized locations of safety stock across the whole supply chain. In addition, the appropriate supply chain performance measurement metrics have been introduced in this paper and the simulation model is developed based on those.

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

International Nuclear Information System (INIS)

Song, Tae Young

2007-01-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

Energy Technology Data Exchange (ETDEWEB)

Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

2007-07-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

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.

Development of a measure of safety climate

Directory of Open Access Journals (Sweden)

N. R. Barnes

1990-06-01

Full Text Available A measure of safety climate was developed to aid management in identifying safety problems and responding proactively to safety issues; to assess the general mood of the workforce to safety; and as a standard for comparison with other organizations. The measure of safety climate was based on items extracted from the Chamber of Mines "Loss Control" audit manual. Reliability analysis performed on the scale indicated consistently high reliability coefficients across three ethnic groups. Factor analysis gave support for the construct validity of the scale. Opsomming 'n Meting vir veiligheidsklimaat is ontwikkel ten einde bestuur in staat te stel om veiligheidsprobleme te identifiseer en om pro-aktiefop te tree; om die algemene gevoel van die werkskragte rakende veiligheid te bepaal en om 'n maatstaf vir vergelyking met ander organisasies daar te stel. 'n Betroubaarheidssanalise wat op die skaal uitgevoer is het daarop gedui dat daar konsekwent hoe betroubaarheidskoefisiënte vir drie etniese groepe verkry word. 'n Faktoranalise het die konstrukgeldigheid van die skaal bevestig. The author acknowledges the financial assistance provided by the Human Sciences Research Council for this research.

Safety culture indicators for NPP: international trends and development status in Korea

International Nuclear Information System (INIS)

Choi, Y. S.; Ko, J. D.; Choi, K. S.; Jung, Y. H.

2004-01-01

Safety culture has been recognized as important to achieve high level of nuclear safety, as several recent events that have occurred in advanced countries were found to have important implications for safety culture. Under the recognition, implementation-focused and practical methods to foster safety culture have become necessary. Development of safety culture indicators for assessing the level of safety culture and identifying some deficiencies is being conducted. This paper examines the regulatory positions of major nuclear power countries on licensee's safety culture, introduces the development status of Korean Safety Culture Indicators and presents its future direction

Challenges and strategies to facilitate formulation development of pediatric drug products: Safety qualification of excipients.

Science.gov (United States)

Buckley, Lorrene A; Salunke, Smita; Thompson, Karen; Baer, Gerri; Fegley, Darren; Turner, Mark A

2018-02-05

A public workshop entitled "Challenges and strategies to facilitate formulation development of pediatric drug products" focused on current status and gaps as well as recommendations for risk-based strategies to support the development of pediatric age-appropriate drug products. Representatives from industry, academia, and regulatory agencies discussed the issues within plenary, panel, and case-study breakout sessions. By enabling practical and meaningful discussion between scientists representing the diversity of involved disciplines (formulators, nonclinical scientists, clinicians, and regulators) and geographies (eg, US, EU), the Excipients Safety workshop session was successful in providing specific and key recommendations for defining paths forward. Leveraging orthogonal sources of data (eg. food industry, agro science), collaborative data sharing, and increased awareness of the existing sources such as the Safety and Toxicity of Excipients for Paediatrics (STEP) database will be important to address the gap in excipients knowledge needed for risk assessment. The importance of defining risk-based approaches to safety assessments for excipients vital to pediatric formulations was emphasized, as was the need for meaningful stakeholder (eg, patient, caregiver) engagement. Copyright © 2017 Elsevier B.V. All rights reserved.

Safety-related operator actions: methodology for developing criteria

International Nuclear Information System (INIS)

Kozinsky, E.J.; Gray, L.H.; Beare, A.N.; Barks, D.B.; Gomer, F.E.

1984-03-01

This report presents a methodology for developing criteria for design evaluation of safety-related actions by nuclear power plant reactor operators, and identifies a supporting data base. It is the eleventh and final NUREG/CR Report on the Safety-Related Operator Actions Program, conducted by Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The operator performance data were developed from training simulator experiments involving operator responses to simulated scenarios of plant disturbances; from field data on events with similar scenarios; and from task analytic data. A conceptual model to integrate the data was developed and a computer simulation of the model was run, using the SAINT modeling language. Proposed is a quantitative predictive model of operator performance, the Operator Personnel Performance Simulation (OPPS) Model, driven by task requirements, information presentation, and system dynamics. The model output, a probability distribution of predicted time to correctly complete safety-related operator actions, provides data for objective evaluation of quantitative design criteria

Development of safety analysis technology for LMR

International Nuclear Information System (INIS)

Lee, Y. B.; Kwon, Y. M.; Suk, S. D.

