Connoted hazard and perceived importance of fluorescent, neon, and standard safety colors.

Science.gov (United States)

Zielinska, O A; Mayhorn, C B; Wogalter, M S

2017-11-01

The perceived hazard and rated importance of standard safety, fluorescent, and neon colors are investigated. Colors are used in warnings to enhance hazard communication. Red has consistently been rated as the highest in perceived hazard. Orange, yellow, and black are the next highest in connoted hazard; however, there is discrepancy in their ordering. Safety standards, such as ANSI Z535.1, also list colors to convey important information, but little research has examined the perceived importance of colors. In addition to standard safety colors, fluorescent colors are more commonly used in warnings. Understanding hazard and importance perceptions of standard safety and fluorescent colors is necessary to create effective warnings. Ninety participants rated and ranked a total of 33 colors on both perceived hazard and perceived importance. Rated highest were the safety red colors from the American National Standard Institute (ANSI), International Organization for Standardization (ISO), and Federal Highway Administration (FHWA) together with three fluorescent colors (orange, yellow, and yellow-green) from 3 M on both dimensions. Rankings were similar to ratings except that fluorescent orange was the highest on perceived hazard, while fluorescent orange and safety red from the ANSI were ranked as the highest in perceived importance. Fluorescent colors convey hazard and importance levels as high as the standard safety red colors. Implications for conveying hazard and importance in warnings through color are discussed. Copyright © 2017 Elsevier Ltd. All rights reserved.

Use of digital computing devices in systems important to safety

International Nuclear Information System (INIS)

1986-01-01

The incorporation of digital computing devices in systems important to safety now is progressing fast in several countries, including Canada, France, Federal Republic of Germany, Japan, USA. There are now reactors with microprocessors in some trip systems. The major functions of those systems are: reactor trip initiation, display, monitoring, testing, re-calibration of detectors. The benefits of moving to a fully computerized shut-down system should be improved reliability, greater flexibility, better man-machine interface, improved testing, higher reactor output and lower overall cost. With the introduction of computer devices in systems important to safety, plant availability and safety are improved because disturbances are treated before they lead to safety action, in this way helping the operator to avoid errors. The Meeting presentations were divided into sessions devoted to the following topics: Needs for the use of digital devices (DCD) in safety important systems (SIS) (5 papers); Problems raised by the integration SIS in the NPP control (7 papers); Description and presentation of DCD of SIS (6 papers); Results of experiences in engineering, manufacture, qualification operation of DCD hardware and software (5 papers). A separate abstract was prepared for each of these papers

Outsource Power, Import Safety? Challenges and Opportunities of the U.S.-China Food Safety Regulatory Cooperation.

Science.gov (United States)

Lin, Ching-Fu

The United States has a high stake in China’s serious food safety problem, as food products of Chinese origin have dominated the U.S. food market in numerous areas and continue to grow. The conclusion of the U.S.-China Food Safety Agreement (“the Agreement”) has allowed FDA to strengthen regulatory cooperation with its Chinese counterpart in various aspects. The Agreement also paves the way for the implementation of the new regulatory tools incorporated in FSMA, especially in the cross-border context. However, both the Agreement and FSMA have certain crucial limitations that may create future hurdles to effective implementation in the U.S.-China cooperation. This paper therefore endeavors to first examine China’s governance challenges over food safety, with a focus on the 2009 Food Safety Law, the 2015 Amendment, and the fundamental problem of “thin” rule of law. This paper moves to analyze the U.S.-China Food Safety Agreement, reviewing the agreement’s strengths and weaknesses. It further assesses FSMA’s innovative institutional design to regulate imported food products and its limitations. However, both the U.S.-China Food Safety Agreement and FSMA arguably create a regulatory dilemma for FDA when addressing imported food safety, due to structural mismatch between the broad scope of power granted to FDA and the long chain of power outsourcing to governments or private companies as primary “regulators.” Neither the Agreement nor FSMA give FDA adequate capacity to closely oversee such “agents” along the chain of power outsourcing. Framing the U.S.-China food safety cooperation as a multilayer structure that “outsources power” to “import safety,” this paper concludes by stressing the need for a robust accountability and effective mechanism for U.S.-China food safety cooperation.

Design, fabrication and erection of steel structures important to safety of nuclear facilities

International Nuclear Information System (INIS)

2001-10-01

Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. The objective and minimum requirements for the design of civil engineering buildings/structures to be fulfilled to provide adequate assurance for safety of nuclear installations in India (such as pressurised heavy water reactor and related systems) are specified in the Safety Standard for Civil Engineering Structures Important to Safety of Nuclear Facilities. This standard is written by AERB to specify guidelines for implementation of the above civil engineering safety standard in the design, fabrication and erection of steel structures important to safety

78 FR 29392 - Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied...

Science.gov (United States)

2013-05-20

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0098] Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied on for Safety AGENCY: Nuclear Regulatory Commission. ACTION... (NRC) is issuing for public comment Draft Regulatory Issue Summary (RIS) 2013-XX, ``Embedded Digital...

Discussion of important safety requirements for new nuclear power plants

International Nuclear Information System (INIS)

Zhang Lin; Jia Xiang; Yan Tianwen; Li Wenhong; Li Chun

2014-01-01

This paper presents the analysis of several important safety requirements and improvement direction. Technical view of security goals on site safety evaluation, internal and external events fortification, serious accident prevention and mitigation, as well as the core, containment system and instrument control system design and engineering optimization, and etc are indicated. It will be useful for new plant design, construction and safety improvement. (authors)

Design for safety: theoretical framework of the safety aspect of BIM system to determine the safety index

Directory of Open Access Journals (Sweden)

Ai Lin Evelyn Teo

2016-12-01

Full Text Available Despite the safety improvement drive that has been implemented in the construction industry in Singapore for many years, the industry continues to report the highest number of workplace fatalities, compared to other industries. The purpose of this paper is to discuss the theoretical framework of the safety aspect of a proposed BIM System to determine a Safety Index. An online questionnaire survey was conducted to ascertain the current workplace safety and health situation in the construction industry and explore how BIM can be used to improve safety performance in the industry. A safety hazard library was developed based on the main contributors to fatal accidents in the construction industry, determined from the formal records and existing literature, and a series of discussions with representatives from the Workplace Safety and Health Institute (WSH Institute in Singapore. The results from the survey suggested that the majority of the firms have implemented the necessary policies, programmes and procedures on Workplace Safety and Health (WSH practices. However, BIM is still not widely applied or explored beyond the mandatory requirement that building plans should be submitted to the authorities for approval in BIM format. This paper presents a discussion of the safety aspect of the Intelligent Productivity and Safety System (IPASS developed in the study. IPASS is an intelligent system incorporating the buildable design concept, theory on the detection, prevention and control of hazards, and the Construction Safety Audit Scoring System (ConSASS. The system is based on the premise that safety should be considered at the design stage, and BIM can be an effective tool to facilitate the efforts to enhance safety performance. IPASS allows users to analyse and monitor key aspects of the safety performance of the project before the project starts and as the project progresses.

Determining the safety of enzymes used in animal feed.

Science.gov (United States)

Pariza, Michael W; Cook, Mark

2010-04-01

The purpose of this paper is to provide guidance for evaluating the safety of enzyme preparations used in animal feed. Feed enzymes are typically added to animal feed to increase nutrient bioavailability by acting on feed components prior to or after consumption, i.e., within the gastrointestinal tract. In contrast, food processing enzymes are generally used during processing and then inactivated or removed prior to consumption. The enzymes used in both applications are almost always impure mixtures of active enzyme and other metabolites from the production strain, hence similar safety evaluation procedures for both are warranted. We propose that the primary consideration should be the safety of the production strain and that the decision tree mechanism developed previously for food processing enzymes (Pariza and Johnson, 2001) is appropriate for determining the safety of feed enzymes. Thoroughly characterized non-pathogenic, non-toxigenic microbial strains with a history of safe use in enzyme manufacture are also logical candidates for generating safe strain lineages, from which additional strains may be derived via genetic modification by traditional and non-traditional strategies. For new feed enzyme products derived from a safe strain lineage, it is important to ensure a sufficiently high safety margin for the intended use, and that the product complies with appropriate specifications for chemical and microbial contamination. Copyright 2009 Elsevier Inc. All rights reserved.

Importance of LWR best-estimate safety calculations for analysis of Fukushima-like accidents

International Nuclear Information System (INIS)

Sanchez Espinoza, V.; Ivanov, K.

2011-01-01

The safety assessment of nuclear power plants relies heavily on numerical simulations, which must include the most important physical models that are representative for the reactor type of interest. The current trends in nuclear power generation and regulation are to perform safety studies by 'best-estimate' codes that allow a realistic modeling of nuclear and thermal-hydraulic processes of the reactor core and the entire plant behavior including control and protection functions. Realistic methods are referred to as 'best-estimate' calculations, implying that they use a set of data, correlations, and methods designed to represent the phenomena, using the best available techniques. The application of best-estimate methodologies in the licensing process requires the quantification of the embedded uncertainties of the used codes. In this field many international initiatives are underway under the umbrella of the OECD such as the Light Water Reactor Uncertainty Analysis in Modeling benchmark, Oskarshamn 2 Boiling Water Reactor (BWR) Stability benchmark, Kalinin-3 VVER-1000 benchmark, etc. that underlies the importance of these issues. The Fukushima accident has shown the importance of the knowledge of the initial phase of the accident regarding the state of the core, in-vessel structures, and containment as well as the amount of fissile material inventories that potentially can be released if the safety barriers fail. For the development of mitigation and prevention measures modeling of the sequence of the events along with understanding of the key physical phenomena driving the accident progression is important. The paper presents the best-estimate coupled methodologies implemented, validated and applied at the Karlsruhe Institute Technology (KIT) for both types of LWRs - Pressurized Water Reactors (PWRs) and BWRs. Example are given with a BWR steady state and transient simulations along with corresponding uncertainty quantification. The on-going development of high

49 CFR 385.317 - Will a safety audit result in a safety fitness determination by the FMCSA?

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false Will a safety audit result in a safety fitness... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.317 Will a safety audit result in a safety fitness determination by the FMCSA? A safety audit will not result in a safety...

Problems in determining the optimal use of road safety measures

DEFF Research Database (Denmark)

Elvik, Rune

2014-01-01

for intervention that ensures maximum safety benefits. The third problem is how to develop policy options to minimise the risk of indivisibilities and irreversible choices. The fourth problem is how to account for interaction effects between road safety measures when determining their optimal use. The fifth......This paper discusses some problems in determining the optimal use of road safety measures. The first of these problems is how best to define the baseline option, i.e. what will happen if no new safety measures are introduced. The second problem concerns choice of a method for selection of targets...... problem is how to obtain the best mix of short-term and long-term measures in a safety programme. The sixth problem is how fixed parameters for analysis, including the monetary valuation of road safety, influence the results of analyses. It is concluded that it is at present not possible to determine...

Sensitivity analysis of parameters important to nuclear criticality safety of Castor X/28F spent nuclear fuel cask

Energy Technology Data Exchange (ETDEWEB)

Leotlela, Mosebetsi J. [Witwatersrand Univ., Johannesburg (South Africa). School of Physics; Koeberg Operating Unit, Johannesburg (South Africa). Regulations and Licensing; Malgas, Isaac [Koeberg Nuclear Power Station, Duinefontein (South Africa). Nuclear Engineering Analysis; Taviv, Eugene [ASARA consultants (PTY) LTD, Johannesburg (South Africa)

2015-11-15

In nuclear criticality safety analysis it is essential to ascertain how various components of the nuclear system will perform under certain conditions they may be subjected to, particularly if the components of the system are likely to be affected by environmental factors such as temperature, radiation or material composition. It is therefore prudent that a sensitivity analysis is performed to determine and quantify the response of the output to variation in any of the input parameters. In a fissile system, the output parameter of importance is the k{sub eff}. Therefore, in attempting to prevent reactivity-induced accidents, it is important for the criticality safety analyst to have a quantified degree of response for the neutron multiplication factor to perturbation in a given input parameter. This article will present the results of the perturbation of the parameters that are important to nuclear criticality safety analysis and their respective correlation equations for deriving the sensitivity coefficients.

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

International Nuclear Information System (INIS)

Chung, Dae Wook

2011-01-01

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

Discussion on several important safety requirements for the new nuclear power plant

International Nuclear Information System (INIS)

Yan Tianwen; Li Jigen; Zhang Lin; Feng Youcai; Jia Xiang; Li Wenhong

2013-01-01

Post the Fukushima nuclear accident, the Chinese government raised higher safety goals and safety requirements for the new nuclear power plant to be constructed. The paper expounded the important indicators of safety requirements and the aspects of safety modification that had been developed for the new NPPs. It also discussed and analyzed the main fields required by the new NPPs safety requirements in the safety goals, safety evaluation of sites, defenses of internal and external events, severe accident prevention and mitigation, design of reactor core, containment system and I and C system, and optimization of engineering measure, which gave some references to the design, construction and safety modifications of new NPPs in China. (authors)

Assessment of importance for protection subsystems at analysis of reliability and safety

International Nuclear Information System (INIS)

Pereguda, A.I.; Povyakalo, A.A.

1995-01-01

Importance of the element estimation in the system, including protection and safety subsystems, by individual variation of the system failure probability relative to the element failure in the case, when the variation constitutes the single step-like function, is considered. The importance of elements by such an approach is the function of time. It is shown that introduction of the safety system not only diminishes the accident probability but essentially decreases the importance of danger source for the object under protection. 6 refs

Maintenance of civil engineering structures important to safety of Nuclear Power Plants

International Nuclear Information System (INIS)

2002-03-01

Civil engineering structures in nuclear installations form an important feature having implications to safety performance of these installations. This safety standard is written to specify the objectives and minimum requirements for the design of civil engineering buildings/structures that are to be fulfilled to provide adequate assurance for safety of nuclear installations in India

How important is vehicle safety for older consumers in the vehicle purchase process?

Science.gov (United States)

Koppel, Sjaan; Clark, Belinda; Hoareau, Effie; Charlton, Judith L; Newstead, Stuart V

2013-01-01

This study aimed to investigate the importance of vehicle safety to older consumers in the vehicle purchase process. Older (n = 102), middle-aged (n = 791), and younger (n = 109) participants throughout the eastern Australian states of Victoria, New South Wales, and Queensland who had recently purchased a new or used vehicle completed an online questionnaire about their vehicle purchase process. When asked to list the 3 most important considerations in the vehicle purchase process (in an open-ended format), older consumers were mostly likely to list price as their most important consideration (43%). Similarly, when presented with a list of vehicle factors (such as price, design, Australasian New Car Assessment Program [ANCAP] rating), older consumers were most likely to identify price as the most important vehicle factor (36%). When presented with a list of vehicle features (such as automatic transmission, braking, air bags), older consumers in the current study were most likely to identify an antilock braking system (41%) as the most important vehicle feature, and 50 percent of older consumers identified a safety-related vehicle feature as the highest priority vehicle feature (50%). When asked to list up to 3 factors that make a vehicle safe, older consumers in the current study were most likely to list braking systems (35%), air bags (22%), and the driver's behavior or skill (11%). When asked about the influence of safety in the new vehicle purchase process, one third of older consumers reported that all new vehicles are safe (33%) and almost half of the older consumers rated their vehicle as safer than average (49%). A logistic regression model was developed to predict the profile of older consumers more likely to assign a higher priority to safety features in the vehicle purchasing process. The model predicted that the importance of safety-related features was influenced by several variables, including older consumers' beliefs that they could protect themselves

Expert evaluation in NPP safety important systems licensing process

International Nuclear Information System (INIS)

Mikhail, A Yastrebenetsky; Vasilchenko, V.N.

2001-01-01

Expert evaluation of nuclear power plant safety important systems modernization is an integral part of these systems licensing process. The paper contains some aspects of this evaluation which are based on Ukrainian experience of VVER-1000 and VVER-440 modernization. (authors)

Expert evaluation in NPP safety important systems licensing process

Energy Technology Data Exchange (ETDEWEB)

Mikhail, A Yastrebenetsky; Vasilchenko, V.N. [Ukrainian State Scientific Technical Center of Nuclear and Radiation Safety (Ukraine)

2001-07-01

Expert evaluation of nuclear power plant safety important systems modernization is an integral part of these systems licensing process. The paper contains some aspects of this evaluation which are based on Ukrainian experience of VVER-1000 and VVER-440 modernization. (authors)

Methodology for identifying boundaries of systems important to safety in CANDU nuclear power plants

International Nuclear Information System (INIS)

Therrien, S.; Komljenovic, D.; Therrien, P.; Ruest, C.; Prevost, P.; Vaillancourt, R.

2007-01-01

This paper presents a methodology developed to identify the boundaries of the systems important to safety (SIS) at the Gentilly-2 Nuclear Power Plant (NPP), Hydro-Quebec. The SIS boundaries identification considers nuclear safety only. Components that are not identified as important to safety are systematically identified as related to safety. A global assessment process such as WANO/INPO AP-913 'Equipment Reliability Process' will be needed to implement adequate changes in the management rules of those components. The paper depicts results in applying the methodology to the Shutdown Systems 1 and 2 (SDS 1, 2), and to the Emergency Core Cooling System (ECCS). This validation process enabled fine tuning the methodology, performing a better estimate of the effort required to evaluate a system, and identifying components important to safety of these systems. (author)

Food safety: importance of composition for assessing genetically modified cassava (Manihot esculenta Crantz).

Science.gov (United States)

van Rijssen, Fredrika W Jansen; Morris, E Jane; Eloff, Jacobus N

2013-09-04

The importance of food composition in safety assessments of genetically modified (GM) food is described for cassava ( Manihot esculenta Crantz) that naturally contains significantly high levels of cyanogenic glycoside (CG) toxicants in roots and leaves. The assessment of the safety of GM cassava would logically require comparison with a non-GM crop with a proven "history of safe use". This study investigates this statement for cassava. A non-GM comparator that qualifies would be a processed product with CG level below the approved maximum level in food and that also satisfies a "worst case" of total dietary consumption. Although acute and chronic toxicity benchmark CG values for humans have been determined, intake data are scarce. Therefore, the non-GM cassava comparator is defined on the "best available knowledge". We consider nutritional values for cassava and conclude that CG residues in food should be a priority topic for research.

Understanding Consumer Confidence in the Safety of Food: Its Two-Dimensional Structure and Determinants

NARCIS (Netherlands)

Jonge, de J.; Trijp, van J.C.M.; Renes, R.J.; Frewer, L.J.

2007-01-01

Understanding of the determinants of consumer confidence in the safety of food is important if effective risk management and communication are to be developed. In the research reported here, we attempt to understand the roles of consumer trust in actors in the food chain and regulators, consumer

RIO: a program to determine reliability importance and allocate optimal reliability goals

International Nuclear Information System (INIS)

Poloski, J.P.

1978-09-01

The designer of a nuclear plant must know the plant's associated risk limitations so that he can design the plant accordingly. To design a safety system, he must understand its importance and how it relates to the overall plant risk. The computer program RIO can aid the designer to understand a system's contribution to the plant's overall risk. The methodology developed and presented was sponsored by the Nuclear Research Applications Division of the Department of Energy for use in the Gas Cooled Fast Breeder Reactor (GCFR) Program. The principal motivation behind its development was the need to translate nuclear plants safety goals into reliability goals for systems which make up that plant. The method described herein will make use of the GCFR Accident Initiation and Progression Analyses (AIPA) event trees and other models in order to determine these reliability goals

Importance of safety review to the safe operation of a nuclear plant

International Nuclear Information System (INIS)

Brinkerhoff, L.C.

1978-01-01

Widely differing standards of construction of nuclear reactors are employed in different countries. Although the reactor vendors, including designers and construction contractors, have a vested interest in safety, the ultimate responsibility for safety rests with the reactor facility operator. Even though governmental agencies, either directly or indirectly, must take a strong lead in developing policies and practices of safe operation, the reactor facility operator must recognize and accept the full responsibility for safe operation of the facility. The policies and practices of safe operation imposed by governmental agencies must help assure the prudent operation and the adequate maintenance of those structures, systems, and components of importance to safety. Since each country has a slightly different philosophy for achieving safety and each vendor utilizes different structures, systems, and components to fulfil this philosophy, it is imperative that the facility operator adequately maintain those engineered safety features and those plant protective systems which have been engineered into achieving the desired levels of safety. An additional method of helping to assure that those structures, systems, and components of importance to safety are prudently operated and adequately maintained is to assign the full safety responsibility for the overall operations of the reactor facility to the operating organization, i.e. assigning a 'line of responsibility' within the reactor facility operator. This assurance can be further strengthened by requiring that the facility operator establish a safety review body that overviews the operation and assures that the operating organization complies with those policies and practices of safe operation which have been imposed on the reactor facility. (author)

Surveillance of items important to safety in nuclear power plants

International Nuclear Information System (INIS)

1990-01-01

The Guide was prepared as part of the IAEA's programme, referred to as the NUSS Programme, for establishing Codes and Safety Guides relating to nuclear power plants. THe Guide supplements the Code on the Safety of Nuclear Power Plants: Operation, IAEA Safety Series No. 50-C-O(Rev.1). The operating organization has overall responsibility for the safe operation of the nuclear power plant. Therefore, it shall ensure that adequate surveillance activities are carried out in order to verify that the plant is operated within the prescribed operational limits and conditions, and to detect in time any deterioration of structures, systems and components as well as any adverse trend that could lead to an unsafe condition. These activities can be classified as: Monitoring plant parameters and system status; Checking and calibrating instrumentation; Testing and inspecting structures, systems and components. This Safety Guide provides guidance and recommendations on surveillance activities to ensure that structures, systems and components important to safety are available to perform their functions in accordance with design intent and assumptions

Positive organizational behavior and safety in the offshore oil industry: Exploring the determinants of positive safety climate.

Science.gov (United States)

Hystad, Sigurd W; Bartone, Paul T; Eid, Jarle

2014-01-01

Much research has now documented the substantial influence of safety climate on a range of important outcomes in safety critical organizations, but there has been scant attention to the question of what factors might be responsible for positive or negative safety climate. The present paper draws from positive organizational behavior theory to test workplace and individual factors that may affect safety climate. Specifically, we explore the potential influence of authentic leadership style and psychological capital on safety climate and risk outcomes. Across two samples of offshore oil-workers and seafarers working on oil platform supply ships, structural equation modeling yielded results that support a model in which authentic leadership exerts a direct effect on safety climate, as well as an indirect effect via psychological capital. This study shows the importance of leadership qualities as well as psychological factors in shaping a positive work safety climate and lowering the risk of accidents.

Positive organizational behavior and safety in the offshore oil industry: Exploring the determinants of positive safety climate

Science.gov (United States)

Hystad, Sigurd W.; Bartone, Paul T.; Eid, Jarle

2013-01-01

Much research has now documented the substantial influence of safety climate on a range of important outcomes in safety critical organizations, but there has been scant attention to the question of what factors might be responsible for positive or negative safety climate. The present paper draws from positive organizational behavior theory to test workplace and individual factors that may affect safety climate. Specifically, we explore the potential influence of authentic leadership style and psychological capital on safety climate and risk outcomes. Across two samples of offshore oil-workers and seafarers working on oil platform supply ships, structural equation modeling yielded results that support a model in which authentic leadership exerts a direct effect on safety climate, as well as an indirect effect via psychological capital. This study shows the importance of leadership qualities as well as psychological factors in shaping a positive work safety climate and lowering the risk of accidents. PMID:24454524

Determination of the number of software tests using probabilistic safety assessment

International Nuclear Information System (INIS)

Kang, H. K.; Seong, T. Y.; Lee, K. Y.

2000-01-01

The broader usage of digital equipment in nuclear power plants gives rise to the safety problems of software. The field test should be performed before the software is used in critical applications because it is well known that software shows non-linear response when it is applied to different target systems in different environment. In the case of safety-critical applications, the result of tests contains usually zero failure case and the satisfiable number of tests is hard to be determined. In this paper, we suggests the method to determine the number of software tests without failure using the probabilistic safety assessment. From the result of the probabilistic safety assessment on total system, the desirable unavailability of software is calculated and the number of tests is determined

Discussion on unpacking inspection of imported civil nuclear safety equipment

International Nuclear Information System (INIS)

Li Chan; Zhang Wenguang; Li Maolin; Li Shixin; Jin Gang; Yao Yuan

2014-01-01

This paper introduces the purpose, contents, process and requirements of unpacking inspection which is the second stage of safety inspection of imported civil nuclear safety equipment, expresses review key points on application documents of unpacking inspection, processes of witness on-the-spot before unpacking inspection outside the civil nuclear facilities by the test agency, discusses understanding of unpacking inspection, supervision of manufacture, inspection prior to shipment, supervision of loading and acceptance by the unit operating civil nuclear facilities, reports on unpacking inspection. Some suggestions on reinforcing the unpacking inspection in China are concerned. (authors)

A new approach to determine the environmental qualification requirements for the safety related equipment

International Nuclear Information System (INIS)

Hasnaoui, C.; Parent, G.

2000-01-01

The objective of the environmental qualification of safety related equipment is to ensure that the plant defense-in-depth is not compromised by common mode failures following design basis accidents with a harsh environment. A new approach based on safety functions has been developed to determine what safety-related equipment is required to function during and after a design basis accident, as well as their environmental qualification requirements. The main feature of this approach is to use auxiliary safety functions established from safety requirements as credited in the safety analyses. This approach is undertaken in three steps: identification of the auxiliary safety functions of each main safety function; determination of the main equipment groups required for each auxiliary safety function; and review of the safety analyses for design basis accidents in order to determine the credited auxiliary safety functions and their mission times for each accident scenario. Some of the benefits of the proposed approach for the determination of the safety environmental qualification requirements are: a systematic approach for the review of safety analyses based on a safety function check list, and the insurance, with the availability of the safety functions, that Gentilly-2 defense-in-depth would not be compromised by design basis accidents with a harsh environment. (author)

Safety assessment of food and herbal products containing hepatotoxic pyrrolizidine alkaloids: interlaboratory consistency and the importance of N-oxide determination.

Science.gov (United States)

Cao, Yu; Colegate, Steven M; Edgar, John A

2008-01-01

Two recent mass spectrometry-based reports concerning Senecio scandens yielded remarkably dissimilar pyrrolizidine alkaloid constituents. In both studies, and in a related analysis of Senecio scandens and Tussilago farfara using micellar electrokinetic chromatography, the presence of hazardous N-oxides of the alkaloids was either not considered or was inadequately considered. This raises concerns about the effectiveness of the methodologies used in these, and similar, studies in assessing the pyrrolizidine alkaloid content and the safety of food, food supplements and medicines for human use. To highlight essential analytical requirements for confident assessment of pyrrolizidine alkaloid-related safety of food and herbal products for human use. Direct infusion-ESI MS and HPLC-ESI MS were used to analyse samples derived from liquid-liquid partitioning experiments and from strong cation exchange, solid-phase extraction of pyrrolizidine alkaloids and their N-oxides. A simple solvent partitioning experiment using pure senecionine and senecionine-N-oxide, two constituents reported in one of the mass spectrometry-based studies of S. scandens, clearly demonstrated the inadequacy of the reported method to detect and quantitate hazardous pyrrolizidine alkaloid N-oxide components. A preliminary LCMS analysis of commercially-prepared extracts of comfrey roots (Symphytum officinale and S. uplandicum s. l.) was used as a model to highlight the analytical importance of N-oxides in the safety assessment of pyrrolizidine alkaloid-containing medicinal herbs. This study highlighted significant differences in the reported identification of pyrrolizidine alkaloids from the same plant species, and clearly demonstrated the inadequacy of some procedures to include N-oxides in the assessment of pyrrolizidine alkaloid-related safety of food and herbal products.

Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

International Nuclear Information System (INIS)

McConnell, J.W., Jr; Ayers, A.L. Jr; Tyacke, M.J.

1996-02-01

This report provides a graded approach for classification of components used in transportation packaging and dry spent fuel storage systems. This approach provides a method for identifying, the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements The general types of transportation packagings and dry storage systems were identified. Discussions were held with suppliers and fabricators of packagings and storage systems to determine current practices. The methodology used in this report is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This report also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems. The safety importance of each component is discussed, and a classification category is assigned

Identification of structures, systems, and components important to safety at the potential repository at Yucca Mountain

International Nuclear Information System (INIS)

Hartman, D.J.; Miller, D.D.; Klamerus, L.J.

1991-10-01

This study recommends which structures, systems, and components of the potential repository at Yucca Mountain are important to safety. The assessment was completed in April 1990 and uses the reference repository configuration in the Site Characterization Plan Conceptual Design Report and follows the methodology required at that time by DOE Procedure AP6.10-Q. Failures of repository items during the preclosure period are evaluated to determine the potential offsite radiation doses and associated probabilities. Items are important to safety if, in the event they fail to perform their intended function, an accident could result which causes a dose commitment greater than 0.5 rem to the whole body or any organ of an individual in an unrestricted area. This study recommends that these repository items include the structures that house spent fuel and high-level waste, the associated filtered ventilation exhaust systems, certain waste- handling equipment, the waste containers, the waste treatment building structure, the underground waste transporters, and other items listed in this report. This work was completed April 1990. 27 refs., 7 figs., 9 tabs

Safety culture - Is it important?

International Nuclear Information System (INIS)

Ayres, R.A.; Reiss, R.E.

1998-01-01

A strong and improving safety culture provides the foundation for building long term success for a company. It is a cultural change for most organizations and requires years not months to achieve. Short term successes are typically achieved and the smart companies build upon and communicate those successes. For long term success, these companies never deviate or become complacent about maintaining a strong safety culture. There are several lessons learned from the nuclear industry that support the need to maintain a strong safety culture: 1)prevention of human errors costs less than dealing with the consequences 2)poorly designed processes cause the majority of human errors 3)quality supervision is a powerful tool in human error reduction 4)performance monitoring/trending and technology based root cause analysis are essential to human error reduction 5)human errors caused by misjudgment need special attention 6)procedural non-compliance needs a focused solution based on organizational psychology 7)the benefits of a well designed accountability system are very significant 8)knowledge and skills, more rules, are the last line of defense against problems. (authors)

Development of regulation technologies for software verification and validation of I and C systems important to safety in NPPs

International Nuclear Information System (INIS)

Kim, Bok Ryul; Oh, S. H.; Zhu, O. P.; Jeong, C. H.; Hwang, H. S.; Goo, C. S.; Chung, Y. H.

2000-12-01

The project has provided the draft regulatory policies and guides regarding the quality assurance of software used to I and C systems important to safety in nuclear power plants, differentiated V and V activities by safety classes which are important elements in ensuring software quality assurance, and suggested V and V techniques to be applied, regulatory guides and checklists for reviewing software important to safety. The project introduced the classification concepts on software quality assurance. The I and C systems important to safety are classified into IC-1, IC-2, IC-3, and Non-IC as based on safety classifications. And the software used to these I and C systems are classified into 3 categories, say, safety-critical software, safety-related software, and non-safety software, in the light of safety importance of functions to be performed. Based upon these safety classifications, the extent of software V and V activities by each class has been differentiated each other. On the other hand, the project has divided software important to safety into newly-developed software and previously-developed software in terms of design and implementation, and provided the draft regulatory guides on each type of software, for instance, newly-developed software, previously-developed software, and software tools

Efficient improvement of nuclear power plant safety by reorganization of risk-informed safety importance evaluation methods for piping welded portions

Energy Technology Data Exchange (ETDEWEB)

Irie, Takashi; Hanafusa, Hidemitsu; Suyama, Takeshi [Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan); Morota, Hidetsugu; Kojima, Sigeo; Mizuno, Yoshinobu [Computer Software Development Co., Ltd., Tokyo (Japan)

2002-09-01

In this work, risk information was used to evaluate the safety importance of piping welded portions which were important for plant operation and maintenance of nuclear power plants. There are two types of risk-informed safety importance evaluation methods, namely the ASME method and the EPRI method. Since both methods have advantages and disadvantages, elements of each method were combined and reorganized. Considerations included whether the degradation mechanisms would be objectively evaluated and whether plant safety would be efficiently improved. The most objective and efficient method was as follows. Piping failure potential is quantitatively and objectively evaluated for failure with probabilistic fracture mechanics (PFM) and for other degradation mechanisms with empirical failure rates, and conditional core damage probability (CCDP) is calculated with PSA. This method reduces the inspected segment numbers to 1/4 of the deterministic method and increases the ratio of risk, which is covered by the inspected segments, to total risk from 80% of the deterministic method to 95%. Piping inspection numbers decreased for safety injection systems that were required the inspections by the deterministic method. Piping inspections were required for part of main feed water and main steam systems that were not required the inspections by the deterministic method. (author)

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

Media-safety of children as important social-pedagogical problem of modern times

Directory of Open Access Journals (Sweden)

Yuliia Semeniako

2017-02-01

Full Text Available In the article the relevance of media-safety as a socio-pedagogical problems. The introduction of media education in the practice of work of preschool educational institutions, the author identified as one of the strategies for overcoming negative influences of media on the younger generation. The concept of “information security”, “pre-school media education”, “media informational security” and identified the main tasks of media education  at the present stage in Ukraine. Determined main problems, the overcoming of which may provide media-safety of preschoolers.Key words: media education, media-safety media, information and communication technology, information security.

Nuclear power plants - Instrumentation and control systems important for safety - Classification (International Electrotechnical Commission Standard Publication 1226:1993)

International Nuclear Information System (INIS)

Stefanik, J.

1996-01-01

This international standard established a method of classification of the information and command functions for nuclear power plants, and the I and C and equipment that provide those functions, into categories that designate the importance for safety of the functions, and the associated systems and equipment. The resulting classification then determines relevant design criteria. The design criteria are the measures of quality by which the adequacy of each functions, and the associated systems and equipment in relation to its importance to plant safety is ensured. In this standard, the criteria are those of functionality, reliability, performance, environmental durability and quality assurance. This standard is applicable to all the information and command functions, and the instrumentation and control systems and equipment that provide those functions. The functions, systems and equipment under consideration provide automated protection, closed or open loop control, and information to the operating staff. They keep the NPP conditions inside the safe operating envelope and provide automatic actions, or enable manual actions, that mitigate accidents or prevent or minimize radioactive releases to the site or wider environment. The functions, and the associated systems and equipment that fulfill these roles safeguard the health and safety of the NPP operators and the public. This standard complements, and does not replace or supersede, the Safety Guides and Codes of Practice published by the International Atomic Energy Agency

Parameters of importance to determine in geoscientific site studies

International Nuclear Information System (INIS)

Andersson, Johan; Almen, K.E.; Ericsson, L.O.; Karlsson, Fred; Stroem, A.; Fredriksson, Anders; Stanfors, R.

1996-12-01

This report identifies and describes parameters, that may be determined in a site characterization study, for performing functional and safety analyses of a deep rock repository for radioactive wastes. The report discusses data needs for rock engineering and for description of other environmental aspects. It is intended that the report be used as a basis for formulating the criteria of acceptance in evaluating a candidate site. The report describes how different parameters influence the safety function, and how they are evaluated in practice. The logical order of performing measurements, due to the need of in-data and influence on other measurements is also discussed. 65 refs

Organizational Climate Determinants of Resident Safety Culture in Nursing Homes

Science.gov (United States)

Arnetz, Judith E.; Zhdanova, Ludmila S.; Elsouhag, Dalia; Lichtenberg, Peter; Luborsky, Mark R.; Arnetz, Bengt B.

2011-01-01

Purpose of the Study: In recent years, there has been an increasing focus on the role of safety culture in preventing costly adverse events, such as medication errors and falls, among nursing home residents. However, little is known regarding critical organizational determinants of a positive safety culture in nursing homes. The aim of this study…

The roles of safety and compliance in determining effectiveness of topical therapy for psoriasis.

Science.gov (United States)

Stein Gold, Linda; Corvari, Linda

2007-01-01

Topical therapies are the mainstays of treatment for most patients with psoriasis because they relieve symptoms and reduce the size and severity of lesions. The effectiveness of a therapeutic intervention is a function of drug efficacy (determined by randomized clinical trial results) and patient safety and compliance. Alterations in any parameter can have a substantial influence on clinical outcomes. However, topical agents can be associated with unwanted and potentially toxic side effects that make physicians reluctant to prescribe them, and patients intentionally discontinue treatment with these topical agents. To maximize effectiveness and improve patient safety, physicians may prescribe medications in combination, sequential, or rotational therapeutic regimens. This treatment strategy has the potential to improve the overall efficacy and safety of topical therapy; however, the effectiveness of this method may be compromised because the complexity of the therapeutic regimen may decrease patient compliance. Newer topical therapies that have a convenient once-daily dosing schedule are needed and will have important implications for patient compliance.

On the Importance of Safety and Security at Work for the Organizational Management

Directory of Open Access Journals (Sweden)

Jeanina Ciurea

2017-12-01

Full Text Available One of the most important aspects regarding human resource management in any organization should be the one concerning the safety and security at work of the employees. Unfortunately, this remains an insufficiently discussed issue, not only in literature, but also in practice. Articles in this field are not so numerous, while official reports indicate a high number of incidents that occur every year, in every country. The enterprises should focus much more on this aspect, but in many cases, the management lacks from this point of view, the policy regarding the safety and health of employees being kept at the lowest positions on the list of aspects that need immediate attention. The present paper tries to highlight the importance of the issue of safety and security at work, the first part consisting in a brief review of the literature in this field, while the second part presents statistical data available for the past years, both in Romania and Europe, regarding this problem.

Computer-based systems important to safety (COMPSIS) - Reporting guidelines

International Nuclear Information System (INIS)

1999-07-01

The objective of this procedure is to help the user to prepare an COMPSIS report on an event so that important lessons learned are most efficiently transferred to the database. This procedure focuses on the content of the information to be provided in the report rather than on its format. The established procedure follows to large extend the procedure chosen by the IRS incident reporting system. However this database is built for I and C equipment with the purpose of the event report database to collect and disseminate information on events of significance involving Computer-Based Systems important to safety in nuclear power plants, and feedback conclusions and lessons learnt from such events. For events where human performance is dominant to draw lessons, more detailed guidance on the specific information that should be supplied is spelled out in the present procedure. This guidance differs somewhat from that for the provision of technical information, and takes into account that the engineering world is usually less familiar with human behavioural analysis than with technical analysis. The events to be reported to the COMPSIS database should be based on the national reporting criteria in the participating member countries. The aim is that all reports including computer based systems that meet each country reporting criteria should be reported. The database should give a broad picture of events/incidents occurring in operation with computer control systems. As soon as an event has been identified, the insights and lessons learnt to be conveyed to the international nuclear community shall be clearly identified. On the basis of the description of the event, the event shall be analyzed in detail under the aspect of direct and potential impact to plant safety functions. The first part should show the common involvement of operation and safety systems and the second part should show the special aspects of I and C functions, hardware and software

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.

Safety assessment of novel foods and strategies to determine their safety in use

International Nuclear Information System (INIS)

Edwards, Gareth

2005-01-01

Safety assessment of novel foods requires a different approach to that traditionally used for the assessment of food chemicals. A case-by-case approach is needed which must be adapted to take account of the characteristics of the individual novel food. A thorough appraisal is required of the origin, production, compositional analysis, nutritional characteristics, any previous human exposure and the anticipated use of the food. The information should be compared with a traditional counterpart of the food if this is available. In some cases, a conclusion about the safety of the food may be reached on the basis of this information alone, whereas in other cases, it will help to identify any nutritional or toxicological testing that may be required to further investigate the safety of the food. The importance of nutritional evaluation cannot be over-emphasised. This is essential for the conduct of toxicological studies in order to avoid dietary imbalances, etc., that might lead to interpretation difficulties, but also in the context of its use as food and to assess the potential impact of the novel food on the human diet. The traditional approach used for chemicals, whereby an acceptable daily intake (ADI) is established with a large safety margin relative to the expected exposure, cannot be applied to foods. The assessment of safety in use should be based upon a thorough knowledge of the composition of the food, evidence from nutritional, toxicological and human studies, expected use of the food and its expected consumption. Safety equates to a reasonable certainty that no harm will result from intended uses under the anticipated conditions of consumption

Hydrogen peroxide: importance and determination

OpenAIRE

Mattos, Ivanildo Luiz de; Shiraishi, Karina Antonelli; Braz, Alexandre Delphini; Fernandes, João Roberto

2003-01-01

A brief discussion about the hydrogen peroxide importance and its determination is presented. It was emphasized some consideration of the H2O2 as reagent (separated or combined), uses and methods of analysis (techniques, detection limits, linear response intervals, sensor specifications). Moreover, it was presented several applications, such as in environmental, pharmaceutical, medicine and food samples.

Initial Q-list for the prospective Yucca Mountain repository based on items important to safety and waste isolation

International Nuclear Information System (INIS)

Laub, T.W.; Jardine, L.J.

1987-01-01

A method for identifying items important to safety based on a probabilistic risk assessment approach was developed and implemented for the conceptual design of the Yucca Mountain repository. No items were classified as important to safety; however, six items were classified as potentially important to safety. These were the shipping cask, the cranes and the truck or rail-care vehicle stops in the cask receiving and preparation area, the hot cell structure of the waste packaging hot cells, the cranes in the waste packaging hot cells, and the waste-handling building fire protection system. In addition, a method for identifying items important to waste isolation was developed and implemented. Two hydrogeologic units of the Yucca Mountain site were classified as important to waste isolation: the Calico Hills nonwelded zeolitic unit and the Calico Hills nonwelded vitric unit. The preliminary Q-list for the Yucca Mountain repository is comprised of the two units of the site classified as important to waste isolation and contains no items important to safety

Initial Q-list for the prospective Yucca Mountain repository based on items important to safety and waste isolation

International Nuclear Information System (INIS)

Laub, T.W.; Jardine, L.J.

1987-01-01

A method for identifying items important to safety based on a probabilistic risk assessment approach was developed and implemented for the conceptual design of the Yucca Mountain repository. No items were classified as important to safety; however, six items were classified as potentially important to safety. These were the shipping cask, the cranes and the truck or rail-car vehicle stops in the cask receiving and preparation area, the hot cell structure of the waste packaging hot cells, the cranes in the waste packaging hot cells, and the waste-handling building fire protection system. In addition, a method for identifying items important to waste isolation was developed and implemented. Two hydrogeologic units of the Yucca Mountain site were classified as important to waste isolation: the Calico Hills nonwelded zeolitic unit and the Calico Hills nonwelded vitric unit. The preliminary Q-list for the Yucca Mountain repository is comprised of the two units of the site classified as important to waste isolation and contains no items important to safety

The determinants of employee participation in occupational health and safety management.

Science.gov (United States)

Masso, Märt

2015-01-01

This article focuses on employee direct participation in occupational health and safety (OHS) management. The article explains what determines employee opportunities to participate in OHS management. The explanatory framework focuses on safety culture and safety management at workplaces. The framework is empirically tested using Estonian cross-sectional, multilevel data of organizations and their employees. The analysis indicates that differences in employee participation in OHS management in the Estonian case could be explained by differences in OHS management practices rather than differences in safety culture. This indicates that throughout the institutional change and shift to the European model of employment relations system, change in management practices has preceded changes in safety culture which according to theoretical argument is supposed to follow culture change.

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

Science.gov (United States)

Kuiper, Harry A; Paoletti, Claudia

2015-01-01

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

Determining Safety Inspection Thresholds for Employee Incentives Programs on Construction Sites.

Science.gov (United States)

Sparer, Emily; Dennerlein, Jack

2013-01-01

The goal of this project was to evaluate approaches of determining the numerical value of a safety inspection score that would activate a reward in an employee safety incentive program. Safety inspections are a reflection of the physical working conditions at a construction site and provide a safety score that can be used in incentive programs to reward workers. Yet it is unclear what level of safety should be used when implementing this kind of program. This study explored five ways of grouping safety inspection data collected during 19 months at Harvard University-owned construction projects. Each approach grouped the data by one of the following: owner, general contractor, project, trade, or subcontractor. The median value for each grouping provided the threshold score. These five approaches were then applied to data from a completed project in order to calculate the frequency and distribution of rewards in a monthly safety incentive program. The application of each approach was evaluated qualitatively for consistency, competitiveness, attainability, and fairness. The owner-specific approach resulted in a threshold score of 96.3% and met all of the qualitative evaluation goals. It had the most competitive reward distribution (only 1/3 of the project duration) yet it was also attainable. By treating all workers equally and maintaining the same value throughout the project duration, this approach was fair and consistent. The owner-based approach for threshold determination can be used by owners or general contractors when creating leading indicator incentives programs and by researchers in future studies on incentive program effectiveness.

Determination of the NPP Krsko reactor core safety limits using the COBRA-III-C code

International Nuclear Information System (INIS)

Lajtman, S.; Feretic, D.; Debrecin, N.

1989-01-01

This paper presents the NPP Krsko reactor core safety limits determined by the COBRA-III-C code, along with the methodology used. The reactor core safety limits determination is a part of reactor protection limits procedure. The results obtained were compared to safety limits presented in NPP Krsko FSAR. The COBRA-III-C NPP Krsko design core steady state thermal hydraulics calculation, used as the basis for the safety limits calculation, is presented as well. (author)

Employee Safety Motivation: perspectives and measures on the basis of the Self-Determination theory.

Science.gov (United States)

Mariani, M G; Soldà, Bianca Lara; Curcuruto, M

2015-09-09

There is a growing body of literature demonstrating that employee's safety behaviour is largely influenced by their motivation to work safely. The Self-Determination Theory, which proposes a multidimensional conceptualization of motivation, is now established in various domains of the academic field (Healthcare, Education, Psychopathology, Organizations, Sport etc.). However, there are few publications concerning its use in the analysis of motivation in a safety context, where it constitutes a new topic of study. The aim of this study was to develop and validate the Italian version of the Self-Determined Safety Motivation Scale and analyze the psychometric properties of the scale in terms of construct validity. The research involved 387 Italian employees from three companies, who occupied medium-low levels in the organizational hierarchy. A good level of psychometric properties was shown. The Italian version of the Self-Determined Safety Motivation Scale is a reliable and valid instrument to assess safety motivation.

Optimization of safety equipment outages improves safety

International Nuclear Information System (INIS)

Cepin, Marko

2002-01-01

Testing and maintenance activities of safety equipment in nuclear power plants are an important potential for risk and cost reduction. An optimization method is presented based on the simulated annealing algorithm. The method determines the optimal schedule of safety equipment outages due to testing and maintenance based on minimization of selected risk measure. The mean value of the selected time dependent risk measure represents the objective function of the optimization. The time dependent function of the selected risk measure is obtained from probabilistic safety assessment, i.e. the fault tree analysis at the system level and the fault tree/event tree analysis at the plant level, both extended with inclusion of time requirements. Results of several examples showed that it is possible to reduce risk by application of the proposed method. Because of large uncertainties in the probabilistic safety assessment, the most important result of the method may not be a selection of the most suitable schedule of safety equipment outages among those, which results in similarly low risk. But, it may be a prevention of such schedules of safety equipment outages, which result in high risk. Such finding increases the importance of evaluation speed versus the requirement of getting always the global optimum no matter if it is only slightly better that certain local one

Statistically based uncertainty analysis for ranking of component importance in the thermal-hydraulic safety analysis of the Advanced Neutron Source Reactor

International Nuclear Information System (INIS)

Wilson, G.E.

1992-01-01

The Analytic Hierarchy Process (AHP) has been used to help determine the importance of components and phenomena in thermal-hydraulic safety analyses of nuclear reactors. The AHP results are based, in part on expert opinion. Therefore, it is prudent to evaluate the uncertainty of the AHP ranks of importance. Prior applications have addressed uncertainty with experimental data comparisons and bounding sensitivity calculations. These methods work well when a sufficient experimental data base exists to justify the comparisons. However, in the case of limited or no experimental data the size of the uncertainty is normally made conservatively large. Accordingly, the author has taken another approach, that of performing a statistically based uncertainty analysis. The new work is based on prior evaluations of the importance of components and phenomena in the thermal-hydraulic safety analysis of the Advanced Neutron Source Reactor (ANSR), a new facility now in the design phase. The uncertainty during large break loss of coolant, and decay heat removal scenarios is estimated by assigning a probability distribution function (pdf) to the potential error in the initial expert estimates of pair-wise importance between the components. Using a Monte Carlo sampling technique, the error pdfs are propagated through the AHP software solutions to determine a pdf of uncertainty in the system wide importance of each component. To enhance the generality of the results, study of one other problem having different number of elements is reported, as are the effects of a larger assumed pdf error in the expert ranks. Validation of the Monte Carlo sample size and repeatability are also documented

Mapping the nomological network of employee self-determined safety motivation: A preliminary measure in China.

Science.gov (United States)

Jiang, Li; Tetrick, Lois E

2016-09-01

The present study introduced a preliminary measure of employee safety motivation based on the definition of self-determination theory from Fleming (2012) research and validated the structure of self-determined safety motivation (SDSM) by surveying 375 employees in a Chinese high-risk organization. First, confirmatory factor analysis (CFA) was used to examine the factor structure of SDSM, and indices of five-factor model CFA met the requirements. Second, a nomological network was examined to provide evidence of the construct validity of SDSM. Beyond construct validity, the analysis also produced some interesting results concerning the relationship between leadership antecedents and safety motivation, and between safety motivation and safety behavior. Autonomous motivation was positively related to transformational leadership, negatively related to abusive supervision, and positively related to safety behavior. Controlled motivation with the exception of introjected regulation was negatively related to transformational leadership, positively related to abusive supervision, and negatively related to safety behavior. The unique role of introjected regulation and future research based on self-determination theory were discussed. Copyright © 2016 Elsevier Ltd. All rights reserved.

Issue on NPP-I and C important to safety-Data Communication

International Nuclear Information System (INIS)

Koo, I. S.; Hong, S. B.; Cho, J. W.; Choi, Y. S.; Lee, J. C.

2010-01-01

1. Issue on CDV and FDIS of IEC61500 - Nuclear Power Plants - Instrumentation and control important to safety -Data communication - Activities on IEC TC45, SC45A/WGA3. 2. As issue the requirements for safety data communication which is essential part of digital I and C systems, the fundamental technology for IT based nuclear I and C is established. 3. Approval and circulation of IED61500 CDV and FDIS - Issue of the international standard, IEC 61500. 4. Issue one IEC61500, three interim documents, three presentations and five technical support to industry, and participation in IEC TC45 and SC45A plenary meeting and intermediate meeting on SC45A/WGA3. 5. Based on IEC61500, an new project on wireless technologyes application to NPP will be proceeded

Quantitative evaluation of the fault tolerance of systems important to the safety of atomic power plants

International Nuclear Information System (INIS)

Malkin, S.D.; Sivokon, V.P.; Shmatkova, L.V.

1989-01-01

Fault tolerance is the property of a system to preserve its performance upon failures of its components. Thus, in nuclear-reactor technology one has only a qualitative evaluation of fault tolerance - the single-failure criterion, which does not enable one to compare and perform goal-directed design of fault-tolerant systems, and in the field of computer technology there are no generally accepted evaluations of fault tolerance that could be applied effectively to reactor systems. This paper considers alternative evaluations of fault tolerance and a method of comprehensive automated calculation of the reliability and fault tolerance of complex systems. The authors presented quantitative estimates of fault tolerance that develop the single-failure criterion. They have limiting processes that allow simple and graphical standardization. They worked out a method and a program for comprehensive calculation of the reliability and fault tolerance of systems of complex structure that are important to the safety of atomic power plants. The quantitative evaluation of the fault tolerance of these systems exhibits a degree of insensitivity to failures and shows to what extent their reliability is determined by a rigorously defined structure, and to what extent by the probabilistic reliability characteristics of the components. To increase safety, one must increase the fault tolerance of the most important systems of atomic power plants

Safety culture management: The importance of organizational factors

International Nuclear Information System (INIS)

Haber, S.B.; Shurberg, D.A.; Jacobs, R.; Hofmann, D.

1995-01-01

The concept of safety culture has been used extensively to explain the underlying causes of performance based events, both positive and negative, across the nuclear industry. The work described in this paper represents several years of effort to identify, define and assess the organizational factors important to safe performance in nuclear power plants (NPPs). The research discussed in this paper is primarily conducted in support of the US Nuclear Regulatory Commission's (NRC) efforts in understanding the impact of organizational performance on safety. As a result of a series of research activities undertaken by numerous NRC contractors, a collection of organizational dimensions has been identified and defined. These dimensions represent what is believed to be a comprehensive taxonomy of organizational elements that relate to the safe operation of nuclear power plants. Techniques were also developed by which to measure these organizational dimensions, and include structured interview protocols, behavioral checklists, and behavioral anchored rating scales (BARS). Recent efforts have focused on devising a methodology for the extraction of information related to the identified organizational dimensions from existing NRC documentation. This type of effort would assess the applicability of the organizational dimensions to existing NRC inspection and evaluation reports, refine the organizational dimensions previously developed so they are more relevant to the task of retrospective analysis, and attempt to rate plants based on the review of existing NRC documentation using the techniques previously developed for the assessment of organizational dimensions

Predicting perceived safety to drive the morning after drinking: The importance of hangover symptoms.

Science.gov (United States)

Cameron, Elaine; French, David P

2016-07-01

People driving the day after drinking are at risk of impaired performance and accidents due to continued intoxication or the effects of alcohol hangover. Drivers are poor at estimating their own blood alcohol concentration, and some drive despite believing they are over the legal limit. It is therefore important to identify other factors influencing perceived ability to drive 'the morning after'. This study tested how accurately participants estimated their legal driving status, and the contribution of beliefs and hangover symptoms to the prediction of perceived driving safety. This cross-sectional study involved 193 students completing a questionnaire and alcohol breath test the morning after heavy alcohol consumption. Indicators of subjective intoxication, severity of hangover symptoms, estimated legal status and perceived safety to drive were measured. A hierarchical linear regression analysis was conducted. No participants thought they were under the English legal limit when they were not, and 47% thought they were over the limit when they were in fact legally permissible to drive. However, 20% of those believing they were over the limit nevertheless rated themselves as safe to drive. Hangover symptoms added 17% variance to the prediction of perceived safety to drive, over and above objective and subjective measures of intoxication. Perceived severity of hangover symptoms influence beliefs about driving ability: When judging safety to drive, people experiencing less severe symptoms believe they are less impaired. If this finding is robust, health promotion campaigns should aim to correct this misapprehension. [Cameron E, French D. Predicting perceived safety to drive the morning after drinking: The importance of hangover symptoms. Drug Alcohol Rev 2016;35:442-446]. © 2015 Australasian Professional Society on Alcohol and other Drugs.

Determination of radioactivity released from fuel to be considered in accident safety analysis

International Nuclear Information System (INIS)

1980-01-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to define a margin of conservatism on activity values used in the following safety analysis - determination of instrumentation ranges - definition of equipment accessibility to personnel - qualification of equipment to post-accident conditions - determination of waste release to the environment

Applying Systems Thinking to Law Enforcement Safety: Recommendation for a Comprehensive Safety Management Framework

Science.gov (United States)

2015-12-01

injuries can also lead to other significant health concerns such as depression and absenteeism , which impact organizational productivity and safety...injuries is important: (1) to determine the impact of costs such as lost wages, medical expenses and insurance claims, as well as productivity ... production and operational safety; and a sustaining institutional culture.53 Safety is often not the primary goal of organizations, as other business or

Health care staffs’ perception of patient safety culture in hospital settings and factors of importance for this

OpenAIRE

Nordin, Anna; Theander, Kersti; Wilde-Larsson, Bodil; Nordström, Gun

2013-01-01

Vitenskapelig, fagfellevurdert artikkel Many hospital patients are affected by adverse events. Managers are important when improving safety. The perception of patient safety culture varies among health care staff. Health care staff (n = 1023) working in medical, surgical or mixed medical-surgical health care divisions answered the 51 items (14 dimensions) Swedish Hospital Survey on Patient Safety Culture (S-HSOPSC). Respondents with a managerial func- tion scored higher than non-managers f...

Representing the Fuzzy improved risk graph for determination of optimized safety integrity level in industrial setting

Directory of Open Access Journals (Sweden)

Z. Qorbali

2013-12-01

.Conclusion: as a result of establishing the presented method, identical levels in conventional risk graph table are replaced with different sublevels that not only increases the accuracy in determining the SIL, but also elucidates the effective factor in improving the safety level and consequently saves time and cost significantly. The proposed technique has been employed to develop the SIL of Tehran Refinery ISOMAX Center. IRG and FIRG results have been compared to clarify the efficacy and importance of the proposed method

Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

International Nuclear Information System (INIS)

Tyacke, M.J.; McConnell, J.W. Jr.; Ayers, A.L. Jr.; O'Connor, S.C.; Jankovich, J.P.

1996-01-01

The Idaho National Engineering Laboratory prepared a technical report for the Office of Nuclear Material Safety and Safeguards of the US Nuclear Regulatory Commission, entitled Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, NUREG/CR-6407. This paper provides the results of that report. It also presents the graded approach for classification of components used in transportation packagings and dry spent fuel storage systems. This approach provides a method for identifying the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements. The general types of transportation packagings and dry storage systems are identified. The methodology used in this paper is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This paper also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems, with a classification category assigned to each component. Several examples concerning the safety importance of components are presented

Safety issues for LMFBR: important features drawn from the assessments of Superphenix

International Nuclear Information System (INIS)

Natta, M.

2002-01-01

Superphenix, which is built on the site of Creys-Malville, is still the biggest LMFBR plant that has been in operation. It is a pool type reactor, as Phenix and the RNR 1 500 and EFR projects. After the analysis of the preliminary safety (1974-1975), the construction was authorised by decree of the Prime Minister in 1977, the authorization for fuel loading and star-up to 3% was given by the minister of industry in July 1985 and full power was achieved in December 1986. The plant was operated until the end of December 1996, producing the equivalent of 320 EFPD, corresponding to half of the maximum barn-up of the first core. The plant was definitively stopped on the 20. of April 1998 by a decision of the French government. During this period of 25 years of licensing, construction and operation of Superphenix, others discussions and preliminary licensing procedures were started for new projects, mainly the RNR 1500 French project and the EFR European project. The operation of Superphenix was also marked by several incidents, which led to additional licensing procedures and important modifications. This period was also marked by an important work of research and development in the safety field, mostly related to the issues concerning hypothetical core disruptive accidents (HCDA) and sodium fires; further, this period was marked by the Three Mile Island accident in 1979 and the Chernobyl accident in 1986. The purpose of this paper is to present some items which were discussed during this period of 25 years and which should be of interest for future LMFBRs. In this presentation, we shall discuss the key issues concerning the safety criteria and options taken with respect to severe accidents, i.e. core melt accidents, giving details on some specific which are less known since they were assessed only lately for Superphenix, sometimes in connection with the on-going safety researches. (author)

Refresher training as an important factor affecting safety of atomic energy utilization facilities

International Nuclear Information System (INIS)

Kapralov, E.

2005-01-01

Refresher training appears to be one of the most important factors, affecting safety of atomic energy utilization facilities. To provide up-to-date refresher training programs and courses TC NRS implements best training practice based on the actual and perspective Russian national and international norms, regulations, standards and recommendations. (author)

Associations between safety climate and safety management practices in the construction industry.

Science.gov (United States)

Marín, Luz S; Lipscomb, Hester; Cifuentes, Manuel; Punnett, Laura

2017-06-01

Safety climate, a group-level measure of workers' perceptions regarding management's safety priorities, has been suggested as a key predictor of safety outcomes. However, its relationship with actual injury rates is inconsistent. We posit that safety climate may instead be a parallel outcome of workplace safety practices, rather than a determinant of workers' safety behaviors or outcomes. Using a sample of 25 commercial construction companies in Colombia, selected by injury rate stratum (high, medium, low), we examined the relationship between workers' safety climate perceptions and safety management practices (SMPs) reported by safety officers. Workers' perceptions of safety climate were independent of their own company's implementation of SMPs, as measured here, and its injury rates. However, injury rates were negatively related to the implementation of SMPs. Safety management practices may be more important than workers' perceptions of safety climate as direct predictors of injury rates. © 2017 Wiley Periodicals, Inc.

Young workers’ occupational safety knowledge creation and habits

OpenAIRE

Hejduk, Irena; Tomczyk, Przemysław

2015-01-01

The problem of young workers'safety culture is important because of the unfavorable demographic trend occurring in the European Union and determinants of competitiveness and innovativeness of the economy. The paper presents the concept and the importance of safety culture and goals of the research program, the aim of which is the construction and verification of the model based on the transfer of knowledge regarding the safety and methods of its implementation.Safety culture is a der...

Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessels

International Nuclear Information System (INIS)

2005-10-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

Determinants for conducting food safety culture research

NARCIS (Netherlands)

Nyarugwe, Shingai P.; Linnemann, Anita; Hofstede, Gert Jan; Fogliano, Vincenzo; Luning, Pieternel A.

2016-01-01

Background Foodborne outbreaks continue to occur regardless of existing food safety measures indicating the shortcomings of these measures to assure food safety. This has led to the recognition of food safety culture as a key contributory factor to the food safety performance of food

Determining quantitative road safety targets by applying statistical prediction techniques and a multi-stage adjustment procedure.

Science.gov (United States)

Wittenberg, P; Sever, K; Knoth, S; Sahin, N; Bondarenko, J

2013-01-01

Due to substantial progress made in road safety in the last ten years, the European Union (EU) renewed the ambitious agreement of halving the number of persons killed on the roads within the next decade. In this paper we develop a method that aims at finding an optimal target for each nation, in terms of being as achievable as possible, and with the cumulative EU target being reached. Targets as an important component in road safety policy are given as reduction rate or as absolute number of road traffic deaths. Determination of these quantitative road safety targets (QRST) is done by a top-down approach, formalized in a multi-stage adjustment procedure. Different QRST are derived under consideration of recent research. The paper presents a method to break the national target further down to regional targets in case of the German Federal States. Generalized linear models are fitted to data in the period 1991-2010. Our model selection procedure chooses various models for the EU and solely log-linear models for the German Federal States. If the proposed targets for the EU Member States are attained, the sum of fatalities should not exceed the total value of 15,465 per year by 2020. Both, the mean level and the range of mortality rates within the EU could be lowered from 28-113 in 2010 to 17-41 per million inhabitants in 2020. This study provides an alternative to the determination of safety targets by political commitments only, taking the history of road fatalities trends and population into consideration. Copyright © 2012 Elsevier Ltd. All rights reserved.

Manual on maintenance of systems and components important to safety

International Nuclear Information System (INIS)

1986-01-01

The Manual should serve as guidance at the plant management level for the maintenance of systems and components important to safety. It includes a detailed description of management systems, administrative controls and procedures. The Annexes contain examples of documents and practices adopted by Operating Organizations of some Member States. It is not the intention of this Manual to address the technical problem of how to maintain a particular component but rather to cover the programmatic aspects of maintenance. It also contains some aspects of surveillance and verification activities. The Manual makes only general statements about radiation protection provisions in connection with maintenance; detailed guidance can be found in other IAEA documents

Work Placements as Learning Environments for Patient Safety: Finnish and British Preregistration Nursing Students' Important Learning Events

Science.gov (United States)

Tella, Susanna; Smith, Nancy-Jane; Partanen, Pirjo; Turunen, Hannele

2016-01-01

Learning to ensure patient safety in complex health care environments is an internationally recognised concern. This article explores and compares Finnish (n = 22) and British (n = 32) pre-registration nursing students' important learning events about patient safety from their work placements in health care organisations. Written descriptions were…

Understanding situation awareness and its importance in patient safety.

Science.gov (United States)

Gluyas, Heather; Harris, Sarah-Jane

2016-04-20

Situation awareness describes an individual's perception, comprehension and subsequent projection of what is going on in the environment around them. The concept of situation awareness sits within the group of non-technical skills that include teamwork, communication and managing hierarchical lines of communication. The importance of non-technical skills has been recognised in safety-critical industries such as aviation, the military, nuclear, and oil and gas. However, health care has been slow to embrace the role of non-technical skills such as situation awareness in improving outcomes and minimising the risk of error. This article explores the concept of situation awareness and the cognitive processes involved in maintaining it. In addition, factors that lead to a loss of situation awareness and strategies to improve situation awareness are discussed.

A Summary of the United States Food and Drug Administrations’ Food Safety Program for Imported Seafood; One Country’s Approach

Directory of Open Access Journals (Sweden)

Brett Koonse

2016-04-01

Full Text Available It is well known that the vast majority of seafood is captured or farmed in emerging countries and exported to developed countries. This has resulted in seafood being the number one traded food commodity in the world. Food safety is essential to this trade. Exporting countries should understand the regulatory food safety programs of the countries they ship to in order to comply with their applicable laws and regulations to avoid violations and disruptions in trade. The United States (U.S. imports more seafood than any individual country in the world but the European Union (E.U. countries, as a block, import significantly more. Each importing country has its own programs and systems in place to ensure the safety of imported seafood. However, most countries that export seafood have regulatory programs in place that comply with the import requirements of the E.U. The purpose of this paper is to describe the United States Food and Drug Administration’s (USFDA imported seafood safety program. The primary audience for the information is foreign government regulators, seafood exporters, and U.S. importers. It can also give consumers confidence that f U.S. seafood is safe no matter which country it originates from.

Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals

International Nuclear Information System (INIS)

1999-10-01

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

A min cut-set-wise truncation procedure for importance measures computation in probabilistic safety assessment

Energy Technology Data Exchange (ETDEWEB)

Duflot, Nicolas [Universite de technologie de Troyes, Institut Charles Delaunay/LM2S, FRE CNRS 2848, 12, rue Marie Curie, BP2060, F-10010 Troyes cedex (France)], E-mail: nicolas.duflot@areva.com; Berenguer, Christophe [Universite de technologie de Troyes, Institut Charles Delaunay/LM2S, FRE CNRS 2848, 12, rue Marie Curie, BP2060, F-10010 Troyes cedex (France)], E-mail: christophe.berenguer@utt.fr; Dieulle, Laurence [Universite de technologie de Troyes, Institut Charles Delaunay/LM2S, FRE CNRS 2848, 12, rue Marie Curie, BP2060, F-10010 Troyes cedex (France)], E-mail: laurence.dieulle@utt.fr; Vasseur, Dominique [EPSNA Group (Nuclear PSA and Application), EDF Research and Development, 1, avenue du Gal de Gaulle, 92141 Clamart cedex (France)], E-mail: dominique.vasseur@edf.fr

2009-11-15

A truncation process aims to determine among the set of minimal cut-sets (MCS) produced by a probabilistic safety assessment (PSA) model which of them are significant. Several truncation processes have been proposed for the evaluation of the probability of core damage ensuring a fixed accuracy level. However, the evaluation of new risk indicators as importance measures requires to re-examine the truncation process in order to ensure that the produced estimates will be accurate enough. In this paper a new truncation process is developed permitting to estimate from a single set of MCS the importance measure of any basic event with the desired accuracy level. The main contribution of this new method is to propose an MCS-wise truncation criterion involving two thresholds: an absolute threshold in addition to a new relative threshold concerning the potential probability of the MCS of interest. The method has been tested on a complete level 1 PSA model of a 900 MWe NPP developed by 'Electricite de France' (EDF) and the results presented in this paper indicate that to reach the same accuracy level the proposed method produces a set of MCS whose size is significantly reduced.

A min cut-set-wise truncation procedure for importance measures computation in probabilistic safety assessment

International Nuclear Information System (INIS)

Duflot, Nicolas; Berenguer, Christophe; Dieulle, Laurence; Vasseur, Dominique

2009-01-01

A truncation process aims to determine among the set of minimal cut-sets (MCS) produced by a probabilistic safety assessment (PSA) model which of them are significant. Several truncation processes have been proposed for the evaluation of the probability of core damage ensuring a fixed accuracy level. However, the evaluation of new risk indicators as importance measures requires to re-examine the truncation process in order to ensure that the produced estimates will be accurate enough. In this paper a new truncation process is developed permitting to estimate from a single set of MCS the importance measure of any basic event with the desired accuracy level. The main contribution of this new method is to propose an MCS-wise truncation criterion involving two thresholds: an absolute threshold in addition to a new relative threshold concerning the potential probability of the MCS of interest. The method has been tested on a complete level 1 PSA model of a 900 MWe NPP developed by 'Electricite de France' (EDF) and the results presented in this paper indicate that to reach the same accuracy level the proposed method produces a set of MCS whose size is significantly reduced.

Assessment and management of ageing of major nuclear power plant components important to safety: CANDU reactor assemblies

International Nuclear Information System (INIS)

2001-02-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring, and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs) including the Soviet designed water moderated and water cooled energy reactors (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which

Assessment and Management of ageing of major nuclear power plant components important to safety: PWR pressure vessels

International Nuclear Information System (INIS)

1999-10-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g., caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs; and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which involves the integration of

Importance of the lower limit of detection in radiological safety

International Nuclear Information System (INIS)

Rafael Terol T.; Hermenegildo Maldonado M.