2005-03-01

The MATRA-LMR-FB has been developed internally for the damage prevention as well as the safety assessment during a channel blockage accident and, as a the result, the quality of the code becomes comparable to that developed in the leading countries. For a code-to-code comparison, KAERI could have access to the SASSYS-1 through a bilateral collaboration between KAERI and ANL. The study could bring into the reliability improvements both on the reactivity models in the SSC-K and on the SSC-K prediction capability. It finally leads to the completion of the SSC-K version 1.3 resulting from the qualitative and quantitative code-to-code comparison. The preliminary analysis for a metal fueled LMR could also become possible with the MELT-III and the VENUS-II, which had originally been developed for the HCDA analysis with an oxidized fuel, by developing the relevant models For the development of the safety evaluation technology, the safety limits have been set up, and the analyses of the internal and external channel blockages in an assembly have also been performed. Besides, the more reliable analysis results on the key design concepts could be obtained by way of the methodology improvement resulting from the qualitative and quantitative comparison study. For an efficient and systematic control of the main project, the integration of the developed technologies and the establishment of their data base have been pursued. It has gone through the development of the process control with taking account of interfaces among the sub-projects, the overall coordination of the developed technologies, the data base for the design products, and so on

Selection and ranking of occupational safety indicators based on fuzzy AHP: A case study in road construction companies

Directory of Open Access Journals (Sweden)

Janackovic, Goran Lj.

2013-11-01

Full Text Available This paper presents the factors, performance, and indicators of occupational safety, as well as a method to select and rank occupational safety indicators based on the expert evaluation method and the fuzzy analytic hierarchy process (fuzzy AHP. A case study is done on road construction companies in Serbia. The key safety performance indicators for the road construction industry are identified and ranked according to the results of a survey that included experts who assessed occupational safety risks in these companies. The case study confirmed that organisational factors have a dominant effect on the quality of the occupational health and safety management system in Serbian road construction companies.

Development and implementation of a hospital-based patient safety program

International Nuclear Information System (INIS)

Frush, Karen S.; Alton, Michael; Frush, Donald P.

2006-01-01

Evidence from numerous studies indicates that large numbers of patients are harmed by medical errors while receiving health-care services in the United States today. The 1999 Institute of Medicine report on medical errors recommended that hospitals and health-care agencies ''establish safety programs to act as a catalyst for the development of a culture of safety'' [1]. In this article, we describe one approach to successful implementation of a hospital-based patient safety program. Although our experience at Duke University Health System will be used as an example, the needs, principles, and solutions can apply to a variety of other health-care practices. Key components include the development of safety teams, provision of tools that teams can use to support an environment of safety, and ongoing program modification to meet patient and staff needs and respond to changing priorities. By moving patient safety to the forefront of all that we do as health-care providers, we can continue to improve our delivery of health care to children and adults alike. This improvement is fostered when we enhance the culture of safety, develop a constant awareness of the possibility of human and system errors in the delivery of care, and establish additional safeguards to intercept medical errors in order to prevent harm to patients. (orig.)

Performance Evaluation and Analysis of Rural Drinking Water Safety Project——A Case Study in Jiangsu, China

Science.gov (United States)

Du, Xiaorong

2017-04-01

Water is the basic condition for human survival and development. As China is the most populous country, rural drinking water safety problems are most conspicuous. Therefore, the Chinese government keeps increasing investment and has built a large number of rural drinking water safety projects. Scientific evaluation of project performance is of great significance to promote the sustainable operation of the project and the sustainable development of rural economy. Previous studies mainly focus on the economic benefits of the project, while ignoring the fact that the rural drinking water safety project is quasi-public goods, which has economic, social and ecological benefits. This paper establishes a comprehensive evaluation model for rural drinking water safety performance, which adapts the rules of "5E" (economy, efficiency, effectiveness, equity and environment) as the value orientation, and selects a rural drinking water safety project as object in case study at K District, which is in the north of Jiangsu Province, China. The results shows: 1) the comprehensive performance of K project is in good condition; 2) The performance of every part shows that the scores of criteria "efficiency", "environment" and "effect" are higher than the mean performance, while the "economy" is slightly lower than the mean and the "equity" is the lowest. 3) The performance of indicator layer shows that: the planned completion rate of project, the reduction rate of project cost and the penetration rate of water-use population are significantly lower than other indicators. Based on the achievements of previous studies and the characteristics of rural drinking water safety project, this study integrates the evaluation dimensions of equity and environment, which can contribute to a more comprehensive and systematic assessment of project performance and provide empirical data for performance evaluation and management of rural drinking water safety project. Key Words: Rural drinking water

Development and use of safety indicators at STUK

International Nuclear Information System (INIS)

Tiipana, P.