1991-01-01

The concept of the Lower Limit of Detection (LLD) it contributes in the solution of some problems related with the radiological safety, such as the realization of the tests of flight of the sealed radioactive sources; the determination of radioisotopes in environmental samples; the estimate of present radionuclides in polluted foods; in general, the detection of small quantities of radioactive materials present in materials of use or consumption by part of the man in his daily life; as the one Lower Limit of Detection is related with topics of statistics, in this work a small review of them is made, it was superficially discussed the mensuration problems related with the establishment of the Lower Limit of Detection

Assessment and management of ageing of major nuclear power plant components important to safety: Steam generators

International Nuclear Information System (INIS)

1997-11-01

This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. They have been compiled using contributions from technical experts in typically 10 to 12 countries for each report, a feedback from a September 1994 Technical Committee Meeting attended by 53 technical experts from 21 Member States (who reviewed first drafts in specialized working groups), and review comments from invited specialists

Determinants of China's energy imports: An empirical analysis

International Nuclear Information System (INIS)

Zhao, Xingjun; Wu, Yanrui

2007-01-01

Sustained economic growth in China has triggered a surge of energy imports, especially oil imports. This paper investigates the determinants of China's energy import demand by using cointegraiton and VECM techniques. The findings suggest that, in the long run, growth of industrial production and expansion of transport sectors affect China's oil imports, while domestic energy output has a substitution effect. Thus, as the Chinese economy industrializes and the automotive sector expands, China's oil imports are likely to increase. Though China's domestic oil production has a substitution effect on imports, its growth is limited due to scarce domestic reserve and high exploration costs. It is anticipated that China will be more dependent on overseas oil supply regardless of the world oil price. (author)

Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessel internals

International Nuclear Information System (INIS)

2005-10-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and ware out of components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of heavy water moderated reactors (HWRs), boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

Modern licensing approaches for analysis of important to safety processes in Nuclear Power Plants

International Nuclear Information System (INIS)

Andreeva, M.; Groudev, P.; Pavlova, M.; Stoyanov, S.

2008-01-01

It is presented within the paper the modern approaches for analysis of important to safety assessment processes in Nuclear Power Plants, included Bulgarian Regulatory Agency's requirements for quantity assessment of these processes applying deterministic and probabilistic approaches for establishing and confirming the design basis and defence-in-depth effectiveness. (authors)

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

International Nuclear Information System (INIS)

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

2001-01-01

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

Behavioral determinants of mothers' safety measures to prevent injuries of pre-school children.

NARCIS (Netherlands)

Wortel, E.; Geus, G.H. de; Kok, G.

1995-01-01

Home-related injuries are a major threat to pre-school children in the western world. In this study the behavioral determinants of 18 parental safety measures were assessed. To select behavioral determinants, the Attitude-Social influence-Self-efficacy/barriers model was used with the inclusion of

Relevant or determinant: Importance in certified sustainable food consumption

NARCIS (Netherlands)

Dam, van Y.K.; Trijp, van J.C.M.

2013-01-01

Perceived relevance and determinance are two distinct constructs, underlying the overall concept of attribute importance. The present study proposes a survey based measure of attribute determinance. Based on construal level theory it is argued and empirically shown that actual choices of certified

DETERMINANTS OF UNSAFE HAMBURGER COOKING BEHAVIOR

OpenAIRE

Ralston, Katherine L.; Starke, Yolanda; Adu-Nyako, Kofi; Lin, Chung-Tung Jordan

1998-01-01

We used a national hamburger preparation survey to estimate a simultaneous equation model of food safety knowledge, attitudes, and hamburger cooking behavior. The results suggest that food safety risk perceptions, palatability attributes, and food safety knowledge play important roles in determining food preparation behavior.

Medication Safety Systems and the Important Role of Pharmacists.

Science.gov (United States)

Mansur, Jeannell M

2016-03-01

Preventable medication-related adverse events continue to occur in the healthcare setting. While the Institute of Medicine's To Err is Human, published in 2000, highlighted the prevalence of medical and medication-related errors in patient morbidity and mortality, there has not been significant documented progress in addressing system contributors to medication errors. The lack of progress may be related to the myriad of pharmaceutical options now available and the nuances of optimizing drug therapy to achieve desired outcomes and prevent undesirable outcomes. However, on a broader scale, there may be opportunities to focus on the design and performance of the many processes that are part of the medication system. Errors may occur in the storage, prescribing, transcription, preparation and dispensing, or administration and monitoring of medications. Each of these nodes of the medication system, with its many components, is prone to failure, resulting in harm to patients. The pharmacist is uniquely trained to be able to impact medication safety at the individual patient level through medication management skills that are part of the clinical pharmacist's role, but also to analyze the performance of medication processes and to lead redesign efforts to mitigate drug-related outcomes that may cause harm. One population that can benefit from a focus on medication safety through clinical pharmacy services and medication safety programs is the elderly, who are at risk for adverse drug events due to their many co-morbidities and the number of medications often used. This article describes the medication safety systems and provides a blueprint for creating a foundation for medication safety programs within healthcare organizations. The specific role of pharmacists and clinical pharmacy services in medication safety is also discussed here and in other articles in this Theme Issue.

Methods for safety culture improvement

International Nuclear Information System (INIS)

Sivintsev, Yu.V.

1998-01-01

New IAEA publication concerning the problems of safety assurance covering different aspects beginning from terminology applied and up to concrete examples of well and poor safety culture development at nuclear facilities is discussed. The safety culture is defined as such set of characteristics and specific activities of institutions and individual persons which states that safety problems of a nuclear facility are given the attention determined by their importance as being of highest priority. The statements of the new document have recommended, not mandatory character. It is emphasized that the process of safety culture improvement at nuclear facilities should be integral component of management procedure, not a bolt on extra

Safety class methodology

International Nuclear Information System (INIS)

Donner, E.B.; Low, J.M.; Lux, C.R.

1992-01-01

DOE Order 6430.1A, General Design Criteria (GDC), requires that DOE facilities be evaluated with respect to ''safety class items.'' Although the GDC defines safety class items, it does not provide a methodology for selecting safety class items. The methodology described in this paper was developed to assure that Safety Class Items at the Savannah River Site (SRS) are selected in a consistent and technically defensible manner. Safety class items are those in the highest of four categories determined to be of special importance to nuclear safety and, merit appropriately higher-quality design, fabrication, and industrial test standards and codes. The identification of safety class items is approached using a cascading strategy that begins at the 'safety function' level (i.e., a cooling function, ventilation function, etc.) and proceeds down to the system, component, or structure level. Thus, the items that are required to support a safety function are SCls. The basic steps in this procedure apply to the determination of SCls for both new project activities, and for operating facilities. The GDC lists six characteristics of SCls to be considered as a starting point for safety item classification. They are as follows: 1. Those items whose failure would produce exposure consequences that would exceed the guidelines in Section 1300-1.4, ''Guidance on Limiting Exposure of the Public,'' at the site boundary or nearest point of public access 2. Those items required to maintain operating parameters within the safety limits specified in the Operational Safety Requirements during normal operations and anticipated operational occurrences. 3. Those items required for nuclear criticality safety. 4. Those items required to monitor the release of radioactive material to the environment during and after a Design Basis Accident. Those items required to achieve, and maintain the facility in a safe shutdown condition 6. Those items that control Safety Class Item listed above

Lithuanian requirements for ageing management of systems and components important to safety of nuclear power plant

International Nuclear Information System (INIS)

Ramanauskiene, A.

2000-01-01

In this paper the Lithuanian requirements for ageing management of systems and components important to safety of Ignalina nuclear power plant (two RBMK-1500 water-cooled graphite moderated channel-type power reactors) are presented

Risk Importance Determination Process of CANDU Maintenance Rule Function

International Nuclear Information System (INIS)

Seo, Mi Ro; Jo, Ha Yan; Hwang, Mi Jeong

2009-01-01

In Korea, Maintenance Rule (MR) programs development for all PWR were completed. However, in case of PHWR (CANDU type, Wolsong Unit 1,2,3,4), the study of MR program was delayed, since the design concepts and operating experiences are different from those of PWR. This paper describes the process and results for the risk importance determination process of functions in scope. The risk importance was determined by PSA Basic Event Mapping and Delphi method. For Delphi evaluation, Delphi evaluation item for CANDU need to be developed because the design and normal operation functions are different from PWR

Assessment and management of ageing of major nuclear power plant components important to safety. Primary piping in PWRs

International Nuclear Information System (INIS)

2003-07-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues. The

THE CONSTRUCTION OF IMPORTANCE-PERFORMANCE GRID IN TOURIST SERVICES RESEARCH WITHOUT THE DIRECT DETERMINATION OF THE ATTRIBUTES IMPORTANCE

Directory of Open Access Journals (Sweden)

Ban Olimpia

2012-07-01

Full Text Available The importance-performance grid is a marketing instrument used to make decisions regarding the growth of the consumers’ satisfaction, by optimizing the attributes of products. This grid is a useful instrument, as it is shown in the paper, to the extent to which the importance and performance of the attributes are correctly recorded. Another idea underlined in the paper is that regarding the difficulty to directly determine the importance of attributes or in the same stage with the determination of the service performance, according to these attributes. The objectives of this paper are to analyze the importance-performance grid (suggested by Martilla and amended by Abalo,through an empirical study in the field of tourist services used and to test the conditions to carry out this grid taking into account the hypothetical case of indirectly determining the importance of the quality attributes. The literature in the field regarding the importance-performance analysis is analysed and the subsequent amendments to the previous grid suggested by Martilla and James in 1977. The present paper is a continuation of several studies on the same subject, in which the following research methods were used: direct survey by questionnaire, the Spearman correlation coefficient, and the entropy calculus. A comparative analysis of the importance-performance grid if directly recording the importance of attributes (through survey by questionnaire and of the indirect determination of the importance of the attributes (through the Spearman coefficient and entropy calculus is being suggested. The results indicate possible uses of methods, yet it raises a series of collateral problems regarding their application. The contribution of this paper is given by the suggestion of two methods to indirectly determine the importance of attributes, which take into account the data measurement scale used and the collinearity among attributes and which lead to pertinent results

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

International Nuclear Information System (INIS)

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

2008-01-01

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

SAFETY CRITERION IN ASSESSING THE IMPORTANCE OF AN ELEMENT IN THE COMPLEX TECHNOLOGICAL SYSTEM RELIABILITY STRUCTURE

Directory of Open Access Journals (Sweden)

Leszek CHYBOWSKI

2012-01-01

Full Text Available The paper presents the need to develop a description of the importance of the technological systems reliability structure elements in terms of security of the system. Basic issues related to the exploration of weak links and important elements in the system as well as a proposal to develop the current approach to assessing the importance of the system components have been presented. Moreover, the differences between the unreliability of suitability and unreliability of safety have been pointed out.

Spatial Determinants of Import Traffic Distribution At Port Harcourt (Nigeria

Directory of Open Access Journals (Sweden)

Soddy I. Inyang

2013-07-01

Full Text Available This paper highlights the result of a study carried out to examine the Geographic determinants of import traffic distribution at the Port Harcourt Port. A substantial aspect of the study involved building a regression model to estimate import distribution from the Port. The import function was specified in log-linear form. The adequacy of the model was then tested; this, involved statistical experiments to obtain the R-squared, as well as t and f values. Further test on the adequacy of the nwdel was conducted through diagnostic exercises designed to check for inulticollinedrity and heteroscedasticity, in the data used. Results obtained show that road distance and manufacturing industries are significant Geographic determinants of import Cargo distribution at the study Port. It is therefore important to lake the two variables into account in any policy or planning exercise at Port Harcourt Port.

Exploring the importance of team psychological safety in the development of two interprofessional teams.

Science.gov (United States)

O'Leary, Denise Fiona

2016-01-01

It has been previously demonstrated that interactions within interprofessional teams are characterised by effective communication, shared decision-making, and knowledge sharing. This article outlines aspects of an action research study examining the emergence of these characteristics within change management teams made up of nurses, general practitioners, physiotherapists, care assistants, a health and safety officer, and a client at two residential care facilities for older people in Ireland. The theoretical concept of team psychological safety (TPS) is utilised in presenting these characteristics. TPS has been defined as an atmosphere within a team where individuals feel comfortable engaging in discussion and reflection without fear of censure. Study results suggest that TPS was an important catalyst in enhancing understanding and power sharing across professional boundaries and thus in the development of interprofessional teamwork. There were differences between the teams. In one facility, the team developed many characteristics of interprofessional teamwork while at the other there was only a limited shift. Stability in team membership and organisational norms relating to shared decision-making emerged as particularly important in accounting for differences in the development of TPS and interprofessional teamwork.

Human factors in nuclear safety oversight

International Nuclear Information System (INIS)

Taylor, K.

1989-01-01

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

The assesment on safety distance determination of hydrogen production plant with RGTT200K reactor

International Nuclear Information System (INIS)

Siti Alimah; Sriyono

2013-01-01

The one of the hydrogen production process method coupled to RGTT200K is the utilization of steam reforming with (methane) natural gas as the feedstock. The integration between RGTT200K and hydrogen plant must consider many safety aspects and one of it is separation distance between these two systems. The purpose of this assessment is to study the sources of fires/explosion and to determine the safety distance between the steam reforming hydrogen production plant and RGTT200K reactor. The used methodology was literature assessment and safety distance calculation with equation R = k.W 1/3 . In this studi, safety distance determination in integration between RGTT200K and hydrogen plant was using equation based on reference of the USNRC Regulatory Guide 1.91 and mass on the equation was mass equivalent of TNT (kg). The results of the study show the hydrogen plant produces 160.000 m 3 /day, if requires storage tanks of 400.000 m 3 (based USNRC equal to 1.859 million tons of TNT equivalent) with factor k is 8, based on the equation R = k.W 1/3 , so the requirement for safety distance is 1 km. This distance may be shortened by adding a fire proof wall barrier and requires further assessment. (author)

Safety climate in OHSAS 18001-certified organisations: antecedents and consequences of safety behaviour.

Science.gov (United States)

Fernández-Muñiz, Beatriz; Montes-Peón, José Manuel; Vázquez-Ordás, Camilo José

2012-03-01

The occupational health and safety standard OHSAS 18001 has gained considerable acceptance worldwide, and firms from diverse sectors and of varying sizes have implemented it. Despite this, very few studies have analysed safety management or the safety climate in OHSAS 18001-certified organisations. The current work aims to analyse the safety climate in these organisations, identify its dimensions, and propose and test a structural equation model that will help determine the antecedents and consequences of employees' safety behaviour. For this purpose, the authors carry out an empirical study using a sample of 131 OHSAS 18001-certified organisations located in Spain. The results show that management's commitment, and particularly communication, have an effect on safety behaviour and on safety performance, employee satisfaction, and firm competitiveness. These findings are particularly important for management since they provide evidence about the factors that should be encouraged to reduce risks and improve performance in this type of organisation. Copyright © 2011 Elsevier Ltd. All rights reserved.

Raising occupational safety - an exceptionally important top rank task

Energy Technology Data Exchange (ETDEWEB)

1986-09-01

Comments on the Consulting Meeting on Safety at Work and Fire Prevention in the state association Energetika, held at the Bobov Dol coal mine on 27.7.1986. The main report, submitted by S. Mishev, manager of the state inspectorate, stated that in 1985 working conditions of 1,074 employees improved significantly and the number of accidents among workers was reduced by a coefficient of 1.92 points compared to 1984. Thirty-eight million levs were spent on improving occupational safety (reducing dust, noise and vibration levels). Measures aimed at preventing fires, in particular at the Maritsa-Iztok briquetting plant and in the Babino coal mine were improved significantly (fire-resistant support of mainroads, backfilling and isolation of goaf, application of anti-pyrogens, methane drainage, remote methane control, etc.). The number of annual inspections by safety inspectors has increased to 9,000. Coefficient of absenteeism due to bodily injury has been reduced by 40.57 points. Dust exposure of miners has also been reduced.

Safety balance: Analysis of safety systems

International Nuclear Information System (INIS)

Delage, M.; Giroux, C.

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

49 CFR 593.9 - Effect of affirmative determinations; lists.

Science.gov (United States)

2010-10-01

... TRAFFIC SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) DETERMINATIONS THAT A VEHICLE NOT ORIGINALLY MANUFACTURED TO CONFORM TO THE FEDERAL MOTOR VEHICLE SAFETY STANDARDS IS ELIGIBLE FOR IMPORTATION... grant. (b) The Administrator publishes annually in the Federal Register a list of determinations made...

Comparison of EPRI safety valve test data with analytically determined hydraulic results

International Nuclear Information System (INIS)

Smith, L.C.; Howe, K.S.

1983-01-01

NUREG-0737 (November 1980) and all subsequent U.S. NRC generic follow-up letters require that all operating plant licensees and applicants verify the acceptability of plant specific pressurizer safety valve piping systems for valve operation transients by testing. To aid in this verification process, the Electric Power Research Institute (EPRI) conducted an extensive testing program at the Combustion Engineering Test Facility. Pertinent tests simulating dynamic opening of the safety valves for representative upstream environments were carried out. Different models and sizes of safety valves were tested at the simulated operating conditions. Transducers placed at key points in the system monitored a variety of thermal, hydraulic and structural parameters. From this data, a more complete description of the transient can be made. The EPRI test configuration was analytically modeled using a one-dimensional thermal hydraulic computer program that uses the method of characteristics approach to generate key fluid parameters as a function of space and time. The conservative equations are solved by applying both the implicit and explicit characteristic methods. Unbalanced or wave forces were determined for each straight run of pipe bounded on each side by a turn or elbow. Blowdown forces were included, where appropriate. Several parameters were varied to determine the effects on the pressure, hydraulic forces and timings of events. By comparing these quantities with the experimentally obtained data, an approximate picture of the flow dynamics is arrived at. Two cases in particular are presented. These are the hot and cold loop seal discharge tests made with the Crosby 6M6 spring-loaded safety valve. Included in the paper is a description of the hydraulic code, modeling techniques and assumptions, a comparison of the numerical results with experimental data and a qualitative description of the factors which govern pipe support loading. (orig.)

What Determines the Choice of Tourist Destination? The Case of Denmark

DEFF Research Database (Denmark)

Jensen, Susanne; Svendsen, Gert Tinggaard

2017-01-01

What determines the choice of tourist destination? Based on the comprehensive tourist surveys by VisitDenmark in 2004, 2008 and 2011, we find that both Danes and tourists from countries close to Denmark attach great importance to safety, but it is also important for nationalities such as American...... and Japanese. Furthermore, tourists staying at hotels and youth hostels ascribe less weight to safety than tourists using other accommodation forms. Finally, returning tourists ascribe more weight to safety than first-time tourists.......What determines the choice of tourist destination? Based on the comprehensive tourist surveys by VisitDenmark in 2004, 2008 and 2011, we find that both Danes and tourists from countries close to Denmark attach great importance to safety, but it is also important for nationalities such as Americans...

Determination of performance criteria of safety systems in a nuclear power plant via simulated annealing optimization method

International Nuclear Information System (INIS)

Jung, Woo Sik

1993-02-01

This study presents and efficient methodology that derives design alternatives and performance criteria of safety functions/systems in commercial nuclear power plants. Determination of design alternatives and intermediate-level performance criteria is posed as a reliability allocation problem. The reliability allocation is performed for determination of reliabilities of safety functions/systems from top-level performance criteria. The reliability allocation is a very difficult multi objective optimization problem (MOP) as well as a global optimization problem with many local minima. The weighted Chebyshev norm (WCN) approach in combination with an improved Metropolis algorithm of simulated annealing is developed and applied to the reliability allocation problem. The hierarchy of probabilistic safety criteria (PSC) may consist of three levels, which ranges from the overall top level (e.g., core damage frequency, acute fatality and latent cancer fatality) through the interlnediate level (e.g., unavailiability of safety system/function) to the low level (e.g., unavailability of components, component specifications or human error). In order to determine design alternatives of safety functions/systems and the intermediate-level PSC, the reliability allocation is performed from the top-level PSC. The intermediated level corresponds to an objective space and the top level is related to a risk space. The reliability allocation is performed by means of a concept of two-tier noninferior solutions in the objective and risk spaces within the top-level PSC. In this study, two kinds of towtier noninferior solutions are defined: intolerable intermediate-level PSC and desirable design alternatives of safety functions/systems that are determined from Sets 1 and 2, respectively. Set 1 is obtained by maximizing simultaneously not only safety function/system unavailabilities but also risks. Set 1 reflects safety function/system unavailabilities in the worst case. Hence, the

Using Dominance Analysis to Determine Predictor Importance in Logistic Regression

Science.gov (United States)

Azen, Razia; Traxel, Nicole

2009-01-01

This article proposes an extension of dominance analysis that allows researchers to determine the relative importance of predictors in logistic regression models. Criteria for choosing logistic regression R[superscript 2] analogues were determined and measures were selected that can be used to perform dominance analysis in logistic regression. A…

Outline of the requirements of application of computer based instrumentation and control systems in the systems important to safety on Bohunice NPPs

International Nuclear Information System (INIS)

Bacurik, J.

1997-01-01

The most important regulatory requirements and issues are described related to the review, evaluation and assessment of computer-based safety-related IandC systems, with emphasis on safety instrumentation and control. These aspects include safety classification and categorization of IandC, ranking of applicable codes and standards, design evaluation on the system level, and software assessment. (author)

31 CFR 9.4 - Criteria for determining effects of imports on national security.

Science.gov (United States)

2010-07-01

... imports on national security. 9.4 Section 9.4 Money and Finance: Treasury Office of the Secretary of the Treasury EFFECTS OF IMPORTED ARTICLES ON THE NATIONAL SECURITY § 9.4 Criteria for determining effects of imports on national security. (a) In determining the effect on the national security of imports of the...

Determining Predictor Importance in Hierarchical Linear Models Using Dominance Analysis

Science.gov (United States)

Luo, Wen; Azen, Razia

2013-01-01

Dominance analysis (DA) is a method used to evaluate the relative importance of predictors that was originally proposed for linear regression models. This article proposes an extension of DA that allows researchers to determine the relative importance of predictors in hierarchical linear models (HLM). Commonly used measures of model adequacy in…

Application of a methodology to determine priorities for nuclear power plant safety issues

International Nuclear Information System (INIS)

Daling, P.M.

1988-01-01

The Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) is sponsoring a research program to determine priorities of nuclear power plant safety issues. A methodology has been developed at the Pacific Northwest Laboratory (PNL) to provide technical assistance in the development of risk and cost estimates for implementing resolutions to the safety issues. The information development methods are intended to provide the NRC with a consistent level of information for use in ranking the issues. The NRC uses this information, along with judgmental factors, to rank the issues for further consideration by the NRC staff. The primary purpose of the priority rankings are to assist in the allocation of resources to issues that have high potential for reducing public risk as well as to remove issues from further consideration that have little safety significance

Corporate financial decision-makers' perceptions of workplace safety.

Science.gov (United States)

Huang, Yueng-Hsiang; Leamon, Tom B; Courtney, Theodore K; Chen, Peter Y; DeArmond, Sarah

2007-07-01

This study, through a random national survey, explored how senior financial executives or managers (those who determined high-level budget, resource allocation, and corporate priorities) of medium-to-large companies perceive important workplace safety issues. The three top-rated safety priorities in resource allocation reported by the participants (overexertion, repetitive motion, and bodily reaction) were consistent with the top three perceived causes of workers' compensation losses. The greatest single safety concerns reported were overexertion, repetitive motion, highway accidents, falling on the same level and bodily reaction. A majority of participants believed that the indirect costs associated with workplace injury were higher than the direct costs. Our participants believed that money spent improving workplace safety would have significant returns. The perceived top benefits of an effective workplace safety program were increased productivity, reduced cost, retention, and increased satisfaction among employees. The perceived most important safety modification was safety training. The top reasons senior financial executives gave for believing their safety programs were better than those at other companies were that their companies paid more attention to and emphasized safety, they had better classes and training focused on safety, and they had teams/individuals focused specifically on safety.

Two important safety-related verification tests in the design of Qinshan NPP 600 MWe reactor

International Nuclear Information System (INIS)

Li Pengzhou; Li Tianyong; Yu Danping; Sun Lei

2005-01-01

This paper summarizes two most important verification tests performed in the design of reactor of Qinshan NPP Phase II: seismic qualification test of control rod drive line (CRDL), flow-induced vibration test of reactor internals both in 1:5 scaled model and on-site measurement during heat function testing (HFT). Both qualification tests proved that the structural design of the reactor has large safety margin. (authors)

Tests on instrumentation and control systems important to safety in nuclear power stations. Systempruefung der leittechnischen Einrichtungen des Sicherheitssystems in Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

1985-01-01

The rule applies to the reactor protection system, to the protection and state boundaries, to control devices important to safety, and to danger alarms of the classes S and I. The system inspection of the control devices of the safety system comprises in-service testing and recurrent testing.

Consideration of future safety consequences: a new predictor of employee safety.

Science.gov (United States)

Probst, Tahira M; Graso, Maja; Estrada, Armando X; Greer, Sarah

2013-06-01

Compliance with safety behaviors is often associated with longer term benefits, but may require some short-term sacrifices. This study examines the extent to which consideration of future safety consequences (CFSC) predicts employee safety outcomes. Two field studies were conducted to evaluate the reliability and validity of the newly developed Consideration of Future Safety Consequences (CFSC) scale. Surveys containing the CFSC scale and other measures of safety attitudes, behaviors, and outcomes were administered during working hours to a sample of 128 pulp and paper mill employees; after revising the CFSC scale based on these initial results, follow-up survey data were collected in a second sample of 212 copper miners. In Study I, CFSC was predictive of employee safety knowledge and motivation, compliance, safety citizenship behaviors, accident reporting attitudes and behaviors, and workplace injuries - even after accounting for conscientiousness and demographic variables. Moreover, the effects of CFSC on the variables generally appear to be direct, as opposed to mediated by safety knowledge or motivation. These findings were largely replicated in Study II. CFSC appears to be an important personality construct that may predict those individuals who are more likely to comply with safety rules and have more positive safety outcomes. Future research should examine the longitudinal stability of CFSC to determine the extent to which this construct is a stable trait, rather than a safety attitude amenable to change over time or following an intervention. Copyright © 2013 Elsevier Ltd. All rights reserved.

Safety of nursing staff and determinants of adherence to personal protective equipment.

Science.gov (United States)

Neves, Heliny Carneiro Cunha; Souza, Adenícia Custódia Silva e; Medeiros, Marcelo; Munari, Denize Bouttelet; Ribeiro, Luana Cássia Miranda; Tipple, Anaclara Ferreira Veiga

2011-01-01

A qualitative study conducted in a teaching hospital with 15 nursing professionals. Attempted to analyze the reasons, attitudes and beliefs of nursing staff regarding adherence to personal protective equipment. Data were collected through focus groups, analyzed by the method of interpretation of meanings, considering Rosenstock's model of health beliefs as a reference framework. Data revealed two themes: Occupational safety and Interpersonal Relationship. We identified several barriers that interfere in matters of safety and personal protective equipment, such as communication, work overload, physical structure, accessibility of protective equipment and organizational and management aspects. Adherence to personal protective equipment is determined by the context experienced in the workplace, as well as by individual values and beliefs, but the decision to use the personal protective equipment is individual.

Simplified Model of Safety Determination Process for a Country with its First Operating Nuclear Power Plants

International Nuclear Information System (INIS)

Saud, Bin Khadim; Chung, Dae Wook

2013-01-01

The two inputs are evaluated and given a color designation based on their safety significance. The performance indicators (PIs) in ROP program were developed from a very large statistical basis given operating experience from 100 reactors over a long period of time. The inspection findings are evaluated in terms of changes in core damage frequency using simplified PRA models and in some cases more complex models. The aim of this paper is to develop a simplified risk assessment approach for inspection findings which does not use PRA directly, but may use direct calculation approach. Thus, it would be helpful for inspectors to determine the safety significance of inspection findings. The objective of this study was to develop a simplified risk assessment approach for inspection findings using direct risk calculation model to determine the safety significance. Risk and categorization scheme are developed to put inspection finding into corresponding ΔCDF category

Simplified Model of Safety Determination Process for a Country with its First Operating Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Saud, Bin Khadim [Korea Advance Institute of Science and Technology, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

The two inputs are evaluated and given a color designation based on their safety significance. The performance indicators (PIs) in ROP program were developed from a very large statistical basis given operating experience from 100 reactors over a long period of time. The inspection findings are evaluated in terms of changes in core damage frequency using simplified PRA models and in some cases more complex models. The aim of this paper is to develop a simplified risk assessment approach for inspection findings which does not use PRA directly, but may use direct calculation approach. Thus, it would be helpful for inspectors to determine the safety significance of inspection findings. The objective of this study was to develop a simplified risk assessment approach for inspection findings using direct risk calculation model to determine the safety significance. Risk and categorization scheme are developed to put inspection finding into corresponding ΔCDF category.

Occupational safety motivation

DEFF Research Database (Denmark)

Pedersen, Louise; Kines, Pete

2010-01-01

Background: Motivation is one of the most important factors for safety behaviour and for implementing change in general. However, theoretical and psychometric studies of safety performance have traditionally treated safety motivation, safety compliance and safety participation unidimensionally....... At the same time many motivation questionnaire items are seldom founded on theory and/or do not account for the theories’ ontological and epistemological differences, e.g. of how knowledge, attitude and action are related. Present questionnaire items tap into occupational safety motivation in asking whether...... or not respondents ‘are’ motivated and whether they feel that safety is important or worthwhile. Another important aspect is ‘what’ motivates workers to comply to and participate in safety. The aim of this article is to introduce a new theory-based occupational safety motivation scale which is validated...

OPG waterways public safety program

Energy Technology Data Exchange (ETDEWEB)

Bennett, T [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

2009-07-01

Ontario Power Generation (OPG) has 64 hydroelectric generating stations, 241 dams, and 109 dams in Ontario's registry with the International Commission on Large Dams (ICOLD). In 1986, it launched a formal dam safety program. This presentation addressed the importance of public safety around dams. The safety measures are timely because of increasing public interaction around dams; the public's unawareness of hazards; public interest in extreme sports; easier access by recreational vehicles; the perceived right of public to access sites; and the remote operation of hydroelectric stations. The presentation outlined the OPG managed system approach, with particular reference to governance; principles; standards and procedures; and aspects of implementation. Specific guidelines and governing documents for public safety around dams were identified, including guidelines for public safety of waterways; booms and buoys; audible warning devices and lights; public safety signage; fencing and barricades; and risk assessment for public safety around waterways. The presentation concluded with a discussion of audits and management reviews to determine if safety objectives and targets have been met. figs.

SKB 91. Final disposal of spent nuclear fuel. Importance of the bedrock for safety

International Nuclear Information System (INIS)

1992-05-01

The safety of a deep repository for spent nuclear fuel has been assessed in this report. The spent fuel is assumed to be encapsulated in a copper canister and deposited at a depth of 600 m in the bedrock. The primary purpose has been to shed light on the importance of the geological features of the site for the safety of a final repository. The assessment shows that the encapsulated fuel will, in all likelihood, be kept isolated from the groundwater for millions of years. This is considerably longer than the more than 100 000 years that are required in order for the toxicity of the waste to have declined to a level equivalent to that of rich uranium ores. However, in order to be able to study the role of the rock as a barrier to the dispersal of radioactive materials, calculations have been carried out under the assumption that waste canisters leak. The results show that the safety of a carefully designed repository is only affected to a small extent by the ability of the rock to retain the escaping radionuclides. The primary role of the rock is to provide stable mechanical and chemical conditions in the repository over a long period of time so that the function of the engineered barriers is not jeopardized. (187 refs.) (au)

10 CFR 50.49 - Environmental qualification of electric equipment important to safety for nuclear power plants.

Science.gov (United States)

2010-01-01

... important to safety for nuclear power plants. 50.49 Section 50.49 Energy NUCLEAR REGULATORY COMMISSION... nuclear power plants. (a) Each holder of or an applicant for an operating license issued under this part... nuclear power plant for which the certifications required under § 50.82(a)(1) or § 52.110(a)(1) of this...

76 FR 13643 - FDA Food Safety Modernization Act: Title III-A New Paradigm for Importers; Public Meeting

Science.gov (United States)

2011-03-14

... Act: Title III--A New Paradigm for Importers; Public Meeting AGENCY: Food and Drug Administration, HHS... announcing a public meeting entitled ``FDA Food Safety Modernization Act: Title III--A New Paradigm for... provided. Request special accommodations due By March 22, 2011.... Patricia M. Kuntze, 301- to disability...

Safety review of experiments at Albuquerque Operations Office

International Nuclear Information System (INIS)

Elliott, K.

1984-01-01

The Department of Energy (DOE) Albuquerque Operations Office is responsible for the safety overview of nuclear reactor and critical assembly facilities at Sandia National Laboratories, Los Alamos National Laboratory, and the Rocky Flats Plant. The important safety concerns with these facilities involve the complex experiments that are performed, and that is the area emphasized. A determination is made by the Albuquerque Office (AL) with assistance from DOE/OMA whether or not a proposed experiment is an unreviewed safety question. Meetings are held with the contractor to resolve and clarify questions that are generated during the review of the proposed experiment. The AL safety evaluation report is completed and any recommendations are discussed. Prior to the experiment a preoperational appraisal is performed to assure that personnel, procedures, and equipment are in readiness for operations. During the experiment, any abnormal condition is reviewed in detail to determine any safety concerns

Safety in times of crises - the importance of industrial emergency plans

International Nuclear Information System (INIS)

Rademacher, H.; Schulten, R.

1989-01-01

Technical and organizational precautions cannot always avoid everyday risks such as accidents, fire, explosions, and other critical situations which without appropriate countermeasures can easily develop into emergencies. While in recent years considerable efforts have been going into improving the technical safety of industrial plants particularly susceptible to accidents (e.g. the nuclear and chemical industry), organizational safety seems to have been neglected. An analysis of different accidents reveals human fallibility rather than technical failures to be causing damage in many cases. Industrial emergency plans are considered to be contributing to the improvement of organizational safety. (orig.) [de

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

Science.gov (United States)

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

2014-07-01

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

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

OpenAIRE

Vladimir Malbasic; Lazar Stojanovic

2018-01-01

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 protecte...

Chemical Hazards and Safety Issues in Fusion Safety Design

International Nuclear Information System (INIS)

Cadwallader, L.C.

2003-01-01

Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

76 FR 29286 - Culturally Significant Objects Imported for Exhibition Determinations: “Pissarro's People”

Science.gov (United States)

2011-05-20

... DEPARTMENT OF STATE [Public Notice 7462] Culturally Significant Objects Imported for Exhibition Determinations: ``Pissarro's People'' SUMMARY: Notice is hereby given of the following determinations: Pursuant... the exhibition ``Pissarro's People,'' imported from abroad for temporary exhibition within the United...

Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals: 2007 update

International Nuclear Information System (INIS)

2007-06-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1119 documents ageing assessment and management practices for PWR Reactor Vessel Internals (RVIs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. irradiation assisted stress corrosion cracking (IASCC) of baffle-former bolts, which threatened the integrity of the vessel internals. In addition, concern of fretting wear of control rod guide tubes has been raised in Japan. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1119 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update relevant sections of the existing IAEA-TECDOC- 1119 in order to provide current ageing management guidance for PWR RVIs to all involved in the operation and regulation of PWRs and thus to help ensure PWR safety in IAEA Member States throughout their entire service life

Evaluating software for safety systems in nuclear power plants

International Nuclear Information System (INIS)

Lawrence, J.D.; Persons, W.L.; Preckshot, G.G.; Gallagher, J.

1994-01-01

In 1991, LLNL was asked by the NRC to provide technical assistance in various aspects of computer technology that apply to computer-based reactor protection systems. This has involved the review of safety aspects of new reactor designs and the provision of technical advice on the use of computer technology in systems important to reactor safety. The latter includes determining and documenting state-of-the-art subjects that require regulatory involvement by the NRC because of their importance in the development and implementation of digital computer safety systems. These subjects include data communications, formal methods, testing, software hazards analysis, verification and validation, computer security, performance, software complexity and others. One topic software reliability and safety is the subject of this paper

The importance for nuclear safety of efficient feedback of operational experience

International Nuclear Information System (INIS)

1987-09-01

Experience of practical operation is a valuable source of information for improving and optimizing the safety and reliability of nuclear power plants. Therefore it is essential to collect information on abnormal events occurring at plants during operation and on all deviations from normal performance by systems and personnel that could be precursors of accidents. For this purpose it is necessary to establish hierarchical systems to feedback operational safety experience at utility, national and international levels and to make these systems as effective as possible. The present report attempts to identify the safety objectives of these systems, to analyse the difficulties presently encountered and to suggest possible improvements

Safety assessment for the 118-B-1 Burial Ground excavation treatability tests. Revision 2

International Nuclear Information System (INIS)

Zimmer, J.J.; Frain, J.M.

1994-12-01

This revision of the Safety Assessment provides an auditable safety analysis of the hazards for the proposed treatability test activities per DOE-EM-STD-5502-94, DOE Limited Standard, Hazard Baseline Documentation (DOE 1994). The proposed activities are classified as radiological activities and as such, no longer require Operational Safety Limits (OSLs). The OSLS, Prudent Actions, and Institutional and Organization Controls have been removed from this revision and replaced with ''Administrative Actions Important to Safety,'' as determined by the hazards analysis. Those Administrative Actions Important to Safety are summarized in Section 1.1, ''Assessment Summary.''

Determination of Causality between Remittance and Import: Evidence from Bangladesh

Directory of Open Access Journals (Sweden)

Dewan Muktadir-Al-Mukit

2013-07-01

Full Text Available This study investigates the relationship between remittance and import for the economy of Bangladesh. The study used different econometric techniques of measuring the long and short term relationship between variables. The Johansen Cointegration test is used to determine the existence of a long term relationships between study variables. The normalized Cointegrating coefficients are found statistically significant and show a stable and positive relationship between study variables. Our Granger causality analysis suggests the existence of a unidirectional causality running from import to remittance. This confirms that remittances have no significant impact on the demand for imported goods rather import exerts a positive shock on the remittance of Bangladesh.

Selection of important initiating events for Level 1 probabilistic safety assessment study at Puspati TRIGA Reactor

International Nuclear Information System (INIS)

Maskin, M.; Charlie, F.; Hassan, A.; Prak Tom, P.; Ramli, Z.; Mohamed, F.

2016-01-01

Highlights: • Identifying possible important initiating events (IEs) for Level 1 probabilistic safety assessment performed on research nuclear reactor. • Methods in screening and grouping IEs are addressed. • Focusing only on internal IEs due to random failures of components. - Abstract: This paper attempts to present the results in identifying possible important initiating events (IEs) as comprehensive as possible to be applied in the development of Level-1 probabilistic safety assessment (PSA) study. This involves the approaches in listing and the methods in screening and grouping IEs, by focusing only on the internal IEs due to random failures of components and human errors with full power operational conditions and reactor core as the radioactivity source. Five approaches were applied in listing the IEs and each step of the methodology was described and commented. The criteria in screening and grouping the IEs were also presented. The results provided the information on how the Malaysian PSA team applied the approaches in selecting the most probable IEs as complete as possible in order to ensure the set of IEs was identified systematically and as representative as possible, hence providing confidence to the completeness of the PSA study. This study is perhaps one of the first to address classic comprehensive steps in identifying important IEs to be used in a Level-1 PSA study.

Solubility limits of importance to leaching

International Nuclear Information System (INIS)

Ogard, A.; Bentley, G.; Bryant, E.; Duffy, C.; Grisham, J.; Norris, E.; Orth, C.; Thomas, K.

1981-01-01

The solubilities of some radionuclides, especially rare earths and actinides, may be an important and controlling factor in leaching of waste forms. These solubilities should be measured accurately as a function of pH and not as a part of a multicomponent system. Individual solubilities should be measured as a function of temperature to determine if a kinetic effect is being observed in the data. A negative temperature coefficient of solubility for actinides and rare earths in water would have important consequences for nuclear reactor safety and for the management of nuclear wastes

Upgrade in the CNSNS of the determination process about the importance for the impact evaluation to the safety of defaults or violations in the national nuclear facilities; Actualizacion en la CNSNS del proceso de determinacion de la importancia para la evaluacion de impacto a la seguridad de incumplimientos o violaciones en las instalaciones nucleares mexicanas

Energy Technology Data Exchange (ETDEWEB)

Espinosa V, J. M.; Jauregui Ch, V., E-mail: jmespinosa@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2014-10-15

Inside the process of Impact Evaluation to the Safety of the Direccion General Adjunta de Seguridad Nuclear of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the Significance Determination Process (SDP) is used, developed by the United States Nuclear Regulatory Commission (US NRC), to evaluate the violations or defaults to the regulatory framework and to determine its importance to the risk by means of a fixed color: Green (Very low impact to the safety), White (Low impact to moderate to the safety), Yellow (Substantial impact to the safety) or Red (High impact to the safety). All this inside the seven safety foundations of the Reactor Oversight Process: Initiator Events, Mitigation Systems, Integrity of the Barriers, Preparation for Emergencies, Occupational Radiological Safety, Radiological Safety of the Public and Physical Safety. At present the US NRC has developed a new version of the SDP, which presents changes in its structure and the opportunity of carrying out informed evaluations in risk, with more detail about the violations or defaults that happen in different areas. The CNSNS carries out the adaptation of this last version of the SDP in order to have an updated tool for the violations and defaults characterization to the regulatory framework happened in the nuclear power plant of Laguna Verde. In this article is mentioned the legal framework that confers the CNSNS the attributions to impose urgency measures and administrative sanctions to its licensees, also is established the definition of the different colors that the SDP contemplates in function of the increased risk (ΔCdf), a description of the SDP objectives and the elements that conform it is presented, in the same way some examples to illustrate its application are raised. Finally, the steps to continue for their implementation are mentioned. (Author)

How the choice of safety performance function affects the identification of important crash prediction variables.

Science.gov (United States)

Wang, Ketong; Simandl, Jenna K; Porter, Michael D; Graettinger, Andrew J; Smith, Randy K

2016-03-01

Across the nation, researchers and transportation engineers are developing safety performance functions (SPFs) to predict crash rates and develop crash modification factors to improve traffic safety at roadway segments and intersections. Generalized linear models (GLMs), such as Poisson or negative binomial regression, are most commonly used to develop SPFs with annual average daily traffic as the primary roadway characteristic to predict crashes. However, while more complex to interpret, data mining models such as boosted regression trees have improved upon GLMs crash prediction performance due to their ability to handle more data characteristics, accommodate non-linearities, and include interaction effects between the characteristics. An intersection data inventory of 36 safety relevant parameters for three- and four-legged non-signalized intersections along state routes in Alabama was used to study the importance of intersection characteristics on crash rate and the interaction effects between key characteristics. Four different SPFs were investigated and compared: Poisson regression, negative binomial regression, regularized generalized linear model, and boosted regression trees. The models did not agree on which intersection characteristics were most related to the crash rate. The boosted regression tree model significantly outperformed the other models and identified several intersection characteristics as having strong interaction effects. Copyright © 2015 Elsevier Ltd. All rights reserved.

Methods and Effects of Safety Enhancement in Korean PSR

International Nuclear Information System (INIS)

Kim, Young Gab; Park, Jong Woon

2009-01-01

Periodic Safety Review (PSR) is a comprehensive study on a nuclear power plant safety, taking into account aspects such as operational history, ageing, safety analyses and advances in code and standards since the time of construction. In Korea, PSRs have been performed for 20 units and have been effectively used to obtain an overall view of actual plant safety to determine reasonable and practical modifications that should be made in order to obtain a higher level of safety approaching that of modern plants. Among many safety enhancements achieved from Korean PSRs, new safety analyses are the important methods to confirm plant safety by increasing safety margin for specific safety issues. Methods and effects of safety enhancements applied in Korean PSRs are reviewed in this paper in light of new safety analyses to obtain additional safety margins

Changing An Electrical Safety Culture - The Importance of Understanding Why.

Energy Technology Data Exchange (ETDEWEB)

Waters, Richard Thomas [Idaho National Laboratory

2015-12-01

Abstract – Electrical workers, regardless of experience, are faced with a major barrier when first introduced to NFPA 70E, “The Standard for Electrical Safety in the Workplace,” and an erroneous electrical safety culture pre-exists. This paper describes, from the author’s point of view, the barrier that he and other electrical workers have experienced and his insight into overcoming the barrier. The author in conclusion will present a series of techniques that can be used to assist other electrical workers in overcoming the barrier.

Auto Safety

Science.gov (United States)

... Safe Videos for Educators Search English Español Auto Safety KidsHealth / For Parents / Auto Safety What's in this ... by teaching some basic rules. Importance of Child Safety Seats Using a child safety seat (car seat) ...

Simplified probabilistic approach to determine safety factors in deterministic flaw acceptance criteria

International Nuclear Information System (INIS)

Barthelet, B.; Ardillon, E.

1997-01-01

The flaw acceptance rules in nuclear components rely on deterministic criteria supposed to ensure the safe operating of plants. The interest of having a reliable method of evaluating the safety margins and the integrity of components led Electricite de France to launch a study to link safety factors with requested reliability. A simplified analytical probabilistic approach is developed to analyse the failure risk in Fracture Mechanics. Assuming lognormal distributions of the main random variables, it is possible considering a simple Linear Elastic Fracture Mechanics model, to determine the failure probability as a function of mean values and logarithmic standard deviations. The 'design' failure point can be analytically calculated. Partial safety factors on the main variables (stress, crack size, material toughness) are obtained in relation with reliability target values. The approach is generalized to elastic plastic Fracture Mechanics (piping) by fitting J as a power law function of stress, crack size and yield strength. The simplified approach is validated by detailed probabilistic computations with PROBAN computer program. Assuming reasonable coefficients of variations (logarithmic standard deviations), the method helps to calibrate safety factors for different components taking into account reliability target values in normal, emergency and faulted conditions. Statistical data for the mechanical properties of the main basic materials complement the study. The work involves laboratory results and manufacture data. The results of this study are discussed within a working group of the French in service inspection code RSE-M. (authors)

The importance of spatial orientation and knowledge of traffic signs for children's traffic safety.

Science.gov (United States)

Trifunović, Aleksandar; Pešić, Dalibor; Čičević, Svetlana; Antić, Boris

2017-05-01

Pre-school children, as well as children from lower grades in primary school, who although rarely, completely independently participate in traffic, represent a vulnerable population from the standpoint of traffic safety. The greatest number of children were injured or killed in road traffic crashes on their way from home to kindergarten or school. Mostly due to lack of experience, children's behavior is confusing and often reckless and hasty. Safe behavior in the traffic environment demands certain cognitive skills. Unlike adults, children have less than fully developed peripheral vision. Also, changes occur in color perception, i.e. discrimination. All this leads to the conclusion that the stage of physical and mental development of the child is very important for safe participation in traffic. So, to estimate if they are sufficiently equipped to participate safely in traffic, a sensitive test for young children that may be suitable for their level of cognitive development is required. Accordingly, road safety education should be arranged in such a way that considers the child's level of development, as has been shown to be more effective when started at younger ages. Play is the most natural and easiest way of learning because it is the lens through which children experience their world, and the world of others. Having this in mind, if we want to measure the abilities of a child, and their preparedness for safety participation in traffic, unavoidable is to use non-verbal tests. The purpose of this study is to explore primary schooler's spatial, and abilities of color perception and memorization, as well as their performances in interpreting the meaning of traffic signs. In addition, neighborhood environmental correlates (rural-urban) and possible individual differences influences on the relationship among these abilities was examined. Knowledge about these factors affecting children's safety can be applied to improve relevant intervention measures for promoting

Assessment and management of ageing of major nuclear power plant components important to safety: PWR pressure vessels. 2007 update

International Nuclear Information System (INIS)

2007-06-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1120 documented ageing assessment and management practices for pressurized water reactor (PWR) reactor pressure vessels (RPVs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. primary water stress corrosion cracking (PWSCC) of Alloy 600 control rod drive mechanism (CRDM) penetrations and boric acid corrosion/wastage of RPV heads, which threatened the integrity of the RPV heads. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1120 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update IAEA-TECDOC-1120 in order to provide current ageing management guidance for PWR RPVs to all involved in the operation and regulation of PWRs and thus to help ensure PWR RPV integrity in IAEA Member States throughout their entire service life

Prevalence and determinants of non-standard motorcycle safety helmets amongst food delivery workers in Selangor and Kuala Lumpur.

Science.gov (United States)

Kulanthayan, S; See, Lai Git; Kaviyarasu, Y; Nor Afiah, M Z

2012-05-01

Almost half of the global traffic crashes involve vulnerable groups such as pedestrian, cyclists and two-wheeler users. The main objective of this study was to determine the factors that influence standard of the safety helmets used amongst food delivery workers by presence of Standard and Industrial Research Institute of Malaysia (SIRIM) certification label. A cross sectional study was conducted amongst 150 food delivery workers from fast food outlets in the vicinity of Selangor and Kuala Lumpur. During observation, safety helmets were classified as standard safety helmet in the presence of SIRIM label and non-standard in the absence of the label. They were approached for questionnaire participation once consent was obtained and were requested to exchange their safety helmet voluntarily with a new one after the interview. Data analysis was carried out using SPSS. Chi square and logistic regression analysis was applied to determine the significance and odds ratio of the variables studied, respectively (penetration test, age, education level, knowledge, crash history, types of safety helmet, marital status and years of riding experience) against the presence of SIRIM label. The response rate for this study was 85.2%. The prevalence of non-standard helmets use amongst fast food delivery workers was 55.3%. Safety helmets that failed the penetration test had higher odds of being non-standard helmets compared with safety helmets passing the test. Types of safety helmet indicated half-shell safety helmets had higher odds to be non-standard safety helmets compared to full-shell safety helmets. Riders with more years of riding experience were in high odds of wearing non-standard safety helmets compared to riders with less riding experience. Non-standard (non-SIRIM approved) helmets were more likely to be half-shell helmets, were more likely to fail the standards penetration test, and were more likely to be worn by older, more experienced riders. The implications of these

Safety leadership at construction sites: the importance of rule-oriented and participative leadership.

Science.gov (United States)

Grill, Martin; Pousette, Anders; Nielsen, Kent; Grytnes, Regine; Törner, Marianne

2017-07-01

Objectives The construction industry accounted for >20% of all fatal occupational accidents in Europe in 2014. Leadership is an essential antecedent to occupational safety. The aim of the present study was to assess the influence of transformational, active transactional, rule-oriented, participative, and laissez-faire leadership on safety climate, safety behavior, and accidents in the Swedish and Danish construction industry. Sweden and Denmark are similar countries but have a large difference in occupational accidents rates. Methods A questionnaire study was conducted among a random sample of construction workers in both countries: 811 construction workers from 85 sites responded, resulting in site and individual response rates of 73% and 64%, respectively. Results The results indicated that transformational, active transactional, rule-oriented and participative leadership predict positive safety outcomes, and laissez-faire leadership predict negative safety outcomes. For example, rule-oriented leadership predicts a superior safety climate (β=0.40, Pleadership on workers' safety behavior was moderated by the level of participative leadership (β=0.10, Pleadership behaviors on safety outcomes were largely similar in Sweden and Denmark. Rule-oriented and participative leadership were more common in the Swedish than Danish construction industry, which may partly explain the difference in occupational accident rates. Conclusions Applying less laissez-faire leadership and more transformational, active transactional, participative and rule-oriented leadership appears to be an effective way for construction site managers to improve occupational safety in the industry.

New radiation protection concept as important safety factor of industrial radiography

International Nuclear Information System (INIS)

Pavlovic, R.; Pavlovic, S.

1998-01-01

Industrial radiography is a method for non destructive testing of homogeneity of various materials based on different absorption of radiation in different material. X and γ radiation are the most often used. Detrimental effects of radiation are observed since its discovery. In order to prevent harmful effects of radiation without unduly limitations of its use, International Commission on Radiological Protection in collaboration with International Atomic Energy Agency have developed International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, Safety Series No 115, adopted in 1996. based on ICRP recommendations from 1991. Besides a lot of changes in radiation protection concept and philosophy, decrement of annual dose limits for occupational exposure from 50 to 20 mSv. (author)

Assessment and management of ageing of major nuclear power plant components important to safety: Metal components of BWR containment systems

International Nuclear Information System (INIS)

2000-10-01

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

Enhancing NPP Safety Through an Effective Dependability Management

Energy Technology Data Exchange (ETDEWEB)

Vieru, G., E-mail: g_vieru@yahoo.com [AREN, Bucharest (Romania)

2014-10-15

Taking into account the importance of the continuous improvement of the performance and reliability of a NPP and practical measures to strengthen nuclear safety and security, it is to be noted that a good management for a nuclear power reactor involves a ''good dependability management'' of the activities, such as: Reliability, Availability, Maintainability (RAM) and maintenance support. In order to evaluate certain safety assessment criteria intended to be applied at the level of the nuclear reactor unit management, equipment dependability indicators and their impact over the availability and reactor safety have to be evaluated. Reactor equipment dependability indicators provide a quantitative indication of equipment RAM performances (Reliability, Availability and Maintenance). One of the important benefits of maintenance and failure data gathering is that it can be used as a support of probabilistic safety assessment (PSA). Also, a good dependability management implementation may be used to complement reactor level unit performance indicators in the field of safe operation, maintenance and improving operating parameters, as well as for Strengthening Safety and Improving Reliability of a NPP. This paper underlines the importance of nuclear safety and security as prerequisites for nuclear power. In addition, it demonstrates how different technical aspects, through implementation of a good dependability management, contribute to a strengthened safety and an improvement of availability of the NPP through dependability indicators determination and evaluation. (author)

Formal Safety versus Real Safety: Quantitative and Qualitative Approaches to Safety Culture – Evidence from Estonia

Directory of Open Access Journals (Sweden)

Järvis Marina

2016-10-01

Full Text Available This paper examines differences between formal safety and real safety in Estonian small and medium-sized enterprises. The results reveal key issues in safety culture assessment. Statistical analysis of safety culture questionnaires showed many organisations with an outstanding safety culture and positive safety attitudes. However, qualitative data indicated some important safety weaknesses and aspects that should be included in the process of evaluation of safety culture in organisations.

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

International Nuclear Information System (INIS)

Apostolakis, George; Weil, Rick

2001-01-01

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

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators. 2011 Update

International Nuclear Information System (INIS)

2011-11-01

At present there are over four hundred forty operational nuclear power plants (NPPs) in IAEA Member States. Ageing degradation of the systems, structures of components during their operational life must be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This IAEA-TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuteriumuranium (CANDU) reactor, boiling water reactor (BWR), pressurized water reactor (PWR), and water moderated, water cooled energy reactor (WWER) plants are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life cycle management of the plant components, which involves the integration of ageing management and economic planning. The target audience of the reports consists of technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present publication is the steam

Framework for continuous assessment and improvement of occupational health and safety issues in construction companies.

Science.gov (United States)

Mahmoudi, Shahram; Ghasemi, Fakhradin; Mohammadfam, Iraj; Soleimani, Esmaeil

2014-09-01

Construction industry is among the most hazardous industries, and needs a comprehensive and simple-to-administer tool to continuously assess and promote its health and safety performance. Through the study of various standard systems (mainly Health, Safety, and Environment Management System; Occupational Health and Safety Assessment Series 180001; and British Standard, occupational health and safety management systems-Guide 8800), seven main elements were determined for the desired framework, and then, by reviewing literature, factors affecting these main elements were determined. The relative importance of each element and its related factors was calculated at organizational and project levels. The provided framework was then implemented in three construction companies, and results were compared together. THE RESULTS OF THE STUDY SHOW THAT THE RELATIVE IMPORTANCE OF THE MAIN ELEMENTS AND THEIR RELATED FACTORS DIFFER BETWEEN ORGANIZATIONAL AND PROJECT LEVELS: leadership and commitment are the most important elements at the organization level, whereas risk assessment and management are most important at the project level. The present study demonstrated that the framework is easy to administer, and by interpreting the results, the main factors leading to the present condition of companies can be determined.

Zolpidem and traffic safety - the importance of treatment compliance.

Science.gov (United States)

Verster, Joris C; Volkerts, Edmund R; Olivier, Berend; Johnson, William; Liddicoat, Laura

2007-09-01

Zolpidem is among the most frequently prescribed hypnotic drugs for those who suffer from insomnia. Recent media reports drew attention to driving impairment after zolpidem misuse. This review summarizes the available data on the effects of recommended use and misuse of zolpidem on driving ability and traffic safety. Both experimental studies and roadside evidence were taken into account. From these studies it must be concluded that patients should fully comply with the prescription instructions of zolpidem, i.e. to take the medication just prior to a full 8 hours of uninterrupted sleep. If this strategy is adopted, zolpidem is a safe alternative to benzodiazpine hypnotics and zopiclone who do show significant driving impairment the morning following bedtime administration. However, to ensure traffic safety higher dosages than recommended (10 mg) or allowing less than 8 hours between zolpidem intake and actual operation of a motor vehicle should be avoided.

77 FR 39613 - Presidential Determination on a U.S. Export Import Bank Transaction with Vietnam

Science.gov (United States)

2012-07-03

... the Export Import Bank of the United States to extend a loan in the amount of approximately $125,870...-10 of June 25, 2012--Presidential Determination on a U.S. Export-Import Bank Transaction With Vietnam... Determination No. 2012-10 of June 25, 2012 Presidential Determination on a U.S. Export Import Bank Transaction...

The Safety of Transnational Imported Second-Hand Cars: A Case Study on Vehicle-to-Vehicle Crashes in Romania

Directory of Open Access Journals (Sweden)

Anatolie Coșciug

2017-12-01

Full Text Available Certain features of imported second-hand cars (e.g., age, degree of wear and tear, technical design can increase their likelihood for traffic crashes. Three official datasets which cover an eight year period (2008–2015 are used to test the connection between importation of second-hand cars and different types of traffic crashes. The traffic crashes database was provided by the Traffic Department of the General Inspectorate of Romanian Police (GIRPTD. The car registration database was provided by Driving-License and Vehicles-Registration Direction (DLVRD. Right-hand driving (RHD cars database was provided by the Romanian Automotive Registry (RAR. A spatio-temporal visualization of data was performed using Geographic Information System (GIS while for the statistical analysis we use regression models and Pearson-Correlation-coefficient. The analysis suggests that a significant part of the variation in the volume of traffic accidents can be explained by the volume of imported second-hand cars at the county level. Moreover, an even stronger direct relation exists between the number of imported second-hand cars and Severe Traffic Accidents but also in the case of RHD imported second-hand cars. The overall impact of imported second-hand cars on the traffic safety in Romania is significant but small in comparison to other types of car registration. Study results belong to the category of empirical evidence production which can improve the quality of existing traffic regulations focused both on organizing and ensuring traffic safety, and on the policy of sustainable transport infrastructure development.

Determinants of import demand for non-renewable energy (petroleum) products: Empirical evidence from Nigeria

International Nuclear Information System (INIS)

Adewuyi, Adeolu O.

2016-01-01

This study estimated determinants of import demand for refined petroleum products in Nigeria for the period 1984–2013. It employed the autoregressive distributed lag (ARDL) bounds test cointegration method and analysed both long-run and short-run determinants of import demand for total and specific petroleum products. In the long-run, aggregate and sectoral incomes are significant determinants of import of refined kerosene. Further, real effective exchange rate (REER), aggregate income (GDP), manufacturing sector's income, domestic energy production (DEP) and population growth rate (PGR) are drivers of import of refined motor spirit Moreover, REER, DEP and manufacturing sector's income are propellers of import of refined distillate fuel. Also, REER and total output of petroleum products are major drivers of total import of refined petroleum products. Short-run results show that previous period GDP, PGR and manufacturing and service sectors' incomes are determinants of import demand for refined kerosene. Moreover, REER, GDP, previous PGR and manufacturing sector's income exert significant effects on the import of refined motor spirit. Further, significant effects of REER, DEP, previous PGR, domestic output of the product and manufacturing and service sectors' incomes on the import demand for distillate fuel were found. Policy implications of the foregoing are articulated in the paper. - Highlights: •Long-run and short-run drivers of import demand for petroleum products were estimated. •kerosene import is income elastic, gasoline import is income and relative price inelastic. •Exchange rate policies may have diverse effects on import of various petroleum product. •Expanding market size has implication for import demand for petroleum product varieties. •Import demand for petroleum products responds differently to various sectoral incomes.

The importance of proper shoe gear and safety stirrups in the prevention of equestrian foot injuries.

Science.gov (United States)

Ceroni, Dimitri; De Rosa, Vicenzo; De Coulon, Geraldo; Kaelin, André

2007-01-01

The aim of this study was to compile specific foot injuries occurring in pediatric patients that result from equestrian sports and to highlight the importance of wearing adequate riding boots to protect the feet. During a 12-year period, 258 children were admitted to Children's Hospital of Geneva for injuries resulting from horseback riding. Amongst these children, 8 sustained foot lesions that required hospital admission. Four children had compression-type fractures of the cuboid (nutcracker fracture of the cuboid) associated with other complex midfoot fractures, 2 had Lisfranc fracture dislocations, 1 had a fracture of the talus with associated intern malleolar fracture, and the last had a fracture of the 5 metatarsals with lateral displacement. All the noted lesions complied with the same traumatic mechanisms. The horse fell on the patient, and the child's foot, entrapped in the stirrup, was caught in between the animal and the ground. The forefoot was bent by indirect violence in abduction by the stirrup, which acted as a fulcrum. Serious foot injuries may occur in children during equestrian activities. These lesions may be very disabling. Therefore, it is important for doctors, instructors, and parents to promote the use of appropriate safety equipment, including strengthened riding boots and safety stirrups.

Importance of the neutron spectrum for determination of radiation damage

International Nuclear Information System (INIS)

Hehn, G.; Stiller, P.; Mattes, M.

1977-01-01

Since the radiation effects of neutrons depend strongly on the neutron energy, the correlation between the induced damage and the fluence of the fast neutrons shows appreciable disadvantages. The measured values of changes in material properties resulted in large differences for the same fast neutron fluence, being partly due to different neutron spectra. The uncertainties in damage data led to strong overdesign of important structural components. Different neutron environment at surveillance sample position may give an underestimation of the embrittlement in the reactor pressure vessel, which has to be avoided. The application of damage functions combined with accurately calculated neutron spectra, promise to be a reasonable solution. The damage function has the advantage of a phenomenological quantity that all spectral effects are included. But the correlation quantity has to be determined of high experimental costs. Therefore approximations of its energy distributions are very important. For the keV energy region the kerma function is reasonably good. For the MeV energy region a higher effort is needed to calculate the displacement cross section. The same holds for the low energy part. In all three parts the formation of stable material property levels may vary, so that the final correlation can be determined only by measurements of material properties in different neutron spectra. In material samples the spectra distribution of the displacement production rate was determined at different local positions outside the reactor core of a PWR and a fast breeder showing the most important energy regions of both reactors. (orig.) [de

Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

International Nuclear Information System (INIS)

Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

2001-01-01

Safety culture is the perception of each individual and organization of a nuclear power plant that safety is the first priority, and at Tokyo Electric Power Company (TEPCO), we have been practicing it in everyday activities. On the other hand, with the demand for competitiveness of nuclear power becoming even more intense these days, we need to pursue efficient management while maintaining the safety level at the same time. Below, we discuss how to achieve compatibility between safety culture and efficient management as well as enhance safety culture. Discussion at Tepco: safety culture-nurturing activities such as the following are being implemented: 1. informing the employees of the 'Declaration of Safety Promotion' by handing out brochures and posting it on the intranet home page; 2. publishing safety culture reports covering stories on safety culture of other industry sectors, recent movements on safety culture, etc.; 3. conducting periodic questionnaires to employees to grasp how deeply safety culture is being established; 4. carrying out educational programs to learn from past cases inside and outside the nuclear industry; 5. committing to common ownership of information with the public. The current status of safety culture in Japan sometimes seems to be biased to the quest of ultimate safety; rephrasing it, there have been few discussions regarding the sufficiency of the quantitative safety level in conjunction with the safety culture. Safety culture is one of the most crucial foundations guaranteeing the plant's safety, and for example, the plant safety level evaluated by probabilistic safety assessment (PSA) could be said to be valid only on the ground that a sound and sufficient safety culture exists. Although there is no doubt that the safety culture is a fundamental and important attitude of an individual and organization that keeps safety the first priority, the safety culture in itself should not be considered an obstruction to efforts to implement

78 FR 4972 - Culturally Significant Objects Imported for Exhibition Determinations: “Chagall: Beyond Color”

Science.gov (United States)

2013-01-23

... DEPARTMENT OF STATE [Public Notice 8158] Culturally Significant Objects Imported for Exhibition Determinations: ``Chagall: Beyond Color'' SUMMARY: Notice is hereby given of the following determinations... Color,'' imported from abroad for temporary exhibition within the United States, are of cultural...

75 FR 71133 - Guidance for Industry: The Safety of Imported Traditional Pottery Intended for Use With Food and...

Science.gov (United States)

2010-11-22

... Nutrition (HFS-317), Food and Drug Administration, 5100 Paint Branch Pkwy., College Park, MD 20740. Send two... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-D-0571] Guidance for Industry: The Safety of Imported Traditional Pottery Intended for Use With Food and the Use of...

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-05-15

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

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

International Nuclear Information System (INIS)

Kim, Yun Goo; Oh, Eung Se

2016-01-01

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

77 FR 38374 - Culturally Significant Objects Imported for Exhibition Determinations: “Drawing Surrealism”

Science.gov (United States)

2012-06-27

... DEPARTMENT OF STATE [Public Notice 7936] Culturally Significant Objects Imported for Exhibition Determinations: ``Drawing Surrealism'' SUMMARY: Notice is hereby given of the following determinations: Pursuant... April 15, 2003), I hereby determine that the objects to be included in the exhibition ``Drawing...

New technique for determining unavailability of computer controlled safety systems

International Nuclear Information System (INIS)

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

1984-04-01

The availability of a safety system for a fusion reactor is determined. A fusion reactor processes tritium and requires an Emergency Tritium Cleanup (ETC) system for accidental tritium releases. The ETC is computer controlled and because of its complexity, is an excellent candidate for this analysis. The ETC system unavailability, for preliminary untested software, is calculated based on different assumptions about operator response. These assumptions are: (a) the operator shuts down the system after the first indication of plant failure; (b) the operator shuts down the system after following optimized failure verification procedures; or (c) the operator is taken out of the decision process, and the computer uses the optimized failure verification procedures

77 FR 41473 - Culturally Significant Objects Imported for Exhibition Determinations: “Lion Attacking a Horse”

Science.gov (United States)

2012-07-13

... DEPARTMENT OF STATE [Public Notice 7953] Culturally Significant Objects Imported for Exhibition Determinations: ``Lion Attacking a Horse'' SUMMARY: Notice is hereby given of the following determinations... April 15, 2003), I hereby determine that the object entitled ``Lion Attacking a Horse,'' to be imported...

Determination of response level for imported meat and poultry

Energy Technology Data Exchange (ETDEWEB)

Houston, Donald L; Engel, Ronald E

1986-07-01

The response level of 75,000 picocuries per kilogram (pci/kg) for imported meat and poultry was determined in accordance with the Food and Drug Administration's (FDA's) Accidental Radioactive Contamination of Human Food and Animal Feeds, Recommendations for State and Local Agencies which was published in the Federal Register of October 22, 1982, and in consultation with FDA. The response level takes into account the total intake of activity from a radionuclide and the average daily consumption of food in the United States. This response level value is based, in part, upon the expectation that the major contributors of radiation to imported meat and poultry will be cesium-134 (half-life 2.1 years) and cesium-137 (half-life 30 years)

Determination of response level for imported meat and poultry

International Nuclear Information System (INIS)

Houston, Donald L.; Engel, Ronald E.

1986-01-01

The response level of 75,000 picocuries per kilogram (pci/kg) for imported meat and poultry was determined in accordance with the Food and Drug Administration's (FDA's) Accidental Radioactive Contamination of Human Food and Animal Feeds, Recommendations for State and Local Agencies which was published in the Federal Register of October 22, 1982, and in consultation with FDA. The response level takes into account the total intake of activity from a radionuclide and the average daily consumption of food in the United States. This response level value is based, in part, upon the expectation that the major contributors of radiation to imported meat and poultry will be cesium-134 (half-life 2.1 years) and cesium-137 (half-life 30 years)

76 FR 58075 - Culturally Significant Object Imported for Exhibition Determinations: “Cervera Bible”

Science.gov (United States)

2011-09-19

... DEPARTMENT OF STATE [Public Notice: 7589] Culturally Significant Object Imported for Exhibition Determinations: ``Cervera Bible'' SUMMARY: Notice is hereby given of the following determinations: Pursuant to... April 15, 2003), I hereby determine that the object to be included in the exhibition ``Cervera Bible...

Modern Aspects of Safety Assessment of Foodstuff

Directory of Open Access Journals (Sweden)

Tetiana Chorna

2018-04-01

Full Text Available Food safety is one of the decisive components of the economic security of each state and is determined by the ability of the country to control effectively the production and import of safe and high-quality food on the generally accepted principles of the world. This sphere of activity in human society has extremely important humanitarian, social, economic and political aspects. The food raw materials and food products quality and safety control is currently the most relevant analytical task. It is more important than environmental pollution, according to some data, more than 70 % of harmful pollutants in the human body gets through food, 20% of water and 10 % of the air. Technogenic pollution of the environment through soil, water and air gets directly into the food. However, food products are contaminated with natural harmful substances that appear in improper storage, in violation of technologies, food processing and processing charts. The article is devoted to the main factors analysis influencing the safety of food products and the improvement of instrumental methods for the study of quality aromatic products (for example, coffee.