2001-01-01

This paper gives an outline of the development and use of STUK's indicator system at the department of Nuclear Reactor Regulation (YTO) in the Radiation and Nuclear Safety Authority, STUK. Indicators used at YTO are measures related to the safety of nuclear installations and regulatory activities. Indicators are numbers, ratios, percentages and amounts of interested matters that are for suitable for regulatory purposes, that is assessment and trending of the safety of nuclear installations and regulatory activities. STUK's indicator system is divided into two main areas: safety of nuclear facilities and regulatory activities. Safety of nuclear facilities is divided into 3 areas based on the concept of defence in de safety and quality culture, operational events and physical barriers. Regulatory activities are divided into 3 areas: working processes, resource management and regeneration and ability to work. These areas are measured using several indicators. At the moment some of indicators are included in YTO's management system to measure whether or not internally set goals are achieved. (author)

MORT: a safety management program developed for ERDA

International Nuclear Information System (INIS)

1977-03-01

ERDA's System Safety Development Center (SSDC) is located at the Idaho National Engineering Laboratory under the EG and G Idaho, Inc., contract administered by the Idaho Operations Office. The SSDC performs a variety of tasks for ERDA's Division of Safety, Standards, and Compliance, for the purpose of improvement and application of safety program elements. Primary among these tasks are development and demonstration of new methodologies, training, consultation, and technical writing. This information package (ERDA 77-38) is an example of the later task, aimed at communicating to a general audience the nature and purpose of major features of the Management Oversight and Risk Tree (MORT) program. The SSDC also originates a guideline series of monographs (the ERDA 76-45 series) for individuals who desire more specific explanations of the MORT program

A Systematic Analysis of Functional Safety Certification Practices in Industrial Robot Software Development

Directory of Open Access Journals (Sweden)

Tong Xie

2017-01-01

Full Text Available For decades, industry robotics have delivered on the promise of speed, efficiency and productivity. The last several years have seen a sharp resurgence in the orders of industrial robots in China, and the areas addressed within industrial robotics has extended into safety-critical domains. However, safety standards have not yet been implemented widely in academia and engineering applications, particularly in robot software development. This paper presents a systematic analysis of functional safety certification practices in software development for the safety-critical software of industrial robots, to identify the safety certification practices used for the development of industrial robots in China and how these practices comply with the safety standard requirements. Reviewing from Chinese academic papers, our research shows that safety standards are barely used in software development of industrial robot. The majority of the papers propose various solutions to achieve safety, but only about two thirds of the papers refer to non-standardized approaches that mainly address the systematic level rather than the software development level. In addition, our research shows that with the development of artificial intelligent, an emerging field is still on the quest for standardized and suitable approaches to develop safety-critical software.

Application of FEPs analysis to identify research priorities relevant to the safety case for an Australian radioactive waste facility

International Nuclear Information System (INIS)

Payne, T.E.; McGlinn, P.J.

2007-01-01

The Australian Nuclear Science and Technology Organisation (ANSTO) has established a project to undertake research relevant to the safety case for the proposed Australian radioactive waste facility. This facility will comprise a store for intermediate level radioactive waste, and either a store or a near-surface repository for low-level waste. In order to identify the research priorities for this project, a structured analysis of the features, events and processes (FEPs) relevant to the performance of the facility was undertaken. This analysis was based on the list of 137 FEPs developed by the IAEA project on 'Safety Assessment Methodologies for Near Surface Disposal Facilities' (ISAM). A number of key research issues were identified, and some factors which differ in significance for the store, compared to the repository concept, were highlighted. For example, FEPs related to long-term groundwater transport of radionuclides are considered to be of less significance for a store than a repository. On the other hand, structural damage from severe weather, accident or human interference is more likely for a store. The FEPs analysis has enabled the scientific research skills required for the inter-disciplinary project team to be specified. The outcomes of the research will eventually be utilised in developing the design, and assessing the performance, of the future facility. It is anticipated that a more detailed application of the FEPs methodology will be undertaken to develop the safety case for the proposed radioactive waste management facility. (authors)

To improve the safety of treatments in radiotherapy by developing a safety culture

International Nuclear Information System (INIS)