The contribution of safety issues to public perceptions of energy systems

International Nuclear Information System (INIS)

Otway, H.J.; Thomas, Kerry

1978-01-01

Public opposition is an important consideration for those responsible for energy planning. An attitude model was applied to identify the underlying determinants of public perceptions of five energy systems: nuclear, coal, oil, solar and hydro. Empirical results are reported in which these energy systems were found to be perceived in terms of four basic dimensions: psychological aspects; economics benefits; socio-political implications; environmental and physical safety issues. For the total sample, safety issues made an appreciable contribution to attitudes toward all of the systems except nuclear energy, where it was not significant. A differential analysis of two sub-samples, those respondents PRO and CON nuclear energy, showed that benefits and safety issues were important determinants of PRO attitudes while CON attitudes were primarily due to psychological aspects and concerns about personal and political power. The role of technical information in the formation of public attitudes toward technological policies is discussed [fr

Importance of Decision Support Systems About Food Safety in Raw Milk Production

Directory of Open Access Journals (Sweden)

Ecem Akan

2015-12-01

Full Text Available In raw milk production decision support systems for control of food safety hazards has not been developed but main points of this system are available. The decision support systems’ elements include data identification at critical points in the milk supply chain, an information management system and data exchange. Decision supports systems has been developed on the basis of these elements. In dairy sector decision support systems are significant for controlling of food safety hazards and preferred by producers. When these systems are implemented in the milk supply chain, it can be prevented unnecessary sampling and analysis. In this article it will be underlined effects of decision support system elements on food safety of raw milk.

Determinants and Stakeholders Influencing Children's Road Safety Education

OpenAIRE

Alonso Plá, Francisco Manuel; Esteban Martínez, Cristina; Useche, Sergio A.; Manso Pérez, Violeta

2016-01-01

Road safety education is, widely, the best base and the greatest assurance of the future in terms of road safety prevention and promotion. Nowadays, RSE constitutes one of the main growing concerns in terms of complimentary education in many countries, taking into account, among other factors, the high rates of accidents that affect the health and welfare of childhood and adolescence. Furthermore, it is a necessity for the community health to create, train, encourage and lead positives attitu...

Safety-I, Safety-II and Resilience Engineering.

Science.gov (United States)

Patterson, Mary; Deutsch, Ellen S

2015-12-01

In the quest to continually improve the health care delivered to patients, it is important to understand "what went wrong," also known as Safety-I, when there are undesired outcomes, but it is also important to understand, and optimize "what went right," also known as Safety-II. The difference between Safety-I and Safety-II are philosophical as well as pragmatic. Improving health care delivery involves understanding that health care delivery is a complex adaptive system; components of that system impact, and are impacted by, the actions of other components of the system. Challenges to optimal care include regular, irregular and unexampled threats. This article addresses the dangers of brittleness and miscalibration, as well as the value of adaptive capacity and margin. These qualities can, respectively, detract from or contribute to the emergence of organizational resilience. Resilience is characterized by the ability to monitor, react, anticipate, and learn. Finally, this article celebrates the importance of humans, who make use of system capabilities and proactively mitigate the effects of system limitations to contribute to successful outcomes. Copyright © 2015 Mosby, Inc. All rights reserved.

Living up to safety values in health care : The effect of leader behavioral integrity on occupational safety

NARCIS (Netherlands)

Halbesleben, J.R.; Leroy, H.; Dierynck, B.; Simons, T.; Savage, G.T.; McCaughey, D.; Leon, M.R.

2013-01-01

While previous research has identified that leaders’ safety expectations and safety actions are important in fostering occupational safety, research has yet to demonstrate the importance of leader alignment between safety expectations and actions for improving occupational safety. We build on safety

The importance of Pharmacovigilance for the drug safety: Focus on cardiovascular profile of incretin-based therapy.

Science.gov (United States)

Sportiello, Liberata; Rafaniello, Concetta; Scavone, Cristina; Vitale, Cristiana; Rossi, Francesco; Capuano, Annalisa

2016-01-01

With the recent introduction of the new European Pharmacovigilance legislation, all new drugs must be carefully monitored after admission on the European market, in order to assess the long safety profile. Currently, special attention is given to several hypoglycemic agents with recent market approval (agonists of glucagon-like peptide-1 [GLP-1] receptor and dipeptidyl peptidase 4 inhibitors [DPP-4i]), which act through the potentiation of incretin hormone signaling. Their inclusion in European additional monitoring is also due to safety problems, which seem to characterize their pharmacological class. In fact, these drugs initially showed a good tolerability profile with mainly gastrointestinal adverse events, low risk of hypoglycemia and minor effects on body weight. But, new concerns such as infections, pancreatitis, pancreatic cancer and above all cardiovascular events (especially risk of heart failure requiring hospitalization) are now arising. In this review, we highlighted aspects of the new Pharmacovigilance European dispositions, and then we investigated the tolerability profile of incretin-based therapies, in particular DPP-4 inhibitors. Notably, we focused our attention on new safety concerns, which are emerging mostly in the post-marketing period, as the cardiovascular risk profile. Evidence in literature and opinions of regulatory agencies (e.g., European Medicines Agency and Food and Drug Administration) about risks of incretin-based therapies are yet controversial, and there are many open questions in particular on cancer and cardiovascular effects. Thus, it is important to continue to monitor closely the use of these drugs in clinical practice to improve the knowledge on their long-term safety and their place in diabetes therapy. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

Discussion on the safety classification of nuclear safety mechanical equipment

International Nuclear Information System (INIS)

Shen Wei

2010-01-01

The purpose and definition of the equipment safety classification in nuclear plant are introduced. The differences of several safety classification criterions are compared, and the object of safety classification is determined. According to the regulation, the definition and category of the safety functions are represented. The safety classification method, safety classification process, safety class interface, and the requirement for the safety class mechanical equipment are explored. At last, the relation of the safety classification between the mechanical and electrical equipment is presented, and the relation of the safety classification between mechanical equipment and system is also presented. (author)

Status of nuclear safety research - 2000

International Nuclear Information System (INIS)

Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

2000-11-01

The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

75 FR 47337 - Culturally Significant Objects Imported for Exhibition Determinations: “German Impressionist...

Science.gov (United States)

2010-08-05

... DEPARTMENT OF STATE [Public Notice 7080] Culturally Significant Objects Imported for Exhibition Determinations: ``German Impressionist Landscape Painting: Liebermann-- Corinth--Slevogt'' SUMMARY: Notice is..., I hereby determine that the objects to be [[Page 47338

More safety by improving the safety culture

International Nuclear Information System (INIS)

Laaksonen, J.

1993-01-01

In its meeting in 1986, after Chernobyl accident, the INSAG group concluded, that the most important reason for the accident was lack of safety culture. Later the group realized that the safety culture, if it is well enough, can be used as a powerful tool to assess and develop practices affecting safety in any country. A comprehensive view on the various aspects of safety culture was presented in the INSAG-4 report published in 1991. Finland was among the first nations include the concept of safety culture in its regulations. This article describes the roles of government and the regulatory body in creating a national safety culture. How safety culture is seen in the operation of a nuclear power plant is also discussed. (orig.)

Determining the relative importance of figures in journal articles to find representative images

Science.gov (United States)

Müller, Henning; Foncubierta-Rodríguez, Antonio; Lin, Chang; Eggel, Ivan

2013-03-01

When physicians are searching for articles in the medical literature, images of the articles can help determining relevance of the article content for a specific information need. The visual image representation can be an advantage in effectiveness (quality of found articles) and also in efficiency (speed of determining relevance or irrelevance) as many articles can likely be excluded much quicker by looking at a few representative images. In domains such as medical information retrieval, allowing to determine relevance quickly and accurately is an important criterion. This becomes even more important when small interfaces are used as it is frequently the case on mobile phones and tablets to access scientific data whenever information needs arise. In scientific articles many figures are used and particularly in the biomedical literature only a subset may be relevant for determining the relevance of a specific article to an information need. In many cases clinical images can be seen as more important for visual appearance than graphs or histograms that require looking at the context for interpretation. To get a clearer idea of image relevance in articles, a user test with a physician was performed who classified images of biomedical research articles into categories of importance that can subsequently be used to evaluate algorithms that automatically select images as representative examples. The manual sorting of images of 50 journal articles of BioMedCentral with each containing more than 8 figures by importance also allows to derive several rules that determine how to choose images and how to develop algorithms for choosing the most representative images of specific texts. This article describes the user tests and can be a first important step to evaluate automatic tools to select representative images for representing articles and potentially also images in other contexts, for example when representing patient records or other medical concepts when selecting

Triangulation and the importance of establishing valid methods for food safety culture evaluation.

Science.gov (United States)

Jespersen, Lone; Wallace, Carol A

2017-10-01

The research evaluates maturity of food safety culture in five multi-national food companies using method triangulation, specifically self-assessment scale, performance documents, and semi-structured interviews. Weaknesses associated with each individual method are known but there are few studies in food safety where a method triangulation approach is used for both data collection and data analysis. Significantly, this research shows that individual results taken in isolation can lead to wrong conclusions, resulting in potentially failing tactics and wasted investments. However, by applying method triangulation and reviewing results from a range of culture measurement tools it is possible to better direct investments and interventions. The findings add to the food safety culture paradigm beyond a single evaluation of food safety culture using generic culture surveys. Copyright © 2017. Published by Elsevier Ltd.

Financial mechanisms and social safety-oriented model of development of the Russian economy (based on import substitution and innovation

Directory of Open Access Journals (Sweden)

T. I. Ovchinnikova

2016-01-01

Full Text Available In article features of import substitution in the socially oriented model determined as economy with the high level of the state income redistribution of subjects of managing and developed on this basis of system of social protection are considered. Import substitution is considered from the traditional point of view – creation of new productions and technologies which are implemented at the expense of own and borrowed funds of investors. The financial mechanisms for implementation of innovations promoting import substitution are offered: industry plans and road maps as availability of reference points for creation of rational amounts of the budget payments and financial resources of the entities necessary for upgrade of productions, and also the directions of financial resources for implementation of specific most important national priorities and innovative investment projects. The volume of investment into the fixed capital correlated to its cost considerably grew from 3.5% in 2003 to 11.6% in 2009, but value of this indicator isn't enough as degree of depreciation of fixed assets in economy of the region constituted 44.9% in 2009. Direct foreign investments prevail: in Krasnoyarsk Krai their share constituted in 2009 – 45.4%, Krasnodar Region – 40.5%, the Nizhny Novgorod Region – 84.5%. In the Voronezh region such entities as KBHA, Federal State Unitary Enterprise State Research and Production Space Center branch of M. V. Khrunichev the Voronezh Mechanical Plant, JSC Sozvezdiye Concern having the high technologies making safety of the country and especially needing investments function. In plans of urgent strategy of social and economic development of the Voronezh region it is supposed to increase specific weight of innovative products of such entities and to increase the level of innovative activity till 2020. The socially oriented model considering import substitution domestic technologies and products needs strengthening of the

Determinants of Knowledge and Safety Practices of Occupational Hazards of Textile Dye Workers in Sokoto, Nigeria: A Descriptive Analytic Study.

Science.gov (United States)

Okafoagu, Nneka Christina; Oche, Mansur; Awosan, Kehinde Joseph; Abdulmulmuni, Hashim Bala; Gana, Godwin Jiya; Ango, Jessica Timane; Raji, Ismail

2017-06-23

Textile dye workers are subject to occupational hazards on a daily basis due to exposure to precarious conditions in the workplace. This study aimed to assess the knowledge, attitude and safety practices and its determinants among textile dye workers in Sokoto metropolis, Nigeria. This is a descriptive cross-sectional study conducted among 200 textile dye workers and the respondents were selected by multi stage sampling technique. Data was collected using an interviewer administered questionnaire. Data was processed using SPSS IBM version 20 and analyzed using descriptive and inferential statistics. Majority of the respondents (74.0%) had good knowledge of workplace hazards; (81.0%) had positive attitude and only 20% observed all the safety practices. Formal education (P=0.047); working less than 5 days a week (P=0.001) and permanent employment (P=0.013) were found to be determinants of respondents' knowledge and attitude towards workplace hazards. Although the respondents had good knowledge and positive attitude, their lack of observance of safety practices brings to fore the need for direct safety instruction and training and retraining of textile dye workers on workplace hazards and safety practices.

Concomitant injuries are an important determinant of outcome of high-grade blunt hepatic trauma.

Science.gov (United States)

Schnüriger, B; Inderbitzin, D; Schafer, M; Kickuth, R; Exadaktylos, A; Candinas, D

2009-01-01

Little is known about the clinical importance of concomitant injuries in polytraumatized patients with high-grade blunt liver injury. A retrospective single-centre study was performed to investigate the safety of non-operative management of liver injury and the impact of concomitant intra- and extra-abdominal injuries on clinical outcome. Some 183 patients with blunt liver injury were admitted to Berne University Hospital, Switzerland, between January 2000 and December 2006. Grade 3-5 injuries were considered to be high grade. Immediate laparotomy was required by 35 patients (19.1 per cent), owing to extrahepatic intra-abdominal injury (splenic and vascular injuries, perforations) in 21 cases. The mortality rate was 16.9 per cent; 22 of the 31 deaths were due to concomitant lesions. Of 81 patients with high-grade liver injury, 63 (78 per cent) were managed without surgery; liver-related and extra-abdominal complication rates in these patients were 11 and 17 per cent respectively. Grades 4 and 5 liver injury were associated with hepatic-related and extra-abdominal complications. Concomitant injuries are a major determinant of outcome in patients with blunt hepatic injury and should be given high priority by trauma surgeons. An algorithm for the management of blunt liver injury is proposed. Copyright (c) 2008 British Journal of Surgery Society Ltd. Published by John Wiley & Sons, Ltd.

Safety assessment of existing highway bridges and viaducts

NARCIS (Netherlands)

Maljaars, J.; Steenbergen, R.; Abspoel, L.; Kolstein, M.H.

2012-01-01

The assessment of the structural safety of existing br idges and viaducts becomes increasingly important in many countries owing to an increase in traffic loads. Most existing standards, however, are developed for the design of new structures. For this reason, an assessment method for determining

78 FR 1916 - Culturally Significant Objects Imported for Exhibition; Determinations: “Impressionism, Fashion...

Science.gov (United States)

2013-01-09

... DEPARTMENT OF STATE [Public Notice 8146] Culturally Significant Objects Imported for Exhibition; Determinations: ``Impressionism, Fashion, and Modernity'' SUMMARY: Notice is hereby given of the following... exhibition ``Impressionism, Fashion, and Modernity,'' imported from abroad for temporary exhibition within...

Improving safety on rural local and tribal roads safety toolkit.

Science.gov (United States)

2014-08-01

Rural roadway safety is an important issue for communities throughout the country and presents a challenge for state, local, and Tribal agencies. The Improving Safety on Rural Local and Tribal Roads Safety Toolkit was created to help rural local ...

75 FR 53730 - Culturally Significant Objects Imported for Exhibition Determinations: “Richard Hawkins-Third Mind”

Science.gov (United States)

2010-09-01

... DEPARTMENT OF STATE [Public Notice 7148] Culturally Significant Objects Imported for Exhibition Determinations: ``Richard Hawkins--Third Mind'' SUMMARY: Notice is hereby given of the following determinations... the exhibition ``Richard Hawkins--Third Mind,'' imported from abroad for temporary exhibition within...

Probabilistic safety analysis procedures guide

International Nuclear Information System (INIS)

Papazoglou, I.A.; Bari, R.A.; Buslik, A.J.

1984-01-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of tissues affecting reactor safety. This guide addresses the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant and from loss of offsite electric power. The scope includes analyses of problem-solving (cognitive) human errors, a determination of importance of the various core damage accident sequences, and an explicit treatment and display of uncertainties for the key accident sequences. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance) and the risk associated with external accident initiators, as consensus is developed regarding suitable methodologies in these areas. This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are essential for regulatory decision making. Methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study

77 FR 61468 - Culturally Significant Objects Imported for Exhibition Determinations: “Balthus: Cats and Girls”

Science.gov (United States)

2012-10-09

... DEPARTMENT OF STATE [Public Notice 8057] Culturally Significant Objects Imported for Exhibition Determinations: ``Balthus: Cats and Girls'' SUMMARY: Notice is hereby given of the following determinations... and Girls,'' imported from abroad for temporary exhibition within the United States, are of cultural...

76 FR 23642 - Culturally Significant Objects Imported for Exhibition Determinations: “Projects 95: Runa Islam”

Science.gov (United States)

2011-04-27

... DEPARTMENT OF STATE [Public Notice: 7433] Culturally Significant Objects Imported for Exhibition Determinations: ``Projects 95: Runa Islam'' SUMMARY: Notice is hereby given of the following determinations... the exhibition ``Projects 95: Runa Islam'' imported from abroad for temporary exhibition within the...

Parameters of importance to determine during geoscientific site investigation

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan [QuantiSci AB (Sweden); Almen, K.E. [KEA GEO-Konsult AB (Sweden); Ericsson, Lars O.; Karlsson, Fred; Stroem, A. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Fredriksson, Anders [ADG Grundteknik AB (Sweden); Stanfors, R. [Roy Stanfors Consulting AB (Sweden)

1998-06-01

This document identifies and describes geo-scientific parameters that are of importance in order to carry out performance and safety assessments of a deep repository for spent nuclear fuel, based on the information that can be obtained from a site investigation. The document also discusses data needs for planning and design of the rock works and for description of other environmental aspects. Evaluation of the different parameters is discussed in the document as well. The document was produced by a working group consisting of the authors and various SKB staff and consultants, and comprises a step in the planning of a geo-scientific investigation programme at the sites where site investigations will be conducted. The goals of the work presented in this report can be derived directly from SKBs ongoing RD and D Programme. The programme stipulates that a geo-scientific site investigation programme must be available before a site investigation begins. This programme is supposed to specify the goals, measurement methods and evaluation methodology, as well as the acceptance criteria against which the site is evaluated. It is pointed out that site evaluation is a collective term for an interactive process consisting of different parts 65 refs, 15 figs, 12 tabs

77 FR 74048 - Culturally Significant Object Imported for Exhibition Determinations: “Connecting Collections...

Science.gov (United States)

2012-12-12

... determine that the object to be included in the exhibition ``Connecting Collections: Collecting Connections... DEPARTMENT OF STATE [Public Notice 8112] Culturally Significant Object Imported for Exhibition Determinations: ``Connecting Collections: Collecting Connections. 50 Years of Pre-Columbian Art at Dumbarton Oaks...

Nuclear safety in perspective

International Nuclear Information System (INIS)

Andersson, K.; Sjoeberg, B.M.D.; Lauridsen, K.; Wahlstroem, B.

2002-06-01

The aim of the NKS/SOS-1 project has been to enhance common understanding about requirements for nuclear safety by finding improved means of communicating on the subject in society. The project, which has been built around a number of seminars, was supported by limited research in three sub-projects: 1) Risk assessment, 2) Safety analysis, and 3) Strategies for safety management. The report describes an industry in change due to societal factors. The concepts of risk and safety, safety management and systems for regulatory oversight are described in the nuclear area and also, to widen the perspective, for other industrial areas. Transparency and public participation are described as key elements in good risk communication, and case studies are given. Environmental Impact Assessment and Strategic Environmental Assessment are described as important overall processes within which risk communication can take place. Safety culture, safety indicators and quality systems are important concepts in the nuclear safety area are very useful, but also offer important challenges for the future. They have been subject to special attention in the project. (au)

Psychological safety and social support in groupware adoption : a multi-level assessment in education

NARCIS (Netherlands)

Schepers, J.J.L.; Jong, de A.; Wetzels, M.G.M.; Ruyter, de J.C.

2008-01-01

In this paper, the authors propose that psychological safety, a sense of interpersonal trust and being valued in a work team, is an important determinant of groupware technology adoption in an educational setting. They develop and test a model of antecedents and consequences of psychological safety.

77 FR 48199 - Culturally Significant Objects Imported for Exhibition Determinations: “Bernini: Sculpting in Clay”

Science.gov (United States)

2012-08-13

... DEPARTMENT OF STATE [Public Notice 7978] Culturally Significant Objects Imported for Exhibition Determinations: ``Bernini: Sculpting in Clay'' SUMMARY: Notice is hereby given of the following determinations...: Sculpting in Clay,'' imported from abroad for temporary exhibition within the United States, are of cultural...

78 FR 50137 - Culturally Significant Objects Imported for Exhibition Determinations: “Chagall: Love, War, and...

Science.gov (United States)

2013-08-16

... DEPARTMENT OF STATE [Public Notice 8424] Culturally Significant Objects Imported for Exhibition Determinations: ``Chagall: Love, War, and Exile'' SUMMARY: Notice is hereby given of the following determinations..., War, and Exile,'' imported from abroad for temporary exhibition within the United States, are of...

75 FR 3781 - Culturally Significant Object Imported for Exhibition; Determinations: “Projects 92: Yin Xiuzhen”

Science.gov (United States)

2010-01-22

... DEPARTMENT OF STATE [Public Notice 6884] Culturally Significant Object Imported for Exhibition; Determinations: ``Projects 92: Yin Xiuzhen'' SUMMARY: Notice is hereby given of the following determinations... ``Projects 92: Yin Xiuzhen,'' imported from abroad for temporary exhibition within the United States, is of...

Contribution of safety issues to public perceptions of energy systems

International Nuclear Information System (INIS)

Otway, H.J.; Thomas, K.

1978-01-01

Public opposition is an important consideration for those responsible for energy planning; however, the formulation of socially viable policies requires an understanding of the reasons for this opposition. An attitude model was applied to identify the underlying determinants of public perceptions of five energy systems: nuclear, coal, oil, solar and hydro. Empirical results (heterogeneous sample of the general public, N = 224) are reported in which these energy systems were found to be perceived in terms of four basic dimensions: psychological aspects; economic benefits; socio-political implications; environmental and physical safety issues. For the total sample, safety issues made an appreciable contribution to attitudes toward all of the systems except nuclear energy, where it was not significant. A differential analysis of two sub-samples, those respondents PRO and CON nuclear energy, showed that benefits and safety issues were important determinants of PRO attitudes while CON attitudes were primarily due to psychological aspects and concerns about personal and political power. The role of technical information in the formation of public attitudes toward technological policies is discussed

Approach to developing a ground-motion design basis for facilities important to safety at Yucca Mountain

International Nuclear Information System (INIS)

King, J.L.

1990-01-01

This paper discusses a methodology for developing a ground-motion design basis for prospective facilities at Yucca Mountain that are important to safety. The methodology utilizes a guasi-deterministic construct called the 10,000-year cumulative-slip earthquake that is designed to provide a conservative, robust, and reproducible estimate of ground motion that has a one-in-ten chance of occurring during the preclosure period. This estimate is intended to define a ground-motion level for which the seismic design would ensure minimal disruption to operations engineering analyses to ensure safe performance are included

A study on enforcement effects of radiation safety control regulations for diagnostic X-ray equipment

International Nuclear Information System (INIS)

Sung, Mo IL; Park, Myeong Hwan; Kwon, Duk Moon; Lee, Joon IL

1999-01-01

The purposes of this study are to analyze the realities after enforcements of safety control regulations for diagnostic X-ray equipment and to suggest means for an improvement of low radiation safety control. A questionnaire survey for medical radiologic technologists was carried out to determine enforcement effects of the safety control regulations. The results of analysis from the survey are as follows. That is, most of he respondents realized the importance of the radiation safety control system, but about a half of them revealed that regulations were not well observed in accordance with their purposes. Only 43.9 percent of the respondents took an active part in quality control of radiation. And responsibility, sex, age, and knowledge for safety control were important indicators for observations of the regulations. Training for the safety control regulations are needed to ensure safety control and proper usage of diagnostic X-ray equipment. And management of organizations using diagnostic X-ray equipment have to understand and stress the importance of radiation safety control system. (author)

The atmospheric corrosion: an important technical-economic and nuclear safety factor during storage in the construction of nuclear power plants

International Nuclear Information System (INIS)

Rodriguez, R.; Rodriguez, J.; Diaz, J.; Gomez, J.; Galeano, N.

1993-01-01

The purpose of this work is to show the results of the research performed to determine the atmospheric corrosion in the region of Juragua nuclear power plant and to offer some practical recommendations to increase the efficiency during the storage of materials, considering technical-economic and nuclear safety aspects

Shutdown Safety in NEK

International Nuclear Information System (INIS)

Gluhak, Mario; Senegovic, Marko

2014-01-01

Industry performance analysis since 2004 has revealed that 23% of the events reported to WANO occurred during outage periods. Given the fact that a plant is in the outage only 5 percent of the time, this emphasizes the importance of shutdown safety and measures station staffs undertake to maintain effective barriers to safety margins during the outage. Back in 1990s, the industry adopted guidance to meet safety requirements by focusing on safety functions. Both WANO and INPO released various documents, reports and guidelines to help accomplish those requirements. However, in the last decade inadequate 'defence in depth' has led to several events affecting shutdown safety and challenging one of the most important nuclear safety principles: 'The special characteristics of nuclear technology are taken into account in all decisions and actions. Reactivity control, continuity of core cooling, and integrity of fission product barriers are valued as essential, distinguishing attributes of nuclear station work environment'. NEK has recognized the importance of 'defence in depth'Industry performance analysis since 2004 has revealed that 23% of the events reported to WANO occurred during outage periods. Given the fact that a plant is in the outage only 5 percent of the time, this emphasizes the importance of shutdown safety and measures station staffs undertake to maintain effective barriers to safety margins during the outage. Back in 1990s, the industry adopted guidance to meet safety requirements by focusing on safety functions. Both WANO and INPO released various documents, reports and guidelines to help accomplish those requirements. However, in the last decade inadequate 'defence in depth' has led to several events affecting shutdown safety and challenging one of the most important nuclear safety principles: 'The special characteristics of nuclear technology are taken into account in all decisions and actions. Reactivity

Evaluation of safety, an unavoidable requirement in the applications of ionizing radiations

International Nuclear Information System (INIS)

Jova Sed, Luis Andres

2013-01-01

The safety assessments should be conducted as a means to evaluate compliance with safety requirements (and thus the application of fundamental safety principles) for all facilities and activities in order to determine the measures to be taken to ensure safety. It is an essential tool in decision making. For long time we have linked the safety assessment to nuclear facilities and not to all practices involving the use of ionizing radiation in daily life. However, the main purpose of the safety assessment is to determine if it has reached an appropriate level of safety for an installation or activity and if it has fulfilled the objectives of safety and basic safety criteria set by the designer, operating organization and the regulatory body under the protection and safety requirements set out in the International Basic safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. This paper presents some criteria and personal experiences with the new international recommendations on this subject and its practical application in the region and demonstrates the importance of this requirement. Reflects the need to train personnel of the operator and the regulatory body in the proportional application of this requirement in practice with ionizing radiation

Dependability Assessment by Static Analysis of Software Important to Nuclear Power Plant Safety

Energy Technology Data Exchange (ETDEWEB)

Ourghanlian, Alain [EDF Lab, Chatou (France)

2014-08-15

We describe a practical experimentation of safety assessment of safety-critical software used in Nuclear Power Plants. To enhance the credibility of safety assessments and to optimize safety justification costs, Electricite de France (EDF) investigates the use of methods and tools for source code semantic analysis, to obtain indisputable evidence and help assessors focus on the most critical issues. EDF has been using the PolySpace tool for more than 10 years. Today, new industrial tools, based on the same formal approach, Abstract Interpretation, are available. Practical experimentation with these new tools shows that the precision obtained on one of our shutdown systems software is very significantly improved. In a first part, we present the analysis principles of the tools used in our experimentation. In a second part, we present the main characteristics of protection-system software, and why these characteristics are well adapted for the new analysis tools. In the last part, we present an overview of the results and the limitation of the tools.

Factors Affecting the Perception of Importance and Practice of Patient Safety Management among Hospital Employees in Korea.

Science.gov (United States)

Kim, In-Sook; Park, MiJeong; Park, Mi-Young; Yoo, Hana; Choi, Jihea

2013-03-01

The study was undertaken to identify factors affecting perception of the importance and practice of patient safety management (PSM) among hospital employees in Korea. This study was conducted using a descriptive design and a self-report questionnaire. Two hundred and eighty employees were recruited from three hospitals using a convenience sampling method. Measures were perception of the importance, practice, and characteristics of PSM. Data were analyzed using descriptive statistics including t test, one-way analysis of variance, Pearson's correlation analysis, and multiple regression. Factors affecting perception of the importance of PSM were whether hospital employees were in contact with patients while on duty, weekly working hours, education on PSM, and perceived adequacy of PSM system construction. Factors affecting the practice of PSM were perceived adequacy of work load, perceived adequacy of PSM system construction and perception of its importance. The findings of this study indicate a need for developing strategies to improve perception of the importance and practice of PSM among all hospital employees, and provide a reference for future experimental studies. Copyright © 2013. Published by Elsevier B.V.

Important viewpoints proposed for a safety approach of HTGR reactors in Europe

International Nuclear Information System (INIS)

Brinkmann, G.; Pirson, J.; Ehster, S.; Dominguez, M.T.; Mansani, L.; Coe, I.; Moormann, R.; Van der Mheen, W.

2006-01-01

The inherent safety features of modular High Temperature Reactors (HTRs) make events leading to severe core damage highly unlikely and constitute the main differentiating aspects compared to LWRs. Furthermore, while a known and stable regulatory environment has long been established for Light Water Reactors (LWRs), different ways of thinking may help to develop a more appropriate licensing process for HTR-based power plants. The HTR-L project funded by the European Commission in the 5th Framework Programme was dedicated to the definition of a common and coherent European safety approach and the identification of the main licensing issues for the licensing framework of the modular HTRs. Several topics were developed during the course of this project. Due to the characteristics of the HTR design, it has been necessary to define specific defence-in-depth requirements which have then been evaluated for implementation in the safety approach. Safety-related functions appropriate for the HTR design have also had to be identified and listed. On one hand, the different possible solicitations of the fuel particles constituted the starting point for the identification of the accidental conditions (by means of the Master Logic Diagrams methodology); these accidental conditions were classified and the most appropriate methods to consider ultra low probability severe accidents were examined. On the other hand, the elements constituting the source term and, in particular, the requirements for the confinement of radioactive products and the conditions required to prevent the need for a 'conventional' containment structure have been discussed. In the definition of the safety approach, attention has been paid to the need to maintain the potentially interesting economic perspectives of HTR reactors. Key issues to be addressed in the licensing process of the HTRs have also been identified. An innovative systems, structures and components classification method has been developed and

77 FR 34121 - Culturally Significant Objects Imported for Exhibition Determinations: “Lucian Freud: Portraits”

Science.gov (United States)

2012-06-08

... DEPARTMENT OF STATE [Public Notice 7917] Culturally Significant Objects Imported for Exhibition Determinations: ``Lucian Freud: Portraits'' SUMMARY: Notice is hereby given of the following determinations... April 15, 2003), I hereby determine that the object to be included in the exhibition ``Lucian Freud...

76 FR 73760 - Culturally Significant Objects Imported for Exhibition Determinations: “The Holocaust”

Science.gov (United States)

2011-11-29

... Determinations: ``The Holocaust'' SUMMARY: Notice is hereby given of the following determinations: Pursuant to... the exhibition ``The Holocaust,'' imported from abroad for temporary exhibition within the United... United States Holocaust Memorial Museum, Washington, DC, from on or about December 7, 2011, until on or...

75 FR 21384 - Culturally Significant Objects Imported for Exhibition Determinations: “The Holocaust”

Science.gov (United States)

2010-04-23

... Determinations: ``The Holocaust'' SUMMARY: Notice is hereby given of the following determinations: Pursuant to... Holocaust,'' imported from abroad for temporary exhibition within the United States, are of cultural....S. Holocaust Memorial Museum, Washington, DC, from on or about August 2010 until on or about April...

What vehicle features are considered important when buying an automobile? An examination of driver preferences by age and gender.

Science.gov (United States)

Vrkljan, Brenda H; Anaby, Dana

2011-02-01

Certain vehicle features can help drivers avoid collisions and/or protect occupants in the event of a crash, and therefore, might play an important role when deciding which vehicle to purchase. The objective of this study was to examine the importance attributed to key vehicle features (including safety) that drivers consider when buying a car and its association with age and gender. A sample of 2,002 Canadian drivers aged 18 years and older completed a survey that asked them to rank the importance of eight vehicle features if they were to purchase a vehicle (storage, mileage, safety, price, comfort, performance, design, and reliability). ANOVA tests were performed to: (a) determine if there were differences in the level of importance between features and; (b) examine the effect of age and gender on the importance attributed to these features. Of the features examined, safety and reliability were the most highly rated in terms of importance, whereas design and performance had the lowest rating. Differences in safety and performance across age groups were dependent on gender. This effect was most evident in the youngest and oldest age groups. Safety and reliability were considered the most important features. Age and gender play a significant role in explaining the importance of certain features. Targeted efforts for translating safety-related information to the youngest and oldest consumers should be emphasized due to their high collision, injury, and fatality rates. Copyright © 2011 National Safety Council and Elsevier Ltd. All rights reserved.

Specific determination of clinical and toxicological important substances in biological samples by LC-MS

International Nuclear Information System (INIS)

Mitulovic, G.

2001-02-01

This thesis of this dissertation is the specific determination of clinical and toxicological important substances in biological samples by LC-MS. Nicotine was determined in serum after application of nicotine plaster and nicotine nasal spray with HPLC-ESI-MS. Cotinine was determined direct in urine with HPLC-ESI-MS. Short time anesthetics were determined in blood and cytostatics were determined in liquor with HPLC-ESI-MS. (botek)

Safety for Users

CERN Multimedia

HR Department

2008-01-01

CERN welcomes more than 8000 Users every year. The PH Department as host to these scientific associates requires the highest safety standards. The PH Safety Office has published a Safety Flyer for Users. Important safety topics and procedures are presented. Although the Flyer is intended primarily to provide safety information for Users, the PH Safety Office invites all those on the CERN sites to keep a copy of the flyer as it gives guidance in matters of safety and explains what to do in the event of an emergency. Link: http://ph-dep.web.cern.ch/ph-dep/Safety/SafetyOffice.html PH-Safety Office PH Department

Safety for Users

CERN Multimedia

HR Department

2008-01-01

CERN welcomes more than 8000 Users every year. The PH Department as host to these scientific associates requires the highest safety standards. The PH Safety Office has published a safety flyer for Users. Important safety topics and procedures are presented. Although the flyer is intended primarily to provide safety information for Users, the PH Safety Office invites all those on the CERN sites to keep a copy of the flyer as it gives guidance in matters of safety and explains what to do in the event of an emergency. The flyer is available at: http://ph-dep.web.cern.ch/ph-dep/Safety/SafetyOffice.html PH-Safety Office PH Department

White paper on nuclear safety in 1993. 1993 ed.

International Nuclear Information System (INIS)

1994-01-01

When the development and utilization of nuclear power are advanced, the securing of safety is the prerequisite. The Nuclear Safety Commission has promoted the various important measures which become the basis for securing the safety, such as the execution of strict safety examination, the preparation and perfection of the guidelines which are used for safety examination, the holding of public hearings, the investigation of failures and troubles, and the reflection of the obtained learnings to the countermeasures for securing the safety. Since nuclear power facilities contain radioactive substances, the prevention of their abnormal release to surrounding environment is the fundamental of securing the safety. The policy of coping with severe accidents was determined after Three Mile Island accident and Chernobyl accident, and the concrete investigation is carried out. In this year, the abandonment of radioactive waste in ocean by Russia was a large problem. In this book, the Nuclear Safety Commission in the last one year and the securing of safety related to the utilization of plutonium for power reactors are reported. Various related materials are attached. (K.I.)

Management of safety, safety culture and self assessment

International Nuclear Information System (INIS)

Carnino, A.

2000-01-01

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

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

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

75 FR 27613 - Culturally Significant Objects Imported for Exhibition Determinations: “The Holocaust (Warsaw...

Science.gov (United States)

2010-05-17

... Determinations: ``The Holocaust (Warsaw Ghetto)'' SUMMARY: Notice is hereby given of the following determinations... Holocaust (Warsaw Ghetto),'' imported from abroad for temporary exhibition within the United States, are of... custodian. I also determine that the exhibition or display of the documents at the U.S. Holocaust Memorial...

40 CFR 80.1238 - How is a refinery's or importer's average benzene concentration determined?

Science.gov (United States)

2010-07-01

... concentration determined? (a) The average benzene concentration of gasoline produced at a refinery or imported... percent benzene). i = Individual batch of gasoline produced at the refinery or imported during the applicable averaging period. n = Total number of batches of gasoline produced at the refinery or imported...

Water Safety

Science.gov (United States)

... Staying Safe Videos for Educators Search English Español Water Safety KidsHealth / For Parents / Water Safety What's in ... remains your best measure of protection. Making Kids Water Wise It's important to teach your kids proper ...

Safety sign designs for children by considering effect of the colors preferences: A case study

Science.gov (United States)

Iftadi, Irwan; Nugraha, Dian Cahya; Jauhari, Wakhid Ahmad

2018-02-01

Color has become a major consideration in ergonomics. Color conveys a message and it is an important element in safety signs. The importance of colors usage in safety sign designs makes the colors research into one of the things that must be done before designing them. So far, research in the related field only focused on the adult's perspective without involving children's perspective in designing the safety signs. This paper aims to find out how children's perception towards colors affects the safety sign designs. This study consist of eight sections which are literature study, direct observation, determining referents and other parameters, determining research respondents, making the booklet, assessing the colors preferences, determining the design's parameter value and creating the safety sign designs. Limitation of the research are the objects are the students with the age of 10 - 11 years old in Grade IV and then the research is conducted in the school day and hours that apply to the school. Chi square test and odds ratio are employed to assess the colors preferences. Twelve safety sign designs are proposed by considering the children's colors perception. The designs are grouped into three types of sign which are Mandatory Action Sign, Warning Sign and Prohibition Sign. Six colors are used to draw the safety signs i.e. red, orange, yellow, green, blue and black. On the basis of the study, it is concluded that the colors that often appears in safety signs is green with the percentage of 75% and that rarely appears is red with the percentage of 8.33%.

Modified enforcement policy relating to 10 CFR 50.49, ''Environmental qualification of electrical equipment important to safety for nuclear power plants'' (Generic Letter 88-07)

International Nuclear Information System (INIS)

Miraglia, F.J.

1992-01-01

Generic Letters, Bulletins, and Information Notices have been issued to provide guidance regarding the application and enforcement of 10 CFR 50.49, ''Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.'' Generic Letter 85-15, issued August 6, 1985, and Generic Letter 86-15, issued September 22, 1986, provided information related to the deadlines for compliance with 10 CFR 50.49 and possible civil penalties applicable to licensees who were not in compliance with the rule as of the November 30, 1985 deadline. Upon review, the Commission found that the EQ Enforcement Policy promulgated in Generic Letter 86-15, could result in imposition of civil penalties that did not properly reflect the safety significance of EQ violations with respect to civil penalties imposed in the past. In the interest of continuing a tough but fair enforcement policy, the Commission determined that the EQ Enforcement Policy should be revised. The purpose of this letter is to provide a modification to the NRC's enforcement policy, as approved by the Commission, for environmental qualification (EQ) violations. This letter replaces the guidance provided in Generic Letters 85-15 and 86-15

Safety factors for neutron fluences in NPP safety assessment

International Nuclear Information System (INIS)

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

2016-01-01

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

Safety analysis and environmental effects of fusion concepts

International Nuclear Information System (INIS)

Anon.

1976-01-01

Fusion reactor concepts have been analyzed to determine the probable interactions with the environment and the resultant environmental effects. Two research projects on tritium oxidation in the atmosphere and carbon-14 formation in fusion reactors are briefly described. A study and report were completed, investigating the potential public safety impact of accidents in fusion power plants. After reviewing the existing information on conceptual fusion reactor designs, PNL identified areas of safety concern, making recommendations on how development of safety information might be best accomplished. Inventories of potentially dispersible toxic materials were classified, and general conclusions were made about their relative importance. The report specifies energy sources with a potential to initiate or propagate an accident. An important product of the study was an assessment logic developed to identify potential accident scenarios that could lead to the release of contaminants to the environment. Though the limited amount of fusion design information allows only a general assessment of accident-initiating events, the logic provides a method for making more detailed safety analyses as more design information becomes available. The same logic was used to identify technological areas where an R and D investment would enhance the technical bases for fusion designs as well as the understanding of safety implications in fusion systems

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

International Nuclear Information System (INIS)

2000-12-01

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

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

International Nuclear Information System (INIS)

2000-12-01

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

Generation of risk importance information from severe accident PSA model

International Nuclear Information System (INIS)

Seo, Mi Ro; Kim, Hyeong Taek; Moon, Chan Kook

2012-01-01

One of the important objects conducting Probabilistic Safety Assessment (PSA) is the relative evaluation of importance of the component or function that is greatly affected to the plant safety. This evaluation is performed by the importance assessment methods such as Risk Reduction Worth, Risk Achievement Worth, and Fuss el Vessley method from the aspect of core damage frequency (CDF). In the Level 1 PSA model, the importance of each component can be evaluated since the CDF is calculated by the combination of the branch probability of event tree and the component failure probability in the fault tree. But, the Level 2 PSA model in order to assess the containment integrity cannot evaluate the risk importance by the above methods because the model is consisted of 3 parts, plant damage status, containment event tree, and source term category. So, in the field that the Level 2 PSA risk importance information should be reflected, such as maintenance rule program, risk importance has been determined by the subjective judgment of the model developer. This study was performed in order to generate the risk importance information more objectively and systematically in the Level 2 PSA model, focused on the containment event tree in the domain PHWR Level 2 PSA model

Determination of safety margins for whole blood concentrations of alcohol and nineteen drugs in driving under the influence cases.

Science.gov (United States)

Kristoffersen, Lena; Strand, Dag Helge; Liane, Veronica Horpestad; Vindenes, Vigdis; Tvete, Ingunn Fride; Aldrin, Magne

2016-02-01

Legislative limits for driving under the influence of 20 non-alcohol drugs were introduced in Norway in February 2012. Per se limits corresponding to blood alcohol concentrations (BAC) of 0.2g/kg were established for 20 psychoactive drugs, and limits for graded sanctions corresponding to BACs of 0.5 and 1.2g/kg were determined for 13 of these drugs. This new legislation made it possible for the courts to make sentences based on the analytical results, similar to the situation for alcohol. To ensure that the reported concentration is as least as high as the true concentration, with a 99% safety level, safety margins had to be calculated for each of the substances. Diazepam, tetrahydrocannabinol (THC) and alcohol were used as model substances to establish a new model for estimating the safety margins. The model was compared with a previous used model established several years ago, by a similar yet much simpler model, and they were found to be in agreement. The measurement uncertainties depend on the standard batch used, the work list and the measurements' replicate. A Bayesian modelling approach was used to determine the parameters in the model, using a dataset of 4700 diazepam positive specimens and 5400 THC positive specimens. Different safety margins were considered for low and high concentration levels of diazepam (≤2μM (0.6mg/L) and >2μM) and THC (≤0.01μM (0.003mg/L) and >0.01μM). The safety margins were for diazepam 19.5% (≤2μM) and 34% (>2μM), for THC 19.5% (≤0.01μM) and 24.9% (>0.01μM). Concentration dependent safety margins for BAC were based on a dataset of 29500 alcohol positive specimens, and were in the range 10.4% (0.1g/kg) to 4.0% (4.0g/kg) at a 99% safety level. A simplified approach was used to establish safety margins for the compounds amphetamine, MDMA, methamphetamine, alprazolam, phenazepam, flunitrazepam, clonazepam, nitrazepam, oxazepam, buprenorphine, GHB, methadone, ketamine, cocaine, morphine, zolpidem and zopiclone. The

Dimensions of patient safety culture in family practice.

Science.gov (United States)

Palacios-Derflingher, Luz; O'Beirne, Maeve; Sterling, Pam; Zwicker, Karen; Harding, Brianne K; Casebeer, Ann

2010-01-01

Safety culture has been shown to affect patient safety in healthcare. While the United States and United Kingdom have studied the dimensions that reflect patient safety culture in family practice settings, to date, this has not been done in Canada. Differences in the healthcare systems between these countries and Canada may affect the dimensions found to be relevant here. Thus, it is important to identify and compare the dimensions from the United States and the United Kingdom in a Canadian context. The objectives of this study were to explore the dimensions of patient safety culture that relate to family practice in Canada and to determine if differences and similarities exist between dimensions found in Canada and those found in previous studies undertaken in the United States and the United Kingdom. A qualitative study was undertaken applying thematic analysis using focus groups with family practice offices and supplementary key stakeholders. Analysis of the data indicated that most of the dimensions from the United States and United Kingdom are appropriate in our Canadian context. Exceptions included owner/managing partner/leadership support for patient safety, job satisfaction and overall perceptions of patient safety and quality. Two unique dimensions were identified in the Canadian context: disclosure and accepting responsibility for errors. Based on this early work, it is important to consider differences in care settings when understanding dimensions of patient safety culture. We suggest that additional research in family practice settings is critical to further understand the influence of context on patient safety culture.

Importance and promotion of linguistic safety in the healthcare setting.

Science.gov (United States)

Diaz, Desiree A; Allchin, Lynn

2013-08-01

The United States has always been and will continue to be a nation of many cultures and languages. In the healthcare arena, this means safety will depend on clear, linguistically appropriate communication between the patient and family and the healthcare provider. Three obstacles exist to this type of essential communication: limited English proficiency, low health literacy, and cultural barriers.

Safety Culture Assessment at Regulatory Body - PNRA Experience of Implementing IAEA Methodology for Safety Culture Self Assessment

International Nuclear Information System (INIS)

Bhatti, S.A.N.; Arshad, N.

2016-01-01

The prevalence of a good safety culture is equally important for all kind of organizations involved in nuclear business including operating organizations, designers, regulator, etc., and this should be reflected through all the processes and activities of these organizations. The need for inculcating safety culture into regulatory processes and practices is gradually increasing since the major accident at Fukushima. Accordingly, several international fora in last few years repeatedly highlighted the importance of prevalence of safety culture in regulatory bodies as well. The utilisation of concept of safety culture always remained applicable in regulatory activities of PNRA in the form of core values. After the Fukushima accident, PNRA considered it important to check the extent of utilisation of safety culture concept in organizational activities and decided to conduct its “Safety Culture Self-Assessment (SCSA)” for presenting itself as a role model in-order to endorse the fact that safety culture at regulatory authority plays an important role to influence safety culture at licenced facilities.

The Evolution of System Safety at NASA

Science.gov (United States)

Dezfuli, Homayoon; Everett, Chris; Groen, Frank

2014-01-01

The NASA system safety framework is in the process of change, motivated by the desire to promote an objectives-driven approach to system safety that explicitly focuses system safety efforts on system-level safety performance, and serves to unify, in a purposeful manner, safety-related activities that otherwise might be done in a way that results in gaps, redundancies, or unnecessary work. An objectives-driven approach to system safety affords more flexibility to determine, on a system-specific basis, the means by which adequate safety is achieved and verified. Such flexibility and efficiency is becoming increasingly important in the face of evolving engineering modalities and acquisition models, where, for example, NASA will increasingly rely on commercial providers for transportation services to low-earth orbit. A key element of this objectives-driven approach is the use of the risk-informed safety case (RISC): a structured argument, supported by a body of evidence, that provides a compelling, comprehensible and valid case that a system is or will be adequately safe for a given application in a given environment. The RISC addresses each of the objectives defined for the system, providing a rational basis for making informed risk acceptance decisions at relevant decision points in the system life cycle.

Reliability and safety of nuclear power stations

International Nuclear Information System (INIS)

Stepanek, S.

1979-01-01

The main problems are briefly discussed associated with the assessment of the safety and reliability of reactor pressure vessels. Two approaches are being applied to the assessment: one is based on the crack arrest temperature, the other on the determination of conditions corresponding to brittle fracture formation and on the determination of the critical defect size. The importance is stressed of continuous in-service inspection which may increase the factor of reliability by up to 10 4 times. (Z.M.)

Determination of Initial Conditions for the Safety Analysis by Random Sampling of Operating Parameters

International Nuclear Information System (INIS)

Jeong, Hae-Yong; Park, Moon-Ghu

2015-01-01

In most existing evaluation methodologies, which follow a conservative approach, the most conservative initial conditions are searched for each transient scenario through tremendous assessment for wide operating windows or limiting conditions for operation (LCO) allowed by the operating guidelines. In this procedure, a user effect could be involved and a remarkable time and human resources are consumed. In the present study, we investigated a more effective statistical method for the selection of the most conservative initial condition by the use of random sampling of operating parameters affecting the initial conditions. A method for the determination of initial conditions based on random sampling of plant design parameters is proposed. This method is expected to be applied for the selection of the most conservative initial plant conditions in the safety analysis using a conservative evaluation methodology. In the method, it is suggested that the initial conditions of reactor coolant flow rate, pressurizer level, pressurizer pressure, and SG level are adjusted by controlling the pump rated flow, setpoints of PLCS, PPCS, and FWCS, respectively. The proposed technique is expected to contribute to eliminate the human factors introduced in the conventional safety analysis procedure and also to reduce the human resources invested in the safety evaluation of nuclear power plants

Safety climate and self-reported injury: assessing the mediating role of employee safety control.

Science.gov (United States)

Huang, Yueng-Hsiang; Ho, Michael; Smith, Gordon S; Chen, Peter Y

2006-05-01

To further reduce injuries in the workplace, companies have begun focusing on organizational factors which may contribute to workplace safety. Safety climate is an organizational factor commonly cited as a predictor of injury occurrence. Characterized by the shared perceptions of employees, safety climate can be viewed as a snapshot of the prevailing state of safety in the organization at a discrete point in time. However, few studies have elaborated plausible mechanisms through which safety climate likely influences injury occurrence. A mediating model is proposed to link safety climate (i.e., management commitment to safety, return-to-work policies, post-injury administration, and safety training) with self-reported injury through employees' perceived control on safety. Factorial evidence substantiated that management commitment to safety, return-to-work policies, post-injury administration, and safety training are important dimensions of safety climate. In addition, the data support that safety climate is a critical factor predicting the history of a self-reported occupational injury, and that employee safety control mediates the relationship between safety climate and occupational injury. These findings highlight the importance of incorporating organizational factors and workers' characteristics in efforts to improve organizational safety performance.

Safety analysis for 'Fugen'

International Nuclear Information System (INIS)

1997-10-01

The improvement of safety in nuclear power stations is an important proposition. Therefore also as to the safety evaluation, it is important to comprehensively and systematically execute it by referring to the operational experience and the new knowledge which is important for the safety throughout the period of use as well as before the construction and the start of operation of nuclear power stations. In this report, the results when the safety analysis for ''Fugen'' was carried out by referring to the newest technical knowledge are described. As the result, it was able to be confirmed that the safety of ''Fugen'' has been secured by the inherent safety and the facilities which were designed for securing the safety. The basic way of thinking on the safety analysis including the guidelines to be conformed to is mentioned. As to the abnormal transient change in operation and accidents, their definition, the events to be evaluated and the standards for judgement are reported. The matters which were taken in consideration at the time of the analysis are shown. The computation programs used for the analysis were REACT, HEATUP, LAYMON, FATRAC, SENHOR, LOTRAC, FLOOD and CONPOL. The analyses of the abnormal transient change in operation and accidents are reported on the causes, countermeasures, protective functions and results. (K.I.)

Fusion integral experiments and analysis and the determination of design safety factors - I: Methodology

International Nuclear Information System (INIS)

Youssef, M.Z.; Kumar, A.; Abdou, M.A.; Oyama, Y.; Maekawa, H.

1995-01-01

The role of the neutronics experimentation and analysis in fusion neutronics research and development programs is discussed. A new methodology was developed to arrive at estimates to design safety factors based on the experimental and analytical results from design-oriented integral experiments. In this methodology, and for a particular nuclear response, R, a normalized density function (NDF) is constructed from the prediction uncertainties, and their associated standard deviations, as found in the various integral experiments where that response, R, is measured. Important statistical parameters are derived from the NDF, such as the global mean prediction uncertainty, and the possible spread around it. The method of deriving safety factors from many possible NDFs based on various calculational and measuring methods (among other variants) is also described. Associated with each safety factor is a confidence level, designers may choose to have, that the calculated response, R, will not exceed (or will not fall below) the actual measured value. An illustrative example is given on how to construct the NDFs. The methodology is applied in two areas, namely the line-integrated tritium production rate and bulk shielding integral experiments. Conditions under which these factors could be derived and the validity of the method are discussed. 72 refs., 17 figs., 4 tabs

ATR confinement leakage determination

International Nuclear Information System (INIS)

Kuan, P.; Buescher, B.J.

1998-01-01

The air leakage rate from the Advanced Test Reactor (ATR) confinement is an important parameter in estimating hypothesized accidental releases of radiation to the environment. The leakage rate must be determined periodically to assure that the confinement has not degraded with time and such determination is one of the technical safety requirements of ATR operation. This paper reviews the methods of confinement leakage determination and presents an analysis of leakage determination under windy conditions, which can complicate the interpretation of the determined leakage rates. The paper also presents results of analyses of building air exchange under windy conditions. High wind can enhance air exchange and this could increase the release rates of radioisotopes following an accident

Perceived organizational support for safety and employee safety voice: the mediating role of coworker support for safety.

Science.gov (United States)

Tucker, Sean; Chmiel, Nik; Turner, Nick; Hershcovis, M Sandy; Stride, Chris B

2008-10-01

In the present study, we modeled 2 sources of safety support (perceived organizational support for safety and perceived coworker support for safety) as predictors of employee safety voice, that is, speaking out in an attempt to change unsafe working conditions. Drawing on social exchange and social impact theories, we hypothesized and tested a mediated model predicting employee safety voice using a cross-sectional survey of urban bus drivers (n = 213) in the United Kingdom. Hierarchical regression analysis showed that perceived coworker support for safety fully mediated the relationship between perceived organizational support for safety and employee safety voice. This study adds to the employee voice literature by evaluating the important role that coworkers can play in encouraging others to speak out about safety issues. Implications for research and practice related to change-oriented safety communication are discussed.

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

African fermented dairy products - Overview of predominant technologically important microorganisms focusing on African Streptococcus infantarius variants and potential future applications for enhanced food safety and security.

Science.gov (United States)

Jans, Christoph; Meile, Leo; Kaindi, Dasel Wambua Mulwa; Kogi-Makau, Wambui; Lamuka, Peter; Renault, Pierre; Kreikemeyer, Bernd; Lacroix, Christophe; Hattendorf, Jan; Zinsstag, Jakob; Schelling, Esther; Fokou, Gilbert; Bonfoh, Bassirou

2017-06-05

Milk is a major source of nutrients, but can also be a vehicle for zoonotic foodborne diseases, especially when raw milk is consumed. In Africa, poor processing and storage conditions contribute to contamination, outgrowth and transmission of pathogens, which lead to spoilage, reduced food safety and security. Fermentation helps mitigate the impact of poor handling and storage conditions by enhancing shelf life and food safety. Traditionally-fermented sour milk products are culturally accepted and widely distributed in Africa, and rely on product-specific microbiota responsible for aroma, flavor and texture. Knowledge of microbiota and predominant, technologically important microorganisms is critical in developing products with enhanced quality and safety, as well as sustainable interventions for these products, including Africa-specific starter culture development. This narrative review summarizes current knowledge of technologically-important microorganisms of African fermented dairy products (FDP) and raw milk, taking into consideration novel findings and taxonomy when re-analyzing data of 29 publications covering 25 products from 17 African countries. Technologically-important lactic acid bacteria such as Lactococcus lactis and Streptococcus infantarius subsp. infantarius (Sii), Lactobacillus spp. and yeasts predominated in raw milk and FDP across Africa. Re-analysis of data also suggests a much wider distribution of Sii and thus a potentially longer history of use than previously expected. Therefore, evaluating the role and safety of African Sii lineages is important when developing interventions and starter cultures for FDP in Africa to enhance food safety and food security. In-depth functional genomics, epidemiologic investigations and latest identification approaches coupled with stakeholder involvement will be required to evaluate the possibility of African Sii lineages as novel food-grade Streptococcus lineage. Copyright © 2017 The Authors. Published by

Nuclear safety - Topical issues

International Nuclear Information System (INIS)

1995-01-01

The following topical issues related to nuclear safety are discussed: steam generators; maintenance strategies; control rod drive nozzle cracks; core shrouds cracks; sump strainer blockage; fire protection; computer software important for safety; safety during shutdown; operational safety experience; external hazards and other site related issues. 5 figs, 5 tabs

78 FR 5556 - Culturally Significant Objects Imported for Exhibition Determinations: “Frida & Diego: Passion...

Science.gov (United States)

2013-01-25

... DEPARTMENT OF STATE [Public Notice 8160] Culturally Significant Objects Imported for Exhibition Determinations: ``Frida & Diego: Passion, Politics and Painting'' SUMMARY: Notice is hereby given of the... exhibition ``Frida & Diego: Passion, Politics and Painting,'' imported from abroad for temporary exhibition...

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

International Nuclear Information System (INIS)

Wahlstroem, B.; Gunsell, L.

1998-03-01

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

76 FR 60113 - Culturally Significant Objects Imported for Exhibition Determinations: “Masters of Venice...

Science.gov (United States)

2011-09-28

... DEPARTMENT OF STATE [Public Notice 7616] Culturally Significant Objects Imported for Exhibition Determinations: ``Masters of Venice: Renaissance Paintings of Passion and Power from Kunsthistorisches Museum..., 2003), I hereby determine that the objects to be included in the exhibition ``Masters of Venice...

75 FR 51518 - Culturally Significant Objects Imported for Exhibition Determinations: “Ballplayers, Gods, and...

Science.gov (United States)

2010-08-20

... DEPARTMENT OF STATE [Public Notice 7126] Culturally Significant Objects Imported for Exhibition Determinations: ``Ballplayers, Gods, and Rainmaker Kings: Masterpieces From Ancient Mexico'' SUMMARY: Notice is..., I hereby determine that the objects to be included in the exhibition ``Ballplayers, Gods, and...

75 FR 45194 - Culturally Significant Objects Imported for Exhibition Determinations: “Drawing from Nature...

Science.gov (United States)

2010-08-02

... DEPARTMENT OF STATE [Public Notice 7096] Culturally Significant Objects Imported for Exhibition Determinations: ``Drawing from Nature: Landscapes by Max Liebermann, Lovis Corinth, and Max Slevogt'' SUMMARY..., I hereby determine that the objects to be included in the exhibition ``Drawing from Nature...

Behavioral safety and OHSAS 18001:2007

International Nuclear Information System (INIS)

Rama Rao, B.S.; Hemantha Rao, G.V.S.

2009-01-01

Analysis of industrial accidents reveals that majority of them are due to human errors. And human errors can be due to lack of knowledge/awareness or inherent behavior of the person(s) involved in the accident. While the former can be tackled through training, the latter requires interventions aimed at behavior modification. Realizing the importance of behavioral aspect of safety, Revised Version of Occupational Health and Safety Management System standard - OHSAS 18001:2007 has incorporated 'behavior' in the planning clause 'Hazard identification, risk assessment and determining controls -4.3.1. (c)'. It reads The organization shall establish, implement and maintain a procedure for the ongoing hazard identification, risk assessment and determination of necessary controls. The procedure for hazard identification and risk assessment shall take into account HUMAN BEHAVIOR, CAPABILITIES and other HUMAN FACTORS. Planning and Control are the mantra. Thus, Risk Management and Mitigation strategies should factor in 'behavioral aspect' so as to be effective. In the absence of this, any amount of focus on safety will be incomplete and does not yield desired results. Best stage to take care of the behavioral safety is during the design of Plant and Machinery. Regular monitoring and periodical inspections will ensure early detection of unsafe behavior/practices and renders preventive measures possible. This paper discusses some of the behavioral patterns of industrial workforce, their ramifications for safety and possible remedies to minimize risk and save human capital for the overall well being of the organization, family and ultimately, the society. (author)

78 FR 45285 - Culturally Significant Objects Imported for Exhibition Determinations: “Egypt's Mysterious Book...

Science.gov (United States)

2013-07-26

... DEPARTMENT OF STATE [Public Notice 8393] Culturally Significant Objects Imported for Exhibition Determinations: ``Egypt's Mysterious Book of the Faiyum'' SUMMARY: Notice is hereby given of the following... exhibition ``Egypt's Mysterious Book of the Faiyum,'' imported from abroad for temporary exhibition within...

75 FR 57825 - Culturally Significant Objects Imported for Exhibition Determinations: “Ancient Chinese Bronzes...

Science.gov (United States)

2010-09-22

... DEPARTMENT OF STATE [Public Notice 7181] Culturally Significant Objects Imported for Exhibition Determinations: ``Ancient Chinese Bronzes From the Shouyang Studio: The Katherine and George Fan Collection... ``Ancient Chinese Bronzes from the Shouyang Studio: The Katherine and George Fan Collection,'' imported from...

76 FR 4987 - Culturally Significant Objects Imported for Exhibition Determinations: “Bali: Art, Ritual...

Science.gov (United States)

2011-01-27

... DEPARTMENT OF STATE [Public Notice: 7311] Culturally Significant Objects Imported for Exhibition Determinations: ``Bali: Art, Ritual, Performance'' SUMMARY: Notice is hereby given of the following... objects to be included in the exhibition ``Bali: Art, Ritual, Performance,'' imported from abroad for...

77 FR 53248 - Culturally Significant Objects Imported for Exhibition Determinations: “Swiss Treasures: From...

Science.gov (United States)

2012-08-31

... DEPARTMENT OF STATE [Public Notice 8004] Culturally Significant Objects Imported for Exhibition Determinations: ``Swiss Treasures: From Biblical Papyrus and Parchment to Erasmus, Zwingli, Calvin, and Barth... Parchment to Erasmus, Zwingli, Calvin, and Barth,'' imported from abroad for temporary exhibition within the...

75 FR 82128 - Culturally Significant Objects Imported for Exhibition Determinations: “Vishnu: Hinduism's Blue...

Science.gov (United States)

2010-12-29

... DEPARTMENT OF STATE [Public Notice 7279] Culturally Significant Objects Imported for Exhibition Determinations: ``Vishnu: Hinduism's Blue-Skinned Savior'' SUMMARY: Notice is hereby given of the following... objects to be included in the exhibition ``Vishnu: Hinduism's Blue-Skinned Savior,'' imported from abroad...

Leadership for safety: industrial experience.

Science.gov (United States)

Flin, R; Yule, S

2004-12-01

The importance of leadership for effective safety management has been the focus of research attention in industry for a number of years, especially in energy and manufacturing sectors. In contrast, very little research into leadership and safety has been carried out in medical settings. A selective review of the industrial safety literature for leadership research with possible application in health care was undertaken. Emerging findings show the importance of participative, transformational styles for safety performance at all levels of management. Transactional styles with attention to monitoring and reinforcement of workers' safety behaviours have been shown to be effective at the supervisory level. Middle managers need to be involved in safety and foster open communication, while ensuring compliance with safety systems. They should allow supervisors a degree of autonomy for safety initiatives. Senior managers have a prime influence on the organisation's safety culture. They need to continuously demonstrate a visible commitment to safety, best indicated by the time they devote to safety matters.

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

Undocumented status as a social determinant of occupational safety and health: The workers' perspective.

Science.gov (United States)

Flynn, Michael A; Eggerth, Donald E; Jacobson, C Jeffrey

2015-11-01

Undocumented immigration to the United States has grown dramatically over the past 25 years. This study explores undocumented status as a social determinant of occupational health by examining its perceived consequences on workplace safety of Latino immigrants. Guided by the Theory of Work Adjustment, qualitative analysis was conducted on transcripts from focus groups and individual interviews conducted with a convenience sample of Latino immigrant workers. Participants reported that unauthorized status negatively impacted their safety at work and resulted in a degree of alienation that exceeded the specific proscriptions of the law. Participants overwhelming used a strategy of disengagement to cope with the challenges they face as undocumented immigrants. This study describes the complex web of consequences resulting from undocumented status and its impact on occupational health. This study presents a framework connecting the daily work experiences of immigrants, the coping strategy of disengagement, and efforts to minimize the impact of structural violence. © 2015 Wiley Periodicals, Inc.

Undocumented Status as a Social Determinant of Occupational Safety and Health: The Workers’ Perspective

Science.gov (United States)

Flynn, Michael A.; Eggerth, Donald E.; Jacobson, C. Jeffrey

2015-01-01

Background Undocumented immigration to the United States has grown dramatically over the past 25 years. This study explores undocumented status as a social determinant of occupational health by examining its perceived consequences on workplace safety of Latino immigrants. Methods Guided by the Theory of Work Adjustment, qualitative analysis was conducted on transcripts from focus groups and individual interviews conducted with a convenience sample of Latino immigrant workers. Results Participants reported that unauthorized status negatively impacted their safety at work and resulted in a degree of alienation that exceeded the specific proscriptions of the law. Participants overwhelming used a strategy of disengagement to cope with the challenges they face as undocumented immigrants. Conclusion This study describes the complex web of consequences resulting from undocumented status and its impact on occupational health. This study presents a framework connecting the daily work experiences of immigrants, the coping strategy of disengagement, and efforts to minimize the impact of structural violence. PMID:26471878

Creating a safety culture in the regulatory authority: The Cuban experience

International Nuclear Information System (INIS)

Ferro Fernandez, R.; Guillen Campos, A.

2002-01-01

The Cuban regulatory authority has been working during several years for the fostering and development of a high Safety Culture level in nuclear activities in the country. As starting point to achieve this objective the assessment of the Safety Culture level in the regulatory authority performance was considered an important issue. For this purpose a preliminary diagnosis was carried out by means of a national survey that allowed identifying some areas of the regulatory activity that required improvements in order to achieve a higher Safety Culture and to immediately implement appropriate actions. Two of the most important actions undertaken were: the statement of the regulatory authority Safety Policy which governs and determines the performance of this organization and its staff and also the implementation of a new interaction practice at top level between the regulatory authority and the utilities of the nuclear sector through the Annual Regulatory Conference. The present paper summarizes these two introduced practices into the Cuban regulatory activity. (author)

Why is variability important for performance assessment and what are its consequences for site characterisation and repository design?

International Nuclear Information System (INIS)

Dverstorp, B.; Smith, P.A.; Zuidema, P.

1998-01-01

The importance of spatial variability is discussed in terms of its consequences for site characterisation and for repository design and safety. Variability is described in terms of various scales of discrete structural features and a pragmatic classification is proposed according to whether the features are: feasibility-determining (i.e. features within which repository construction and operation is not practical and which preclude long-term safety); layout-determining (i.e. features which, if avoided, would enhance long-term safety); safety-determining features (i.e. features which cannot be shown to be avoidable and which strongly influence the calculated long-term safety of the repository system). The significance with respect to the geosphere-transport barrier of small-scale pore structure within the various classes of feature is also discussed. The practical problems of characterising variability and modelling its effects on radionuclide transport are described. Key factors affecting groundwater flow and radionuclide transport are identified, models that incorporate spatial variability are described and the estimation of appropriate parameters for these models is discussed. (author)

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A.

2013-01-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A., E-mail: emotta@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

75 FR 78335 - Culturally Significant Objects Imported for Exhibition Determinations: “Thomas Lawrence: Regency...

Science.gov (United States)

2010-12-15

... DEPARTMENT OF STATE [Public Notice 7268] Culturally Significant Objects Imported for Exhibition Determinations: ``Thomas Lawrence: Regency Power and Brilliance'' SUMMARY: Notice is hereby given of the... determine that the objects to be included in the exhibition ``Thomas Lawrence: Regency Power and Brilliance...

77 FR 12103 - Culturally Significant Objects Imported for Exhibition Determinations: “Colorful Realm: Japanese...

Science.gov (United States)

2012-02-28

... DEPARTMENT OF STATE [Public Notice: 7807] Culturally Significant Objects Imported for Exhibition Determinations: ``Colorful Realm: Japanese Bird-and-Flower Paintings by It[omacr] Jakuch[umacr] (1716-1800... determine that the objects to be included in the exhibition ``Colorful Realm: Japanese Bird-and-Flower...

EXAMINATION OF SECURITY EVENTS AS DBEs FOR MGDS IMPORTANT TO SAFETY SSCs

International Nuclear Information System (INIS)

J.M. Hartsell

1998-01-01

A portion of the safeguards and security system for the Mined Geologic Disposal System (MGDS) has been identified as QA-1 based on the classification of structures, systems, and components (SSCs) performed in accordance with QAP-2-3, ''Classification of Permanent Items'' (Reference 5.2). The classification analysis, ''Classification of the Preliminary MGDS Repository Design'' (Reference 5.9), identifies the ''Safeguards Material Control and Accountability'' system as a QA-1 SSC based on the identification of unauthorized intrusion, sabotage, theft, and diversion as potential Design Basis Events (DBEs). The purpose of this analysis is to provide justification to eliminate these events as DBEs for the MGDS based on a review of the Codes of Federal Regulation (CFRs) for geologic repositories (10 CFR 60), commercial reactor facilities (10 CFR 50), independent spent fuel storage installations (ISFSIs) and monitored retrievable storage (MRS) installations (10 CFR 72), and other relevant guidance documents in an effort to clarify that security events should not be considered in the QA design process of important to safety SSCs for the MGDS. The MGDS is a first of a kind geologic repository and no licensing precedent has been established for this type of facility

Equipment line-up developed for structuring programmed digital systems important to safety

International Nuclear Information System (INIS)

Remus, L.; Colling, J.M.; Buisson, J.