2008-01-01

Following the radiotherapy accidents between 2004 and 2006, the I.R.S.N. deemed necessary to lead a study on the safety of treatments in radiotherapy and on the use and the adaptation to the medical domain of safety analysis approach developed for the nuclear installations. Of this study, six mains lines of investigation appear: Endow the radiotherapy services with real referential of safety, reinforce the robustness of the organization of radiotherapy services, improve the safety of the equipment and software at the design and operating stages, improve the management of the expertise and reinforce the operating feed back on incidents and accidents. The main learning from this study is the benefit that could be gained by fitting the safety analysis concepts and methods to the specificities of radiotherapy considering the organization of it collective work, the cooperation between actors stemming from different jobs as well as the interactions between actors and technical systems in the process of the treatments, when they are put into service and during their periodic checks. (author)

Development of GoldSim Program Template for Safety Assessment of an LILW Disposal

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jeong, Jong Tae

2010-08-01

A modeling study and development of a methodology, by which an assessment of safety and performance for a low- and intermediate level radioactive waste (LILW) repository could be effectively made has been carried out. With normal or abnormal nuclide release cases associated with the various FEPs and scenarios involved in the performance of the proposed repository in view of nuclide transport and transfer both in geosphere and biosphere, a total system performance assessment (TSPA) program has been developed by utilizing a commercial development tool program, GoldSim. The report especially deals much with a detailed conceptual modeling scheme by which a GoldSim program modules, all of which are integrated into a TSPA program template were able to be developed. Degradation effects of the near-field such manmade barriers as waste container and the silo on the performance of the repository are also modeled and quantitatively and deterministically/probabilistically evaluated with input data set currently available or assumed. In-depth system models that are conceptually and rather practically described and then ready for implementing into a GoldSim TSPA program are introduced with illustrations. The GoldSim TSPA template program developed through this study is expected to be successfully applied to the post closure safety assessment required for an LILW repository such as Gyeongju repository

Restructuring within an academic health center to support quality and safety: the development of the Center for Quality and Safety at the Massachusetts General Hospital.

Science.gov (United States)

Bohmer, Richard M J; Bloom, Jonathan D; Mort, Elizabeth A; Demehin, Akinluwa A; Meyer, Gregg S

2009-12-01

Recent focus on the need to improve the quality and safety of health care has created new challenges for academic health centers (AHCs). Whereas previously quality was largely assumed, today it is increasingly quantifiable and requires organized systems for improvement. Traditional structures and cultures within AHCs, although well suited to the tripartite missions of teaching, research, and clinical care, are not easily adaptable to the tasks of measuring, reporting, and improving quality. Here, the authors use a case study of Massachusetts General Hospital's efforts to restructure quality and safety to illustrate the value of beginning with a focus on organizational culture, using a systematic process of engaging clinical leadership, developing an organizational framework dependent on proven business principles, leveraging focus events, and maintaining executive dedication to execution of the initiative. The case provides a generalizable example for AHCs of how applying explicit management design can foster robust organizational change with relatively modest incremental financial resources.

Conclusions and Recommendations of the IAEA International Conference on Topical Issues in Nuclear Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing

Main Conclusions and Recommendations of International Conference on Topical Issues in Nuclear Installation Safety: Ensuring Safety for Sustainable Nuclear Development

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

Over 200 participants from 33 countries and three international organizations came and actively participated and contributed to focused discussions and the success of the conference. The following points summarize the key conclusions and recommendations of the conference with respect to nuclear safety. 1. The nuclear safety approach is based on the philosophy developed in the 60's: defense in depth principles and deterministic criteria. When properly applied and completed by probabilistic analyses and operational experience feedback, it continues to be a successful approach. However, guarding against the risk of accidents requires constant vigilance and high technical competence and a never ending fight against complacency. In this context, having a strong leadership with a commitment to continuous improvement and a vision of sustained excellence is a key element of nuclear safety. Continuous improvement in safety also should be pursued through scientific research and operational experience feedback. 2. An accident anywhere is of concern to all Member States. Therefore, it is in the interest of all Member States to share and collaborate on safety matters. Participation of all Member States in international nuclear safety instruments and conventions, including liability for nuclear damage, is considered beneficial to global safety. The Convention on Nuclear Safety, the Joint Convention, international cooperation through IAEA and other organizations, bilateral or multilateral arrangements are important elements for establishing networks for sharing and transferring knowledge. It is acknowledged that the IAEA's Safety Fundamentals and Safety Requirements provide a sound foundation for high level nuclear safety. IAEA Safety Standards should be the basis for the establishment and maintenance of safety infrastructure. The IAEA's peer reviews and services such as IRRS, OSART, Site Evaluation and Reactor Safety Reviews provide also a valuable platform for sharing