1986-01-01

The use of the programmed digital techniques in systems important to safety led to developing equipment line-ups which allow to procedure, through using a restricted number of sub-assemblies, a variety of facilities capable of performing diversified functions. Upon remembering the requirements that such equipment are required to meet (quality assurance both at the design and production stages, qualification, testing opportunities, etc.) the equipments produced by MERLIN GERIN are described in this paper. Such equipments include a whole set of printed circuit boards, plug-in units with self-engaging connectors and the related cabinets to accomodate them. The following systems are made up of such equipments: Digital integrated protection system; Rod control and monitoring system; Reactor power distribution monitoring equipment. This equipment line-up has been gradually complemented and is still further expanding both as a result of the component further development or for the purpose of meeting new requirements or applications (new digital neutron instrumentation, local area networks). Experience gained thus far provides us with the capability of working out in a short time programmed systems for further applications in the nuclear power field

Mean importance measures for groups of events in fault trees

International Nuclear Information System (INIS)

Haskin, F.E.; Huang, Min

1994-01-01

The method of moments is applied to precisely determine the mean values of three importance measures: risk reduction, partial derivative, and variance reduction. Variance reduction calculations, in particular, are significantly improved by eliminating the imprecision associated with Monte Carlo estimates. The three importance measures are extended to permit analyses of the relative importance of groups of basic and initiating events. The partial derivative importance measure is extended by assessing the contribution of a group of events to the gradient of the top event frequency. The group importance measures are quantified for the overall fuel damage equation and for 14 dominant accident sequences from an independent probabilistic safety assessment of the K Production Reactor. This application demonstrates both the utility and the versatility of the group importance measures

Mean importance measures for groups of events in fault trees

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E.; Huang, Min [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Sasser, M.K.; Stack, D.W. [Los Alamos National Lab., NM (United States)

1993-10-12

The method of moments is applied to precisely determine the mean values of three importance measures: risk reduction, partial derivative, and variance reduction. Variance reduction calculations, in particular, are significantly improved by eliminating the imprecision associated with Monte Carlo estimates. The three importance measures are extended to permit analyses of the relative importance of groups of basic and initiating events. The partial derivative importance measure is extended by assessing the contribution of a group of events to the gradient of the top event frequency. The group importance measures are quantified for the overall fuel damage equation and for 14 dominant accident sequences from an independent probabilistic safety assessment of the K Production Reactor. This application demonstrates both the utility and the versatility of the group importance measures.

Mean importance measures for groups of events in fault trees

International Nuclear Information System (INIS)

Haskin, F.E.; Huang, Min

1993-01-01

The method of moments is applied to precisely determine the mean values of three importance measures: risk reduction, partial derivative, and variance reduction. Variance reduction calculations, in particular, are significantly improved by eliminating the imprecision associated with Monte Carlo estimates. The three importance measures are extended to permit analyses of the relative importance of groups of basic and initiating events. The partial derivative importance measure is extended by assessing the contribution of a group of events to the gradient of the top event frequency. The group importance measures are quantified for the overall fuel damage equation and for 14 dominant accident sequences from an independent probabilistic safety assessment of the K Production Reactor. This application demonstrates both the utility and the versatility of the group importance measures

Exploration of Important Issues for the Safety of SFR 1 using Performance Assessment Calculations

International Nuclear Information System (INIS)

Maul, P.R.; Robinson, P.C.

2002-06-01

SKB has produced a revised safety case for the SFR 1 disposal facility for low and intermediate level radioactive wastes at Forsmark: project SAFE. This assessment includes a Performance Assessment (PA) for the long term post-closure safety of the facility. SKI has a responsibility to scrutinise SKB's safety case that is shared with SSI. Quintessa has undertaken a review of SKB's case for the long term safety of SFR 1 to assist SKI's evaluation of SAFE, and this is given in SKI-R--02-61, henceforth referred to as the Quintessa Review. The current report describes the independent PA calculations that provided an input to that review. Since 1999 SKI has been developing a PA capability for SFR 1 using the AMBER software. Two key features of the approach taken have been: To represent the whole system in a single model; and To allow the time-dependency of all key features, events and processes to be represented. These capabilities allow a better understanding of the key features of the system to be obtained for different future evolutions (scenarios). This report presents a summary of the work undertaken to provide SKI with a PA capability for SFR 1 and the calculations undertaken with it. Calculations have been undertaken for radionuclides transported in groundwater and gas, but not for direct intrusion by humans into the wastes. It should be emphasised that the purpose of the Performance Assessment calculations described in this report is not to provide an alternative assessment of potential radiological impacts to that produced by SKB. The aim is to use the models that have been developed to investigate the important features of the system and to help SKI scrutinise the case put to them by SKB. The PA calculations that have been undertaken are by no means comprehensive, and various issues could be investigated further if required. The key issues that have been identified can be summarised as follows: 1. The SFR 1 system has a number of different timescales that can

Non-Destructive Techniques in the Tacis and Phare Nuclear Safety Programmes

International Nuclear Information System (INIS)

Bieth, Michel

2002-01-01

Decisions regarding the verification of design plant lifetime and potential license renewal periods involve a determination of the component and circuit condition. In Service Inspection of key reactor components becomes a crucial consideration for continued safe plant operation. The determination of the equipment properties by Non Destructive Techniques during periodic intervals is an important aspect of the assessment of fitness-for-service and safe operation of nuclear power plants The Tacis and Phare were established since 1991 by the European Union as support mechanisms through which projects could be identified and addressed satisfactorily. In Nuclear Safety, the countries mainly concerned are Russia, Ukraine, Armenia, and Kazakhstan for the Tacis programme, and Bulgaria, Czech Republic, Hungary, Slovak Republic, Lithuania, Romania and Slovenia for the Phare programme. The Tacis and Phare programs concerning the Nuclear Power Plants consist of: - On Site Assistance and Operational Safety, - Design Safety, - Regulatory Authorities, - Waste management, and are focused on reactor safety issues, contributing to the improvement in the safety of East European reactors and providing technology and safety culture transfer. The main parts of these programmes are related to the On-Site Assistance and to the Design Safety of VVER and RBMK Nuclear power plants where Non Destructive Techniques for In Service Inspection of the primary circuit components are addressed. (authors)

A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

International Nuclear Information System (INIS)

Yang, Seung Hyo; Choi, Sun Do

2012-01-01

Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control

A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

Energy Technology Data Exchange (ETDEWEB)

Yang, Seung Hyo; Choi, Sun Do [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2012-10-15

Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control.

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)

75 FR 48736 - Culturally Significant Objects Imported for Exhibition Determinations: “Kurt Schwitters: Color...

Science.gov (United States)

2010-08-11

... DEPARTMENT OF STATE [Public Notice 7117] Culturally Significant Objects Imported for Exhibition Determinations: ``Kurt Schwitters: Color and Collage'' SUMMARY: Notice is hereby given of the following... objects to be included in the exhibition ``Kurt Schwitters: Color and Collage,'' imported from abroad for...

75 FR 28848 - Culturally Significant Objects Imported for Exhibition Determinations: “The Original Copy...

Science.gov (United States)

2010-05-24

... DEPARTMENT OF STATE [Public Notice 7027] Culturally Significant Objects Imported for Exhibition Determinations: ``The Original Copy: Photography of Sculpture, 1839 to Today'' SUMMARY: Notice is hereby given of... included in the exhibition ``The Original Copy: Photography of Sculpture, 1839 to Today,'' imported from...

Resolving conflicting safety cultures

International Nuclear Information System (INIS)

Slider, J.E.; Patterson, M.

1993-01-01

Several nuclear power plant sites have been wounded in the crossfire between two distinct corporate cultures. The traditional utility culture lies on one side and that of the nuclear navy on the other. The two corporate cultures lead to different perceptions of open-quotes safety culture.close quotes This clash of safety cultures obscures a very important point about nuclear plant operations: Safety depends on organizational learning. Organizational learning provides the foundation for a perception of safety culture that transcends the conflict between utility and nuclear navy cultures. Corporate culture may be defined as the knowledge, attitudes, and beliefs shared by employees of a given company. Safety culture is the part of corporate culture concerning shared attitudes and beliefs affecting individual or public safety. If the safety culture promotes behaviors that lead to greater safety, employees will tend to open-quotes do the right thingclose quotes even when circumstances and formal guidance alone do not ensure that actions will be correct. Safety culture has become particularly important to nuclear plant owners and regulators as they have sought to establish and maintain a high level of safety in today's plants

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

Determining minimally important score differences in scales of the Copenhagen Psychosocial Questionnaire

DEFF Research Database (Denmark)

Pejtersen, Jan Hyld; Bjorner, Jakob Bue; Hasle, Peter

2010-01-01

AIM: To determine minimally important differences (MIDs) for scales in the first version of the Copenhagen Psychosocial Questionnaire (COPSOQ). METHODS: Data were taken from two separate studies: a national population survey (N = 1062), and an intervention study at 14 workplaces (N = 1505). On th...

The impact of health and safety committees. A study based on survey, interview, and Occupational Safety and Health Administration data.

Science.gov (United States)

Boden, L I; Hall, J A; Levenstein, C; Punnett, L

1984-11-01

In a study conducted to determine if the existence of a joint labor-management health and safety committee (HSC) was correlated with either the number of Occupational Safety and Health Administration (OSHA) complaints or hazardousness, as measured by OSHA serious citations, virtually no effect could be detected in a sample of 127 Massachusetts manufacturing firms. At a sample of 13 firms, interviews of HSC members were conducted. Committee attributes and perceptions about committee effectiveness were compared with the number of OSHA complaints and serious citations. There were fewer complaints and fewer serious citations at firms with HSCs that were perceived as effective. Results of the study suggest that the objective attributes of the committee may be less important to its success than the commitment of management and labor to solving workplace safety problems.

Communication's Role in Safety Management and Performance for the Road Safety Practices

OpenAIRE

Salim Keffane (s)

2014-01-01

Communication among organizations could play an important role in increasing road safety. To get in-depth knowledge of its role, this study measured managers' and employees' perceptions of the communication's role on six safety management and performance criteria for road safety practices by conducting a survey using a questionnaire among 165 employees and 135 managers. Path analysis using AMOS-19 software shows that some of the safety management road safety practices have high correlation wi...

"Too big to fail" or "Too non-traditional to fail"?: The determinants of banks' systemic importance

OpenAIRE

Moore, Kyle; Zhou, Chen

2013-01-01

This paper empirically analyzes the determinants of banks' systemic importance. In constructing a measure on the systemic importance of financial institutions we find that size is a leading determinant. This confirms the usual "Too big to fail'' argument. Nevertheless, banks with size above a sufficiently high level have equal systemic importance. In addition to size, we find that the extent to which banks engage in non-traditional banking activities is also positively related to ...

Preliminary study on improving safety culture in Malaysian nuclear industries

International Nuclear Information System (INIS)

Ibrahim, Sabariah Kader; Lee, Y. E.

2012-01-01

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed

Preliminary study on improving safety culture in Malaysian nuclear industries

Energy Technology Data Exchange (ETDEWEB)

Ibrahim, Sabariah Kader [KAIST, Daejeon (Korea, Republic of); Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-10-15

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed.

The importance of safety in achieving the widespread use of hydrogen as a fuel

Energy Technology Data Exchange (ETDEWEB)

Edeskuty, F.J.

1997-09-01

The advantages of hydrogen fuel have been adequately demonstrated on numerous occasions. However, two major disadvantages have prevented any significant amount of corresponding development. These disadvantages have been in the economics of producing sufficient quantities of hydrogen and in the safety (both real and perceived) of its use. To date work has mostly been properly centered on solving the economic problems. However, a greater effort on the safety of new hydrogen systems now being proposed also deserves consideration. To achieve the greatest safety in the expansion of the use of hydrogen into its wide-spread use as a fuel, attention must be given to four considerations. These are, obtaining knowledge of all the physical principles involved in the new uses, having in place the regulations that allow the safe interfacing of the new systems, designing and constructing the new systems with safety in mind, and the training of the large number of people that will become the handlers of the hydrogen. Existing organizations that produce, transport, or use hydrogen on a large scale have an excellent safety record. This safety record comes as a consequence of dedicated attention to the above-mentioned principles. However, where these principles were not closely followed, accidents have resulted. Some examples can be cited. As the use of hydrogen becomes more widespread, there must be a mechanism for assuring the universal application of these principles. Larger and more numerous fleet operations with hydrogen fuel may be the best way to begin the indoctrination of the general public to the more general use of hydrogen fuel. Demonstrated safe operation with hydrogen is vital to its final acceptance as the fuel of choice.

Behavioral based safety approaches

International Nuclear Information System (INIS)

Maria Michael Raj, I.

2009-01-01

Approach towards the establishment of positive safety culture at Heavy Water Plant, Tuticorin includes the adoption of several important methodologies focused on human behavior and culminates with achievement of Total Safety Culture where Quality and Productivity are integrated with Safety

Safety balance: Analysis of safety systems; Bilans de surete: analyse par les organismes de surete

Energy Technology Data Exchange (ETDEWEB)

Delage, M; Giroux, C

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses.

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

An approach for Periodic Safety Review (PSR) of units 5 and 6 of Kozloduy NPP

International Nuclear Information System (INIS)

Kichev, Emil

2014-01-01

Periodic Safety Reviews (PSR) is complementary to the routine and special safety reviews and does not replaced them. It determines the level of compliance with current safety requirements and covers all safety aspects of NPP operation and all equipment (SSCs) on site. Three levels of importance are defined for the documents in PSR (towards higher conservatism): Bulgarian documents; IAEA documents; Documents of manufactures and suppliers of the equipment (SSCs). The scope and activities consists of four stages and includes 14 safety factors (SF). Cooperation with external companies and organizations in areas with proved experience is used.

Safety assessment of automated vehicle functions by simulation-based fault injection

OpenAIRE

Juez, Garazi; Amparan, Estibaliz; Lattarulo, Ray; Rastelli, Joshue Perez; Ruiz, Alejandra; Espinoza, Huascar

2017-01-01

As automated driving vehicles become more sophisticated and pervasive, it is increasingly important to assure its safety even in the presence of faults. This paper presents a simulation-based fault injection approach (Sabotage) aimed at assessing the safety of automated vehicle functions. In particular, we focus on a case study to forecast fault effects during the model-based design of a lateral control function. The goal is to determine the acceptable fault detection interval for pe...

Mitigating construction safety risks using prevention through design.

Science.gov (United States)

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

2010-04-01

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

15 CFR 705.11 - Determination by the President and adjustment of imports.

Science.gov (United States)

2010-01-01

... Foreign Trade (Continued) BUREAU OF INDUSTRY AND SECURITY, DEPARTMENT OF COMMERCE NATIONAL SECURITY INDUSTRIAL BASE REGULATIONS EFFECT OF IMPORTED ARTICLES ON THE NATIONAL SECURITY § 705.11 Determination by... national security, the President is required by Section 232(c) of the Trade Expansion Act of 1962, as...

Major food safety episodes in Taiwan: implications for the necessity of international collaboration on safety assessment and management.

Science.gov (United States)

Li, Jih-Heng; Yu, Wen-Jing; Lai, Yuan-Hui; Ko, Ying-Chin

2012-07-01

The major food safety episodes that occurred in Taiwan during the past decade are briefly reviewed in this paper. Among the nine major episodes surveyed, with the exception of a U.S. beef (associated with Creutzfeldt-Jakob disease)-related incident, all the others were associated with chemical toxicants. The general public, which has a layperson attitude of zero tolerance toward food safety, may panic over these food-safety-associated incidents. However, the health effects and impacts of most incidents, with the exception of the melamine incident, were essentially not fully evaluated. The mass media play an important role in determining whether a food safety concern becomes a major incident. A well-coordinated and harmonized system for domestic and international collaboration to set up standards and regulations is critical, as observed in the incidents of pork with ractopamine, Chinese hairy crab with nitrofuran antibiotics, and U.S. wheat with malathion. In the future, it can be anticipated that food safety issues will draw more attention from the general public. For unknown new toxicants or illicit adulteration of food, the establishment of a more proactive safety assessment system to monitor potential threats and provide real-time information exchange is imperative. Copyright © 2012. Published by Elsevier B.V.

Determining animal drug combinations based on efficacy and safety.

Science.gov (United States)

Kratzer, D D; Geng, S

1986-08-01

A procedure for deriving drug combinations for animal health is used to derive an optimal combination of 200 mg of novobiocin and 650,000 IU of penicillin for nonlactating cow mastitis treatment. The procedure starts with an estimated second order polynomial response surface equation. That surface is translated into a probability surface with contours called isoprobs. The isoprobs show drug amounts that have equal probability to produce maximal efficacy. Safety factors are incorporated into the probability surface via a noncentrality parameter that causes the isoprobs to expand as safety decreases, resulting in lower amounts of drug being used.

75 FR 53012 - Culturally Significant Objects Imported for Exhibition Determinations: “Treasures of Moscow...

Science.gov (United States)

2010-08-30

... Rublev Museum,'' imported from abroad for temporary exhibition within the United States, are of cultural... Determinations: ``Treasures of Moscow: Icons From the Andrey Rublev Museum'' SUMMARY: Notice is hereby given of... determine that the exhibition or display of the exhibit objects at the Museum of Russian Icons, Clinton, MA...

China's nuclear safety regulatory body: The national nuclear safety administration

International Nuclear Information System (INIS)

Zhang Shiguan

1991-04-01

The establishment of an independent nuclear safety regulatory body is necessary for ensuring the safety of nuclear installations and nuclear fuel. Therefore the National Nuclear Safety Administration was established by the state. The aim, purpose, organization structure and main tasks of the Administration are presented. At the same time the practical examples, such as nuclear safety regulation on the Qinshan Nuclear Power Plant, safety review and inspections for the Daya Bay Nuclear Power Plant during the construction, and nuclear material accounting and management system in the nuclear fuel fabrication plant in China, are given in order to demonstrate the important roles having been played on nuclear safety by the Administration after its founding

Safety culture

International Nuclear Information System (INIS)

1991-01-01

The response to a previous publication by the International Nuclear Safety Advisory Group (INSAG), indicated a broad international interest in expansion of the concept of Safety Culture, in such a way that its effectiveness in particular cases may be judged. This report responds to that need. In its manifestation, Safety Culture has two major components: the framework determined by organizational policy and by managerial action, and the response of individuals in working within and benefiting by the framework. 1 fig

Safety culture: modern slogan or effective contribution to safety?

International Nuclear Information System (INIS)

Salm, M.

1994-01-01

Safety culture is defined and its impact on nuclear power plants is documented using the words of the INSAG of IAEA. Two examples from the field of aviation and space flight testify, that the upper management, by its sheer image, may considerably influence actions of the lower levels of the hierarchy. Management therefore can do a lot more for safety than is commonly assumed. Two examples, although separated by 57 years, show that the mentioned influence remains unchanged inspire of progress in management- and organisation-methods as well as in safety-engineering. Safety culture is an overriding element of safety, acting at all levels of a hierarchy. Its action is most important on those levels, for which precise reglementation is hardly possible. The chain of technical and organisational measures guarantees safety only under the condition, that it is embedded in 'safety culture'. Safety culture therefore merits our full attention. (author) 1 fig

Safety strategy and safety analysis of nuclear power plants

International Nuclear Information System (INIS)

Franzen, L.F.

1976-01-01

The safety strategy for nuclear power plants is characterized by the fact that the high level of safety was attained not as a result of experience, but on the basis of preventive accident analyses and the finding derived from such analyses. Although, in these accident analyses, the deterministic approach is predominant, it is supplemented by reliability analyses. The accidents analyzed in nuclear licensing procedures cover a wide spectrum from minor incidents to the design basis accidents which determine the design of the safety devices. The initial and boundary conditions, which are essentail for accident analyses, and the determination of the loads occurring in various states during regular operation and in accidents flow into the design of the individual systems and components. The inevitable residual risk and its origins are discussed. (orig.) [de

Determination of mineral contents of wild Boletus edulis mushroom and its edible safety assessment.

Science.gov (United States)

Su, Jiuyan; Zhang, Ji; Li, Jieqing; Li, Tao; Liu, Honggao; Wang, Yuanzhong

2018-04-06

This study aimed to determine the contents of main mineral elements of wild Boletus edulis and to assess its edible safety, which may provide scientific evidence for the utilization of this species. Fourteen mineral contents (Ba, Ca, Cd, Co, Cr, Cu, Fe, Mg, Mn, Na, Ni, Sr, V and Zn) in the caps and stipes of B. edulis as well as the corresponding surface soils collected from nine different geographic regions in Yunnan Province, southwest China were determined. The analyses were performed using inductively coupled plasma atomic emission spectrometer (ICP-AES) after microwave digestion. Measurement data were analyzed using variance and Pearson correlation analysis. Edible safety was evaluated according to the provisionally tolerable weekly intake (PTWI) of heavy metals recommended by United Nations Food and Agriculture Organization and World Health Organization (FAO/WHO). Mineral contents were significantly different with the variance of collection areas. B. edulis showed relative abundant contents of Ca, Fe, Mg and Na, followed by Ba, Cr, Cu, Mn and Zn, and the elements with the lower content less were Cd, Co, Ni, Sr and V. The elements accumulation differed significantly in caps and stipes. Among them, Cd and Zn were bioconcentrated (BCF > 1) while others were bioexcluded (BCF < 1). The mineral contents in B. edulis and its surface soil were positively related, indicating that the elements accumulation level was related to soil background. In addition, from the perspective of food safety, if an adult (60 kg) eats 300 g fresh B. edulis per week, the intake of Cd in most of tested mushrooms were lower than PTWI value whereas the Cd intakes in some other samples were higher than this standard. The results indicated that the main mineral contents in B. edulis were significantly different with respect to geographical distribution, and the Cd intake in a few of regions was higher than the acceptable intakes with a potential risk.

The importance of safety in achieving the widespread use of hydrogen as a fuel

Energy Technology Data Exchange (ETDEWEB)

Edeskuty, F.J. [Los Alamos National Laboratory, Los Alamos, NM (United States)

1998-07-01

The advantages of hydrogen fuel have been adequately demonstrated on numerous occasions. However, two major disadvantages have prevented any significant amount of corresponding development. These disadvantages have been in the economics of producing sufficient quantities of hydrogen and in the safety (both real and perceived) of its use. To date, work has mostly been properly centered on solving the economic problems. However, a greater effort on the safety of new hydrogen systems now being proposed also deserves consideration. To achieve the greatest safety in the expansion of the use of hydrogen into its wide-spread use as a fuel, attention must be given to four considerations. These are, obtaining knowledge of all the physical principles involved in the new uses, using that knowledge to put in place the regulations that allow the safe interfacing of the new systems, designing and constructing the new systems with safety in mind, and the training of the large number of people that will become the handlers of the hydrogen. Existing organizations that produce, transport, or use hydrogen on a large scale have an excellent safety record. This safety record comes as a consequence of dedicated attention to the above-mentioned principle. However, where these principles were not closely followed, accidents have resulted. Some examples are cited. As the use of hydrogen becomes more wide-spread, there must be a mechanism for assuring the universal application of these principles. Larger and more numerous fleet operations with hydrogen fuel may be the best way to begin the indoctrination of the general public to the more general use of hydrogen fuel. Demonstrated safe operation with hydrogen is vital to its final acceptance as the fuel of choice. 18 refs.

Importance of cattle breeding in the nourishment safety of families in the rural area of Paipa, Boyaca

Directory of Open Access Journals (Sweden)

Diana Milena Soler Fonseca

2011-05-01

Full Text Available In the rural municipality of Paipa, Boyaca many families rely on cattle breeding to obtain from this activity, suficient income and resources to meet their basic needs, however little is known about the true role of this species in the nourishment safety of rural families in the municipality of Paipa in Boyacá, for that reason, this study aimed to analyze the importance of general breeding cattle in the nourishment safety of thirty peasant families in the municipality of Paipa, Boyacá and get to know the social and cultural roles that are generated by this livestock activity. The obtained result was that the cale are raised as a second choice in the pursuit of economic resources, after the birds. In cattle production an average of  five animals per farm are raised, the widely used breeds are the Normando, Holstein and crosses between them; milk production dominates with an average yield of 150 liters/week per family; income and costs production depend on the number of cattle raised, the gained income is used to purchase food for home, but savings are not encouraged; the consumption of dairy products is very low and beef cattle is not consumed within the household; animals management is in charge of all family members (both genders. In general, cattle farming make interesting economic contributions to the countryside families, but these revenues are used to purchase food of high nutritional value, also a2ecting the nourishment safety of the studied families.

The relationship between organizational leadership for safety and learning from patient safety events.

Science.gov (United States)

Ginsburg, Liane R; Chuang, You-Ta; Berta, Whitney Blair; Norton, Peter G; Ng, Peggy; Tregunno, Deborah; Richardson, Julia

2010-06-01

To examine the relationship between organizational leadership for patient safety and five types of learning from patient safety events (PSEs). Forty-nine general acute care hospitals in Ontario, Canada. A nonexperimental design using cross-sectional surveys of hospital patient safety officers (PSOs) and patient care managers (PCMs). PSOs provided data on organization-level learning from (a) minor events, (b) moderate events, (c) major near misses, (d) major event analysis, and (e) major event dissemination/communication. PCMs provided data on organizational leadership (formal and informal) for patient safety. Hospitals were the unit of analysis. Seemingly unrelated regression was used to examine the influence of formal and informal leadership for safety on the five types of learning from PSEs. The interaction between leadership and hospital size was also examined. Formal organizational leadership for patient safety is an important predictor of learning from minor, moderate, and major near-miss events, and major event dissemination. This relationship is significantly stronger for small hospitals (learning from safety events. Formal leadership support for safety is of particular importance in small organizations where the economic burden of safety programs is disproportionately large and formal leadership is closer to the front lines.

The clinical importance of radiological determination of the heart volume

International Nuclear Information System (INIS)

Jaedicke, W.; Ong, T.S.; Barmeyer, J.

1982-01-01

The size of the heart is an autonomous, important parameter of its functional state, i.e. in the radiologic heart diagnostics, the measurement of the heart volume is of equal value as the shape analysis. A size determination which must be exact enough for course controls and differentiation from the normal picture makes sense only if the measurement is carriet out in 3 dimensions and not in only one as is done when determining the heart-lung-quotient. The heart volume measurement carried out in lying or sitting position is considerably more reliable than in standing position as too many extracardiac factors influence the heart volume when the patient is standing. The echo cardiogram is a nearly ideal supplement but no competitor of radiological heart volume measurement and can be of the same value as or superior to heart volume measurement for functional diagnostics only in diseases limited to nearly exclusively to the left ventricle as in coronary diseases. (orig.) [de

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

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

Safety of nuclear power plants: Design. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

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

CONCEPTUAL APPROACHES TO FORMING MECHANISM OF INVESTMENT SAFETY REALIZATION

Directory of Open Access Journals (Sweden)

Vladimir Talover

2016-11-01

Full Text Available The purpose of the paper is theoretical justification of theoretical approaches while developing the mechanism of the state investment safety. The tasks of the system of the national economy investment safety are the following: developing investment potential, creating favourable investment climate, forming mechanisms of stable investment activity in the key branches of economy. At the same time, it should also be noted that the complex approach that would allow sufficiently justifying and practically solve the problems of defining indicators, factors of the investment policy and directions of its assurance in realization of the mechanism of investment policy is not sufficiently developed nowadays. This fact determines research topicality. The issue of assuring investment safety is of a special importance in Ukraine that has to assure market economy development, to overcome deformations in the economy structure, to renew products and production apparatus in the industry, to master new kinds of activities. Methodology. The survey is based on the generalization and development of views of the scientific-economic schools, uses approaches of the international agencies and recommendation and normative materials of Ukraine concerning realization of the state investment policy as a totality of interrelated levels and subsystems that allows establishing main functions of the investment safety system. Results of the survey shows that the mechanism of investment safety includes some kinds, forms and methods of organizing investment relations and investment activity, ways of their quantitative determination and establishing interdependence. The concept of investment policy is based on the complex approach and includes the blocks which are locally structured in such way that they allow forming adequate system of its indicators and conducting monitoring of their changes under the influence of the determined factors. The peculiarities and elements of

Determining consumer purchase intentions: the importance of dry matter, size, and price of kiwifruit.

Science.gov (United States)

Jaeger, Sara R; Harker, Roger; Triggs, Chris M; Gunson, Anne; Campbell, Rachel L; Jackman, Richard; Requejo-Jackman, Cecilia

2011-04-01

Knowledge of the relative importance of food quality attributes in determining consumer purchase intention is critical for robust assessment of economic opportunities for industry growth. The aim of this study is to demonstrate how conjoint analysis methodology that incorporates tasting of fruit can be used to collect such information. Three hundred Japanese consumers took part in research designed to measure the importance of dry matter (DM), size, and price of kiwifruit (Actinidia deliciosa "Hayward" and Actinidia chinensis "Hort16A") for purchase intention. Measurement of consumer liking for kiwifruit of different DM content was a key first step. Liking increased as DM increased and was accompanied by increased purchase likelihood/choice probability for kiwifruit. The size of kiwifruit presented to consumers varied from "small" to "extra large." Consumers liked "mid-sized" kiwifruit over "small" or "extra-large" kiwifruit. Despite these differences in liking, size was of little importance in determining purchase likelihood/choice probability for kiwifruit. Price was a very important factor in determining purchase likelihood/choice probability but was less important than DM content. As price increased, purchase likelihood/choice probability decreased. Beneath these general findings, heterogeneity existed. Some consumers placed more/less importance on the focal purchase drivers than suggested by the aggregate model. Overall, the results suggest that incentive schemes already implemented by industry should consider rewarding high-DM fruit more than fruit size.   This research has contributed to the New Zealand kiwifruit industry gaining a better understanding of the relative importance consumers place on DM, size, and price of kiwifruit and has resulted in changes to grower incentive schemes. The research approach presented forces consumer to tradeoff attributes of kiwifruit against each other and decide on how important two key quality attributes-DM and

Safety issues at the defense production reactors

International Nuclear Information System (INIS)

1987-01-01

The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors endash the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. The report is necessarily based on a limited review of the defense production reactors. It does not address whether any of the reactors are ''safe,'' because such an analysis would involve a determination of acceptable risk endash a matter of obvious importance, but one that was beyond the purview of the committee. It also does not address whether the safety of the production reactors is comparable to that of commercial nuclear power stations, because even this narrower question extended beyond the charge to the committee and would have involved detailed analyses that the committee could not undertake

Patient safety in out-of-hours primary care: a review of patient records

Directory of Open Access Journals (Sweden)

Wensing Michel

2010-12-01

Full Text Available Abstract Background Most patients receive healthcare in primary care settings, but relatively little is known about patient safety. Out-of-hours contacts are of particular importance to patient safety. Our aim was to examine the incidence, types, causes, and consequences of patient safety incidents at general practice cooperatives for out-of-hours primary care and to examine which factors were associated with the occurrence of patient safety incidents. Methods A retrospective study of 1,145 medical records concerning patient contacts with four general practice cooperatives. Reviewers identified records with evidence of a potential patient safety incident; a physician panel determined whether a patient safety incident had indeed occurred. In addition, the panel determined the type, causes, and consequences of the incidents. Factors associated with incidents were examined in a random coefficient logistic regression analysis. Results In 1,145 patient records, 27 patient safety incidents were identified, an incident rate of 2.4% (95% CI: 1.5% to 3.2%. The most frequent incident type was treatment (56%. All incidents had at least partly been caused by failures in clinical reasoning. The majority of incidents did not result in patient harm (70%. Eight incidents had consequences for the patient, such as additional interventions or hospitalisation. The panel assessed that most incidents were unlikely to result in patient harm in the long term (89%. Logistic regression analysis showed that age was significantly related to incident occurrence: the likelihood of an incident increased with 1.03 for each year increase in age (95% CI: 1.01 to 1.04. Conclusion Patient safety incidents occur in out-of-hours primary care, but most do not result in harm to patients. As clinical reasoning played an important part in these incidents, a better understanding of clinical reasoning and guideline adherence at GP cooperatives could contribute to patient safety.

Seismic safety of Paks nuclear power plant

International Nuclear Information System (INIS)

Katona, T.

1993-01-01

An extensive program is underway at Paks NPP for evaluation of the seismic safety and for development of the necessary safety increasing measures. This program includes the following five measures: investigation of methods, regulations and techniques utilized for reassessment of seismic safety of operating NPPs and promoting safety; investigation of earthquake hazards; development of concepts for creating the seismic safety location of earthquake warning system; determination of dynamic features of systems and facilities determined by the concept, and preliminary evaluation of the seismic safety

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

International Nuclear Information System (INIS)

Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

2001-01-01

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

Perceived School Safety is Strongly Associated with Adolescent Mental Health Problems

NARCIS (Netherlands)

Nijs, Miesje M.; Bun, Clothilde J. E.; Tempelaar, Wanda M.; de Wit, Niek J.; Burger, Huibert; Plevier, Carolien M.; Boks, Marco P. M.

School environment is an important determinant of psychosocial function and may also be related to mental health. We therefore investigated whether perceived school safety, a simple measure of this environment, is related to mental health problems. In a population-based sample of 11,130 secondary

Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

International Nuclear Information System (INIS)

Khazanov, A.L.

2005-01-01

The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

Seismic methodology in determining basis earthquake for nuclear installation

International Nuclear Information System (INIS)

Ameli Zamani, Sh.

2008-01-01

Design basis earthquake ground motions for nuclear installations should be determined to assure the design purpose of reactor safety: that reactors should be built and operated to pose no undue risk to public health and safety from earthquake and other hazards. Regarding the influence of seismic hazard to a site, large numbers of earthquake ground motions can be predicted considering possible variability among the source, path, and site parameters. However, seismic safety design using all predicted ground motions is practically impossible. In the determination of design basis earthquake ground motions it is therefore important to represent the influences of the large numbers of earthquake ground motions derived from the seismic ground motion prediction methods for the surrounding seismic sources. Viewing the relations between current design basis earthquake ground motion determination and modem earthquake ground motion estimation, a development of risk-informed design basis earthquake ground motion methodology is discussed for insight into the on going modernization of the Examination Guide for Seismic Design on NPP

The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

Nuclear criticality safety program at the Fuel Cycle Facility

International Nuclear Information System (INIS)

Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

1994-01-01

The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

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.

Specification of requirements for the implementation of ASICs and FPGA in instrumentation and control systems important to safety in German NPPs

International Nuclear Information System (INIS)

Schnurer, G.

2007-01-01

This paper gives an overview concerning the design as well as the verification and validation of Application Specific Integrated Circuits (ASICs) and Field Programmable Gate Arrays (FPGA) in German NPPs which are applied to carry out I and C functions. The qualification procedures dealt with restricted on ASICs without any microcontroller core. Dependent on the different safety categories, recommendations concerning the qualification level and procedures are elaborated which have to be achieved for ASICs and FPGA. Important aspects within the framework of the expert judgement for upgrading of safety relevant I and C by ASICs and FPGA are dealt with. These aspects are of general character and are mainly focused on suitability test procedures and robustness requirements of ASICs and FPGA

76 FR 58074 - Culturally Significant Objects Imported for Exhibition Determinations: “Sanja Iveković: Sweet...

Science.gov (United States)

2011-09-19

... DEPARTMENT OF STATE [Public Notice: 7590] Culturally Significant Objects Imported for Exhibition Determinations: ``Sanja Ivekovi[cacute]: Sweet Violence'' SUMMARY: Notice is hereby given of the following... exhibition ``Sanja Ivekovi[cacute]: Sweet Violence,'' imported from abroad for temporary exhibition within...

76 FR 58075 - Culturally Significant Objects Imported for Exhibition Determinations: “Sanja Iveković: Sweet...

Science.gov (United States)

2011-09-19

... DEPARTMENT OF STATE [Public Notice: 7590] Culturally Significant Objects Imported for Exhibition Determinations: ``Sanja Ivekovi[cacute]: Sweet Violence'' SUMMARY: Notice is hereby given of the following... exhibition ``Sanja Ivekovi[cacute]: Sweet Violence,'' imported from abroad for temporary exhibition within...

Use of risk importance measures in maintenance prioritization

International Nuclear Information System (INIS)

Dubreil Chambardel, A.; Ardorino, F.; Mauger, P.

1997-01-01

A RCM method has been developed at EDF since 1990 to optimize maintenance through a prioritization of resources for equipment that are important in terms of safety, availability and maintenance costs. In 1994, the Nuclear Power Plant Operations Division decided to apply this method to the most important systems of the French PWRs. About 50 systems are in the scope of the RCM. Those that have a role in safety were ranked depending on their contribution to the risk of core melt provided by PSAs. The RCM studies on the 20 most important to safety systems are performed by the Nuclear Power Plant Operations division, the other 30 systems are studied on sites. The RCM study consists first in the research of equipment and failures modes significant to safety, availability or maintenance costs and the evaluation of the performance of those equipment. Those studies lead to the distinction of equipment and failure modes that are critical or non critical to safety, availability and costs. The last part of the study consists in optimizing maintenance on those equipment. In this process, risk measures are used to help defining equipment and failure modes critical to safety. This is done by calculation of risk importance measures provided by PSAs. We explain in this paper which measures of risk have been defined, how PSAs allow calculation of those measures, and how we used those results in the RCM studies we processed. We give also extensions of the use of those measures in the process of defining optimized maintenance tasks. After having defined a RCM method for the French PWRs, the Nuclear Power plant Operations Division decided to start a generalized program of maintenance optimization for the most important systems. The three criteria on which the method relies are: safety, unit availability and maintenance costs. We present here the safety aspect of the method and more precisely these of risk importance measures in the RCM process. (author)

78 FR 9938 - Ethyl Alcohol for Fuel Use: Determination of the Base Quantity of Imports

Science.gov (United States)

2013-02-12

... INTERNATIONAL TRADE COMMISSION [Investigation No. 332-288] Ethyl Alcohol for Fuel Use: Determination of the Base Quantity of Imports AGENCY: United States International Trade Commission. ACTION... the statutory requirement that the Commission make such determinations. Section 423(c) of the Tax...

75 FR 38589 - Culturally Significant Objects Imported for Exhibition Determinations: “Venice: Canaletto and His...

Science.gov (United States)

2010-07-02

... DEPARTMENT OF STATE [Public Notice: 7072] Culturally Significant Objects Imported for Exhibition Determinations: ``Venice: Canaletto and His Rivals'' SUMMARY: Notice is hereby given of the following... exhibition ``Venice: Canaletto and His Rivals,'' imported from abroad for temporary exhibition within the...

76 FR 10936 - Culturally Significant Objects Imported for Exhibition Determinations: “Richard Serra Drawing: A...

Science.gov (United States)

2011-02-28

... DEPARTMENT OF STATE [Public Notice: 7348] Culturally Significant Objects Imported for Exhibition Determinations: ``Richard Serra Drawing: A Retrospective'' SUMMARY: Notice is hereby given of the following... objects to be included in the exhibition ``Richard Serra Drawing: A Retrospective,'' imported from abroad...

78 FR 52997 - Culturally Significant Objects Imported for Exhibition Determinations: “Yoga: the Art of...

Science.gov (United States)

2013-08-27

... DEPARTMENT OF STATE [Public Notice 8440] Culturally Significant Objects Imported for Exhibition Determinations: ``Yoga: the Art of Transformation'' SUMMARY: Notice is hereby given of the following... ``Yoga: the Art of Transformation,'' imported from abroad for temporary exhibition within the United...

Determination of import process during Yucca Mountain Site characterization

International Nuclear Information System (INIS)

Hastings, P.S.; Gwyn, D.W.; Wemheuer, R.F.

1996-01-01

Construction of an underground Exploratory Studies Facility (ESF) for characterizing the Yucca Mountain site precedes the design of a potential repository, with site characterization testing and ESF construction conducted as parallel activities. As a result of this fact, a program is required to: (1) provide for inclusion of the underground excavation into a potential repository, (2) minimize the potential impact of ESF construction on site characterization test results, and (3) minimize the potential impact of ESF construction and site characterization testing on the waste isolation capabilities of the site. At Yucca Mountain, the Determination of Importance (DI) process fulfills these goals. This paper addresses the evolution of the DI process; describes how the DI process fits into design, testing, and construction programs: and discusses how the process is implemented through specification requirements

TH-C-18C-01: MRI Safety

Energy Technology Data Exchange (ETDEWEB)

Pooley, R [Mayo Clinic, Jacksonville, FL (United States); Bernstein, M; Shu, Y; Gorny, K; Felmlee, J [Mayo Clinic, Rochester, MN (United States); Panda, A [Mayo Clinic, Arizona, Scottsdale, AZ (United States)

2014-06-15

Clinical diagnostic medical physicists may be responsible for implementing and maintaining a comprehensive MR safety program. Accrediting bodies including the ACR, IAC, Radsite and The Joint Commission each include aspects of MR Safety into their imaging accreditation programs; MIPPA regulations further raise the significance of non-compliance. In addition, The Joint Commission recently announced New and Revised Diagnostic Imaging Standards for accredited health care organizations which include aspects of MR Safety. Hospitals and clinics look to the physicist to understand guidelines, regulations and accreditation requirements related to MR safety. The clinical medical physicist plays a significant role in a clinical practice by understanding the physical basis for the risks and acting as a facilitator to successfully implement a safety program that provides well-planned siting, allows for the safe scanning of certain implanted devices, and helps radiologists manage specific patient exams. The MRI scanning of specific devices will be discussed including cardiac pacemakers and neurostimulators such as deep brain stimulators. Furthermore for sites involved in MR guided interventional procedures, the MR physicist plays an essential role to establish safe practices. Creating a framework for a safe MRI practice includes the review of actual safety incidents or close calls to determine methods for prevention in the future. Learning Objectives: Understand the requirements and recommendations related to MR safety from accrediting bodies and federal regulations. Understand the Medical Physicist's roles to ensure MR Safety. Identify best practices for dealing with implanted devices, including pacemakers and deep brain stimulators. Review aspects of MR safety involved in an MR guided interventional environment. Understand the important MR safety aspects in actual safety incidents or near misses.

Glove box adaptation of oxygen, nitrogen and hydrogen determinator

International Nuclear Information System (INIS)

Ramanjaneyulu, P.S.; Phanindra Kumar, M.; Kulkarni, A.S.; Revathi, R.; Saxena, M.K.; Tomar, B.S.

2017-01-01

Radioanalytical Chemistry Division (RACD) is involved in chemical quality assurance (CQA) of various nuclear fuels and materials related to various DAE projects including FBTR and PFBR. Determination of oxygen, nitrogen and hydrogen in these fuels is one of the important steps in the CQA of material. For this purpose, O, N and H determinator was indigenously designed, fabricated and commissioned with the help of M/s Chromatography and Instruments Company Ltd., Vadodara, India. The present article describes about glove box adaptation of this instrument and various safety features incorporated in the glove box and instrument at Lab. C-25, RACD, as per the recommendations of the plant level safety committee

76 FR 53993 - Culturally Significant Objects Imported for Exhibition Determinations: “New Photography 2011...

Science.gov (United States)

2011-08-30

...Notice is hereby given of the following determinations: Pursuant to the authority vested in me by the Act of October 19, 1965 (79 Stat. 985; 22 U.S.C. 2459), Executive Order 12047 of March 27, 1978, the Foreign Affairs Reform and Restructuring Act of 1998 (112 Stat. 2681, et seq.; 22 U.S.C. 6501 note, et seq.), Delegation of Authority No. 234 of October 1, 1999, and Delegation of Authority No. 236-3 of August 28, 2000 (and, as appropriate, Delegation of Authority No. 257 of April 15, 2003), I hereby determine that the objects to be included in the exhibition ``New Photography 2011: Zhang Dali, Moyra Davey, George Georgiou, Deana Lawson, Doug Rickard, Viviane Sassen,'' imported from abroad for temporary exhibition within the United States, are of cultural significance. The objects are imported pursuant to a loan agreement with the foreign owner or custodian. I also determine that the exhibition or display of the exhibit objects at The Museum of Modern Art, New York, New York, from on or about September 27, 2011, until on or about January 16, 2012, and at possible additional exhibitions or venues yet to be determined, is in the national interest. I have ordered that Public Notice of these Determinations be published in the Federal Register.

Safety Tips: Basketball (For Parents)

Science.gov (United States)

... Staying Safe Videos for Educators Search English Español Safety Tips: Basketball KidsHealth / For Parents / Safety Tips: Basketball ... make sure they follow these tips. Why Basketball Safety Is Important Fortunately, very few basketball injuries are ...

75 FR 53013 - Culturally Significant Objects Imported for Exhibition Determinations: “The Pre-Raphaelite Lens...

Science.gov (United States)

2010-08-30

... DEPARTMENT OF STATE [Public Notice 7139] Culturally Significant Objects Imported for Exhibition Determinations: ``The Pre-Raphaelite Lens: British Photography and Painting, 1848-1875'' SUMMARY: Notice is..., I hereby determine that the objects to be included in the exhibition ``The Pre-Raphaelite Lens...

77 FR 23318 - Culturally Significant Object Imported for Exhibition Determinations: “African Cosmos: Stellar Arts”

Science.gov (United States)

2012-04-18

... Determinations: ``African Cosmos: Stellar Arts'' SUMMARY: Notice is hereby given of the following determinations... the exhibition ``African Cosmos: Stellar Arts,'' imported from abroad for temporary exhibition within... object at the Smithsonian Institution's National Museum of African Arts, Washington, DC, from on or about...

Food Safety & Standards

Institute of Scientific and Technical Information of China (English)

无

2005-01-01

@@ An increasing number of people have realized that food safety is an important issue for public health. It not only concerns public health and safety, but also has direct influence on national economic progress and social development. The development and implementation of food safety standards play a vital role in protecting public health, as well as in standardizing and facilitating the sound development of food production and business.

Road safety policy of the European Union.

NARCIS (Netherlands)

2013-01-01

The European Union (EU) is important for national road safety policies. The EU has several policymaking instruments, such as binding regulations and directives, and non-binding recommendations. An important element in the EU policy plans on road safety are the non-binding European road safety

Electrical safety code manual a plan language guide to national electrical code, OSHA and NFPA 70E

CERN Document Server

Keller, Kimberley

2010-01-01

Safety in any workplace is extremely important. In the case of the electrical industry, safety is critical and the codes and regulations which determine safe practices are both diverse and complicated. Employers, electricians, electrical system designers, inspectors, engineers and architects must comply with safety standards listed in the National Electrical Code, OSHA and NFPA 70E. Unfortunately, the publications which list these safety requirements are written in very technically advanced terms and the average person has an extremely difficult time understanding exactly what they need to

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

Science.gov (United States)

Mansur, A.; Nasution, M. I.

2016-01-01

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

76 FR 63701 - Culturally Significant Objects Imported for Exhibition Determinations: “Anglo-Saxon Hoard: Gold...

Science.gov (United States)

2011-10-13

... DEPARTMENT OF STATE [Public Notice 7640] Culturally Significant Objects Imported for Exhibition Determinations: ``Anglo-Saxon Hoard: Gold From England's Dark Ages'' SUMMARY: Notice is hereby given of the... exhibition ``Anglo-Saxon Hoard: Gold From England's Dark Ages,'' imported from abroad for temporary...

77 FR 59701 - Culturally Significant Objects Imported for Exhibition Determinations: “Wari: Lords of the...

Science.gov (United States)

2012-09-28

... DEPARTMENT OF STATE [Public Notice 8046] Culturally Significant Objects Imported for Exhibition Determinations: ``Wari: Lords of the Ancient Andes'' SUMMARY: Notice is hereby given of the following... ``Wari: Lords of the Ancient Andes'' imported from abroad for temporary exhibition within the United...

Conceptual Grounds of Navigation Safety

Directory of Open Access Journals (Sweden)

Vladimir Torskiy

2016-04-01

Full Text Available The most important global problem being solved by the whole world community nowadays is to provide sustainable mankind development. Recent research in the field of sustainable development states that civilization safety is impossible without transfer sustainable development. At the same time, sustainable development (i.e. preservation of human culture and biosphere is impossible as a system that serves to meet economical, cultural, scientific, recreational and other human needs without safety. Safety plays an important role in sustainable development goals achievement. An essential condition of effective navigation functioning is to provide its safety. The “prescriptive” approach to the navigation safety, which is currently used in the world maritime field, is based on long-term experience and ship accidents investigation results. Thus this approach acted as an the great fact in reduction of number of accidents at sea. Having adopted the International Safety Management Code all the activities connected with navigation safety problems solution were transferred to the higher qualitative level. Search and development of new approaches and methods of ship accidents prevention during their operation have obtained greater importance. However, the maritime safety concept (i.e. the different points on ways, means and methods that should be used to achieve this goal hasn't been formed and described yet. The article contains a brief review of the main provisions of Navigation Safety Conceptions, which contribute to the number of accidents and incidents at sea reduction.

The use of GIS tools for road infrastructure safety management

Science.gov (United States)

Budzyński, Marcin; Kustra, Wojciech; Okraszewska, Romanika; Jamroz, Kazimierz; Pyrchla, Jerzy

2018-01-01

There are many factors that influence accidents and their severity. They can be grouped within the system of man, vehicle and environment. The article focuses on how GIS tools can be used to manage road infrastructure safety. To ensure a better understanding and identification of road factors, GIS tools help with the acquisition of road parameter data. Their other role is helping with a clear and effective presentation of risk ranking. GIS is key to identifying high-risk sections and supports the effective communication of safety levels. This makes it a vital element of safety management. The article describes the use of GIS for the collection and visualisation of road parameter data which are not available in any of the existing databases, i.e. horizontal curve parameters. As we know from research and statistics, they are important factors that determine the safety of road infrastructure. Finally, new research is proposed as well as the possibilities for applying GIS tools for the purposes of road safety inspection.

Regulatory Safety Requirements for Operating Nuclear Installations

International Nuclear Information System (INIS)

Gubela, W.

2017-01-01

The National Nuclear Regulator (NNR) is established in terms of the National Nuclear Regulator Act (Act No 47 of 1999) and its mandate and authority are conferred through sections 5 and 7 of this Act, setting out the NNR's objectives and functions, which include exercising regulatory control over siting, design, construction etc of nuclear installations through the granting of nuclear authorisations. The NNR's responsibilities embrace all those actions aimed at providing the public with confidence and assurance that the risks arising from the production of nuclear energy remain within acceptable safety limits -> Therefore: Set fundamental safety standards, conducting pro-active safety assessments, determining licence conditions and obtaining assurance of compliance. The promotional aspects of nuclear activities in South Africa are legislated by the Nuclear Energy Act (Act No 46 of 1999). The NNR approach to regulations of nuclear safety and security take into consideration, amongst others, the potential hazards associated with the facility or activity, safety related programmes, the importance of the authorisation holder's safety related processes as well as the need to exercise regulatory control over the technical aspects such as of the design and operation of a nuclear facility in ensuring nuclear safety and security. South Africa does not have national nuclear industry codes and standards. The NNR is therefore non-prescriptive as it comes to the use of industry codes and standards. Regulatory framework (current) provide for the protection of persons, property, and environment against nuclear damage, through Licensing Process: Safety standards; Safety assessment; Authorisation and conditions of authorisation; Public participation process; Compliance assurance; Enforcement

Investigation on regulatory requirements for radiation safety management

International Nuclear Information System (INIS)

Han, Eun Ok; Choi, Yoon Seok; Cho, Dae Hyung

2013-01-01

NRC recognizes that efficient management of radiation safety plan is an important factor to achieve radiation safety service. In case of Korea, the contents to perform the actual radiation safety management are legally contained in radiation safety management reports based on the Nuclear Safety Act. It is to prioritize the importance of safety regulations in each sector in accordance with the current situation of radiation and radioactive isotopes-used industry and to provide a basis for deriving safety requirements and safety regulations system maintenance by the priority of radiation safety management regulations. It would be helpful to achieve regulations to conform to reality based on international standards if consistent safety requirements is developed for domestic users, national standards and international standards on the basis of the results of questions answered by radiation safety managers, who lead on-site radiation safety management, about the priority of important factors in radioactive sources use, sales, production, moving user companies, to check whether derived configuration requirements for radiation safety management are suitable for domestic status

Nuclear criticality safety 2005 and 2006. Monitoring, follow-up and communication

International Nuclear Information System (INIS)

Mennerdahl, Dennis

2007-03-01

A number of selected issues have dominated during 2005 and 2006. This include development of models for realism based on physics (not only statistics and praxis), criteria for criticality safety, regulations and standards, burnup credit, determination of source convergence in calculations, substantial improvements in calculation methods, validation of those methods, etc. In spite of some criticism against certain parts of the NRC FCSS/ISG-10, it is an important document. It should support both authorities and utilities to determine adequate safety margins. To a large extent, the principles that have been applied in Sweden since the 1970's are supported. The extra safety margin (MMS or Δk m ) that protects against unknown uncertainties in k eff should be related to the known uncertainty. In Sweden this has been achieved by limitation of the total, statistically determined standard deviation to 0.01. In addition, FCSS/ISG-10 supports the principle of using different values of Δk m for normal situations than for design basis incidents (must have very low probabilities). In Sweden, Δk m have been included in the design limits that have been 0.95 for normal scenarios and 0.98 for incident scenarios. The corresponding values of Δk m are 0.05 and 0.02. They are exactly the same values as are mentioned in FCSS/ISG-10. The recently issued SCALE 5.1 is very important for burnup credit. Similar capabilities have been available in Sweden, in the form of CASMO, PHOENIX and their predecessor BUXY, for more than 30 years. SCALE 5.1 makes reactor calculations available in a procedure that is easily accessible to specialists on criticality safety. The physics simulation of the irradiation (Monte Carlo through KENO in 3-D or deterministic through NEWT in 2-D) becomes much more realistic with SCALE 5.1 than with earlier versions. A very important project is the OECD/NEA study on reference values for criticality safety. The final report has now been distributed. Among other issues

78 FR 24288 - Culturally Significant Objects Imported for Exhibition Determinations: “Frida Kahlo, Diego Rivera...

Science.gov (United States)

2013-04-24

... DEPARTMENT OF STATE [Public Notice 8290] Culturally Significant Objects Imported for Exhibition Determinations: ``Frida Kahlo, Diego Rivera, and Masterpieces of Modern Mexico: The Jacques and Natasha Gelman..., 2003), I hereby determine that the objects to be included in the exhibition ``Frida Kahlo, Diego Rivera...

75 FR 53013 - Culturally Significant Objects Imported for Exhibition Determinations: “Chaos and Classicism: Art...

Science.gov (United States)

2010-08-30

... DEPARTMENT OF STATE [Public Notice 7137] Culturally Significant Objects Imported for Exhibition Determinations: ``Chaos and Classicism: Art in France, Italy, and Germany, 1918-1936'' SUMMARY: Notice is hereby... hereby determine that the objects to be included in the exhibition ``Chaos and Classicism: Art in France...

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

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

Safety analysis SFR 1. Long-term safety

International Nuclear Information System (INIS)

2008-12-01

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

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

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

Food Safety is an Important Public Health Issue: Chloramphenicol Residues Determination by Liquid Chromatography Tandem Mass Spectrometry (LC-MS/MS) in honey.

Science.gov (United States)

Krivohlavek, Adela; Žuntar, Irena; Ivešić, Martina; Andačić, Ivana Mandić; Šikić, Sandra

2014-12-01

Honey is used for nutritional, medicinal and industrial purposes and antibiotic residues may harm its quality and constitute a danger to human health. The broad spectrum antibiotic chloramphenicol (CAP) was used for curative purposes in veterinary medicine, but is now forbidden in European Union (EU) because of its many serious side effects (e.g. aplastic anaemia, grey syndrome, severe bone marrow depression and hypersensitivity). The aim of this study was to facilitate analyses of the quality and safety of Croatian honey distributed to whole European Union market; an assessment that has not previously been made. CAP in honey was qualifying and quantifying by validated liquid chromatography tandem mass spectrometry with negative electrospray ionisation method (LC-MS/MS). The target antibiotic was separated on chromatographic column Zorbax SB C18 (150 mm x 2.1 mm, 3.5 μm) with a gradient elution using acetonitrile - 0.1% formic acid mobile phase at a flow rate of 0.3 mL/min, with column temperature 35°C for CAP and 5D-CAP as internal standard. Homogenised honey samples were diluted with acetate buffer solution and extracted on Oasis Hydrophilic-Lipophilic-Balanced (HLB) sorbents. The method was used to analyse 280 domestic honey samples collected throughout Croatia between 2005.-2013. Recoveries of the method for real (acacia, chestnut, linden and flower) honey samples were 102% with RSD 8.4%. The value CCα and CCβ were 0.09 and 0.12 μg/kg, respectively. Results showed only three subsequent positive detections (1.1%) of CAP in honey. Analysed honey samples from Croatia showed good quality and safety what is the one of the main objective in consumer health policy in EU.

76 FR 53524 - Culturally Significant Objects Imported for Exhibition Determinations: “Once Upon Many Times...

Science.gov (United States)

2011-08-26

... DEPARTMENT OF STATE [Public Notice: 7568] Culturally Significant Objects Imported for Exhibition Determinations: ``Once Upon Many Times: Legends and Myths in Himalayan Art'' SUMMARY: Notice is hereby given of... included in the exhibition ``Once Upon Many Times: Legends and Myths in Himalayan Art,'' imported from...

76 FR 12786 - Culturally Significant Objects Imported for Exhibition Determinations: “Poetry in Clay: Korean...

Science.gov (United States)

2011-03-08

... Determinations: ``Poetry in Clay: Korean Buncheong Ceramics from the Leeum, Samsung Museum of Art'' SUMMARY... in Clay: Korean Buncheong Ceramics from the Leeum, Samsung Museum of Art,'' imported from abroad for temporary exhibition within the United States, are of cultural significance. The objects are imported...

77 FR 53959 - Culturally Significant Object Imported for Exhibition Determinations: “Dancing Into Dreams, Maya...

Science.gov (United States)

2012-09-04

... DEPARTMENT OF STATE [Public Notice 8009] Culturally Significant Object Imported for Exhibition Determinations: ``Dancing Into Dreams, Maya Vases From the IK'Kingdom'' SUMMARY: Notice is hereby given of the... exhibition ``Dancing Into Dreams, Maya Vases from the IK'Kingdom,'' imported from abroad for temporary...

78 FR 8682 - Culturally Significant Object Imported for Exhibition Determinations: “Vermeer's Woman in Blue...

Science.gov (United States)

2013-02-06

... DEPARTMENT OF STATE [Public Notice 8177] Culturally Significant Object Imported for Exhibition Determinations: ``Vermeer's Woman in Blue Reading a Letter'' SUMMARY: Notice is hereby given of the following... object to be included in the exhibition ``Vermeer's Woman in Blue Reading a Letter,'' imported from...

Evolving framework of the LNG industry: Expected growth and continuing importance of safety

International Nuclear Information System (INIS)

Kagiyama, Ichiro

1992-01-01

A major increase in LNG trade, expected from the 1990s onwards, is quite significant in that a new framework will be developed. These changes and developments may well prove to be some of the most notable that have ever occurred in the 30-year history of the LNG industry. All over the world, new buyers and sellers are entering the scene, while in Japan, small and medium-size businesses are switching to LNG. Transporters and LNG carriers are also expecting an increase in their numbers. We are about to see a wide-ranging diversification in terms of the geography and the size of the companies that deal with LNG. Safety continues to be the main issue in promoting the development of the LNG market. The wider the spread of LNG, the greater the need will be for further development of the systems and organizations for transferring safety technology and skills. In addition to enhancing safety, it will be necessary to seek harmony with the social environment. This paper discusses measures for the future based on the author's many years of experience, particularly in the field of receiving terminals

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

Compilation of Microbiological Testing Results for Human Pathogens And Indicators Bacteria in Foods Imported by Australia During Recent Years

Energy Technology Data Exchange (ETDEWEB)

Newton, K. [Australian Government Analytical Laboratories, Pymble, NSW (Australia)

2005-01-15

Australia is a net food exporting country, but also imports a considerable quantity of food from worldwide sources. Monitoring for safety of foods imported into Australia is the responsibility of the Australian Quarantine Inspection Service (AQIS). AQIS carries out the inspection and testing of food imports under the Imported Foods Inspection Program (IFIP). An advisory committee which contains food safety experts, conducts risk assessments on foods and advises AQIS on risk categorisation of the foods, and on the testing to be conducted. The rate of testing of individual food types is determined initially by the risk category, with high risk foods undergoing a higher rate of sampling than do lower risk foods. When a good safety history is established through the testing program for a high risk product from a particular producer, testing frequency is reduced. Sampling rates switch from sampling of all shipments to random sampling. The inspection and testing program is designed to comply with WTO requirements. (author)

Determinants of labor safety management in Spanish companies; Determinacion de la gestion de la seguridad laboral en las empresas espanolas

Energy Technology Data Exchange (ETDEWEB)

Fernandez Muniz, B.; Montes Peon, J. M.; Vazquez Ordas, C. J.

2011-07-01

Managing health and safety risks in an integrated way with the operations of the organization has been of increasing importance in recent years. This approach reduces accident rates, reducing losses and improves the firm's productivity. However, very little attention has been paid to analyse the organizational factors that favour or limit the implementation of the safety management system in firms. In an attempt to address this gap in the literature, the present study focuses on the identification of the characteristics of the organization that encourage the development of this system. The results show that several factors, as firm's size, previous experience on quality and environmental management or internationalisation, among others, have a positive influence on safety management system. (Author) 62 refs.

Host genotype is an important determinant of the cereal phyllosphere mycobiome

DEFF Research Database (Denmark)

Sapkota, Rumakanta; Knorr, Kamilla; Jørgensen, Lise Nistrup

2015-01-01

The phyllosphere mycobiome in cereals is an important determinant of crop health. However, an understanding of the factors shaping this community is lacking. Fungal diversity in leaves from a range of cultivars of winter wheat (Triticum aestivum), winter and spring barley (Hordeum vulgare...... and location have minor effects. We found many host-specific fungal pathogens, but also a large diversity of fungi that were relatively insensitive to host genetic background, indicating that host-specific pathogens live in a 'sea' of nonspecific fungi....

77 FR 26599 - Culturally Significant Objects Imported for Exhibition Determinations: “The Artist in the Garden”

Science.gov (United States)

2012-05-04

... Determinations: ``The Artist in the Garden'' SUMMARY: Notice is hereby given of the following determinations... the Garden'' imported from abroad for temporary exhibition within the United States, are of cultural... also determine that the exhibition or display of the exhibit objects at The New York Botanical Garden...

Water safety and drowning

Science.gov (United States)

... among people of all ages. Learning and practicing water safety is important to prevent drowning accidents. ... Water safety tips for all ages include: Learn CPR . Never swim alone. Never dive into water unless ...

75 FR 82069 - Ethyl Alcohol for Fuel Use: Determination of the Base Quantity of Imports

Science.gov (United States)

2010-12-29

... INTERNATIONAL TRADE COMMISSION [Investigation No. 332-288] Ethyl Alcohol for Fuel Use: Determination of the Base Quantity of Imports AGENCY: United States International Trade Commission. ACTION: Notice of determination. SUMMARY: Section 423(c) of the Tax Reform Act of 1986, as amended (19 U.S.C...

76 FR 81004 - Culturally Significant Objects Imported for Exhibition Determinations: “Woman in Blue, Against...

Science.gov (United States)

2011-12-27

... DEPARTMENT OF STATE [Public Notice: 7739] Culturally Significant Objects Imported for Exhibition Determinations: ``Woman in Blue, Against Blue Water'' by Edvard Munch SUMMARY: Notice is hereby given of the..., Delegation of Authority No. 257 of April 15, 2003), I hereby determine that the object ``Woman in Blue...

76 FR 6650 - Culturally Significant Objects Imported for Exhibition Determinations: “Splendors of Faith/Scars...

Science.gov (United States)

2011-02-07

... DEPARTMENT OF STATE [Public Notice: 7319] Culturally Significant Objects Imported for Exhibition Determinations: ``Splendors of Faith/Scars of Conquest: The Arts of the Missions of Northern New Spain, 1600-1821... hereby determine that the object to be included in the exhibition ``Splendors of Faith/Scars of Conquest...

76 FR 13638 - Ensuring the Safety of Imported Foods and Animal Feed: Comparability of Food Safety Systems and...

Science.gov (United States)

2011-03-14

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2011-N-0135..., to request onsite parking, or to submit the full text, comprehensive outline, or summary of an oral presentation: Juanita Yates, Center for Food Safety and Applied Nutrition, Food and Drug Administation, 5100...

Improving food safety within the dairy chain: an application of conjoint analysis

NARCIS (Netherlands)

Valeeva, N.I.; Meuwissen, M.P.M.; Oude Lansink, A.G.J.M.; Huirne, R.B.M.

2005-01-01

This study determined the relative importance of attributes of food safety improvement in the production chain of fluid pasteurized milk. The chain was divided into 4 blocks: "feed" (compound feed production and its transport), "farm" (dairy farm), "dairy processing" (transport and processing of raw

Obtaining Valid Safety Data for Software Safety Measurement and Process Improvement

Science.gov (United States)

Basili, Victor r.; Zelkowitz, Marvin V.; Layman, Lucas; Dangle, Kathleen; Diep, Madeline

2010-01-01

We report on a preliminary case study to examine software safety risk in the early design phase of the NASA Constellation spaceflight program. Our goal is to provide NASA quality assurance managers with information regarding the ongoing state of software safety across the program. We examined 154 hazard reports created during the preliminary design phase of three major flight hardware systems within the Constellation program. Our purpose was two-fold: 1) to quantify the relative importance of software with respect to system safety; and 2) to identify potential risks due to incorrect application of the safety process, deficiencies in the safety process, or the lack of a defined process. One early outcome of this work was to show that there are structural deficiencies in collecting valid safety data that make software safety different from hardware safety. In our conclusions we present some of these deficiencies.

Pickering seismic safety margin

International Nuclear Information System (INIS)

Ghobarah, A.; Heidebrecht, A.C.; Tso, W.K.

1992-06-01

A study was conducted to recommend a methodology for the seismic safety margin review of existing Canadian CANDU nuclear generating stations such as Pickering A. The purpose of the seismic safety margin review is to determine whether the nuclear plant has sufficient seismic safety margin over its design basis to assure plant safety. In this review process, it is possible to identify the weak links which might limit the seismic performance of critical structures, systems and components. The proposed methodology is a modification the EPRI (Electric Power Research Institute) approach. The methodology includes: the characterization of the site margin earthquake, the definition of the performance criteria for the elements of a success path, and the determination of the seismic withstand capacity. It is proposed that the margin earthquake be established on the basis of using historical records and the regional seismo-tectonic and site specific evaluations. The ability of the components and systems to withstand the margin earthquake is determined by database comparisons, inspection, analysis or testing. An implementation plan for the application of the methodology to the Pickering A NGS is prepared

76 FR 60112 - Culturally Significant Objects Imported for Exhibition Determinations: “Byzantium and Islam: Age...

Science.gov (United States)

2011-09-28

... DEPARTMENT OF STATE [Public Notice 7615] Culturally Significant Objects Imported for Exhibition Determinations: ``Byzantium and Islam: Age of Transition (7th-9th Century)'' SUMMARY: Notice is hereby given of... included in the exhibition ``Byzantium and Islam: Age of Transition (7th-9th Century),'' imported from...

Tools to quantify safety culture

International Nuclear Information System (INIS)

Avella, B.

2011-01-01

This paper reviews the notion of safety culture and then describes some of the tools that can be used to assess it. Required characteristics to obtain reliable tools and techniques are provided, along with a short summary of the most common and important tools and techniques used to assess safety culture at the nuclear field is described. At the end of this paper, the reader will better understand the importance of the safety culture of the organization and will have requirements to help him in choosing reliable tools and techniques. Further, there will be recommendations on how best to follow-up after an assessment of safety culture. (author)

Application of the AHP method to analyze the significance of the factors affecting road traffic safety

Directory of Open Access Journals (Sweden)

Justyna SORDYL

2015-06-01

Full Text Available Over the past twenty years, the number of vehicles registered in Poland has grown rapidly. At the same time, a relatively small increase in the length of the road network has been observed. As a result of the limited capacity of available infrastructure, it leads to significant congestion and to increase of the probability of road accidents. The overall level of road safety depends on many factors - the behavior of road users, infrastructure solutions and the development of automotive technology. Thus the detailed assessment of the importance of individual elements determining road safety is difficult. The starting point is to organize the factors by grouping them into categories which are components of the DVE system (driver - vehicle - environment. In this work, to analyze the importance of individual factors affecting road safety, the use of analytic hierarchy process method (AHP was proposed. It is one of the multi-criteria methods which allows us to perform hierarchical analysis of the decision process, by means of experts’ opinions. Usage of AHP method enabled us to evaluate and rank the factors affecting road safety. This work attempts to link the statistical data and surveys in significance analysis of the elements determining road safety.

Administrative Management Competencies for Safety Professionals.

Science.gov (United States)

Blair, Earl H.; Logan, Joyce P.

1999-01-01

In a 1997 study, 245 safety professionals and educators identified and prioritized management competencies that are important for safety professionals. Results show that the most important competencies are communication, listening, motivating others, creative thinking, and flexibility. (JOW)